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UK r f~ it ng, Mange oft' 2~ No~ar Poar 1150 C C: i l 3..
~~~M Iv MN UENANCE I3ROGRA\IM- NUCLEARK: S;AFET'Y NKV 1W ST'IAFFI* jN:;Y; I EVIARTNOI5
týt J 1.LM 4 Ai gt'~ I Ilq app o p subJ'u C3V'3 3131 .p33 I t i S ' Vsn0I3I i .3 I ly i cI'nffe. Q ~
7 As
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3')vet.0i c pro ra a3~3t3311 th:3.' :31331~ ( N) , Br'Ii:.t.r (m ),:3 And WIL11333' 33
Ba3t1 I jt(3 3i: Nuclea plants .3 .':t This re irw> rxi in thn a, A of: 1).~. 3~3 33 ( ,,
pl333 aj ad1.1131 uac)l(y,C:33 (2) 3. t3.1..a 33ix !3.I,3 ( ''1) wor it i l l. n psn (4)3'3.3 3
overal j an L ) :nint n n r and (5)i tn il qualit. .qv null
vil 1vs ini the j 3[ ma rlp,3' cr ar a wI .'rmphas'33 33. is p:1 ":313' on th-33 work
:l c~i ln.lr ! I 3:1 r.)ui. Ii 13(3(:: pr ce s TVA; ni333~ri al lvii and V.13 Np -A n I 3'2Pizan
Ilailnteni pr grm an (3333~ hav 1ru 33'). i a i 3:3 :o3 I m.' 13.3 r33 n~ v* v L s its~ 3
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NS V:; i' c1~ Cf333l p 3t a( t331 .3 r a: .v o: t. p. :t y31 u,, r Vl I vj N3ohnIa's2L L'h''s v.hCZ8
R'3 ' ~.2l(IiI Lwo 1. 1 4: ha&333 a3v.:: I I owe Conco I. . E''' i i now nv 033: 33 you
H, 's ).re of thi ri' vp r 'Ihwi l r ~ " l y " . I1!MC I i
11 I j\ Q I nyc n n U I o you a~~. L3: a' I. a I vrd h "IA y u hAv N 'I
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MTEFfS OFR~EVI JEW: YfE I;B;AVY\ 4 MA~~RCH 8;, 19B"
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S .COPE.
II ONCtLUS I QN AN mom:Cm:nPATION
i1*.'DTAI.S......................... .. ...
~4
1..
r
A t~z~c~y' raIfl J\~ .i ¶~.*
C. ,Wor k Contro PC rocess; . .. . .
2 OWe rva~io. n of Aw iv IhI.
-4, NSClO! P((hlan Rein i U'y
IQ, Onsi te qu~a I. i L suac
IV PE RSONNEL . GUn ACTED.... .. .. ....
1)OCPM~N rS H~V IER .. .......
I.
7.8
DoLao x I ~ PP~US )2 2
ZA
. . ... . . . .8
i
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7-77 7,
MONE
The~ maintenan~ce revie was.~ SnCdlilcto at Sjequykit Ntila ar PWOu (S0j.
`Bý.rowns Ferr y Nuiclear Plan~it (flFN) , Wa t L s hay Niic ear IA ant L(N ,:i'ri
t h6 Off icb of UNv Icar Pow'rr (NIJC PH) anid D)iv''ision of Qual ity. Ass;urridd
t(DQA) off ices in (That la;1ogi. 11510 re'y'ipwvr!; iutervi owed 1 -sonilo
cogniznnt oIf ma jt nai~ice act ivi t~ies;. rviteweý.l jroc:ditircs a n d L I ter
documents pe iMainiig to t lie veontro 0 of t.hWa* aiCt i --i tiCS , ILC , (Id~
P1 tnt. meet ings, andI alIso oltsirvttI work in pr'ogre:;
"01 t LONC.LUSI1ONS. AND RECOMMENDATIOuNS
A ,..
cone]c "ii ion
.
* -I appe~tred to NSI'AS that c:lemenlts of it mai mt enInflCe Prgm Val U
jadc'quaqplIy ad'dressed by AMIV: s; 'op i a I 19-po rt and tzhe, 14ii. 16 ENP,.
Quali ty As sora nco H'anna 1 (NQAMI In I ahe revie,. of: Le' A cmp t
*moent.inmg p roce~dure&; it appe ared Myh t..the p rogram for mak 0A Itn,~e
Was ad I.: It. (.' I Y .:, ( tI-Q-.!c d i I I t I I ;QN a Md 'B N I ir 0CC d l re C S od t
s trut ctios.. How~eve r,, At HN pl a ant. marlay.'t haI~:d riecog'ii 'edjthQQT VA
* hc: Si~ procedures~ wrre inadtequa~te an anionsZ weI wre being s i
tLc, *imip rQvt t.he p rocduires ( cc lrr to. sect ion I ! I A for Mea i .es I
13.. ..........
- Thc cgalizait jonn I St~rutvttre
i H mmati ;n~toauo act iX'it ils-~ i s ha A p
Vally-sound a t all'p1 ant-.
Roconi mp"7m .i .: o f con vO r o I fw i.tii ns
Lhe organiztation awd jtl=1w
Lo Chatitv' :trli-i m cuot r00 shhlotild'
ji7p1)roveQ or i Zati011
of I vi MU T ss ( refvr, Li, section l .1 fo
G. W4ork UAW r Process off"1. P'Ianu~irim
andI 'Suchedulin'
will vf y
Izi~dt'nit i n~ i Li ion A. ReWomwihi Li t
co (I1!! Lh'tb-i Llit' renpon~;ibi. ii y for deLvr(1011 dII t: i
idenmitficrit.o an~id avoii ahil1ity. Q. sparv- pat Us wa t~..'s'fo
Tit'. r&j()t iLi d In li n ty (yf deteititmfre tlu.,ý itiTi ( to n Se 14 13 "7
11~~~1 .C. f
a.I)
~' I, . -..2.
..........
ý07 2, Ob~rviv~tion
oft Acti p
*Coniclus ion
P r f iiiah ofC L1 he
obse rved ma in I oriaa ur aVrii Vi Liv$as
pi rvdj
adqOPi that: t he ma intenaince
prrsonna. Wh uoIvcI
Yin tiLh
*activityV aqpearcd
knoleugeab le of hiv, act iv i tyj and LWcý
w~ork wa:s per formied1 i n4 ,4cor.i'4id41t
w i t h apj'iivod 1)rpi itire'
( refer to sect ion 1I .C.2 foe- details2).
'Coll
Kos ymaii ll.- e ia niff' ICS I. 9i
.
R-85-03-NPS02, ImiRuErIJdent
iti~cat~io ofi CLiit icaL.S'Astumy
in
§lpyres , anntd
~iC)*Ejl
11ieit tn vl I Ii Ca 11ce C~
Conicluion;
MiR,; w ri e, not alw y bei'. ing r u rpiipt' 1' i denitifIie I'S!
01Y 1i
lust rUMCUL Wid EleI i~t4cal
MNijt om4nii S'c-Lin
o o CS;'S;eC-
C r;!i C S(. t go ri es. A\Na result
QA ' rovi aws. we ii' nut-.
prfoarinel and pon UintpiiI
euiroce Lest WX was n rot alway.W'
pro 4 P-
12iIV Al(t
ed cc I
(reit
L~ 1
in Ci 1H.C.3.c b)r - de~ li 1)
Sectijons: s~hould
provides tra~iniing
in id! ut; i fyngCS
ulwi-
menut .ani 'wnvre: tI; CKKC l 1ining;
aire Imo d ii
7 4
I-~ I O? I
~!sjitt I t-m~ oi f- Is ai ni
lR 01
q gIy
Con~ic In:; i oil *
Tho OceIa-tr (lulli Uy A: n ranuc:
MlanualI ( NQAN),
Phr F i tý t;
Lion4 2.1, p~ i;:rapti
3,~1 .1, ;1 states,
''C on ccn Le t on a
marnliiru-n~iu vol
any Winu * h- C.,SC: livii and
fcuri Wah'C
r -vr, appriip4
itro st iny)
:.li 1) he p4: 4rkirsed i
vo ci f o~p-ra.t ional
a(op (:4 lIi LyX MRNP; vo rd nut
1 a
beiný, punjer i -l fire;i a-I by th.' BPN leet r i ci ma iritUnarueý0!
J
section for pwma
in-i anc W-4~ t. ig hf CSSC
equ i pment. (r Ir
LO see t ion II I.C.
O I r de-t a ils),
4-.
Rrow~n:; Fe r- ry mai i it Lna I' si.- L i alns rho" I d etplias~i
ze the nlcE 41
f 6r 144):; t Fiii;" v I) Lilt
L i l .iii n f (;2(. s i 1 pmon i! . * liui tp
n 4'i '14 *'
-4thuli(i 1 Pract icen (A 6.1) a4nd sec~ioni iinstirctjrio
Ii teritr .,
as; app I i rob1 I v , shsnt I i 4'iit. i fy LK.Ii impon4rtance( of *1
est-ingq
oil1 i
j~. -
'~
""1
NT
ASME~~~~~~~~~~~ CeC : iP;titit~it~'Viy-S~ -03 -NPS -04,t1 ifli~ -
I.. IC. It I ;, i oilI
MEe Se~ co I i o I' io X I '.'i I %'e Ie'st i Ili',~ i t hew p
ft-tmrmtI wor an S:CCL ion X I vat Nun~; r v f c r to sccti ot Ii I (Q :ay
to~~4 to W"~t tiI.~
Rke Cotmwened t. i oil
I e I ') lt I )o st e A I o \11 A!t oi I 1n:m th) v; I ro -. l
:int i i n i~ o i Jent j ry toIn -ii'. %"hi (:Ii ti 1 (:11 din.1 it.
*~~S Arri I.u;
Htiret, t I; RaI- smc i on;~ wer: not, i dent i f yvi n g the nteqd A oA;i :E. i X)n v f, t e:t ig whII v woitr oni;ý-
SPVL!6ni XI Va 1 Yes It t b c r 10 t.ion I I I C .~3. C ie f uý t3i 1,tl
nti t'c. n t ti c~i I I M.' I (in I 11 Ii Li I t~t rifi CII Mti di ~It. rpow ic
o f tho A!S!P-'. on2. Xi XI. plump atnid 'in I v' prtog ram Adt -in how to a
Guidt- int di o np otitt *N wi I t rto tt ci thalti i ii m i nte.n L. 1
in it.' :;iiv, r I Iue t ha I i 111" wtCLiunrt ktt -' ti olh
s t-~ ii: fnt ined as~ drsignui t ; (rvC to ilg t tionp~ r I zI pC 3i, t i
deLaneic I S ;I io t nigt. h it n' o
Each s ~iti L ievenidiI d ii p illa o tittru, siuucit . i out t6h ng f t : hot
~c f: i L I t ol luh!! l ft o i c I I ,k ia nt suctI. is I v C L i "gt n r In Im.p r n '3s
hf1 i Hg lope a 0 a I ILosit itt ng lit ivnuU suc colfI eA..~ t"J AStM.lgt IR
HOn W fi sutch ai li sI Iitt is Seqttoyatl (\-S IL-5.3 3,4HItxvenancecQA~~., SiffHni..
3*.
STIP TOPt
AA (nnLU N Ok tt-va I Am(' p, jI
FlI~ I o j. %l u I1 !-IIIiI L( 1 .1, O
(2 tc t;i I'ltl
I t Ivc " "s rinru M~ ni C" ir S~.1 o . l.v
Th NM I" ti Caint I. Noiu Ilm S c in id n t a p a ih
D.
L
dovel'-p and implom""I a. prw.-idr:; -I C, hod 4" W, -7 .41
t 919 Q I Y AS.Suvinc,".
SgryQ11d ncv of Ma (ull.pnaui 0
"TOW
,-AmIve. ot{ bu. i , " , y 1 ' 01"f• ' [ ( "'fc. t.o• sect inn, 11"4.) 1, -.ý ,Ond. 3 for W alk',1 I )... .":. ..... i
Ontt:i Le tt I itI a. VtIA;t~if pa ''Ic: i II I-v r u t., t Iin dkivp s. I tI rye v
/6
.AA
r
;y"W T1A 1SLD
!n
K Y ,f-
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T'AILS
The 'To Ii ~caI Wpmr 4l~'cfc Ow 1AI on X.~ c;'n.,~tti'I
Mane~1itia: I (. NQAMi) *h ii'n t he ro.i' s.v ro I I li; i w , ~ aiiIeK
c,' & rtj n o in' TIV, A~ t- I v'~ t .ir p~et 11 irtt ut A rc v i #-,' 6 1 t ho
TopI i cn I i'-*jcirt. andc tho ci' A w~i jc pi r I c' o rile 1 le 0 ~ itjfi Iw. i
t 11 (illIi t -. : 11 r'.t w'1 *gci Io am r fC I~~f IV cii i " I I oc(t mal lii nI
The fl~igK m vt X[lld;jrn
Ic. Wri ttenc c','CtIV"Missu;rdtic~ hsgnivi prjinc ipwiL. resQAti 1- '~
C. l'Ccc~ a i u dv;(' li II s t cuidr fes. c 1cI I
w 0 7 ade'lplr-H:.'l by thi! Ttp ca l k- t, r t a-1! 1 ttiho
NQA1M.
A rev.'i K a cI 1 I a nL a dmin iius t ra L I VO ro-'c rd" r wc ai;d, iv .vlmc ti. ~wa; cc!r f ormed~a Q cculoermi tic~ i f hy app!p UK! cabIrcp reui.&Mlit. ut>--
hf. To pi lca I c r)prt ,.. NA.`. A NS I INI A *.7, 0 (: R., . Acpc'nua1i P
Mi ,cn aISeiI i cat. ions: (05) rr a.I'.'lciltc Iv itllr"n 6
Ii:u r". i "UL, i l id I tia yxac2inral io Q. th ' I. I Ivwtpg. dccc i
me: It :; A'!:cc j cM.ra.t ivc I M UM; :uC Kc: A I-.
If, jz.- r!d COnut.ro I :;l icic.r"lionsc~ (P 1I I) Q5c Se"oya1 i~h StadaiIrd L
I ract-Ros: - Admi :u i rau ct iv (SQA~) -h'c -'c S'cjun .Mi ..
tand:rdc ,*ai I' ic es, j c - Ho hanicrc i Ii I SON1 -) -5 c7 '5 8; rut -
* i~Tch'in i ca 1I1 nn Lu MrcC i oii (II 10 I( , -69c, mcuid -7q InVaccM Mjj.M M
Ld the re~vie~w M the ahovc ;crc)C'turck~, Sut " rv ill~Ic 16n ns*tL i
tiOn:; (SI I)-94. 1. aind -9K8.2 :ir'. . I n . iccent. MA: hhet~nihce ý F.
J: ,. lM eLrciui: (ill ).cg/ .cii -1l34 w.eie :co I 0Cya.; nt ed J5gfl 31111 1 0, i
dietLa i. c'I wc haC ki I :;StL. Jr ap a r Pd I roc6 !iJ~in UR G/ - 13 6 9c " P raced"re
1'd;,Iil;tici (W ck! ist fori Ma int.eicnic'', . I'n;I, and Cal ibra.3 .o . ........
I I'4.edciic Unf.; U;I int INcc I c':c I, Po.'.ri P I' acn ;'' I. apli~( I IL i pitybo
the NS Rr, the 1 cr n pi - i)c J1 or Mai;: ict-e~n.-ccc wa~ n~eu tc.1v
WHOM~sw' in SQN pr(Uc'Itcu n and :iui trctdrincAI(fl ecpt ;f`r6
rlosItwniL 3ii canc( tLe~t. ig ac c~t& (commonV~i ;c'ic' ai lu re (r'eJerMA i~ 1 10 And 11 .I.5 ~ for Mal)
14
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. 1ý
4' 44,44"44'.
4~,4',4
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C'>)444,44
.4 '4' i'. jcwcd HOl: prokus_:; iti.k i I Ci A'ei I e It I ( ir~e ta
S it I! pri'iCilliIt Ware:v ~4'¾ and PhV i as', H 'ivSATY NO,':
A ccolmji i shod by a~ Ail a i 44 Ii na Ior. A I I A Lii Ag jkiip 1501
('a lIisli''i WI cli cri.Th- I-( I criiicc d INItAM ,idI Ii P" I! Ljtt i I II Ii'#
t,(-) i;Ilp ni (. wa ma IAl' Ii ;mnt i";pero i ado . 'iii''i. Timr ONtc wikii
a n I e v H: ! tio wV ., Ill d t o Al l I S ( i i b V i I ' . s ie I " I m i f i c4
i f a re.v I AL u W 1 ail C:i fi': lNI Iý',. 'I'll i I & #:; 1,S 1'." I-ac ,ws I bV
tim. 'maiih;gi'iii't, a '1.ill t rak inrg s.51 #111 (MA V). 110 1AIV
ric''i sed.
Y P ii?'.'? iF''i '
(li res ri'W Ii i i ri jI: 1 t c~lril tiýfAI I l I11 It li ;S wa:; ''no r tHi go.ll I n*
LI CI if 4.1 2*' (IIuat r Performanc Jm r(iin Pin. j itC41ltC a .i II #S aS Oi: roil)
Im : L) i(ii4 ' SI t I,411 v'] Ic4! The ci pillg ii i;ll'.eti am~idi
1..! ye rw d hA nd ma i lit '115 i Ia I. Ii i I I I t I I t.!;' I .445i 1 *#. I IIt
ift4 L" A(iir e c mpIo n 01(N5l rm wa P w n l
• i¸¸I ,i
4 a s I i ,I
C, Viewri r t i nv hr4I:5 itd III axmit b iQ to I Y p'mitiI( y Iii
sit': p m'H'4 lul' dI' 11''P~ A'',H'''~ Iri - 1v :;' 1t' Q 7C I -3. 1,
;II it (i i I r' -ns J i ii W , 1 1"111 it. : ahit' ii w, I4 I 'l irt I I on! C!i x c )
4 4,
S
I
4.)
:orAa nly *ioil
Ova rV i .'w
ALotd111rc vU the i':it.pali I.i el 5l~ l
*repiorted to the suicr i iL (ni1ohtfi anthey were ';oi 11)1 C I
mechanijcalI , elect r i c':i , sId i n 5t rumen ctl ina i n t iiailcK and for r
buil Iding secrvi ces,
TIhe ma i ntellanrce o ri;:1i pi Aa t. ri cli.' 3t d 1- t0 icCl:nd l n
* a f, f 0 t, cd 4 . ' t 1:e rta r ganizi:a t. n ill t he 0 f f i c iof e r [
g .o' e s.a L imp ac L. rcci I It (I I -orn) h :: ra ia: cnw
i i ty, tor maj~or ni i nt. iinict Act i v i ti us rmn the va Ifrner Ww'
Fi c Id Serv'iices Group, back Lot p I a nt ma; i nL~eiallCe Thi Q-,li
inclu Ided slrh act.i vit io as' the i-duel ins, f lonr worl~, Imajor...
valv e work ( such as con 1a imentt. i :o I1t.i va yes) . snubbe ci,
-'e.Id - turbi ne f loo' act i vi t es. lIn most- c'tso Lhe.. llaltpoyp'IM...
p ill~ rur i s jion for 'these a acU vi L j i cS Was aI I o absorbed awhy KQ
j the ma initelance sect ionsl~. The. recent, decnt cal Udt. lonl.1Iso TO 0
ji tf I u 2IcIMI 1!d Lh plantt. lt i vtAld ( ct~ 10, n . all',' eng i nce
hoaiid~ ~e postions originallyv locaLe'. in the Nuclear.Central:.n-01
O.f fi ce, ChtaLM0a hnt bte; shifte to th p'ntq. At ' h
t int Ill J) t II i s rica'I. I MA i iuiih (: r of newly 31' aI aua tM posi;it Cnl
had no. [ee .t! d e.the plannIIIing andts( hch. 1; irlg organiz
I ions for SQ andi \~W4 wCeiv sifi iar, hil. contrastei d with rhat
* a L BP,` ( rcCc r to s c ct. i o ii Ill . C . I for de!t& 1.), Al1,1l 1) Iant Ls
o ccr'a. c r joing th1 1e poret ntagc it f i 1ipl.: I v i L. in in . thi,
tu n Ltteilaice sect i aiti h hi s w i I I R urar Ci 1i. el iill ip r ." of
haul11 1 clv pe !-SO l W I: I e:V i vi i !,, L he p, 1)1-n tt. jd i t.r hte Ii .Imi~t-Ils .29
,lday.s maxi:mum~r serv icecon~id iLi ari
nanc(: act.v \' IW es wda s~ 1 t.1 it L w,-, s ha 1a i ca I Ily sOul)(J.. rh e O l
wer p a WLo cimrrli conto Is wi Lhti n the nrgaiiii it 1)1
s rti uo 1c I urn a I I p I n n L a . V arii ms. w~ys n performinciig v i lit '
Nn~dIce~~' pro' iI "volvins, . The!;t: chinyt it M's I uil d i t a ". n 1) L al H
%- wIl c ji2 r cII; an-~ I I e lel i ao:; a i i c ao spec i Ii (. roca .ot r lIn i t. O
ap v i r i c p1I a nt v rows. suth ct L" In c i no , a i ir ('Int i t. I Oil il l~
tdlieaet[.geitematt andi va lve icrews; adil at. B H, s ;lc' i f i4 It i ift*-' ''
crows., wi Lii L~ ishin .rhi ft, siiperv'is tn. The': 1M-N;UhVe01....
1ment, may ref I ect imlp io'.vneils ii ni 1:jinl.oniantc: ~e t ri V-if t ovn
Browns MIX Qv
ifatin l.enanLu p ract We.(c: as eam (:(lI i if i ed by, rpron! e:vent t. KJV1 h
RF'N s i tL invovlv ing f i Itur e oat a hti gh presrca t cc.csol ant.14
ii jeci:jolt (HPC I ) i soIa Lin vatlvI e tlue L'1 a reverscei .pi iiionQ10
gear, diliutlulal . evint. ass0(:iitteuld wih ',it 'Inupen ~qii.i~t.
,Val Ive a criirid a co re s pr-ray ch c k. va I ve a i-!op (uir.biI) ýit',y fi .....
HPG I due La flIi ;ddjust; lii'ii of a IM sn w itIchi. Aln (ii far(cilO t.71. '
cofrne wshl L qo 1o Khu-tr t o..d cssLhs cnens VABN rer e .. Lati
i ii i ou.' osm n fiiup S~e iai [ It 't tit'C I r...L ni itela I spjIc ~po gi [In
' ine I read unI iet1jt i t[ ilIdt AiC Q.01 W.F.We Li d aIbute min-l~
~ .~ a1 1( a dv on i fm I r.e In f: gomi 1 fi "I n o .4 tIll. u e mac InItoýiriemnpwr-mr 'vr Av O mii iih L of- hi fi r, aO s2!; 6)
~~ utp 'ofamtac~h shift w hilt Wian hoc ri y Lyo di r et-aliiinciii
~oftAheft: Lbmq ity sift Ie~rit'' 119 Lda ci rl, y iaou itL t1ii
soction acylviQ& Lit , o iaidonii hajjý .40,,'~~
~ Sb'eintnttothi;N"'RS~ itvit w'tm s'i ~ to 13F;N ,- finrthtr
a]iLi it as' w.er;' iiiove toie ei v \e n ifi andfý i n'j,' y~L; si fts AF
of-'.~ ;h6Q &WuI ie i. bi ut IoV,6f'. iiiinpow~oi- W~ i Itia Led .,t.
bc 0% 0%~L1 wth h~ o Iof=>40% / 0 C IN, wintem-
WE in:QpQ~srKZwho wpry o iginpiPiv phed"Il Kc
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A7095'
UNITED STATES COVERNMENT
• . >a: . .:'"' emorandum
TO R. M. Pierce, P
, ROM. K. W. Whitt, Di
DAT 'JUL 0 9 1985SUBJECT: WATTS BAR NUCLE
REGARDING CABLESAFETY REVIEW S
The Nuclear Safan employee conwho had identinaire. The coneinstallation, atation and enfoi
001 '85 0709TENNESSEE VALLEY Al
05 0JTHORITY,
roject Manager, Watts Bar Nuclear Plant, 9-169 SB-K
rector of Nuclear Safety Review Staff, E7B31 C-K. "
AR PLANT (WBN) - INVESTIGATION OF AN EMPLOYEE CONCERNROUTING, INSTALLATION, AND INSPECTION - NUCLEAR
TAFF REPORT NO. 1-85-06-WBN
ety Review Staff (NSRS) conducted an investigation ofcern at IAN per request from the Division of Personnelfied the concern from the employee's exit question-tern was in regard to the adequacy of cable routing,.nd inspection at VIBN as well as adequacy of implemen-rcement of QA/QC programs.
V.:.- . . . .
The NSRS investigation of the employee's concern substantiated theweakness in the area of implementation and enforcement of QA/QCprograms. Although the investigators could not substantiate the morespecific concerns, significant shortcomings related to cable sizing,installation, and inspection were identified.
The NSRS investigators held a discussion meeting with the appropriatemanagement members of OE on June 28, 1985, to finalize their commentson the factual accuracy of this report. It is our understanding thatan integral response is being prepared by OE for issuance concurrentwith this report. It is ainticipated that this response will addressthe planned corrective actions for resolution of the findings of thisinvestigation as well as findings closely related to this subjectmatter identified by other groups.
Although the Office of Engineering intended to implement a set of"corrective action programs" to rectify a number of significantdesign deficiencies identified by others as well as NSRS, the processof establishing additional evaluation groups, task forces, and con-duct of further studies with no substantial/beneficial end result wasrioted to have been largely ineffective. NSRS believes that highpriority should be assigned to the findings of this report. tor exped-itous development and implementation of corrective measures that areeffective in recurrence control.
This report contains six recommendations, the resolution of which isconsidered to be essential to the establishment of a justified posi-tion regarding readiness of WBN unit I for plant operation above 5percent power.
The findings of this report should also be reviewed for applicabilityto other nuclear plants, operating or under construction, and shouldhe reviewed for reportability to NRC.
'qL
L E. l
NSRS F1PlanBuy U.S. Savings Bonds Regularly, on the Payroll Savings
... ,.~.. ~ Irrs' Ah' ~-~-- - ~
R. M . Pierce
JUL 0 9 1985WATTS BAR NUCILEAR PLANT (WBN) - INVESIG(;A'ION OF AN EMPLO'YEE CONCERNREGARDING CABLE ROIITIN6, INSTALLATION, AND INSPECI'ION - NUCLEAR SAFETYREVIEW STAFF REPORT NO. 1-85-O6-WBN
It fyou ha3ve any 11est-S ions concernling the c¾)nhttnt of the i olort . Is east!contacL Mansour (nit ty a t. ext eltiori on2200 1n Knoxv i I If.
jfK. ~ (~4K. W. t~hitt
MG:WCSAttachmentcc (Attachment):
RIMS, SI26 C-KC. Bonine, 12-1 ;, ;It-KB. M. Cadotte, LWCnO C-K (w/i ,itt'ichm,,ntP. W. Cantrell, '1I2A12 C-KW. T. CoLtlte, Watts R,1ar NiC ITRC. W. Crawford, (,70 CST2-C. P. Dar Ii ntp, I750 (SS'I2-,
M. J. IuI in, 13Y') CUHB-C(• H. G. Parris, SOOA ('.ST2-C
001 '85 0709 051
TENNESSEE VALLEY AUTHORITY
'NUCLEAR SAFETY REVIEW STAFF
NSRS REPORT NO. 1-85-06-WBN
SUBJECT: INVESTIGATION OF' AN EMlPLOYEE CONCERN REGARDING CABLEROUTING, INSTALLATION, AND INSPECTION AT WATTS BARNUCLEAR PLANT
DATEOF REVIEW:
REVIEWERS:
APPROVED BY:
FEBRUARY 29 - APRIL 15, 19R5
2?I/DATE
RimPs, ýL24 G.K
&rn~-.. -. min4wfraflin -
TABLE OF CONTENTS
Index to Abbreviations and Acronyms ....... .............
1. Background . . ...... ................
II. Scope ................... .............................
I11 . Management Summary . . . . . . . . . . I ... . . . . . . .
IV. Conclusions/Recommendations ........... .................
V. Details .. . . . .......... . . ....... . . .........
A. Cable Design and Installation ProgramRequirements - TVA Program Documents ... ...........
1. Office of Engineering ......... .......... .....2. Office of Construction . . . . . . . . . . . . .
B. Program Implementation ........... .......... .......
1. Cable Sizing and Routing Program and Practices2. Cable Pulling Activities Program and Practices3. "Limited QA" Program Implementation ... .......
C. Cable Bend Radius . . .. . . . . . . . . . . . . .
1). Generic Applicability of INPO Findings to WBN .
E. Quality Assurance OrganizationVerification of Cable Program Activities ...........
I. Quality Management Staff (OE) .... ...........2. Construction QA Branch (OC) .. ..... ..........
VI. Documents Reviewed/References ..................
i
2
5
8
8
910
12
121828
30
62
73
7375
76
q
INDEX 'TO ABBREVIATIONS AND ACRONYMS
ANSI - American National Standards Institute
App R - Appendix R to 10 CFR 50
BEE - Bellefonte Electrical Evaluation
BFN - Browns Ferry Nuclear
BLN - Bellefonte Nuclear
BLP - Bellefonte Design Project.
CAT -m Construction Appraisal Team
CONST - Construction
CQA - CQAB - CONST QA branch.
CSCP - Cable Schedule Computer Program
DQA - Division of Quality Assurance
DIR - Design Information Request
DS - Design Standard
ECM&D - Engineering T Construction Monitoring and Documentation
EEB - Electrical Engineering Branch (of OE)
EN DES - Engineering Design (Presently OE)
EEU - Electrical Engineering Unit (of CONST)
EP - Office of Engineerinlg Procedure
EQC - Electrical QC IUnit (of CONST)
FCR - Field Change Reque:; t
FSAR = Final Safety Analyses Report
ICFA - Insulated Cables Engineering Association
IEEE - Institute of Electrical and Electronic:; Engineers
INPO - Institute of Nuclear Power Operations
(I,)QA QA(L) - Limited QA Program
MA - Modifications an(d Additions Instructions
M&A.- Modifications and Additions Unit (of CONST)
NEC ,National Electric Code
NCR - Nonconformance Report
NUC PR - Office of Nuclear Power (WYDN)
NV - Node Voltagi
OC - Office of Construction - CONST
4~4'
01) - OuLside Diameter
OE - Office of Engineering
OEDC - Office of Engineering Design and Construction
OQA - Office of Quality Assurraitce
[iMS - Project Management SLaff
PRM - Program Rtquirenent riManual
QC - Quality Control
QCI - Quality Control Instruction
QI' - Quality Control Procedure
QMS - Quality Management. Staff (of OE)
RII 7 Region ,1
R - Bend Radius (whi le pul Ii ng)
R - Minimum. Bend Rad.ins (while pn iill gpmrin
RT - Bend Radius (while training)
R1T min - Minimum Bend Radius (while training)
RG - Regulatory Guide
SEP " Special Engineering Procedure
SQN " Sequoyah Nucleir
SRI - Specification Hevi.sion Notice
T"ROI - Tracking, Riport. ing Opvn Items (Sy.;t eam)
WBIDP - Watts Bar Design Project
WBN - Watts Bar Nuclear Plant
;k
r
Iii
100
ivy
I. BACKGROUND
In January 1985 , the Nuclear Safety Review Staff (NSRS) was contact edby personnel from the Office of Construction (OC) with a potentialemployee concern regarding " implementing and enforcing QA and QCprograms at TVA's nuclear power plants. The concern was brought tothe attention of OC by the Division of Personnel who had routinelyreceived it as a conunent on an employee exit questionnaire from anex-employee at Watts Bar Nuclear Plant (WBN). NSRS agreed to investi-gate the concern at thc request of O.
"I,.
I'11. SCOPE
The scope of the investigation was bas;ed on a single telephone inter-view conducted by NSRS managementt wiit h the concerneied emp1oyee,, inwhich the employee expressed a concerii regardinug the adequacy of theWBN QA program for rout ing, installing, and inspecting electricalcables. This investigation was conducted to determine whether or not:
1. Cable routinrg was determined and approved by the engineering pro-ject to assure design criteria and FSAR requirements were met.
2. Cable instal lation was performed in the proper sequence, i.e.that cable routinrig was performed and ipproved by engineeringprior to construct ion craft installing (pull i ng) the cable,primarily to athieve separation criteria required hy TVA designcriteria and FSAH,
3. Inspection of the cable puill ing process was adequate to assurethat the cable was; pulled through the approved design route or if'the approved route was c 'o;ed, ain alternate route was determinedand approved by engineering prior to puilling the cable.
Additionally, NSRS decided to review the activities of OC and CE QAgroups to determioe the effectiveness cf. their respective verification
(i.e., audit and surveillance) programs.
During the invest igation, NSHS became aware of several previouslyidentified problems and issues regardiing the adequacy of some cablidesign and installation triterna and associated documentation. Theinvrstigators reviewed the resolution of these previously identifiedissues as they wore deemed to he very closely re'lated to the scope ofthis investigation.
Th# investigation began on February 28 and concluded on April 15,1985. The invest igators revviewed eng i nee ring, installation, andinspection specifications and requirements as well as evidence ofimplementation of the requirements. Interviews were held wiLh per-sonnel from the Electrical Engineering Branch (EEH), Watts Bar DesignProject (WBDP), and WBN construction site, and the cable pulling andinspection processes were observed.
IlM. MANAGEMENT SUMMHARY
Trhe NSRS nvestigat ion .ujbstant iated that t fh'r' w•v'r' si ylr f icant and
f rndamenta 1 prot) I ems with esabliiShir•g, impleme'nt ing, arid enforcingQA/QC program rerqi, iiem'nts for cablinK r LI"t VI :ties. The;l areas ident. i-
f i ed below, I nadequat or inconmpl ete dhesigrn standards, and/or :ori-
struction specifications as w'll as faiilure to responsivV'ly resolve
the identified p r(hbI em• s, hav (rest I te,1 it atn iinlhvtermi nate catIle
itsta I lat i on at WHN, . Thre ex i s encr o1 I Ihep c nitd i i io[:-, Will not
p)rovi de assuran ce that the cable syste'm wil he capail"e (f performingR
the intended' ftinctin!,' lhiring the life, of tLh, plant. for all postulatted
events and cond it ionrs.
These area(. of inadeqri,icy we're:
I Cable bend rni s re'qirirements.
2. Cable pull ti;io-l renj ir remerit.s anir! pract rIis.
3. Voltage drop aridl short ci r(-iit (i, rren t determirnat ion and veri fi-ca t o•n.
4. Quality ass:: anice organizat ion veri ficaLion of cble p'rog ram
activities.
S "Limited QA' program developmrnt 'ind impl!em'ntationr:
6 ,Management 'on t ro I and systems t , as s re that i d ent. if i ed p robl emswe• 'e revieowed for 1 a p I CAb i Ilit y t.o ,) N ,lii IL I in a. t ime I y mariner
The NSRS ilvest igat in ,lit d nrot sit);it ;i i at L b a ntp I n( ' spe c.ifi c conce rnsof the employee. Thr ifrver'tigat~ors determine', that cablh routing was
selected by OE and t he install at, ion were in the proper sequence.
I. Cable Bend kali iis Renju i rement.:;
OC was piermittod by OF0 to be;ndl the (ahlvs p•lr'mane'iLly to a radirsis
of one-half of values whicih in 19$ I were roi"cgrnized to be antindustry sLandar'! for minimr~m vailes Lo which a cable can be .permanently bent , t he reby form i rg bend.; sha rpe r than permi ited.
NRC in 1982 questioned the acceptability of al I Lhose cables thathad been permanent ly bent to one-half of the standard values at
WBN. OE and OC joiritly developod a pkiri of act.ion which for all
pract ical purposes ;aciCepLed the inst a I I d c ond it ion nf the cablesalthough a nuumber of design standard drawings, and a construction
specification were revised to delete the allowable excessive bendradius and inicui hd, industry standards criteria. 'rhese dlocuments
were released in late 1983 and early 1984.
However, much of Appendix R cables as we'II as other cables forWFIN unit I pulle IdI and acc(-pted in a croridance' with NdJC PR proced-
tires may have been installled wit.h exccssive bends. The NUC PR
2
a
1)proce(Iure w;rs not I. rr c ted to l ,e I. v tv I i on.f -h i fcriteria untit IM r. rcIr 1985. Al though O and 0Cs f inalLion ar-cepted thie instal (d condti t ion of th(esoe cablesbased on "OE/ OC devel oped" v;, I ties, NSRShas sAer inis iquestlit! valid(ity of these "OE/OC doveloled" v; lies. 'rhesideveloped" val ies are riot siil)ort.ed by suif Icient just ifi
Bendi rig cables to vi IUCs l ess tihanI tit- he n'1.st ry st andar.'has the potent ia l of i rrevers itile-e Adverse' ifocts on tspiral wound shielding and caile insulation rt-sulting iit. ion of the t ua it i ed cable life ( f nder norm.. I condi ticprobab le acc, I veratLed a f fects due to ha rsih e.iv i roimentaI so worthy to note that Violat ion of industry standinstallation of these, cables could potrentially, invalid,,ivronmental qualification certification of the cahle.
2. Cabht. Pril 'rension Requirements and Pract ices
Construction Specification G.- 38 has tot defined the .mecalculating ina ximim a I lowahl' 1 t1'.,s ion for mI t i -cable pthas it. f i nu II y :stab 1 i she!d the method of pu I i ig mul1utilizing a break link. Also, the industry has consideside wall pressure as a limiting factor for cable pullingties for many years. Hlowever, OF: has orl.y recently acknithe importance of this paramet.er and plans to incorporate(-38.
rad i i:;idi s os . . .
at WBiNt ions one "OE/OCcat. i onsi
dI vaIluithe cable.itI ed r .,luons with
i t i slards i nla t e t he
thod oftills nori -c(abl es ,:'•
:red theact ivi -
owleedgedit into
The actual method of calculating maximum allowable tension, themethod of pul]ling, and monitoring have been determined, by theinvestigators, to he inadeqrrate to ensure a cable pull is suc-cessfully completed without insulation degradation. Addition-ally, cables have recently ween puitl ld at WHN based on an FCRthat has not been finally approved, and it is understood that itwon't be approved totally. NSRS has quest ions about the validityof the FCR mCLhod irregardlesss of its final disposition'by OE.G-38 has not addressed the inspection requi rements and document.a-tion of multi-pulls ai; well is pull-backs. Fai lure to ensurethat maximum allowable tension as well as side wall pressure isnot exceeded in any cable pulling operations increases the-poten-tial for cable damage (insulation degradation) which is notnecessarily dettected visibly or through testing. InsulationdeRgradation can ultimately cause cable failure which will subse-quently prevent sLartup/running of equipment. Improper installa-Lion of cables could also potentially invalidate the environment-al qualification certification of the cable.
3. Voltage Drop .,nd Shot.tCircui.t Cr'.rrnt D2eterminat.ion and Verifi-cation
o There are no indi c.'t i on,; that. LW has perlornied short circuitcalculations as '" I" as voltage drop calculations for level3 cables ( inve r; )jy..,tor.:; did not piursiue levels 4- or 5).
o The automated vah:Ju sizinig program which performs voltage
drop calculations is based orn O.)s estimate of the length
½'
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and not the .ctua I inst al let li.ngt h , aind o:nsidvrahle dif -ference is very possible,
Disregard for the short circuit current factor can have a detri-mental affect leading to shortening of nsul at ion life and stibse-quent cable failure, whereas failuire to ,nsure proper voltagesupplied to the equipment. will render the operability of the
• equipment, indeterminate under the worst coultit, ions.
4. Ac t i t yi_ýss.,•a.._ riz2nizati.9.Verification o. Cle P r&ýrTActivities
In addition to the invest i gat ion of the rout.i ip,, insta I la tion,and in, .pect iou of cables, NSRS revi ewed the h;,pl i cable QA organi -
zaLti on act ivit irs in their respe ctive areas. 'rie inivestigatorsnoted that the OE QMS had respionsihiility for QA verification ofWBI)P and EE. cable design act ivi ties and t hit OC CQA!I had QAverificat ion responsibility for cable instal lat ion and inspectionact ivities.
The OE QA veri ficat ion program for electricial design activitieswas determitned tt- he irnadie'qiat #' AuditS I ai led to properlyreport def iciericies, require responses or e:ffective resolutions,and lacked sufficient scope and depth to meaniigfully assess piro-gram adequacy and effectiventess. The empha s s of audits andsurveillances during performance appeared to h,, on administrationof documents rather than on process capabilities and results.
The CQAB. surveillance program was effectively identifying prob-lems with the cable program, but. was inconsistent in assuringthat appropriate, effective resolution was accomplishled, therebyproducing ineffectiveness of the conilucted surveillances.
5, "Limite ...Q! P.'. aa['r!.mar, a n ll. .tt Irion
Office of Erigine ring and Construction Program' RequirementsManual (OEDC PRl) was supersd.d by the Nuclear QA Manual (NQAM)effective December' 31, 1I84. The OEDC PRI had provided a repre-sentative listing of features that were considered to be limitedQA. This representative listing was not incorporated into theNQAM. Presently there are two features that are considered by OFand OC to fall within the limited QA program at WBN. Other thanthese twospecific feat•ures, the investigators could not identifyevidence that feat nre- s' ecific p rogram.; or controls had beenestablished or implemented, therefore concluding that the limitedQA circuits for other than these two feat ures were treated as ifthey were non-QA circuits,
NSRS believes that the phi losophly of a "limited QA" program wasan attempt to recognize that special management controls werenecessary for nonsafety-related system teaturtis that were impor-tant to safety or plant reliability. However, the development ofthis concept into a program which not only identified and commun-
.ica;.ed requirements as well as the features to which it-applied,but also implemented the controls, was unsuccessful.
4
IM!
V ~ /
6. Management Cont ry and System11ý1 to Assure that lclefLt/i flied Problemswere Reviewed. fr._•Ap.. !l.icaiI i.t _y•o W.tN Un itL I i n .1 Time ly Mariner
The INPO had id!ent fi ed proh - )ms with the desi gn and installationof the electrical systems at 8ellefonte Nuclear Plant (BI.N),which were considered to be very serious by OE. The BEE team wasformed to determine the adequacy of. the electrical systems at BLNas well as the extent of the INt'O findings. vi BEE team sub-sLantiated the IN'O •indings atd de Itemined that BIN electricalsystems did noL meet. the liceiu:;ing recli xerement., Ss bsequent I y,an -OEDC team deve(lope.d recommendations or plans of action which,would have eventinially corrected the ihdentif iedt findings at OLN,This OEDC t-eam also determined that the majority of the BEEfinding h .• no ',,eric applicability to other TVA plants. Althoughthe proposed, r;c,mmiTvendaLtions.; to correý't tht' identtified p1roblemswere to be applied first to BL.N, no consideration was extendedfor applicahi )ity of the corrective measure to 'BN unit I at thatti me.
The 4'1SRS .vest igators hel ieve that a generic applicabilit)reviev of the INP( findings as well as B.EF team findings shouldbe performed for WBN unit I prior to power escalation above the 5percent level. This determination was principally based on thefact that tL,, OE program that, established and controlled engi-neering tasks of basic discipline-nature was not unique perplant.
It is worthy to note that the invest igators independently andwithout prior knowledge of the INNPO and IIFF fiidings had identi-fled a number of similaiý/identical problems at '/BN.
IV. CONCI,USSIONS/RECOMMFNI)ATIONS
A. 1-85-06-WBN-Ol, The Adequacy (if the Dispos;it ions for I dentifiedCable Bend Radius Problems
Conclusion
The investigators determined that. there was not sufficient manu-facturer's documentataon/jasstification/test. data nor engineeringbasis (proiided b.,, OE) t.o substantiate the final dispositionsdocunmented for NCRs or establishment of or R Tm values formulti-condacctor cables.• FurtLher, the iavilahle ?n~ormation, aswell as OE)C-develope!d a ccep)tance criteria for the samplingprogram used to justify t~he a3.-installed conditions, lack engi-neering support (see section V.C for details).
Recommendat ion
Establish Values for RTnn as well as RP Tin that are fullysupported by manufacturer s test data. Alply these values for,dispositioning of nonconformed items . As appropriate, samplesize should be selected at. WBN unit I for Class IE cables, then acontrolled inspect ion condulcted based on fully supported Rpmin
'5
"I
and R v1 Vallu :; .1u1, the -vslilt l . t, 0 .) o t,, 1e( ;i a ale y of ', .V-.I-as- instahd Iab , s. If valiat ion of the results of the a
I ing program Ia Is to adequately .just fy th , ,•ts- Iistal led cond i • . '
L ions , then Lthe devel(pment of a t orma I i nst.' rv ice su rye i I ance/,inspeCtion program sho, Id he cotis ider,(t Al I shortcomings of the
reviewed materi .11 ,!; discussed in this report should he consid-.ered and proper resolutions addressed.
B. 1-85-O6-o •N-O2, The Adeu(-acy of the. 1 Pr. g rim for Cahle.e ,. ,g.. nA..i.v Ac tv t es.2
Conclusion ,
The OE and PC':s establ ished aind dociimiiteid liir-xram was determinedto be inadequate to accomplish the cable p ll 1 ln ivit ies. The - "pas' and present programs have been i nade(uqat f, incons istentand i i viol ati on oif t li accept ,d i ,nlu:;trv r I ;tindards antl pract ices-(see sect ion V. IB2, .3, and V.C for details)
Recommenda t. I, o"
OE ma nageeri t cr it , IId revi t- G - 3T 8 ii1t G-40 tI r rrpora te reso ju-t. ions to th. i d nt if ld p, rob Ih, i .,, sd is, thids report andsubsequent I y WI"N OF, OC ,ant JUC P" managentcrCt PR'oij I d revisse thefirelevant OK documenits s wel I i as OC a:t NIT, PR procedures. Thefinal adequacy of the present calt t iIsa I at. ion should then beevaluated per revi sod acceptance crit,'ria A simi lar samplingapproach , as d i s cus sed in t he. ro'crmmenda t on sect ion for[-85-06-WBN-()I, shoul d he crsI, Ivred . If ,va luat ion of theresul of th,, sampling program Iii Is to adequately justiIy theas-installed crndi tions, then the du~ve I Opmetint of an inserviceinspection program shouild he con;iderd. .d
C. I-85-06-WBN-03, Short Circuit arid Voltage IDrop Calculations
Cornclus io. .
The investigatnr:; determined t.hat evidence to suhstlant.iate per-formance of vol ta ge' drop andI short ci riii t calculations forvoltage level 3 power cables was riot avai lahle (see section V.B.1Ifor details.)
Recorimenda t i on,
OE should perform short ci rciii t and voltage ,irop cal cIu I at ions forthe level 3 power circuits t o ens:ure the adequacy of the size ofthe i ns ta I lot l ca h I e to per form i s i nt ended I inc t ion: -
" "D. l-85-06-WHN-O4, The Veril_ ion .r.g ,a-,, m Ineffectiveness
ConclA us ion
The OE QA vori ficat ion program for olectrical engineering anddesign act ivities wis deterininil to he inae•.quate (see sectionsV.E. 1 and V.E.2 for LetaiIs).
6
------------
Recommendat ions
1. OE Q1S should plan, schdule, and conduct audits and sur
veillances that . encompass the verification of technical
issues and assure adequacy of programs as well.as resultsz,
achieved rather than administration issues. .•
a V
2. OC QAB at W]BN should perform Limely follow-tup to ensure that 74'5.00
effective corrective actions have beeni taken. ...,..e.iL o .an Do u en e .V s'"¢,
1-85-O6-W4BN-05, Underdevelopment of Establised'and Documented IF%Liite A Pr ncorporatehe EstabliSLId.... .d .. ... .
Limit ed OAPro&KSram 2,9
Conclusion -****
The implementat ion of the limited QA program as established in .
OEDC-PRH-2QAI-2 was determined tu he inadequate. Also, the NQA -
.-.was determined to be inadequate in address.ing the limited- QA
program .s established by superseded OKDC-PRM-2QAI-2 document.A.7•
(see section V.B.3 for details).
Recommendation
The Divison of Quality Assurance (DQA) should identify the re- ... '..
quired "special controls" applicable to systems previously. iden :
tified as "limited QA' in the NQAI. Appropriate line organ ".
zations should incorporate those requirements into the- OE,- OC,. ...;".
and NUC PR procedures for implementation by the appropriate-::'%:
offices. -In view of the fact that WIN had recognized security
and fire protection as the only two systems for limited QAc .n:'•
sideration, OF should perform an evaluation to ascertain ;the,
impact of not implementing the established "limited QA".programon the other systems identifLed in OEDC-PRWi-2QAI-2. The purpose P"¢":"
of this evaluation should be to determine the extent and depth ofj
the impact on the qual.ity and reliability of "limited". QA-fea- 7 ..
tures contributions to the safety of the plant.
. -85-06-WBN-Ob, Timely.and Responsive Corrective Actien:; for...
Resolution of Identified ProblemsF
P-, It t. n
The NSRS determined that OE has been very lax about resolvinga a. I
longstanding cabir bend radliu•s problem. It was determined that I"n.the progress made toward resolution of problems identified by A,.
.INPO and BEE has been less than adequate. The nature and magni-7
tude of findings of this report as well as INPO and. BEE team '"..report ..fin ing
report findings applicable to WBN unit 1 are of sufficient s ig-.-:
nificance that an immcdiate comprehensive evaluation. to ensure -
_that WIBN unit I meets its licensing requirements is consider'ed
necessary prior to exceeding a power level of :"rcent ,"M
7N
..~ ,-..~
i7 I 171171MITWIM
V.v
Mo
, to. -"
'... . . . 2 "
-.
' 2 :• - , . .
The• final OK Action Team report wliich was intended to. authorik, e p,?C
,."i"initiation of corrective actions/studies has not , yetj been
approve'd. Formation .of. task forces, eva luat ion .teams, etc.,,i
while often valuable in determining the scope and extent of:-:
problems and necesssary resolutions, have also, so far, resulted.,?::
in postponing the implementat ion of the 'necessary actions' that
: are required to correct the 'problems, Much effort and time Iare
expended on the administration of reviews, studies, and verifa-i
tion of problems with less effort on the f ina l corrective act ion .
implement at ion of. the problem resolution p)h;ase. (see ..sictiaons) .
v.g.2, V.C., and V.0 for details).
Reconmendation
The NSRS recommends a comp rohens i ve eva I opm ti cnn of i indi ng, of
this report as well as those of INPO and BiEE reports that are "'
applicable to WRN unit 1. The purpose of this evaluation should'
be to determine if these findings, individually or collectively, -""N--
are violations of WBN licensing requirements. It is recnmmended:"i!-
that thi.s ova luati on be conducted by a group i nependenL from OE ".a"'
or OC organizations. -
*It is also recommended that nu's Action Team recommendation, be,
placed on the highest priority for WBN unit I. W no
DETAILS
A. qable DesiCa and Installation Program Require:ments -TVA Program
Documents ..- , 1
Design ciiteria and requirements for the WI3N electrical distri-"Q
bution system were identified in the WBN Final Safety AnalysisQ
Report (FSAR), sections 3Wand 8. These sections specified that
the electrical systems woul.d be designed ano installed in accord-:I: ly
ance with selected appropriate industry standards and regulatory V?
criteria for assurance that the systems vould function as in-
tended for all postulated conditions., To implement these. commit-
ments for cable systems, OE developed office- and branch-level--:,, f
procedures, specifications, drawings, and design standards. `'"
, Among tho:.c considered pertincnt to the invest i gation and re-,
viewed by NSRS were: General Construction Specification- G-38, :..
"Installing Insulated Cables, Rated Uip to 15 KV"; EP 3.10, 'Design >,
Verificatiorn Methods and Performance of Design Verification";EP ',14.n
.4.03, .'Field Change Requests Initiated by CONSr'; EP 4.06,0"Field 3- "-.ANY".-
Change Requests Initiated by NIJC PR"; Engineering Project EPs
43.13 and 43.19 nn Use of cablv and conduit schedules, respec-. '"
'..tively, electrical design standards (VS-E) series 12 and :13,an .3
-.. various conduit and cable drawings. '
The Office of Construction had developed a program for controlof- --
-. 'conduit and cable installation at WIN consisting of QAproceduresjk,.
30- and program policies defininm OE/OC design change interfacesand ,i-' -. 3 KU;
requirements for inspection of work.. The construction "projectV, "- "
'in order, to implement the installation and inspectiond;'require-- j
8
Merits, had dlve.l oped and i•suied QC i nut ruct i ols and procedure%
addressed inl det:aiI in sect ion V.1.
I Office of Engineerin.
OF was bas i cal ly resp ns ible for dev elopiing and ma iLtaini1iR
a progralin Lo assuIre t he des igni , n'iI procuirrement of cable
systems was performed in accordanct . with conti tments t:,estab) i ;hed i nlustLry standardIt.s such as.' tIose ofm IlEE. and
I CEA. Two groups in OF , EEB and WfID1', s ha red re spons i i I i ty
for selecting ani .siupport in fg les in I hase , esLabl ishing
design ,ind installatinn criit.eria, purchaising material, and
verifyi,,g design adequacy. OF. was al. so to translate these
criter init speci f i cat. i :o , drawings, andI other e1g iiteer-
ing docuennt.s used hy OC to assu re, the Insta I latioI of cahle
systems w,.i , per fo rmed in ,icvordance, with the estab I i shed
requi rement:s. Bas ica I ly a I tihough a close interface
exi sLed, FIEB estatl ished requ i rements and purchased cable,
and WBIW designed the cable systems for actual installation.
Among thf inimerous considerat. ions .ind. calcu]lations necessary
to assure the ability (if the cable to perform its intended
function for all design post.ulatel cond itions were: (a) the
routing of all cable to assure physical separation of redun-dant class IE circuits, (h) qualification of the cable for
use in harsh environments, (c) determination of the cable
type arid size to supply adequate power, i.e., current carry-
ing capacity or ampaci ty, (d) the length of the cable from
source to load t.o assure both adequate voltage availability
(voltage drop) and ?pr1opriately responsive short-circuit
protection, and (e) methods of install ing the cable to
provide assurance that neither the insulation nor the shield
would be damaged. These- install at ion c.ns iderat ions in-
cluded: (I) the maximum allowable tension applied to .a
cable dluring pulling, (2) the maximum allowable pressure on
a table as it is pul led around hends to reach its installed
configuration (widewall pressure), and (3) the maximum radii
to which the cable may be forced to bend either during
pulliing when the cable is under tension (R P) or during
training (RT) when the cable is in place and no longer.tinder.tension but may he bent. to allow terminations.
Integrail with these cons.idierat ions was the design of a
complex raceay system to support and p]roLedt thie cable
which were to provide thi physical separation of safety-
related cliss 1i cables.
Primarily, to perform cahl, rout ing, (^E Project Controls
Section had developed, ;i computer program designated as
"CSCP" in this report. This program had the capability,
depending on the cable's voltage level and other inputparameters, to size particular cable:s as wel . as route all
cables, which were uniquely identified. The logic of the
software was such that t. he computer wo I d automat ica 1 ly
6
9
p
MAN
soy"& vK..
route a cable via the shortest raceway path, whichavoided
violating separation crit eria. Computer routed cables were
then "released" to construction via, an OE/1OC computer pro-
gram interface, whe reby the OC Engineering-Construction
Monitoring and I)ocumentation (ECM&D). program "read" the OE
cable schedule and printed the cable pull slip and. "from"m
and "to" termination slips used by OC to install the cable.
Any routing pr-oblems encountetred during pulling were to have.
been referred to WBDP for resolut in. Ulnder no circum-
stances was OC to determine the routing and install the
cable without prior approval from WRDP.
The application of a QA program to cable (and raceway) was.
required by IOCFRO5( and speci fied in the 'SAR, P&., . and OE.procedures. The eWtent_ of QA program controls applied to
cables depended on the function or location of the-Cable)OE identified class IF cables, those requiring the total QA
program application, t.o OC for installation via the ECM&l)
pull slip. The pull slip specified total .routing in divi-sional raceway (Train A or R) and required independent QC
verification of all required quality attributes, includingrouting. NoWclass IE, or nonsatety-related cables, were
identified to construction via routing in nondivisionalraceway and Aid not require any independent verification.
"Associated" cables (nonsa fety-related cables which wererouted in divisional raceway) required QC verification.,ofrouting andI cable type. A fourth classification, "limitedQA," or application of partial QA controls was to have beenapplied to nonsafety-,related cable systems subject to regu-
latory requirements or determined by TVA to serve secondarysafety ftuctions or be of special importance to fulfillingthe TVA mi~ssion, OE-EP 3.41, RI dated .April 24, 1984,"Limited QA Program Application," identified EEB as respon-sible for specifying both tvhe cable systems subject to
limited QA and the specific applicable QA requirements viathe Q-L~ist. and appropriate design documents used by OC forinstal lat ion.
-sky;`&ASK
A5A
2. O ffi.e of Cnstruction
OC WBN was responsible for establishing a program to install
and i n sp:ct the cabl, systems des ignd . by OE. The WBNiorganizat ions primarily involved in cable installat ion werethe Electrical Engineering Unit• (EEIJ) A and C, Modifica-
tions and Additions; (MFA) Group, and craft electricians.The Electrical Quality Control (EQC) Unit performed desig-nated inspections.
Cable installation was to have been performed at WBN in
accordance with requirements of QCI 3.05., R2 dated Februa-.ry 27, !985, "Cable installation," or in accordance with NUC
PR procedure MAI-3, R3 dated February 14, 1984, P.'Installa-tion and Inspect ion of Ins"Ilated Control , Signal, and Power
• ]i"-: ,"i
I()
i
Into,
BY
ArCables , if the cables; Io be i n:ta I led were for areas a I -
ready transferred to NUC PR. Installalion of most, of
Appendix R cables in unit I was performed by OC M&A Group.
Inspection of cable installation was to have been performedper QCP 3.05, R7 dated February 27, 1985, "Inspection of
Cable Installation," by EQC unless the cables were for areas
turned over to NUC PR. That being Lhe case, then NUC PR
site QC personnel inspected cables to the requirements ofMAI-3.
NSRS investigators reviewed procedural requirements, ob-
served installation and inspection of cables, interviewedcognizant EQC, EEU, M&A, and craft representatives and
supervisors, and reviewed associated documentatLion .and
concluded that the following sequence describes the generalinstallation and inspection processes for cable at WBN.
a. The OC ECM&D program generat .ed a three-part form for
each individual cable to be installed once the routehad been determined by the OE WBDP. The first sectionof the form was the "pull slip" which contained, infor-mation such as cable identificaLion, the approvedrouting including conduit, the estimated length of thecable, the allowable pulling tension, and the qualityclassification of the cable. The other two parts ofthe form contained information for terminating thecable at the "from" and. "to" devices.
b. The pull slips were issued to the crafts by the EEU inwork packages or by M&A in workplans. These plans andpackages with the pull slips constituted authority forthe cable installation to proceed.
c. Craft personnel walked the prescribed route to deter-mine the approximate length of cable to be pulled andidentify problems, if any, with the prescribed route.
The craft woul.d request issuance of required cabletype, and depending on the quality classification ofthe cable, the craft. would cut and install the cable ornotify F:QC for inspection.
d. For cables classified "QA=Q," corresponding to IEEEclass IF cables (safety related), an EQC inspectorvcrfififed and documented the cable type and reel fromwhich it was to be cutt, prior to cutting. The inspec-
tor also checked the prescribed route for problems andwitnessed the entire pulling process for conformance torequirements. .For cables classified "QA=P," corre-sponding to nonsafety-related cables routed partiallyin divisional raceway, EQC verified the cable type andwitnessed the pull for conformance to the prescribedrouting only. For cables classified "QA=L" (limited
KOK 4":
ýA
Al, on
II
J
............ . ................
QA) and "QA:N" (nonsafety r;elated routed in nondivi-sional raceway), EQC inspection was not required by.QCI-3.05 or performed.
e. When routing problems with the prescribed route wereidentified, either during pre-pull inspections orduring pulling, the appropriate site engineering uhitiwas notified for disposition. Routing changes weremade on the pull slip in accordance with QCP 1.13, R13dated October 13, 1984, Pr.eparation and Documentationof Field Change Reqjuevsts." After teleph,)ne approval ofthe routing was obtainted by the site engineering unitfrom the WBDP, then the modified pull slip was returnedto the craft for installation. Thet original cable, ifpartially pulled, was either pjwlled out or was cut off,designated as a "spare," and left in place.
f. The relevant information for the completed pull wasdocumented on the reverse side of the cable slip by EQC(or on the MAI-3 data sheet when inspected by'NUC PR
QC) . This included recording of the tension monitoringdevice-, measured bend radius, actual cut-length of eachcable, and applicable revision of QCP-3.05 as well asQC signature and date of inspection. Subsequently thepull slips were filed as a life of the plant record and'the ECM&D cable program was updated to show that the'cable pull was completed.
Investigation of how the above-described design, installa-tion, and inspection processes were accomplished and how theprogram had evolved revealed that several problems had beenidentified in the past by cognizant. organizations. Some keyissues remained to be resolved, and initial correctiveactions were found to have not always been adequate as thefollowing sections indicate.
B. Pro ram Im lementat ion
I. Cable Sizi'_ and Routi_Prora.m..and Practices
To investigate the employee's concerns regarding cablerouting, installation, and inspection, NSRS reviewed themethods by which EEB and WBDP assure the appropriate designcriteria are satisfied and actively accomplish routing ofall classifications of cable.
The investigators reviewed principle OE documents control-. ling and relating to Cable Schedule Computer Program (CSCP),as well as ECM&D programs and subsequently held discussionswith cognizant OE and OC personnel, the outline of which isas follows:
P",
4,,
'A"
12
a Cable Sizing and Eval-iuat ion
(I) (SCP(2) Voltage l)rop(3) Short-Circuit Currents
Sb, Cable Routing and Evaluation
.(I) CSCP(2) ECM&D(3) Inspection
c. CSCII Verification
a. Cable Sizing and Evaluation
(1) CSCP
The CSCP has the capability to select the proper
cable size for voltage levels 3 and 4 if provided
with the temperature, ac/dc voltage and ,ampere
r e qu irements for the particular circuit. The
program has the capability to perform the voltage
drop calculation when maximum voltage drop.value
for that particular circuit has been provided in
addition to those parameters listed for cable
sizing. The CSCP was limited in performing the
voltage drop calculation for voltage level 4
cables only. Voltage 4evels are defined as
follows:
VI - Signal cables for thermocouples, strain
gauges, thermal converters, and other signals. that
are 100.millivolts or less.
V2 - Signal cables for input to and output from
the computer other than thermocouplcs; instrument
transmitters, recorders, and other~signals 'greater
than 100 millivolts, tachometers, and indicators;
rotor eccentricity annd vibration detectors;.
shielded annunciator cables used with solid state
equipment; and CAP (codes, alarms, and paging),
cables for source B system.
V3 - All alternating current (ac) and direct
current (dc) power cables of 250 volts or less
that carry less than 30 amperes, CAP cables for
source A system, and all other control cables.
4
V4 - All 4 80-volt power cables and all ac and dc
power cables of 250 volts or less that carry 30
amperes or more.
VS - All 6900-volt cables.
13
_71 I
( 2:' ) V o' I t a g_D.. : . .3 r o p1 .
DG-E12.7.2, RI , ,'Cab Ie Sched lt Ic Devel opment ,."
described how the deSigners were to initially size
the cable and sublsequent ly, after the cable had
been routed, to perform the volt~age drop calcula-
tion to ensure the voltage drop did not exceed the
NEC paragraph 210-19 at ftull load.
Di scussions with WBI)I pe rsonne I re veal ed thatvoltage drop calculat ions for voltage level 3
power circuits were eit bher done MIut not documented
or not done at all. Thi investigators did not
confirm whether voltage drop calculations for
voltage levels 4 and 5 were performed and docu-
mented for those cables that were sized manually.The BEE findings (discussed in section V.D) also
had confirmed that these calculations were not
available for voltage level 3 cables.
It was noted by the investigators that thosevoltage drop calculations performed by the com-
puter, or manually if done, were in fact based on
the design projected/estimated length and not theinstal led l.ength. This subject is further de-tailed in section V.B.1.b on cable routing. : Thesefindings were also substantiated and confirmed as
discussed in section V.D.
Voltage drop calculations basedl on the installedleugth of the cable will indicate whether proper
starting voltage is being supplied to the equip-ment. Such engineering calculations will provide
evidence that the equipment will be operable Under
the worst electrical conditions.
(3) Short-Circuit Current
• .:• . .': *, , {-•
... ... ... ... .... .. ... ... .. :
,ý.<
X.
The designers were also directed to ensure thatthe conductors were sized large enough to carry
the short-circuit current I long enough for the
protective device to trip wihhout qufficient heat
buildup, which may damage the cable insulation.As the result of subsequent discussions with OE
personnel, the investigators concluded that short-circuit calculations were not either documented or
performed for voltage level 3 power circuits.This problem had been identified earlier by, OE,but resolution was pending approval by the OEAction Team (disc'ussed in section V.D).
Electrical Design Guide DG-EI2.6.2, RO, "Selectionof Conductor Sizes Based on Fault Current
Criteria" provided the means by which one could
14
C-
OlfeT.s
calculate Ie for low and medium voltage .level
power cable,. This guide noted that "failure to
determine the minimum allowable conductor, size'
based on'the criteria included in this guide means
that the thermal effect of circuit currents are
being disregarded. This can have a number of
detrimental effects from shortening of insulation
life to permanent damage caused by generation of.
voids under the insulation, which can lead to
subsequent cable failure." This guide also stated
that I consideration is necessary when the fault
duratiOn and short-circuit current magnitude,
rather than voltage drop and load were predominant
criteria. Again the investigators did not confirm
whether short-circuit calculations had been per-
formed and documented for voltage levels 4 and 5.
b. Cable Routing and Evaluation
( ) CSCP
The designers received cable routing cards after
the cables were sized manually or automaticallythrough CSCP. They would indicate the "to" and
"from" routing of the cable for the points of
entry and exit from the cable tray network and
then the routing.program would select the shortestavailable route throughout the tray system net-
work. The tray system network had been, designed
to maintain the voltage level separation as well
as "train" separation aldd as such were uniquelyidentified both on the physical drawings' of the
tray system and actual tray installations. Cables
were also physically identified with unique iden-
tifiers that included voltage level designation aswell as train designation. The physical drawings
detailing cable tray network had been reviewed
independently and approved for issuance.: The
cable tray network information that existed-in the
CSCP was based on the physical drawing and thereby
investigators concluded that due to the cable tray
network identification system and computer codes,there was sufficient assurance that the cable
routing program was adequate although the formalverification of the program had not been conducted
arid documented. The investigators also determined".
that when consiruction forces could not pull the
cable a:> routed, they would utilize the.approved
process of calling the WBDP personnel for alterna-
tive route and document this accordingly.
,AQ~
'~"~5)~
.~
15
F
II
. . • ,- :i,.: , :, 4
(2) ECMl&I
That portion of the FCM&fl program that generated
cable pull cards utilized the CSCP of OF for the
generation of the pull cards. Cable pull cards
could not have been generated unti I OE had re
leased the cable routing and WBN had completed,,,
the installation of the designated raceway, until
recently, when the program was changed.: to allow
generation of cable pull cards as soon as routing 'ww'Is~~~ idnife by .11 led
ws idet if ied by 0;. rThe investigators concluded.
that this change was inappropriate and .contrary to
the original intention of the program and . in-
creased potential for allowing cables to be routed
in raceways that were not originally intended in
the routing, by use of the FCR. This situation'"
could potentially prematurely fill up certain
"ections of the cable tray network. Discussion-.with WBN personnel did not conclusively identify . .the benefits this change could have brought about L'`
other than to increase the amount of cable actual--'-- .
ly pulled. One individual interviewed stated that
elimination of QC inspection ot raceway prior to
cable pulling was approved due to "Production
Pressure."
The ECI&1) program, aside from providing cable pull
cards, also maintained an inventory of. cables ,:.
pulled as well as installed footage .(i.e.,..cut. '. '. Y
length) for each cable. The investigators learned
that the actual footage of installed cable per.
circuit was approximately 12 to 15 percent on the
average longer than the CSCP estimate on which the
voltage drop calculation (when and if performed)
was based. Although the actual cut length of.each
cable installed was determined to be recorded in :
the ECM&D, the CSCP dit] not examine this value to !1
ensure maximum voltage drop had not been exceeded-.,-? -
thereby ensuring the adequacy of the cable. size.
It was also concluded that the CSCP did not auto-
-7
1a10% .aLy vrwY Oy VULgC urop for Lnose caDieSthat had been rerouted, In view of the fact that
the average installed footage was longer than
estimated footage and in conjunction with uncer-
tainti.es regarding original voltage drop calcula-
tions Ias discussed in section 'V.B.l.a.(l) 1) the
investigators concluded that the actual installed:,.,.,,.:lengths.should be verified to have not resulted in
exceeding the maximum voltage drop allowed, and
that short-circui.t protection remains_ adequate.g
I[nsnect ions . .. >i•,(3)
-7.-n=snections. _ .',$
WBNP QCI-3.05, I0, "Quality Control Instruction o .n
16
.. ...............
-'na
C
• ... . , L
for Cable Installation," defined inspection re-
quirements for di fferent. classes of cable as
follows:
For QAzQ, documentation of all cable
installation inspection criteria includ-.,
ing the termination was required.
For QA=P, inspection and documentationof the cable type, routing, and sepa~ra-
tion was required.
For QA=L, inspection in accordance with
limited QA program was requi red.
For QA=N, no inspection or documentation
of any sort, 'w'as required. .-
The QA=Q, P, I., or N field had appeared on the
:able pull card recently based on the identifical
ion process by WTIN personnel. The investigators
•oncluded that:
a) Although there was a reference to the limited
QA program, the only systems considered to.be
limited QA at WBN were fire protection. and
security system.
QC defined the circuit classification such as.
those for QA=I, without OE verification' of:
this activity. Insofar as the inve'stigatorsOcould conclude, OE had, not established.'a
verifiable method of designating all QA=L
circuits for OC. This subject is further
detailed in section V.I.3.
b) QA=P defined those nonclass IE cables that
are partially or completely routed in class
IE raceway system. Regulatory Guide. (RG)'
1.75 established the requirements, for,: the
associated circuits to be identical. to:those
as class IE circuits. The investigators
reviewed NCR 5465 RO, which had identified
many associated cables that had notý been
properly identified, inspected, and document-
ed. It was as the result of this NCR that
WBN initiated identification of associated
circuits as QA=P. Although this was notrecognized and/or acknowledged by WBN prior
to February 25, 1984, the investigators
concluded that this same concern wasnorigi-
nally raised by the NSRS in a memorandum from
IH. N. Culver to J. W. Anderson, dated Septem-
ber 15, 1983 (GNS 830916 050). This memoran-
dum referenced EEB memorandum, discussed in
17
0
-- a.,5.
_,,777 'ý,74777y
+"'":'++.•t?..+,:o.t .. . . "/sect i on V.0: suhsectk o" 11 which foib"al l
•L:~p!,,t,.,:.practic'al purposes in iL i a.Ily ( I) recognized
• :: "•: .. i : • ,.: :: v ... t h e l a c k o f a p p r o p r i a t e t r e a tm e n t f o r a s s o c i -
... ,,.,, ,:. /,,.,• "a~ed circu~its as well" as (2) the needed re-
'.::' t .q u irem e n t . Ilow e v e r , 'a c t io n to c o r re c t: t h is
S•...omission was not. taken by WBN management
.• , :. '-: :. . n i l N C R 5 4 6 5 w ,a s i s s u e d o n F e b r u a r y 2 5 ,
... -,.::,._'1984, roughly eight months later..YrAsain,
. -.... although WBN personnel were toadI.U by"'tOCI
personnel, as documented in the EEB memoran-
-. :.d- u|tm re.'ferredl t o above , neverthelessi,.3 he
program that .was Wsahl ished was determihied
,, -or OE's instUnctions. The investigator's
review of final dispositio)n of NCR 5465
-' "revealed noncompliance witLh the intent. of
:i.:. -the reql i irements as welIl as inappropriate-
- ' h~ess of correct ive ac't~ion An that. the actual
routing inspecti()n was done b~y the drift
foreman rathvr t.han• the inspectors (same at
,BEE findin C7 disc:ussed in section VD).
"The invvstigators int•rviewed OE~s cognizant personnel
-. to determine and veri fy that the CSCP had been ade-
quately •documented and that various features of , the
program which provided .design related information
. either to OE or OC had properly and independently been
verified, The conclisions were that. no formal verifi-
.: •..cation of the adequacy of the program soft~ware had been
(t. oile. Although the investigators !had not requested
,i :, :that. an NCR be issued for the above-mentioned conrerni
...
.OE issd an NCR dealing with lack of CSCP program
vquirerimenn. However, act
o2sso wasl no trakecbtice angees
.4'..'
.45.
.4.,.,..
Cs.-.
.r.
*'*1
•,•,
"'4'..
-. ~,~~'
ýT& OtCps.
The primary document defining and communicating general
engineering requirements for cable installations was General
Construction Specification G-38, "Installing Insulated
Cables up to 15,000 Volts." G-3R was controlled by EEB and
used by OC to generate site procedures to implement its
requirements. At the time of the review, G-38, R5 datedFebruary 13, 1985, was in effect with SRN-G-38-4 applicable
but unincorporated.
The investigators reviewed the following documents defining
the program and implementation results and evaluated each
individually as outlined below:
a. Program Review and Evaluation
o 'RLN. FCR F35i12o SRN-G-38-4
.5,,
zlj?
Ax"
1
o WBN FCR E205160 GCS G-38 R5
b. QA Surveillance Review and Evaluation
o WB-S-85-08-C00
c. Program Implementation and Evaluation
o 3WBN NCR 58140
d . NSRS Overall Conciusions
a. Pjqam~ Review and Evaluation
BLN FCR E3512
BI.N submitted an FCR No. E3512 on April 30, 1984 (BLN840501 586), requesting revision to certain parts ofG-38; in particular, addition of exception 4 to G-38section 3.2.1.3 was to be read as follows:
in order to Ruide a cable tb 'ough raceways itis permissible to attach all conductors ofthe cable to a single break line providedthat the breaking strength 6f the pull breaklink does not exce:d the maximum allowablepu I I force (F ) as (iet ermined by 'Section.>3.2.1 .3a. Cabfis may be pulled together in,this configuration with each cable break line'attached to a single pull rope or multipleropes if required.
OE approved this FCR on October II, 1984, and stated..that the subject change was approved and issued as partof SRN-G-38-4 on September 4, 1984.
SRN-G-8:3-4
SRN-G-38-4 published on August 27, 1984, witheffective date of October 31, 1984, maintained themethod of calculating F for a cable.
m
thesame
Although this SRN attempted to clariy tLhe cable h Ipulling operation such as: (I) proper method ofattachment of conductors to. the conventional pullingeye or crimp-on pulling eye, (2) proper point of place- OIL,"ment of break rope or dynamometer, nonetheless it..,:, ,
failed .to consider the actual circumstances OC. was.::0 0 .
confronting. This SRN dealt with simplistic cable pull'!;.operations and did not address/clarify thewneeded 1-irequirements for calculation of F for multicable pull
mnor did it clearly s;tate the proper method of monitor-
ing the F for mIticable. pull activities. AThe GOCS -m .
19
-I
14 MMUMOMW
¾'
-. •, R5 issued "uP February 23, IM~, acknowledged not
hayvig incorporated the SRN-G-38-04 on this revision due
to the need for addit ional OF./OC study of its implica-t ions.
WIN FCR E20516
WBN submitted FCR E20516 on October 23, 1984 (WON
84 1024 300) request inng OE's conf i rm;,t ion of theirinterpretation of section 3.2. 1 of SR&N-G-384, which
read as follows: ''Our i.nt.rpretat i .ol o t.eword•_ 12iSRN-G=38-4 section 3.2.1 haive been summarized as................................1.1.. L tT .i!7,')--i~iS¥.'li;P!i19L -i-i4L-ft !1, Le.
0les-ca- p lla.t.one time us i n 8 s
01e fuse link or break link using either a basket
weaive/ma I,-e's ortby direct cOnnec tion to the con-.ductor(s). Use the F formula tocalculate the max 7tot(s) in thepu1l, Use the siai letcofnduictor..
circular mti area for thTs "alculation. The confirmat-ionf-this•-s- i, Lrpreat-ion as"requesdte to be pro-
vided prior to WIN unit I fuel loading.
This FCR was verbally and conditionally approved onOctoher 23, 1984. The conditional approval was proced-urally contrcnlled per EN DES EP-4.03, although the FCRhad not yet been finally approved at the time of thisinvestigation, Discussions with cognizant management-of EEB responsible forr final disposiition of the FCRrevealed a high degree of apprehension on their part toapprove the WBN FCR.
A,
I'.
.........................................................:."¾'.•• .'. >':: .,
It must be noted that OE's program for handling FCRs
requi red 30 days response time for the approval or
maximum of 6 months if there was a written agreement.
between EN DES and CONST project managers. -The in-
vestigators could not locate any such agreement; The
significance of this issue,. as any other FCR that, hadreceived verbal and conditional approval, was concluded.to be that if and when the FCR was rejected or not
approved as submitted, theh the condition of all work
performed under that FCR would become indeterminate.This would( consequentl ty require tracking of all work
done unlder such a system and NSRS concluded that great
potential existed for oversights as wcl I as inadequate
tracking of this type act ivity for subseq'"nt reworkand thereby lowering lhe con f idence level, not to
mention the economical loss as the result of the estab-
lishment of such tracking system and the subsequent
.required rework.ot i
MCI• , , Jf,(.S G-. 8, R.)
The GCS G-38, R5, issued by OE on February 13, 1985,established in section 3.2,1.1.a that "the force used
¾ -
20
7
to pull a particular size conductor shall not exceed"the manufacturer's recommendation or the maximum allow-able pulling force, Fm, as determined by section3.2.1.3."m
Section 3.2.1.3, maximum allowable pulling force,.notedthat cables shall be pulled according to manufacturer'srecommendations or specifications when available..Otherwise F shall be calculated per section 3.2A1.3.2; f,-:and so tha9t calculated F values are not exceeded ,break rope/links shall be utilized per conductor f. •
Section 3.2.1.3.2, the maximum allowable pulling'forceshall be determined by one of the followingmethodswhen not provided by the cable vendor:
a. When pulling on the conductor (sections3.2.1.2.b and 3.2.1.2.c above), the . .maximum allowable pulling force can bedetermined as follows:
F 0.008 x n x cmxl (see Notes 2m and 3)
Where F Maximum allowable pulling:.m force, pounds
n Number of conductors in the cablecmil = Circular mil area of one of
the conductors (see Note 1)
NOTES
1. For a cable having multiple size,.conductors, use the smallest size. . ,,
conductor to determine cmil. . ... .
2. For instrumentation cable-, F.shall be calculated by Lne abov:equation but shall not be allowedto. exceed 100 times the cable'sminimum bending radius (see section3.2.1.6) in feet.
3. For medium-voltage power cables, Fshall be calculated by the abov0equation but shall not be allowedto exceed 300 times the cable' rrminimum bending radius (see sectioni3.2;1.6) in feet.
b. When pulling cable using a basketweave ..grip (section .3.2.1.2.d), the maximumallowable pulling force shall not ex-,,"-ceed 2000 pounds for unshielded, jacket- ":ed cables and 1000 pounds for shielded,jacketed cables. .""
21
LL
V~
I
k.,
ý0 K 7,S4
Sections 3.2.1.6 referred the user to UiS-E12.1.5 whichestablished R valuos (see section V.C for addition,- :,al details). TminSection 3.2.1.2 defined the method of preparation :of
cable for pulling as follows:
b. Conventiona _-Type Pulling E.e .
Cables may be connected by means "of abreak rope or break link to one side ofa conventional pulling eye and pulled by.,a pull rope attached to the other side ... ,of the pulling eye. To use this methodof cable pulling, remove enough jacket, : . .',,insulation, and filler -materials toallow the conductor to be folded back on :.AY.itself to form a loop. The break- ropeor break link shall he attached to thisloop and shall not be attached in. any.'ý:J,way to the jacket or insulation.
c. Pulling Eyes Which Attach Directly to ,the Conductor . .
In certain instances, moisture-proofingof the cable end may be required. Also,-when pulling larger size cables, the endbeing pulled may become quite large and *&..
bulky if the method described in b above-'':,is used. Depending upon the type and-size of the raceway, the number of bends ;Minvolved, number of cables being simu -....taneously pulled, etc., the large, bulkyend of the cable may cause great diffi= VAT..culty in pulling. When dealing withthis type of problem or where otherwisethought to he desirable, a pulling eye.. io. -4which attaches directly to the conductorK':'.(such as a crimp-on-the-conductor. pull ......
ling eye available from Cyprus Cable.- VA
Support Systems Co,, ') may be used. .
In order to use Ivpe of pulling ''! 4
eye, remove enough aCKeL, insulation, .and filler materials to allow the' bare ' ;Iconductor tAo be inserted into the barrel.,of the pulling eye. The pulling eye .shall then he attached to the conductor '. ,according to manufacturer's instruc-,tions.
d. Basket Weave Grips ' .- ',. -
Use of a basket weave grip (such as, aKellems Pulling Grip available from the
22
S Y
Q
KV
QW,
K
7
,ýZ,ý' AMIOF 5
'EM,2~
ioaQ ý
Kellems Division of Hlubbell) provides '
another acceptable method of. pullingcables. The basket weave grip offers,..,several advantages. It is e 'n -. Ii.
stalled and adjusted, quickly removed ,.reusable, and lies flat to the cable.For unshielded cable, the basket weave W.4: 4
grip simply slips over the end of the .cable and directly onto the jacket- orinsilation, requiring no preparation of .
the cable end prior to pulling. 'AV - ," ,
Section 3.2.1.2.3 defined the cable pull preparation 2for a multiconductor cable as follows:
Where multiconductor cables are to be pulled A .Iby either method described in b or c above,".each conductor must be treated as thoughit' "were a single conductor. and connected to the .tpulling eye to avoid excessive stress . on -logindividual conductors. Special type cablessuch as coaxial', triaxial, and signil cablesPshal) also have the shield or drain wire inaddition . to the conductor attached to the.'pull rope.
None of the above stated paragraphs had been revised asi.. -the result of revision 5. Revision 4' of this documenthad been issued on March 26, 1984. " -': ";.":" ,'.••!
b. Q, Surveillances Review and Evaluation-
WB-5-85-08-COO
WBN QA unit conducted surveillance report No. WB-5785-7''08-COO on October 15, '1984. This surveil lance,' was-,":conducted during cable pulling activities 'associatedwith fifth diesel circuitry. It was noted from this
surveillance report that 26 different size cables were `-Fpulled all at once utilizing a mechanical cable pullerwhile observing the pull tension (F ) on the dynamome-ter. The F of each cable was calculated based on the ,information "that was provided in the site procedure and
OCS C-38, which was, F 0.008 x n x Cmil as discussed;earlier in this sect in. Then the F s of all thesecables were added together and 80 percent of the totalwas determined to be the F for the entire pull.' The j',;F of some of these 26 cables was 'as low as 65'pounds .YQ9Ad as high as 394 pounds, while 80 percentrof-the zK 2 , i
total individual F s equaled 3935 pounds. The' report' - ,-,
indicated that the( dynamometer reading did not exceed-the 3750 pounds which was below the maximum allowablel-PRF for the pull. The investigator concluded - that:.
23Z
Fm~~~ ~ ~~ .:.... 1.,..,
, ':-Q f~-" . ,, T O.,
%~~
. ... , . ~ ~..; •? - .,'(I) Al though the 80 perc'ent of total of individual F "Va titu for each cab11 , was ,,se, the process di( no.ensure that the cables' individual F s were nOt -exceeded. Thhe focus of attention was on notexceeding the total pull forces without regards toindividual cables F s since individual break. ropes",or links were not used for each cable...
. ..(2) The engineering basis for utilization of the '.80 *'.
* percent. of the summation of individual F s ap-,peared to be a conservative figure which ZaS atone time approved by GCS G-38 and the site proceti-ures that were effectiveearlier in the project.Prior to that, 100 percent of total F s were usedas the controll ing F for the entire pull..m , .
(3) The, QC inspectors were performing the F calculaLions for the multicable pulls rather than FEU,-. 9personnel.
(4) The calculation records are not maintained at. all,-; {nor their accuracy veri fied. ' '7
(5) Records (identifying which individual cabl es were .involved in multicable pulls were not required ormade.
There were, no assurances that the cables were .. notdamaged in view of the fact that cables with'as low as .; ....F= 65 pounds were handled and pulled with a combined.'F = 3750 pounds.m
4 .The ma in purpose o f uti I iat ion of dynamometer or break •.rope/link is. to ensure the cable(s) would not be dam-X~ du r ing p uI n g a c LiVit.i Vi S.tie nd a9s su ch t he methodutilized here was determined to be unacceptable. .
c. ponram Implementation and Evaluation
WBN NCR 5840
...WBN generated NCR 5840 RO on October 18, 1984,, docu- -mentinR the following violations:
(1) Some cables had been pulled based on G-36,R3 con-cept while ,-38 R4 was in effect.(2) Specific cables that violated 6-38 R4 as stated in";;!I above, were unknow n.
.""(3) No inspection documents were generated for,"multi-
24
bov,'P'" ! 47
NOW or
(4) Listed a number nl cablt's that were known to have y'y: sly"r'';'be!n pulled using G;-38 requ r foment s '.
InvestigaLors noted that:0 G-38 R3 permitted the use of F 80 percent (?
+ F + F * .) utilizing a single be 'rope/l-ink Value at less than or equal to F. as 5calculated above. . "
o G-38 R4 changed the requirements to utilization of Aa break rope/link per conductor and deleted the,80 ,.>4' ;percent rule.
J. C. Standifer's memorandum of December 24, 1984, toGuent,:r Wadewitz (EE• 841227 912) dispositioned thisNCR as follows:
Please refer to your memorandim to me dated : .October 24, 1984 (W'IN 841024 100). The uset : ,of excessive pull tension can cause damage to ," ,cable insulation that would not necessarily,.he deLected in the inspections dnd tests 4' AliSted in section 3. However, lue to thecables heinR pulled as a group with thepulling force being limited to 80 percent ofthe sum of the maximum all owahle pulli ng-forces of the individual cables, the.instal-lat ion wi l I he acceptable for use as. is.Since revision 4 of General Construction: ,Specification G-3R, the Office of Engineering',has been evaluating its cable- pulling Kre-qui rements. An industry survey has been made ,..to determine cable pul I ing practices being ".'used by architect-engineering firms and otherutilities. From this effort., we have con-eluded that the maximum allowable pullingforces for group cable pulls of this type canbe less conservative than the present re-rluirements in G-38. These changes will bereflected in the next revision of P-38, whichis currently in progress,
The investigators determinrd that the final dispos-tioning for this NCR ",se-as-is" was inadequate forthe following reasons: ..
Individual break rope/links had nnL been utilizedas 6-38 R4 had required. TIfit :;~ NSRS investigators could find no engineering.'.'justification for the adequacy of the-80 'percent.>formula or for L100 percent formula for multipulls, swhen only one break rope/l ink was uti I ized..)'.
25
.o Apparent disregard for yer.ification of adequacy of.
the established program by not requiring documen.
tation. of th inspection results of multicable
pull activities performed in violation of, require-
ments.
n 70,
Ant
d. NSRS Overall Conclusions
The investation as
activities
O0
I dentConsIdent
It wtypesonetot ialnwhich
a
igators determined that some of the consider-
well as essential elements of cable..pul!
are:
tification of pull type
deration of attributes/restrictions
ification of pulling methods ","
.!ficai~ton of Pull Typ~e
a•S determined that has ical ly there were two : !'.>
of cable pulling. Type I was defined to be-
single cable pull whereas type 2 was defined.' .
be mult icablo pull Each type could poten-C
ly include a number of combinations, some of .
h are defined below: ....
Type I pull - single cable pull.
-- Single cable, single conductor. -" ,. .. . 07.•
-- Single cable, mulLiconductor.-.allVconduc-
tors ,,ame size...
-- Single cable, tnulticonductor
- all conduc-
tors not the same size. ' .
Type 2 pull - multicable pull,
-- Multicahles -" all cables identical ;.. . .
Multicatles - cables; of different makeup,". -
Single conductor cables - different sizes., on j
- Single conduclo'O cable with multiconductor ,
cable(s) - same s ize. 'N
-- Single conductor cable(s) with multicon-
dictor cable(s) - different sizes,. .'
0
-- Multiconductor cable(s) same size'with
multiconductor cable(s) - not same sizei.
-- Multiconductor cable(s) - not same:size
with multiconluctor cable(s) - not same.,
26
..~'2' .
0:
boo, - On;
A M-'
-- Single conductor cables - same Size wiLh
mul1t.i conduct or cdlbl~ I ) .S N
(2) Consideration of All At triutes/Rlestrictionsi.' s
The att r-ibut~es that are essent i al for successfulcompletion of a cable pull, were for the purpose"of this sect. ion, defined to be:
(a) Avai labilIity of F from manufacturer for allcables involved in the pull.
(b) A formula t(o Cdlculite the F for eachcablea weC II as ratch p)ill ,
(c) Calculation of expected F per pull (includes.Aýconsideration of d and P ?elow) . -"
(d) Availabi li.ty of maximum allowable side. •.llpressure val Izes . -.
(e) Calculation of expected side wall pressure/expected tension at bends.
(3) Identification of Pull in•jMethds
Methods of pull ing a,ý described in G-38 are:
(a) Convent ioniil - t ype pulling eyes
(h) Pulling eyes attLached directly to the conduc-tor.
WHO
(c) Basket. weave grips.
The investigators reviewed OE's principle o documentsgoverning, cable pul I ing act ivitres and concluded thatCO-jthese documents had not adequateIy addressed theWbasicre;eds of OC and it was as the result of this shortcoming that the two FCRs were initiated; As .an ':
example, th,! GCS G-38:
U l Did not adequately and clearly define the pullingmethod for mult icaule pull activitLies and applica- ,tion of break rpe/I ink for posrihle combinaLionsof pulls as shown ahove for a type 2 pull '.'
Did not provide a method of calculating F Vforamulticable pull as shown above for a type.'pull,:',
Did not provide or acknowledge the side wallpressure and tension at bends and method .,ofcalculating it.
270'
0
0
3. " Limi t~ed (
From a recognizant.applicatinThe OEDCfeatures i
o I.iqn
o Of'
o Iecha
The. investigators noted that Bechtel among others.in the industry had, 'for the I ast 10 years', con- ..
sidered the .effects of side wall pressure as a
factor affecting cable pIulling activities, whereas
TVA had not. cons;idered it. tint iI this .year. EER .engineers stated int1ent ions of incorporatingconsideration of the side wall pressure "factorinto the general specificat.ion.
Did not require inspect ion of and subsequent.r. ...
documentation of multicable pulls.
Did not establi.<sh requi rements for "pull hack"'activities, where- "pil I back" was defined to be
where cabIle(s) wore removed from raceways.
Notes 2 and 3 no I;ection 3.2.3.2 to G-38 R5 weredetermined i rre I evant to the sect ion it had refer-enced. The referenced sect ion 3.2. 1.6 of G-38 as:discussed i n secction V..C dealth with R . valuesTml
and not R . values. 'The limits that nMe 3 hadPpn" , In Intg
placed onE for medium voltage cables, for exam-.placd mcabl' bndin fo
pie, (300 x catIe s minimum bending radius foa r
cable with minimum hend inX radius of 18 inches:would he 300 x 18 inches x % 450 pounds)., an
extremely low limit for medium voltage cable.tens ion.
•A. .mplemnta t ion . . "
View of OF. and 0C. procedures. ,nd inte rviews with
personnel, NSRS investigators learned, that'. the.-n of the "I imited QA" program was truly limited.PRI listed in 2QAI-2 RI a representative-list. of,
n the l. imited QA program as fol lows: . " " .
d Radioactive Waste Disposal System. ...
a s T r ea t me ni tS ys t em,.
iniccal Fire Protect inn.
Protect ion Systm.e Detect ion Sys:I eom.ve Barrier 1Pro t.:t ion SeaI, .p Doors and An!;ocia ed Controls.C Fire and Smoke Dlampers arid Contraols,
r'p roof ing.
ency L.ighting Systems in Nuclear Safety-Related
Retardant Coatigs.•
28
• ,;: " ;-:'.. . ;".'r;,-,i.
o Fi re0 F i rv
Fi rFir
INAFir
o lEmerR
Areas
o Fi re
o Plant
''~'2
.24
-kat n ystem e
nt,4 S42.
''iI 7 only
o Radinavit ve SolidifiaLt.i(,n and Pa.
o Gaseous IHadioactive Waste 'reatmet
o Steam Generator Blow Down System
The OEDC PRM, however, was superseded ,ffpctiVe December.31i
1984, by the Nuclear QA Manual which did not incorporate
this list of features, but. refer,' to "Q" or" . ists for
program extent determination. As ,previously state-"JOEEPA
3.41 addressed the general reqUirement; of0 "limited QA"
application, but the investigamtors l•od rno clear recogni-
tion of what qu(ality conttrols were tn have been applied to
which features', From the interviews aid dlocmefnts ireviewed,
it was apparent, that fire piotct. ion ant plant ,security,
systems were the only fea ttre' ahout wh i ch a concensus was
reached iin OE that some limited quality assurance program
was, aplp Iel, Construction specifitcations for these systems
had been generated requiring, among other at!tributes,-. that
construction engineering inspections be perfnrmed.to verify
instillation adequacy. However, beyond the establishment of.
two genral construction specification!-, and EPs requiring
that "limitel QA" programs be established, the investigators
could nrot identify evidence that indicated feature-specific
programs or controls had been implemented or any cognizant
personnel awareness of what constituted "limited QA."'
Office of Construction program procedures did not address
the concept of existence of "limited QA." Some. 'ABN.'site
procedures acknowledged or referenced "limited QA:," and
QCI-1.39 R7; I)ecember 13, 1984, "Fire Protection :QA'YProg-
ram," described requirements for application of "limited QA'Q
to features of fire protection systems, referencing 'both
Construction Specification G-73, "Inspection, Testing, *and
Documentation Requirements for Fire Protection Systems .and.-
Features," and OE-EP 1.55, 'Fire Protection Limited QA
Program," EEU-A had section instructionn pertaining to both
security and fire protection itrspectioon requirements.
However, corresponding procedures or instructions Afor other
"limited QA" system features identified in 2QAI-2 were not
in existence. From interviews with site QC inspectors and
engineers, the investighmtors learned that the- consensus
opinion regarding "limited QA" was:
TO 2
ivy 224W .
M AY.24"'
low' 2' ,
II
O "It" applied to some fire protection and security .
system features, .
o "It" means QC was not involved in inspection. Crafts
or engineers inspec ted the work,
... o If "it" appli Ied to specific cables, the manual input to
the ECM&) program would result in printing .•QQA=L" Qt ,
(limited) on the pull and termination slip''which
meant crafts or engineers would inspect routing, 4. - '..2
29 2'
I, ;-.' .
.. .....
NSRS 1h I ,ves th Iat t[e phi lo. jdiy of " I Iwas sol unld in t hat an a t t rni t ','ij t,additiOlial hi;iiagemelrit COllt Ill Is wer nI'Lc ssI
related system features that were I import;,plant r(l iahi Ii ty. However, the developmeninto a program which not only (1) ident i fieed requirements as well as the features tobut. also (2) implemented the controls,
Cable Bend Radius
Tho~ fnllInwi n• •tuh)ectijon.: di 5;(iIJS5 t hi' recent Ii i
C.
bend radius problems:
0 1979
1. DIR E-9 Submitted.2.. DIR E-9 Clarified.
o 1981
3.
o 1982
4.5.6.
DIR E-9 Rescinded.
NRW: Unresolved It.(!m at WRBN.NRC Viol.-ition at. BIN.NR(" CAT Findings at BLN
mi ted QA 1) ropra, .-Im
t recognize? that Lry for nonsaf ety y '
nt to safety ort of this conceptd and connunicat-which it applied
was "nsuccessful I
Lory of the cable
Ro I .iurse of Actions.
ndi Resolve Cable
ntify Evaluate,n for WBN and BLN
m1 Which Di1sposi
0 19837. Assi.st.rant OEDC Manager Delegat.ed Lead I8. As.;sistant OEIDC Manage.r Estahl ishil(' C9. EEIB Developed l Plans.10. BL[N Indication of Age of the Problem.11,. EB hMeet ing w ith WBN.12. Ff.3 HMevt ing with B.IN.13. Stand Alone Quality Information Is ;iid14. OEDC Program to Ident i fy , Eva I uate , a
Hend Radius Problem Issued.15. Special Engineering Procedure to Ide
and Resolve Cahle Bend Radius ProblenIssued.
16. WBN I)esign Project Manager Memoranduct ioned Cabhle Bend Radius Problem,
17. Design Document.s Issued,
'A
198418.19.20.
Design [ Document.,; lt ;;ld.NRC Closed Unreso lwed Itern at WIN.NRC Closed Violation at IMLN.
.. ~
~!.. > .,.
0 198521. NSRS Evaluation
30
................ ............. 'M o m
A tt~"'
Subsections I through 20, present Od chrno I•logically,, represented Y..the mi lestone o cjivi ties of OE a Al OC du r rng the course -of cable-'ý.fbend radius problem identif icat ion , eva 1ua ionn, and resolution:. . 'Q.The investigators have provided the appropriate verbatim:excerpts"..- .,of the foll owi ng documents and no at tempt s have been made to-"" 1iparaphrase the information where paraphrasing was deemed to heinappropriate.
1979.
1. The Watts Bar Nuclear Pllant ConstruCL inn ProjecL Managertransmitted a Design Information Reqre•t (DIR) No,. -9 toSequoyah and Watts Bar Design Project Manager on April 30 'g1979 (WBN 790430 114), r efq est itng interpretation/clarifica - A. K JKH'ý'&'_Qtion of cable bending radlii requirements as applied to.thecable tie down radii. The DIR No. E-9 noted that:
Design Standard DS-E13. 1.2, Cable Bending Radii -'-4for Pulling in Conduit, gives minimum bend- radiifor pullinrg cable, Can we ilterlpret this to mean "that. after the cahble is i[l uled, the minimum tiedown radii can be 50 percent C;f Lhp pulling radii,In many instance, the p"l I ing radii must be. ex- . "ceeded when tying dlown cable in c.able trays andwhen forming the cable for termination in junctionboxes and cabinets.
2, The Sequoyah and Watts Bar Design Project Manager disposi-tioned the subject DIR on May 25 1979 (SWP 790522 045) as tool",follows:
After the cable has been pulled it shall be per-missible to use a minimum tie down value of 50 ..-
percent of the pulling radi i. For additionalguidance for bending cable at terminal equipment,follow equipment manufacturer's recommendation as . .idescribed in section 2.2.6 of G-38.
1981
'4
2 -
3. The Siquoyah and Watts Bar Design Project. Manager revisedDIR E-9 on May 18, 1981, in his memorandum to Watts BarNuclear Plant Construction Project Manager (EEB 810510 938)as follows:
"The referenced DIR. is related to the minimum bending radiiof insulated/jacketed cable, when being formed for termina-tion in junction boxes and cabinets, or being tied down incable trays after cables have been pulled. After- furtherqevaluation of the "training" radius of cable, we have deter-mined the recommended values of insulated Cable, Engineers&,,Association (ICEA) are applicable. The training.:radiusAisthe minimum to which a cable should be bent without-1.tension
31
-. 1 -0ý
.......
on- the cable. Thus Engineering Design disposition As •-.
revised to read as des cr ibed be low . . .
The appliLKble ICEA training radii for insulated cables is .3 .
as follows: 12 times the *completed cable diameter for •
shielded power-cables (e.g., 8-kV power cables). .. .'i:
Cable training radii for other 600 volts or less cablesdepends on insulation thickness and overall cable diameter: ý.:v.,"To
Insulation Overall Diameter of Cable (inches)Thickness (inches) 1.00 6-nd .. less T-1-.01.T to 2_.000 2.001 and over
Minimum Training RadiusAs a Multiple of Cable Diameter
0.155 and less 4 . 60:170 - 0.310 5 6 70.325 and over 7 *,:8
Cable tray fittings at WRN ar proe i .led with a 12-inchradius. Therefore cables can he "t rained" to notMless than , Q,the above radius before tying them down in cable .trays. ý"v.When training cable in junction boxes and cabinets prior totermination, it is normal cnnstruction practice to removethe outer jacket from the cable, beyond the permanent cable SIT T" A.-tag, to provide a neat and orderly insttallation of individ-ual conductors. With the cable jacket removed, the cab!e " '
diameter will be reduced and allow a smaller training radiiof the cable, as tabulated above.'
2 ' " " ";;••": i< '- '' m198:
okl-
4. In June 1982 an NRC inspector (inspect in report 50-390/82-27, 50-391/82-24) identified an unresolved item:. ?Re-inspection of Cable Installed Under DIN E-9 Prior to theIssue of Revision I at WBNP." The NRC inspector's concernwas that DIR E-9 allowed a Lie down value of 50 percent ofthe pulling radii as established in the Electrical DesignStandard DS-E13. 1.2 whereas the revision I to the DIR E-9issued by EN DES incorporated ICEA training radius..tablewhich required tie down radius that is larger than the.50-percent pulling radius.
•5. In July of 1982, an NRC inspector ( insplction report 50-438/82-17, 50-439/82-17) identified an unresolved item: "Dis-crepancies Between Cable Rend Radii and Vertical Cable TrayFittings," at BLN. The NRC inspector's concern was that the'established minimum bending radius for cables per G-38 re-quirement was greater than that of 900 vertical fittings
which have a 12-inch bend radius and that TVA had purchased-
:~~ ~~~~~ :.::i .'"2!.
6.
P _!''• : , .,: :; ¢:,, :o•;. .,..:
i._
several di fferent cable types with minimum bending, radiigreater than 12 inches.
The NRC inspection report. (50-438/82-22, 50-439/82-22) ofAugust 1982 noted that the above item had been evaluated andfound to be a violation since TVA had installed. cables :in.cable trays with radii that. violated the cable manufacturerrecommendation and TVA's general specification.
The NRC, CIE, Division of Reactor Programs, Reactor Con-struction Programs Bran¢-h, conducted an inspection..' .n.,,during September and C(.:toner 1982. This inspecti-n.reportcommonly referred to as the "CAT" (Constructior...AppraisalTeam) report* No. 50-438/82-32, 50-439/82-32, noted-amongother problems that:
electrical cables-were installed with lessthan the allowable minimum bend radius. . . aswell as bend radius problems, pertaining to trayradius versus minimum cable radius (which .-hasalready been identified as a violation by RuI).:
1983
7. The Assistant Manager of OEDC memorandum of June"13, 1983,to the files on the subject of "Time!i, nss and Responsive-ness - Meeting with the Electrical Engineering Branch, Divi-sion of Engineering Design - June 9, 1983" (EDC 830613 030)noted the following:
a
Construction Specification G-38 defines TVA re-,..quirements for cable bend radii and is in accord-..ance with industry standards. In July 1982, anNRC" inspector at Bellefonte noted violations ofG-38 and an NCR was written, " Sinc'e then, a con-certed effort has been made by Bellefonte CONST to :-identify to EN DES violations related to mediumvoltage cable. By -July 1,. 1983, EEB will have.answers to all CONST requests for relief fromG-38.. This problem potentially impacts Watts Barand this problem is being investigited by WBN. 11From an EEH perspective at least, there does not-appear to be a fully integrated effort to resolveall aspects of this problem for all projects...EN DES will evaluate the total effort. and makerecommendations by. June 24, 1983.
8. The Assistant. Manager of OEDC memorandum of June '21,.1983,to the files on the subject, "Timeliness and Responsive-ness - Meeting with Involved Organizations on June 20, 1983"(EDC 830622 008), the following course of action was.estab-_.lished:
33
................ ..........-7ý - -111-ý`
...." ':. -' . r • .... ...
. .. ;.. •.........<-
atlial inr an(h will "1;umv-tne ead1
-t w•• c I v . .
SeEISQ a inplac toallow ~JEPCto inform
NRC that the 2 roblem has he ill be re
solved . t Be lefote and that, act ion has been or" , -ecurrene Watts .ra
_wilL -• . ... ... ..... •.- .. ............ xev....r.............~. ." .--. V-
Watts Bar will be formu ated concurrntl. with the
formulation of the plan f Bellefonte Irphca-
tion. .foAr Sq.oh. n, Browns FerrY will.aSo be,
evalu Iai ted.
As soon as practicahiv, but not latr than one
actions. OQA will be uinormed. " *.:.,..
W.. R. rown will deternine what artions have been.:.-,'
cf th......tBelefne n wa i t ioI have
Aeen takSeno"prevent"reuz,',nce. l1, will aLkso -
oll!ct the- documentat.a ion that ex s ts for suchl'or Watts Bar. ,
T3 with nformationp ,i...rbe tributionoF.hr..
Iq83. ýR wtapropriate distribution to others. "'-"
9. F. W. Chandler memorandum of July 1, 1983, to 4. NY, Sprouse
on the subiect, "OEDC Program to Identify, Evaluate,"and
Resolve Cable Bend Radius Problems at Bellefonte and.Watts,
Bar Nuclear Plants" (EEB R30/01 940), noted the following:
Refer to Dwight H. Patterson's memorandum1..-
(OEDC) .files, "Timeliness and Responsiveness --
Meeting with Involved Organizations on June 20,..
1983" (EDC F 0622 00R), wit h your endorsement to
me to hari,'!e for EN DES.
A.' '~
,~ ..f~,
As y",, know, the minimum cable bend Aadii values.' M
arc specified in Construction Specification G-38.-,'. .
These values reflcct. those contained in industry
standards developed by Insulated Cable Engineers
Associatinn (ICEA). Several NCRs have been .-.
written by CONST for specific cases where, the.
instIa led c:able bend radius is less than the .
established G-38 values for field installed. .. *.-. .•;
cables. EEB has been actively contacting the
seven cable manufacturers of shielded power cables.
for WBN and " BLN to dete rmine if a reasonable,.,,
relaxation to a lesser cable' bend radius •. s "
acceptable.
EEB will take tine WEDC lead to develop the program", a,,-
-for defining the nature, extent, and implications
34.., . w,
" " "' ' ""• :: "::• :': '7 ' I.. I
of the cable bend radius problem as i , exists' i. t . .
BIN and WHN
Team me•.bers for Lhis program arc C H. Sudduth
and J. F. Wagner of EEB, J. L, Springer of BLP Ed
Benni 'h oK BLN CONST, J. 0. Collins of WBP,-and: ' QR'"i
:Paul ;heppa'd..of-WBN-CONST. :.
Out p,lan is to identify, evaluate, and resolve " .MC
cable bend radio: problems of inst.al led cables at
kiLN and WEN.
The identification process will determine the
degree of cable bend radius prob lem areas by.
categories, such as may occur in cable tray rout
*ing, transition from cable tray to conduit, condu~ A"V
let, and electrical equipment. This process -wilI
involve conducting interviews with engineering
personnel of EN DES and CONST, consulting withq'"f
. other utilities, and performing a random sampling :io§
program of installed cables, jointly by EN DES and
CONST at WBN and/or RLN.
EN DES will evaluate the dAta from the installed.
cable sampling program to determine the accepta-," :
: bility 'of .the installed cables. EN DES will also I j
determine if a generic condition exists (by prob-
lem area category). For unacceptable cable in".Q.:
stallation; corrective action will be determined ." . -;•-'.
' jointly by EN DES and CONST.
To implement the plan, EEB is preparing a special ::" :
engineering procedure (SEP) for ,rN and RM with:
first draft planned for review comment by July.8,
1983, to involved organizations.
For ongoing cable installations, CONST shall., a' ...
fol low established cable bend .rad i us values.in
- Construction Specification G-38 or receive spec fi -.:"' .
ic relaxation of those values from EN DES prior to
cable installation per established Y procedures. "'
10. The July 1, 1983, memorandum from lonnie 5. Cox to ýW.R., •
Brown on the subject, "Bellefonte Nuclear Plant -. Cable"Bend""
Radius Problem" .(RLN 830705 OR6), partially noted nthat.:"
The cable bend radius problem was identified
approximately six years ago. and was 'disCusse~d CC',.. C
between EEB and the site. The first formal:,dc .. '
.mentation was in 1980.
.11. The Electrical Engineering lranch management held a meeting Q:
on the subject of WBN cable bend radius problems on 'Julyi7,
.35
C.- ' . 5 . : ' . ,
t- .. : ' C',,:. . . ,: ' : . * : . p C. .
no ý eo
Q1-,
0" ~
too, .
"I
,
.*-*, ."-
1983, with management personnel from electrical units of WBN A Qand management personnel fromi Electrical Pesign Section of:,WB Design Project and douimented the minutes of the meeting, ...to the Electrical Engineering Branch file:; on July 23 1983(EEB 830725 916), as follows:
4.0 Purpose
The purpose of this meetinrg was to discusscable bend radius problems at WRN (and BLN),to determine extent and severity of problems,and to. explore methods to resolve them.
5.0 Discussion
1. J. Scruggs began the discussion by refer- Aring to recent meetingis on timeliness and 04
responsiveness urgent need to take UI:action on open items. Several NCRs have beenwritten by CONST at WBN and BI.N concerningthe fai lure to meet the specified cable bendradius - requirrmentS. To address the con-cerns, C. IH. Shdduh stated that a team corn-,prised of .1. L. Springer (BLP), Ed Bennich.,"I"(BLN-CONST), .J. P. Wagner (EER) , C. H. Sud-duth . (EFB), P. L. Shepherd (WBN-CONST), andJ. 0. Collins (WBP), with FEB taking. the.I ead, has been established to define the -n ,nature, extent., and imp] i ,ions of cable . :bend radius problems as they e., at WBN andBIN. C. II. Sudduth briefly dis ... : d theprogram outline und the draft of specialEngineering Proced're (SEP) 83-08 whichassigns organizational respnnsibilities and 0,'V ,provides procedures for i dent. i fying, evaluat-ing, and resolving-cable bend radius problems,," .. : nat WBS and BIN. He also reported that EN DES- .,.dispo-'itions WBN NCR 4274, RI, and NCR 4194have been completed and distributed. -The
disposition to NCR 4274, RI, is that Ithe ITcondulet will be replaced with a .pu ll . ,b.,
per ECN 4012, to allow cable repair of dam-agel jacket. ' The disposition of NCR 4194 " " -accepts the as-instialled, cables in the 12-inch radiis cable tray fittings and permitscable installation to' continue in 12-inch-..,radius cable tray fittings. It was empha Qsized that any other ongoing cable installa. -
ions shall fol low estab ished cable bendradius values in G-38 unless specific reliefof those values are received from EN'4DEprior to cable installation.
• . .. . V.' '
36. .. . ... ,. . .:., -. : :.M
K
p
:.'
Shepherd stLat .ed hat. a to- L , 1 inspection hadlbeen conduct.ed o i the V5 (6900-volt, circuits)level cable trays excluding 12-inch radiusfittings at WBN. Approximat~ely 80-90 possi-hble cable bend radius violations on class IE.caibles were found in this inspection. NCýR ,4933 has been written concerning these vio.alations. lie also said that the resolution to
NCR 4 194 (dea I i ng witLh 12- inch radli us fit-t ings ) wou 1(d possibly resolve a number of .
these violations. CONST indicated that the-same Instal lat ion pract ices and procedures ' "were used in all cable (both class IE and" ,nonclass IE) i nsta I lat ioon., For class IE " ,cables, the inspector "walks-ont" the cabletray/conduit route, then allows cable instal-lation to begin, lie the. observes that the . :.,'2cable is installed in the correct tray/con- .duint. The cable is mostly hand laid in tray,not pulled in the tray. The cahle bend -atthe exit of tlie tray to a Conduit, is towardthe end of cable, installation. Most of the:.:
cable pul I ing problems Occur in conduits forcontrol and s igria I cables.. Few pullingproblems occur with pow(er cahles. NonclassIE cables receive no inspection or verifica- ,.-t. ion checks du ring i nsta I Iat, ion, but as withclass IE cables functional tests are per-fo rmed after insta latio,
C. H. Sudduth asked i f nonclass 1E cablesthat are installed in divisiona l cable traysare inspected. The nonclass IE (associated)cables installed in divisional cable trays.have not received inspection because CONST. . . .has not interpreteid G-38 to require QA docu-mentation for associated cables. Afterdiscussion of the RG 1.75 imposition byNRC-.NRR for TVA to analyce "associated" .caf'les routed in divisional cable trays withsubsequen t rout i ng in common t rays at LWBN,Stidduth st ressed tihe importance of treating.,any future instial led associated cables. the ;same as class IE cables.. -..
In reply to th( question of documentation,CONST indicated that. the pull ing tension ischecked with a dynamometer, but the actual.value is not recorded. However, it is then " :"signed off" by an inspector indicating the:.:.measured value is less than the calculatedvalue on the cable pill cardIs. Similarly,the inspector may indicate on the termination:,.,.card that the installed cable bend radius"isgreater than tile allowable value.
3 7 . ... :.
1-
A d i sc ss iC on foII o wt -I th.'i Ide fi ned fouri;' .. -possible categories where CIh le bhend radiusý!'':.problems may occur: (1) along cable tray'.*,>routing, (2) transitions between tray to trayor tray to condii t , (3) CondIIIlets and boxes,and (4) within electrical equipment. Anevaluation of these categories will be con-ducted by the OEDC team, for the differentvoltage levels of installed class IF. cabIt:s.
The determination of magnitude of violationsin voltage level 5 cable. rout ing was dis-cussed. The number, of violat ions listed in KWTIN NCR 4933 will he compared by WBN -CONSTwith the total. number of possible violations.,to determine the magnit.tide (percentage of'total) of the V5 level violations of 6-38requi rements . (Some of. thes,, cables were.:installed and inspected duiiring the period of'May 22, 1979, and May 18, 1981, when EN 'DES.disposit.ion of DIR-E9 al lowed WBN-CONST to'tie down (training) cables to. one-half of theI.ec, ommended (pulling) vaI Ie of cable bend.-radius.
In the discussion concerning possible viola-tions on lower-volt.age (600V power and con-t ro I ) level c(able routings, Shepherd empha-sized that. due to the use of mutiiconductor.control cable (having an overall jacket), thecable bend radius requirement on the cable ODof the outer jacket should not be used in thecomputation. Instead, he stated that controlcables, because of their small OD and low*.voltage, would not be a problem, and that .they should be-evaluated from the perspectivethat the requirements of G-38 may be conser-vative, ,even though G-38 reflects the guide-lines from industry standards.
V41
a
.'
In discussing the oracticality of inspectingall low-voltage power (V4 level) cable trays,,it w:, stated that there are at least twiceas. many V4 trays compared to V5 trays; thecables vary more in size and are coated wild,' -.Vimasco, thereby making it very difficult to "measure the actual cable bend radius. Thesefactors would make a total inspection of V4.:trays at WBN impractical. He emphasized that,.ithe computer cable routing program should be ..utilized more in any sampling program. Oncethe determination is made as to which cable ! isize(s) may have a potential cable bend
38
, , . • ,. *' • :•• ¸•e•-,:•2,,••
radius problem, tLhan the computer can ident iL ,fy thnse cables, which can he randomly
YV
yon -
700
samp I ed.
6.0 Action Items
6.1 WBN-CONST will determine .magnitude(percentage of total) of cable.: bend.:radius violations of V5 level .::cable.trays by July •5, 1983, and send toWBl'n. . .
6.2 (WRN-CONST and WRIP will prov ide C. H...,Sudduth comments on (Ira ft SEP. 83-08., by. :
July 14, 1983.
12. On July 19 and 20, 1983, the Elect rica I Engineering Branchmanagement held meetings with management personnel-:: from.--,,Electrical Engineering Unit of BIN and management personnelfrom Bellefonte Design Project and documented the minutes of:-.,the two-day meeting to the Electrical Branchi'.files ony. ,n"August 4, 1983 (EEB 830805 91b), as follows:
4.0 L" 2r0ose"
The purpose of this mect ing was to discusscable bend radius problems at. 8LN (and WBN),to determine extent and ;everity of problems, ., §111and to explore methods to resolve them.
5.0 Discussion - July19, 1983 cet.in . ...
M. J. Scruggs began the discussion by refer-. "-ring to recent meetings on timeliness :and.e : .
responsiveness and the urgent need to- take :action on open iteml. Several NCRs have been l.written by CONST at. BLN and WBN concerning ,'.the failure to meet the specified cable bendradius reqli rements . To address the .con-. '.'i :.cerns, C. H. Sudduth stated that a team corn-. .prised of. J. L.. Springer (ILP), Ed Bennich '".(BLN-CONST) , J. F. Wagner (EER), C. H. Sud-dth (EEB, P. L,. Shepherd (W3N-CONST), and J.P. Collins (WBP), with EEB taking the lead,has been established to define the nature,extent, and implications of cable bend radiusproblems as they exist at 81,N and WBN. -
C. H. Sudduth briefly discussed, the p ':" " : •outline and the draft of Special Engineering..,..Procedure (SEP) 83-08.which assigns organi'za-tional responsihilities and provides proced-.mires lor identifying, e.va luat ing , andrcovinrg cable bend radius problems at BLN and
39
C
GVY
Vol
QV -41K
Est 0,,
-No
WIHN, lie also gaveya -status report on EN ONES •
di:sposition of BILN nnneoplforma ces and dl5-'
cussed 4 draft standalone quality information.;.
memorandum--- Iabulating relaxed cable. bend
radii for installed shielded power (V5 level )P" "
cahles. The relaxed values are based .:onfl.- . 2:'
information provided by the cable manufactur-: .
ers. The reduced cable bend radius valuer . 1.
will be used, during a walkdowin Of he class':.<.
IE train A and. I. (VR ) cable routings,, to
determine if violations exist .
The team members discussed the possibility:of -
changing the minimum . table bending require-"A .ý1
ments to ntinimize having to rework cable tot
and/or modify cable raceways. At the present
time we do not have any qualification datato
,relax the estabh i shed cable bend radius .. - A
values, except for the shielded power cable . .a. >.
invnlved in existing nonconformance reports.
As soon as the team can establish a value
that will envelope a reasonable worst-caseminimum bending radius, additional data may.:-
be obtained that will allow relaxed values ;..,
for other voltage levels of cables: 480V
(V4), control (V3), and instrumentation (V2,.Q
and V1, if. appl icable) ... However, : due to. :
possible reduction, of quali fied cable ,life...n ,
due to the use of less than Construction.Specification G-38 requirements, the team ..
mimhers, at this time, do not have sufficient . .. ....
justification to recommend that G-38 be
revised to reduce the minimum bending radius-.........."'.
for all types of cables for all future cable' ."-
installations. Individual NCRs are continu- ow... :
ing to he resolved on a case-by-case basis by
EN DiES and/or CONST. It'was emphasized that .'
ongoing cable, installations shall follow: -
established cable bend radius values in q-38...
unless specific relief of those values-are -;.
received from EN DES prior to cable installa-. .
Lion.
Discuss ion - July 2?, 1983 ,Ieeting- .:
5.1 The team members discussed possible sampling: ".
inspection methods that will provide adequate
assurance that reasonable worst-case cable-. -
bend violations will he detected. " They.;,,-
agreed that results of the WBN total inspec" .
tion of the. class il V5 Atrays justified the'
same type ins;pection of the class IE VS level-'. 7..v
cables at BILN. It was also determined that. 2
it would he more efficient to also do a total I
40'.• ,•..', .. , g
inspection of class IE cables in all othervoltage level cable trays that are in the:-same tray tier with the train A and B VS 5trays. From the inspection results, the OEDCteam will determine the magnitude (percent oftotal) uf violations in establishing a confi-dencc factor to determine the need for addi .
tonal inspections. Random inspections will
also be made at class IE rwitchgear termina-Lions and at other Clas 5 IF. terminationswhere nonconformances. have been written,
4
,.,-4~,
Potential violations in conduit bodies. ýtl
(Crouse Hinds condulets) and available>.methods of obtaining qualificaticn data were.,..discussed in detail. BLN-CONST. has deter.-
mined what types and sizes of cable that can.be installed in condulets (Tees and' LB).O 'This data and a suitable computer programwill be used by CONST to determine and tabu-late the best possible bending radius of all-iof their cable types. The computer programwill identify cable bend radius violations,potential violations, and possible-acceptable',installations. The data from actual viola-.tions will be reviewed by the OEDC team, and'. ý'I.
the number of possible violations will, beestimated and used to establish a reasonableworst-case bending radius. Worst-case data.will be reviewed by EN DES (EEB) who willcontact cable vendors, as appropriate, to -
determine if relaxed cable bend radius valuesi>',!can be obtained. Where relaxed values'cannot/ýbe obtained, the team will further evaluate:and determine the course of action(s).
6.0 Action Items
IS '
6.1 EEB will issue a standalone qualityinformation memorandum by July 28,.1983,,, 7so that the inspection team can inspecti'i-all VS class IE cables to the reducedbending radius values at BLN.
6.2 BLP and BIN-CONST will review cables.",,,presently installed in Tee and LB condu-lets and by July 28, 1983,. select-, arepresentative combination of, ,;cabletypes and sizes that can be installed invarious size Tee and LB condulets andthat meet the design fill requirements.This information, along with information. >-from items 6.3 and 6.5 below will....be","--used for determining if additionalqualification tests are required.'
41. ... . . .... 4, .', 7
X. OWN
'ilt
6.3 EER will immediately conta't BLN cablevendors and cable test laboratories tos.e what qualificat ion data is availablefor unshivIded power, control ,and
instrumentation cables instailed l with -
cable bends much more severe than G-38values and obtain their recommendationsfor possible test configurations, - ifadequate data does IoL exist. The cablevendor and cable test laboratory con-tacts will be completed by August 12i1983."
6.4 BLN-CONST will provide comments-n by'July 28, 1983, on the draft SFP.'83-08, .•"Identification, Evaluation, andResolu-.Lion of' Cable Rend Radius Problems atBel lefonte and Watts Bar NuclearPlants."'
6.5 CONST shall run a computer program byAugust 23, 1983 (BLN $30606 089), toidentify cable bend radius violations,potential violations, and acceptable -cable installations.
7.0 Post Meetng Nes
7. I The standa lonememorandum listedabove was issued830729 925).
qual it.y informationunder action item 6.Aon ,July 28, 19831(EEB
7.2 The information listed under action item6.2 above was received informally from
BIP on July 28, 1983.
7.3 Commentsitem 6.4July 28,from FEB
on draft SEP 83-08 for action:were provided by BLN-CONST on1983. SEP 83-08 was released
on August 4, 1983.
.. ., .. ...
7.4 On July 29, 1983, the six-miember! OEDC.team met to finalize the implementation
procedure of the program outlined in SEP83-08. The implementation proceduredefined the sampling program that isbeing conducted at BLN the week "of
August I, 1983. The OEDC team will
evaluate the results of the sampleinspection together with the results of
the CONS'r computer program related ý tocables installed in condulets. Forunacceptable class IE cable installa-
42
10, Too &V
Lions, the OEDC team wi I I establ ish
recomhnendat. ions for the course of action
to be taken for resolution and a sche-. I
dule for comniletion, -
.. V
13. The' Watts Bar . Design Project Manager issued "Standalone :•.
Quality Information" to Watts Bar Nuclear Plant Construction .4.
Project ManaRer on July 28, 1983, on the subject,. "WBNPKTV
Units I and 2 - Minimum Cable Bend Radius for Installing
Insulated Cables" (EEB 830729 926), as follows: . .. .
For ongoing cable installations at WBN, CONST
siall follow established cable hend radius valuesin Construction Specification .G-38 for- both: ,
.. pling and training cables, or receive specific-.
relaxation of those values from E.N DES prior to.
cable installation. The training radius, .,hich.,may occur anywhere along the cable route, refers, -
to the radius to which a cable has been bent and
left in a completed configuration.
For the WBN installed shielded power cable andthe on-hand shielded power cable yet to be in-..
stalled, the minimum training by cable manufactur--",..-:er and cable size is as follows:
A matrix of seven cable manufacturers by name.was shown on "."the left hand column of an included table with values. in •
inches for minimum training radius for seven different size .'" -.cables appear on the seven rows for each cable manufacturer. ....
This matrix was for WBN shielded power cables, voltage level.,5 only and indicated relaxation.of installation factors- for -,
the different cable sizes to as low as 4.4 (Note: . ICEA
minimum installation factor is 12,) The Standalone QuAl"ty
Information continued as follows:
The above tabulated values are acceptable at WEN.regardless of where the trainirng radius occurs(e.g., in standard cable .tray fittings, in non-
.ig,?
2,'< - - .
standard manufactured cable tray fittings, -in
Lransitions from tray Lo tray or tray to conout-,in conduit boxes, in electrical equipment, etc.)
These values are based on information provided by
the respective cable manufacturer.
To date, these are the only available cable bend
radius values, for training cables, which have
been relaxed. from the values specified in G-38; '
these relaxed values apply to WBN.
14. An OEDC program to identify, evaluate, and resolve cable
bend radius problems at..WBN and BLN was developed.and issued !'. !
on July 29, 1983 (EEB 830805 929), with team members,<one '.
each from WBN, BLN, WBN Construction, BLN Construction,:andj ."P
two members from EEB.
43 . , .
• , .•. . ... . ....- '
4..
This program was; an implemvntat, ion procedu re for, OEDC teammembern; to fol low so tht. tihoy couilId o)bta in information'.,needed for identifying, evaluat ing , and resolving cable be n dradius problems of installed class IE cables at WBN and BLN.-%,JA
15. The Special Engineering Procedure EN DES SEP 83-08, :Identification, Evaluation, and Resolution of Cable Bend RadiusProblems at Watts Bar and Bellefonte Nuclear PlantsY (EEB-R830805 941), was issued on August..4, l983. This SEP estab= '-A""A" 61 ished a number of act ions for EN DES per'sonnel to take inorder to identify and document cable bend radius problemsevaluate them, and provide resolution for those determinedto be problems.'
16. The Watts Bar Design Project Manager issued a memorandum to'Watts Bar Nuclear Plant Construct ion Project Manager onOctober 14, 1983, on the subhject "WBNP Llrits I and 2 .NRC .-
Unresolved Items ReinspecLion of Cable linstalled Under D1RNo. E-9 Prior to IssuanCe of Revision I" (EEB 831014 936),as follows: .. ,
Refferences: 1. My memorandum to you (dated,October-27, 1982 (SWI' 821101;036)
2. My memorandum to you dated June .
30, 1983 (EEO 830630 910)
3. My memorandukm to you dated July . . .28, 1983 (EEH 830729 926)
EN DES dispos.ition, dated May 22, 1979 (SWP 790522 .:.
045), of D)esign Information Request (DIR) No.. E-9 4.a I owed cablIes; to be t ie, down (t ra ined) to 50 { -percent of their pulling radius values. -This ... ...
allowance was rescinded by Revision I to DIR E91, ,dated May 18, 1981 (E-B 810519 938). The subject " ..NRC unresolved i trems relate to the concern.ofothose cables installed during this two-yearperiod. This memorandum addresses the adequacy of,.the training radius of installed cables at.WBN.
As yon know, WBN CONS'r wrote NCRs 4194 and 4933relative to class IE shielded power (V5 level)cables - installed in trays and transitions fromtray to conduit; reference I informed you that ENDES was requesting informat ion from WBN -cablevendors that would allow cable training radii les..than the minimum cable bending radii for pullingthese type cables, as specified in DS-E13.12 andTable 3.2.1.2-I of Construction SpecificationG-38. Relaxed cable training radius values,!received from WBN cable vendors, for these cableswere provided in references 2 and 3. In . somecases, a relaxed value of less than $0 percent:was
44
AT,
X:,
S1 :........,.,-"• ti
.i:i,,.:: •A ?'?
All OV
H•
obt.-ained from tthe cable vcNdnr.
WHN CONSTha, ..
Comnpltedt closure of NC:s 4194H Hl and 4933 R2 "
Therefore, DIR-E9 has been satisfied
for V5 level .Q
cables.
From .the information received from cable vendors'
together with a review of cable bend radii in
Insulated Cable Engineers
Association (ICMA)
standards, EN DES has approved
Electrical Design
X."'7
Standard DS-E12. 1 ,5 on September
20, 0983 .(ESB
831005 203), which includes relaxed values, for
installing insulated
cables; this design standard-L
was dist.ributed on September
28, 1183 (ESR 831005
201). DS-E12.1.5 describes
the .minimum bending
radii for pulling cable during installation and
for training cable after pull~ng.
This design
standa rd supersedes section 2:0I of l)S-E.I3.1.2,
RO_ .
and Table 3.2.1.2-1 of G-38, Revision 3. A speci
fication revision notice (SRN) is in progressto
revise 0-38, to delete Table 3.2.1.2-1, and referr..ý,
/ýYý
ence f)S-E12.5.$.
As noted in Table. I of DS-F12.1.5, the installa
"
tion actor for the Inllation of unshielded
power and control cables is now either a 4 or 5
depending on overall cable ON.
These factors are
relaxed from an overly conservative 6 or 7 factor .
for unshielded power cables as previously
required. /
in Table 3.2. 12-1 of G-38. Section 4. 1. of .
DS-E12.1.5 also allows the minimum training radius
of multiconductor cables to be relaxed to a value
.
equal to the 00 of one of the single conductors
t imes the appropriate instal lation factor 'from
Table I. Therefore,; the relaxed training values
of multiconductor cables are a )pproximate y 50.
percent or less. of the pulling radius values., _.
An OEDC task team was formed July I, 1983, to-''
identify, evaluate,
and resolve cable bend radius,
problems at WBN and BIN. Since construction
activities are similar at the two plants, a samp- , " .. too
ling inspection program of installed
cables., was
done at BLN on behalf of both plants. Cables in- ,",'' _
trays, in transitions from trays, and in electri
" .
cal equipment were examined
in this inspectiOn. .,.
program, excluding violations
already covered in Q.
NCRs. Approximately 10 additional
cable bend.- . :Tf
radii were found which violated the minimum bend
radius requirements of G-38, These violations
will be resolved using the relaxed values .- in-...
)S-E12.1.5.0
As part of the ta,;k team's effort, a computer,:
program, utilizing condulet vendor's bend radius,
.
145KM '" ,-
-7
T-7 A.77777
PnS,
data, '.'a s run on Crinldj it s contain. ng ciasS' I :. A,,-.cables. From a wa1kdown of suspect conduits, only .*.9 contained condrilets tMat. hMve cahle installed toless than the training value of DSUE12. M5 the.
inst lied training radius of the 9 cables ý (mark .. :.No. WDO) is 76 percent of the required value..:" fThese cables are identified in WBN NCR.5062.W.".Information from the cable vendor of these cableswi I allow an installation factor of 2k times theA 'cable 01) for the training' radius of the cables. i.i '
This factor is 50 percent. of the pull ing factor of:-" ".Q.,5. Therefore, with the EN DES disposition7and.. .. "closure by CONST of WBN NCR '062, we conclude that':.no further action is required to resolve thesubject NRC open items.
17. The following design document changes were subsequently made;Q.in 1983: ;.
E Electrical Design Standard DS-E13. 1.2, "Conduit Sizes ""for Cables of Various Diameters and Bending Radii,""RO b a'v'rtr-was deleted August 1983,
Electrical Design Standard l)S-E12, 1.5, "Cable Minimum .''2':-Bending Radii for Field Insulated Cables- Ratedli05,00OVolts and Less," RO, was issued September:20, 1983V.',, .Electrical Design Standard DS-EI3.6,2, "Raceways'Use, of M,'•Conduit Bodies in Conduit. Systems," RO, was.• issued on .-November 15, 1983. ..
1984
18. The following design document changes were subsequentlly made""Ts.in 1984:
0 Electrical Standard Drawing SD-E05.3.2, "Electrical /Standard Dlrawing - Wiring Switchboard Panel " Wiring l.oMethods," R2, was issued on February 2, 1984..
o Electrical Design Standard. D-.3,6.1, ."Raceways, '".,-NConduit Box Design - iinurm Requirements," Rl , ;was -issued on February 6, 1984. '. ,-''<
o rThe TVA GCS G-38, "'Intall ing Insulated Cables Rated .p" ''.'
to 15,000 Volts," R4, was issued on March.,28 .: 1984...5_ ',
19. The NRC inspection report 50-390/84-38, 50-391/84-032, oA.f kJune 1984 closed the unresolved item as follows: X-
* The licensee issued work plan. 3673 to inspect.*,"'i•2:ig'.- inntalled cable. for minimum hend radius -in.,'a#c,." cordance with Ceneral Construction Specification.:•§,,.ý
. (>3-311, "'inta.lling Insul ted Cables Rated up toi 15K -
46........................................ '. •;-......',.'".. 55', ;5.
' " ' • v,~~:"~".';7"',Z•:-£c•-'•
T 2. '2-
"ygs
Y Iw .4
• '. '. 5 -.. •"•7*".- ". '!
Volts.'' As a result ofL the inspection threenonconlorming cond it Lon repurts (NCR) numbers.
4194, 4933, and 5062 were issued documenting...: -
cables that had a minimum bend radius .less than ''
that specified in the specification. The licenseecontacted various cable manufacturers by letter to n 007determine if the "as-installed" cable bend radius&would be damaging to the cable. The manufactur- .cr's reply indicated that the as-installed cablebend radius was satisfactory and that the` TVA-specification in this area was very conservative.. 01..."
Design engineering has accepted the manufacturer's "":reply. Based. on the above the subject cables.were. '
accepted as installed and the NCRs were cleared.
20. The NRC inspection report 50-438/84-19, 50-439/84-18, of'-
October 1984 closed the above stated violation based on the A'
following: i.
The licensee's letters of September '9, .1982 , W E.
September 24, 1982, and December 16, 1982, have". .heen reviewed and determined to be acceptable, by 'Region rl, The licensee has issued NonconformingCondition Report (NCR) No. 1889 documenting cablesthat had a minimum bend radius less than specified............'in the General Construction Specification ..(GCS).G-38. The GCS-G-38, "Installing Insulated Cables.Rated up to ISK Volts," is the governing specifi- ..: -cation for cable installation. The licensee.contacted various cable manufacturers by letter'todetermine if the "as-b•iLt cable bend radius would ...he damaging to the cable. The manufacturer's 70 00replies indicated the as-constructed cable -bend ,radius was satisfactory and that the TVA specifi-;;'... .cation in this area was very conservative. 'Design Y ,...engineering has accepted the manufacturer',sreplies.
Based on the above, the subject cables wereaccepted as insta II ed. .
The licensee had estahlished a task team composed..ý , ," *<
of representatives from Engineering Design: (EN .."'.DES). and Construction, This task team will review"... In :. ' A2
all identified cases where the cable bend radius :Jis less than the specification and will disposi-.:•olt..-'"A1tion them on a case by case basis.-All 'future .i' s
installations will comply with the establishedbend radius or receive specific relaxation.of.'the-'. 0values from the vendor prior to instaIIing the .cal Ic ,
.......... " ...".--. -• ..: . ....
A.
=OWN~1
z' ~ 12
1985
21. NSRS EvalIua t ion[
The fo) lowing represents Llie out I ine of' NSHS evaluat ion for
cable bend radius problems:
0 1 " IntOduCi o n..0 1)efinit.ion and I Iuta oI u.
o Industry Salard.0o Industry Practices.0 Cable Per formance Hepia iremeiit.o' . Ila•sis.0 Evalu at ion of Presfmit OF: Program.o Evaluation of W.3N NCR.o prvaluation of N thC PR .Srocedu r MA1-3.0 v tiat i on of Pertinent Inforn•at ion.- >Ko -Overall Conclusions.
Introduction ""; :.' -•
"The NSRS investigators determined that t he most effeect.ive-method U; ' 11.
*of presentat.ion of information reia ted to the adequacy. o f: cable.-
bend rad ius pi,)rc)1m 'reso lIt ion would Ihe In focus on the end>l
product of OEDC's extensive efforts to resolve the problem and to
refer to i ntermed i atv action(s) oiil y when deemed to be necessary .yto establish and suipport the position. ." -
Tab Ie 1 Ii sis sevewral of thlie (dcumtnts wh ich were. issud:att Ilheresult of OEI)C efforts to resolve the cable, bend radiuas problem ;.that were riewed by NSRS:. ' ..
. . .. .. . .. .. *. . ,_- ', -2, >.,.
Table 2 Ii sts NCRs of wh i clh invest i gators became aware '.:andI
reviewed that rela t'd to cable bend radius problem *:at SQN.
WBN, and HILN. It must be, noted that the invest igators did" • '
attempt t o) ens urc thatL the I i st ings i n both of . the .two
tables were all conclusive as well as ident i fying the impor-tant documents that were the foc a l govern ing dncuments.
TA H[.E
Tbh EEc issued, revi sed, or otherwire, dieleted the following document .-.a ,
the.- resulIt of OEDC rerrnmendaL ions
I . Electrical Design o S.indaird IDSEI3- 1.2, 'Conidu it r ise5 for Cables ofVarious Diameters and 11ending Radi," H), was deleted August 198,3
S2. Electri(cal De iv n ,g t an1ard .S-k 12, Ia r, ")al S -e Mi nimu1 1ending 1i adi ( i
tor Field Insulated,! Cables Hat. ed 1 (000 Volts and 1,ess " RO, wa "
issued September 20, 1983.
3. Electrical Desigo ;t .indlard 1)S-El *j . 2,"Raceways Itile of Conduit.IBodies .
•. inl Conduit Systems," R0, was iSuiiceid on November Pa, 19H3,
48' " " ' '""""
• " " A ?~~~' r ,'+ • , "
~ A"
~
4. Electrical Starrdartl t)rawing SI)-EIS.3.2 , Elt,crical Standard Drawuing Q :-
Wiring Switchboard Panel Wiring MeLhods,7 R2, issued on February 2,
i984.
5. Electrical Design Standard DS-I:3.6.l, "Raceways Conduit Box Design
Minimum Requirements," RI, was issued on February 6, 1984.
6. The TVA GSC 0-38, "Installing Insulated Cables Rated Up.'to 15,000 .. .
Volts," R4, was issued on March 28, 1984.
TABLE 2 ,
The EEB personnel provided the listing of the fol lowing NCRs that identify
cable bend radius problems of any sort at SQN, WBN, and BLN, . . ...
SQN NOR 2845 .. :.
WBN NCRs 4194, 4933, 5062, 4274*
BLN NCRs 1889, 2053, 2331, 2372, 2490*, 1716* ".1
*Those NCRs ident i fied by the invest igators as a result of a_ cursory
review. of related ,documents.
Definitions ard Illustrations
To facilitate the presentation of relevant. material and min mi ze"y '.
the complexity of all .issues related to the cable bend radius •! *'*"-'.
concerns, the fllolwing definitions are provided:
0 R , mintinrur1n pullirtg bend radius i ! de ined to fe the
SriAIIest radlius tn which a cable may be bent during pullingoperat ion (cable is under tension). This radius is. measured don the inner curvature of the cable and not the axis.
R T , minimum traini..g ,eend radius is defined.to be- thesmfItest radius to which a cable may he hent'lafter all '
pulling operations have been completed (cable is under zero&
tension),. This radius is measvred on the inner curvature of ., 1~'._
the cable and nlot the axis. " .
Medium-volIayV .cables .Cables rit.e'l for use in 5-15 kV 0;
power appliation.
low-v dlt I ae cables - Power, ront ro• , a nd instrumentation -`, .,.,*
cables ratedl for use in 600-volt or Iless application, . V .
To 'ilIlust rate' the bacic constr~ut inn of a cable, the cro~sssectional views of the cunstructioi of medium volta and.
voltagecables are provided in Figure 1.
I ndust ry St andai rIt ' :': •• ..."i:" ".;
The; ICEA st andards de ined t he t ia hnin radii to we . the :'! 7-4
• -. ...
t'~CONDUCTORSHIELD
INSUIATION
~1,
T'P P (,Al.
CONDUCTOR.,
-JACKETý
SHIELD
CONDUICTORJACKETI
UCTOR
iring ireal
POWER:l CABLE - 1*,V!I)M V'OLTACE
CONSTRUCT ION
F1 ILER€,r
INtS ULATUOL.-COND
CA 8 I.EJACKET '-7
j
TY PI CA 1,
COtS'lR IUCT IN - 600 V.CAilA,I;
(:ndiactir Aluioldfing 7 A conmducit ng r'a1erhlt oprilted In mrtnufnrictover the w~irfr ofie i th !I tofduCto~r'nd .f Irm irlruzdiri fiev
nne IIIPI uIrI tfa n, theP Iriu'io i n~(tion.. . .-
InunuLt ion shielding~ A rotnillwt lng' mnterala apilefd uovor the oonduactilr I nljI itflt I owm'q
"hoath (JA~cket.) -The ovvirnal pro? 1'ci vo covering (,,r tit,' In.tillatc(f (al I
49 A
-- C--A
V
K
0 0
-~1
minimum values
to which the cables; Iay hi' bent for, permaiontL
i
training during
instIa lat ion." I further
definted -that" these.'•
''
minimum bend rad ii va I ues
. . do not apply to condu i t ''nI,
sheaves or other ca rved sit r faces a round wihich the cable mayhe lie
put lled under tension while heing ine;tailed.
Lar La radii bends tY
a rre tuired t.• su.ch cond it i ons• (NSRS underl ining)
The minimum t ra iniing radi i has been defined
to he a function of. f
the ove ral Id Iiameter . of' cahlt,
multipled by a factor
commonly
referred to as an instaltation
factor. This iiutallationŽ,factor
i
for mhielded powe'r, rontrol
and signal cablels has been defined as-,1
12 by ICEA. The installation factors
of 4, '), or 6 times tl
overall cable
diameter are the ICEA established
values:.for
.•
unshielded power and controlI
cablcs wi th overal Icakble
'diameter ''
of less than I inch, more than I inch and lcs- than 2jinches sad,
more than 2 inches , respect
ively for those
conductors,.. with
conductor insulation
thickness of 155 neis or less.
Industry Pract ices
The industry ita general
uses t he Ri av.m i ues at termination •.
points of the cable and as such° for a fal t iconductor
cable, the' I
jacket is removed
as we.l l as the fi ler material and individual
-
conductors are terminated
accordingly. It is only at termination
" '2
points that the jacket
hai; been removed ,and is no longer
an
int egral part, of the cable,
Theretfore for the purpose
of
calculating R. values
the standards allow
atilizat ion'of
,the
O of indivi •aal coductor ra t.her than t he overall
OD ' of the
cable, The overall
01) of the cable is iat ended to be considered'
anywhere else along the cable
route, since
the jacket .:remai ns,'
intact.
. ..
Another application
of R T within the industry
is for'-forming
2 J
cable in the cable trays around only horizontal
bends to maintain
an orderly mad neat cable Iiydown
arrangement. This practice
of , ,
forming thOw cable to its respective
R. i value is only'done when ",:-
the cable i!: under zero t.ension, thul precluding
its application '5<
for vertical rims since the weight
of the cable maintains tension,"
on the cable. In this situation
also the overall .jacketed
cable"
01) must be th, determining factor
for calculating RT'
and not.-
the OD of individual conductors.
Cable Performance Re~t i rement
, '
The basic requ i rement
f or cable perforniance
is that the cable
should have a serviceable
life at least equal to the designAife
of the power generating station
at the desipn voltage
and current,..
ratings while subjected
to the dlesigned
environmental conditions,
Cable rel iab!ility,
in a nmeclear plant.,
is of utmost importance
for assuring safe shutdown
of, the plant under all postulated,*.-.
conditions. Thtrm al tabhi I ity, moisture
resistance, . fire
resistance, as well as radi:aLiotn
res istance are among.
those,:•>
characteristLics which the cable must conform
to in order, ,.to
50
provide assurance that the ca bl. w'ill perform its Itended design 4
function.
EEB Basis
The basis upon which EEB had developed its philosophy and, con-.
sequently design standards, General Specifications, and RTmn R
values as well as dispositioning NCRs were found to be..
1. Use of installation factor multiplied by conductor OD (for
multiconductor cable) rather than cable OD for establishing
RTmin s acceptable values for nontermination situations.
2. Assumption that. when cables were pulled R was satisfied'.
and that only while training were HTmin1rlems generatedMPGDrtia
3. Disregardingý tension inherent in vertical runs,. both 'An'
conduits and cable tray systems, by allowing applicatiOn,'ofý.,
R values.Tmin
Evaluation of present OE Program .
I. Electrical Design Standard DS-E12.1.5, RO, "Cable Minimum
Radii for Field Insulated Cable-, Rated 15,000 Volts. and
Less," issued September 20, 1983. . . . ..
o Table I of this standard provided one set of instal-ý.
lation factors :for calculation of R and' R
These values were based on applicableN&eAwhich defined R Therefore, the Design Standard
was determined tImWve unacceptable since it established
that R equals H. , whereas ICEA required.Rpmin* to .be greCITVe than R Pm.n "
Tmin .
o The second paragraph of section 3.0 of this standard
should, but did not have a qualification statement._..limiting its application to the. points where cable is.,being terminated. Only when the outer jacket hasibeen.-
removed can one apply the OD of the individual,:7con-ductors for calculating R 'values.
Tm in
o The exceptions listed under section 4 were determined .:'r
to be totally inadequate and unsupported by, an engi-
. neering justification. A multLiconductor cable. as • ....
previously discussed should not have its R value
based on the conductor OD; rather, it is to bem sed.onoverall cable OD, as detined per applicahle :ýý,.ICEAstandards for all points of cable route other ..than .
termination points.-1
o Adequacy of information on Tables 2 and 3 of Electrical.,,-•
Design Standard DS-E12.1.5 was found to be indetermi,
nate as annotated in Table 3 of this section.
51
... . ..
• °- '.2." 2.
U
3.
-Eh
NSHS has re1pr i nt ed page 4 o4 this ,LtIndard. in it% .
entirety and has alpha-coded, its evaluation- and pre-::sented -it here as page 1 of Table 3. Explanationf..Pf _k."
alpha codes is on page 2 of this table.
o 'This standard only dealt with RTmin values ...and not _
R P m v. ue s . .... T m
Electrical Design Standard DS-E13.6.2, RO, "Use of Conduit L.
Bodies in Conduit Systems," issued November 15, 1983.
o This standard defined the reu ir~enemints for selec-.'t ion •
of a condulet fitting for a particular application 2ffbased on the inner radiius of the condulet. Discussions:
under part 5 of this sectioI clearly indicated. that amajor attribute in selection of proper size condulet,namely the sizeC of condiulet opening, had beerin.;over-looked. Therefore NSRS concluded that this 'standardwas not fully adequate for its intended use. It wasrecognized that there were references in this standard -. '
to other documents that NSRS had concluded-: wereinadequate and these inadequacies a-re discussed sepa--rately per given document in this part of the report-.. ..: .. .....- .
Electrical Design Standard DS-E 13. 1.2, RO, "Conduit Sizes'-for, Cables of Various Diameters and Cahle Bending Radii,deleted around August 1983.
Paragraph 3.0 of this standard ,lefi ned the cable bend radiifor pulflkiS in conduit to he equal to the OD of the-cable -.-•- -
multiplied, by installation factors that had minimumw:values-equal to those provided by ICEA standards forR . '"Thisfurther illustrated that EB considered R T 1A t-R Through the evolution of cable bend ra'dius problem .-,Eh1aocuiment language shifted from discussion of bend radius"•and "pulling" bend radius values as the governing values: to -.
Rm . values. ICEA required that R be greater than Y!Tmin • •trin •-",•:
RTmi' but specified only R, values, Had FEB design >..T iln .. .
documents specified R n . v!ani ur's greater than ICEA. re-quirements for R. P[Uin all-owi g R;min to equal. theIt(larger R I wouldn have been both a conservative andjustified] eclfaiLty.
Although the minimum installation factors in this.standardwere for R and the standard was deleted, nevertheless .
the acceptarmtIt y of the work performed while. the ýstandard.::."`ý-,
was in effect is indeterminate. .. .:
-5.2... ......... .4"" .-• • ; .• . . .,:' ' ; : '
'-4
I ...................v.•t• • •.,r<... ,4* 4 . '¢.,%, : ,;.•.. <,,.i,,• •/ ') -,, .-
S-GROUP: CABLE•:''ITITLE: Minimum Rad i i
•- ,.• . .. - Cables Rated 1,
Cable ManufacturerCable. Size a (7c-
OkoniLe Company 3,6t(4.4 x cable OD)
S, : Collyer N/AInsulated Wire
_(I X-. able OD)
Anaconda-Ericsson, N/AIncorporated(8.4 x cable-OD)
Rome Cable Corp. N/A(10.9 x cable O0)
S' .. Essex Group N/A(7 x cable O)
Genvral Cable N/A-" *, (7 x -able OD)
Triangle-Plastic N/AWirt, Ia l Cable
: (7 x cable O):¢;I
Pag'Y~l of~ 2I
I Il I WI-
5,000 Volts an LssELECTRICAL-DESIGN:STANDARD'DS-E12.1.5
IORIG ISSUE 9-20-83REV NO.REV DATE:TABLE 2 ISHIELDED POWER CABLES (Wy Lc'vrl) Level)_ •-
Minimum Training Radius inches . '.. 1wb 4/ d' W6 6b '*MC PIT_
i
4.91N 5.8
C~ 7~..
• q, .................. .. ,.
9.10 N/A
N
N/A
N/A
~,4
IIN
N/ '
I 6.68.""F
12.00 '':
B
C
7 .59.. s ii,:..
N/A
- --- t-.-.--.-- r - !
8.39
C,
N/A
12.00D
N/A
N/A
7.21
X
N/A
N/A
N/A
8.05
X
NIA
N/A
10.24
A
N/A
N!A
10.77A
N/A
9.4ý
X
N/AI
NA'
,/A ,
NIA
10.00
A.
N/A
"I/ . 97;
1. fincludes section 4.1 criteria for multiconductor cable.
A. Ri C:, D,' F, F*, r, ann d X S..,e pu 2 for oxnl anit inn.
"TAR 1 ~-""
C ble Manufacturer
BILN -SHIELDED POWER CABLES (V5 I.evel) . .
Minimum Training Radius (inches)
2/0QAWG _ 7/0 AWG 300 MCII 400 MCII 500 CICable Size
Olkwi il I v Coinl'illl!
(4.4 x cable. O)
Coliyeri. ksn itcablie
(8.0 x cable OD)
9.10 N/A N/A N/A N/A';
- - I
-4.
52A
.....................................................''.,"f,{.""7
Page 2 of. 2-"
TABLE 3
EXPLANATION OF ALAPHA CODES
A. Actual testing conducted by Essex Group, accepted RT min 7 x OD.0,1for only those cable sizes that were tested.
B Actual testing conducted by Collyer Insulated Wire, accepted.`("..
RT = 8.2 x O0 = 12" for only the cable size tested.Tmin
C Anaconda Ericsson, Incorporated, conducted a very simplified test,'-,.accepted RP, 11.75" for the cable tested and RT mm 12"V. for!,all other cawle sizes smaller than the tested one. Acceptability.was based purely on visual examination.
D Rome Cable Corporation did not conduct any kind of test, acceptedR = 10.9 x OD, did not provide an engineering basis.T min
E Okonite Company provided engineering basis for the acceptability ofRT m = 4.4 x OD = 6.64".
F Okonite Company provided engineering basis for the acceptability, of,
RTm = 6 x OD = 8.844". and not 4.4 x OD = 6.68" as noted inpage'? of this table.
G Power Cable Engineering Center provided R . 12" for all cable
sizes smaller than l/c 500 mcm, acceptabiTpi hased on item C.,above.
X EEB.did not provide any documentation to substantiate manufacturer'.s.recommendation/approval for the relaxation of R x OD to thoselisted. .-
The NSRS considers the testing reports and an engineering basis-provided .
by the cable manufacturer, listed as A, B, C, and E, to support. the cable ,
40-year service life performance requirement adequate for normal-.conditionshowever, the adequacy of cable performance under abnormal conditions(environmental as well as electrical) remains indeterminate and is .' - . .
detailed in subsection for "Cable Performance Requirements."
k
U
~
'V
72
52B
7-*,T 177 2 , -: 7
•,A¢ : "../i :iil
V~.
/
k
A'
4. Electrical Standard Drawing SD-E15.3.2, R2, "SwitchboardPanel Wiring Method," isstied February 2, 1984....................................... ''.........:. ';.....
0 This standard applied to TVA wired panels ':and i,ý'TVAj:¢hismodifications made to.-.vendor panels. Note 6. Of•t "Adocument was considered to be adequate as long as the,:--
minimum -bend radius referenced to was defined tjo, be.R,,n and since this was' applicable to, panel wiringble istrintdn wdnc'th r."•wtere cable is terminated, then the OD of the conductor
is the proper OD for calculation of RTm when' the,,.
outer jacket has been removed. . ,.
5. Electrical Design Standard DS-E13.6.1, RI, "Conduit Box.
Design - Minimum Requirements," issued February..6_1ý`,":198 4 .,.
0 This design standard established the minimum require- '.ment for sizing the opening of the embedded conduit. t..
boxes. This sizing is dependent primarily. on the ",•minimum .ul__li._ng radius of the cable. Although. the.standard illustrated an embedded box, nevertheless themethod of calculation and engineering basis -. weredetermined to be identical for exposed boxes and:•condulets. This document referenced DS-E12.1.5 for -•
determining the H values and as previously stated,DS-E12.1.5 providei ohnly R , values and therefore onecould not obtain R valPuJes as was necessary.,A -,
Pm'nthough the NSRS inves-ligators concluded thatr'.the value ,to be used for siziing the 'box opening was R ''asnoted in this • document, EEB management'--pe r'onnnel t.i +
responsible for development of DS-E12.1.5 and'those EEB i, 'management personnel responsible for GCS"G-38 felt.,R values were applicable. .It must be. noted" that .t~e'%asis for OEDC team evaluation and resolution ofcable bend radius problem was the fact that"...R ,values were applicable and NSRS found this posititon obe unjustified. The EEB personnel involved in the OEDC-"-:',-i,-team confirmed that although the cable may not.'be under '.:ýt---
zero tension, the amount of tension is insignificant'.The 1CEA standard allowed "zero tension" rather *than <tv
"insignificant tension" for which R factors..,ouldbe utilized.
" .Tmin
o NSRS concluded that the major aspect. of cable bend
radius problem as it related to use of conduletsi'as,!tipull points was overlooked by the OEDC; 1..-team' sl;:evaluation. The actual opening'size of condulet or box,-,,to allow the cable to be pulled out and fed :back .in--without potential damage did not appear to be a routing.: ,iinspection consideration at all, The investigtators":,>while visiting WBN, randomly selected a cable.pull."operation and witnessed a cable pull in process.,where,-., ,the crafts, the foreman, and the inspector were all :present and were about to pull a cable: througha"condulet that did not have, sufficient openingto allow
,T:••53. '
d
Lhe cab1,le to he pi ld out Ind fed back in without. .violating Hp I This activity was being accomplished dunder Workpaia' 5093 RO-l for cable 1PLC3504 . in the ýauxiliary building for unit I. This cable was pulled .'.. -
through a section of conduit and out through a-condulet .
that already contained another cable of the same size.'Upon NSRS inquiries as to the adequacy of the openingof the condulet, the QC inspector (NUC PR). appearedunaware of the requirement for the minimum size' of the j'.
opening and offered to consult with ain engineer,. The 'craft. foreman indicated that' there were a number of ,
other places where the same situation existed.and.. ,
decided to stop further cable pull operation. .•- .:. "-
6. General Construction Specification GCS G-38 RS, "Installing'Insulated Cables Rated Up to 15,000 Volts," issued February .-.
13, 1985.
0 Paragraph 3.2. 1.6. I explicit ly stated that I n value i -!
are determined through the same method as usingthe same installation factors. This' establiise;tART, nequals RH which was considered to be erroneous'sin e1:P,,11_the instUaitat.ion factors referred to were ICEA values..established for calculating R R values-were.'.for zero tension on the cabdmbi Ic ~n stipulated.,'cable in the pulling process (i.e., und~ rension). ande rtherefore must be larger than R values.
Tmin
Paragraph 3.2.1.6'2 required OC to determine that thecables,; can be installed per designated route withoutviolatio of cable hend radius. This requirement, inthe judgme,*. of NSRS, was misplaced since the time toverify the adequacy of the raceway to accept- and.contain the cable i-s during design and installation of ,½the raceway and not during the cable pulling operation...
0 Paragraph 3.2.1 .6.3 permitted a cable to be bent to
values less than its R temporarily. There was noengineering basis provdT•e in support of this reliefnor is ther, a minimum time limit established for thisviolation. This was considered by NSRS to be unjusti-*fied since degradation of cable structural integrity asthe result of overstressing while being bent. to alesser than permissible Rrmin is not a function of. timeonly. * Thin
This same paragraph stated that where feasible,.cableshall be visually inspected where it had temporarily :ýbeen bent to values less than RH . . NSRS concludedthat visual' inspection would no.m necessarily detectstructural damage such as shield separation.
I
54
10,15 -T
R.AW
mom, trw:s
Milk~
vas $Q
Evaluation ot WBN NCRs,
NCR 4194
WBN generated NCR 4194R on July 22, 19A2, which .identifiedFl
violation of R values for a number of medium .voltage level 0. Tcables. This dRiiwas revised non October 22, 1982, *and (disposk-'9tioned by WQBN Design Projct. Mlaager on J,,e :Jio,.1983 :yThe'; ;di spositioning of Lhe NCR was based on the inquiries *that EE p1had;'-'0made to the seven cable manufacturers that had provi~dhd mCed iUll :"-'ý..,.ý,.
volLage cables to WBN. The detail of NSRS review of the manul.-iMfacturers" material is covered in section V.C, "Evaluationf-qPresent OE Program."
Table 3, a mod i tied tatle tLaken frolm flS-E 12. 1 . 5, ideit if iedspecific cable mant-factlrers anld their crurersponding supplied,',nvoltage level 5 cable sizes. Also included with Table 3 in theNSRS evaluat inn of Lhe manufactuirers' jstil it icain of.relaxaLion ;
.of R from iICEA standards. for cabl es s uhujvect.ed Qto ::) maior ,1a '•,--operajihg ei nv i rOuiment.. As can .be seeni Irom a review ,,of theQ.Aýinformat ion alpha coded hy NMRS, those cable s identif ied with A, ::..B, C, anid E ('odes were determined to have aidequate manufacturer's .•Ojustificatioi for normal environmental ant tiins, Therefore,-thennor.-cables nonconfnrmed in this NCR must hie reviewel to ensure thait`.,they are thoei,' ident ified as A, 11, C2, Aini E, or otherwise the,:?,"i "`,•dis;positinnling of tLhis NCR conuld not have been-, adequate.Additionally, further test ing must. he conducted to determine. theacceptability or the elaxi;9 wiluaws for cables that are syubj•ecedto harsh environmental condition,'n " n.:" ..
NCR 4274
" C NtR 4274 issued originally on hay II, 1083, identified cablest 5•W;
that had been damaged in a condulet at well as having violated2;R Although no reasons were 1rovided an to how the cableswere damaged or what, could have caused the damage, the OEdisposition was; to replace the condulet with a Ul! Iboxand J""repair the damagre. . .
It is noted that no attempt. was made to determine as to whya "Vj
condulet was used in theý first placeZ 'The instruction for .pre-VY b.venting furnher noncojormance was to cnmpy with G-38-rrequire. -K7
ments, which was inuappropri:ate s:ince the inustalled condulet sizewas i nadeqjua te a~nd1 an A result cable was bent more sharply thaunallowed: GCS C-40 which provided requirements for installation :,T -
of a raceway, in' tluding conduits, , did not, address sizing of pulIlQ,-'-boxes/condulets. Sizing of pull boxes/condulets is covered I' YDS-E13.6.1 (which was detailed earli.r in subseCLion, S of"'Evaluation of Present OE Program).
NCR 4933 ... ...
'0'oNCR 4933 was initial ly generated on. june 22, 1983, 'to identify I'Violations of R for medium voltage level cables in cable trayrmin
x,
....... ......
-'4.
'~ ~ ~
-~ '.. .~.
-~ ~,.. '4
-''.7,
W",'
systems for a large number of cables. This NCR was, revised'to:_
reflect those cables that did not meet the relaxed..:values. as;`'-
obtained by EEB from cable manufacturers and to indicate that ,:4i
most of the violations were as a result of DIR E-9 •'"which 1
permitted cables to be tied down to tray rings fox T PR.......inprior to Mlay 18, 1981, when the said DIR was rencindeo. ::"•-.
OE approved the recommendcd disposition of reworking those cables.
that exceeded the .relaxed values to values not less..than those
received from cable manufacturers. F: W. Chandler's memorandum jof September 16, 1983, to J. A. Raulston (EEB 830921 903). on .'the
subject,. "Medium Voltage Cable Bend Radius, *NCR--"4933,-. Final
Report-to NRC," noted that: :.,""'; 41
From an engineering evaluation of the cable design and:%,.- /•.
the minimal amount of .rework that is necessary, the'
serviceability of the cable will not be adversely .. .
affected; therefore, we concur that the dispositioning-k '.:.v- -
of NCR 4933 should be rework. .
It should be noted that none of the cable manufacturers provided'-justification or test results to indicate that a cable- can be-.•forced to form a bend with radius of less than ICEA values, or.'',-
relaxed manufacturer values for a long period of time without-'.
damaging the' structural and functional integrity of thei.cable..Although GCS G-38 R5 paragraph 3.2. 1.6.3 stated that.:
-It is permissible to use a cable which has' had itsminimum training radius tem)orsarily exceeded if"theoverstressed area is relieved by returning the cable to '
an acceptable bend radius. Where feasible, the cable .-..-
shall be visually inspected to ensure that no damage .can .
be determined in the area of the bend.
Issues to note are:
(1) GCS G-38 R5 stated that R can be violated temporarilywithout specifying by how mtch* or how long. Some,,cablesidentified in the NCR could have sustained a temporaryexcessive bend configuration for two years,
(2) There was no analysis justifying temporarily" violating i'''•RTm in .-
(3) Damages that medium voltage cables could receive as the.
result of this violation are not. necessarily, visible, .
therefore visual inspectior may not detect the; damage.
(4) Feasibility has no relevance to the examination of. the* structural and functional integrity of the cable. '
• --
iN: ,
564
W*V
NCR 5062
NCR 5062 RI issued October 16, 1983, identified three-sets of low
voltage cables that, had been befit to values less than"R Tmin in
conduit fittings. OE dispositioned the cables with recoamenda-."ýkJ
tion of rework for two sets of cables and use-as-is for the.third,&<',
* set.
The investigators concluded that: ..._
o The rework disposition was found to be unacceptable as
previously detailed in the NCR 4933 evaluation.'
o The use-as-is disposition was indeterminate since there was
no objective evidence to indicate the values to which these.'
cables were .in fact bent. The NCR 5062 stated -that "
the minimum bend radius of 5.255 inches for these cablesh d.',
been violated in the conduit fittings," with no indicationý:,,
of the actual installed radius. ,:.
Thn information supplied to WBN CONST by J. C. "Standifer's'," •
memorandum of October 14, 1983, to G., Wadewitz.(EEB 831014
936) did not adequately address, the justification'-for the
acceptance of the use-as-is si.nce (1) the cable manufactur" ''i
ers for those cables were. not identified and (2) the actual
bend radius to which the cables had been bent was not docu-:i
mented/I isted.
Evaluation of Nuclear Power Procedure IAI-3
WBN. Modifications and' Additions Instruction MAI -3 R3,- Installa-,
tion and. Inspection of Insulated Control, Signal and Power .
Cables," dated February 14, 1984, was reviewed and found to be;i'
inadequate for its intended use in a numl'ei of *areas already..•.•
discussed elsewhere in this report. The investigators.noted that.
paragraphs 4.4.3.4 and 6.1.5 of this procedure permitted "the use
of minimum tie down value of 50 percent of the bend radius." As
previously discussed WBN CONST was cited by NRC in mid-1982 on.,-,
this same subject. The investigators' discussions with WBN N1JC
* PR cort-izant management revealed that this procedure was revised'i
on 4arch 4, 1985, to comply with G-38 requirements. The adequacy
of pulls made during the "50 percetit rule" was concluded to be, ):
indeterminate at this time.. This procedure was used for WBN unitV
I acceptance criteria for Appendix R cables recently: pulled.
. Evaluation of Pertinent Information .. 'i: .
The following is a synopsis of selected subsections V; C. I through `""
20 which addressed the development history of bend radius.prob-<
lems followed by NSRS evaluation of the subsection.
o Subsection I had defined R values and subsection; 2.provided clarification of R , and defined it to be. '_m
after the cable haTVeen pulled. It also referr
57"/ .
............ ..........
* 2<
.4-~.4
the reader to the mann fact irer' s recommendat i on values" perG- 38. .... - i•i
* There is no industry acknowledged practice that had'estab-
lished oRr . = R nor could FEB provide any engineering .. ... ,V,-
basis fori.•ls re'a.'onship. Also, it has long been known
that cable manufacturer information of this nature had never,:;
been requested or made available unless there was anexcep-
t.ional r tituation. . - .. ,"..
o Subsection 3 rescinded the ýR R , .I . .relationship
although it. emphasized that this re"lationship was fore .
cable termination...... .or when ". cable is being tied
down in a cable tray after. the cable has been, pulled." .
The ICEA values were noted to be applicable for determina-
tion of R "The training radius is the minimum to which -Y-,
a cable sRI'ld be bent without tension on the cable .was,. ,
provided as; the condition that must. be met for using ICEA
R~. values,. This document provided approval of. ap pIi%fl n of conductor 01) rather than overall cable .01) at .. -.
termination points as. well as R values that must be met.•Ta e n
while training cables in cale with 12-inch radius.
Although EEB personnel had just recognized the applicabilityof ICFA values for R there was no indication that any.of IEA vluesfor Tmo
consideration was given •o determine the adequacy of cables..
pulled while allowing the Rp T RIi. It was, alsoP'minl Ti
apparent that cons iderat i oft was not .,Vn Lo (1) , RTminvalues for cable installation in vertical cable trays as
these cables continue to be under tension--the weight:, of the '
cable--until the cable is tied down to the cable tray..? The
ICEA R values cantot )e applied for installation of.
cable in any kind of raceway, cable tray, conduit, etc,,. as
long as the cable is. tundte-r t.ension; and (2) the fact.-that'.ICEA R values for shielded cable was 12 times- cable, OD,
while jin tray fittings h,-1,' 12-inch hend radius; therefore - .
those cahles of overall 01) greater than I inch could 'not. be ....
tied down in the horizontal fittings in a form-;that was...4 $•..,
parallel to the tray siding, nor could the cable follow, the-..
contour of 12-inch vertical fittings without lbendidig itself .
to a value less than RTmin. -. -.. .-
.0 Subsequently NRC Region. II inspectors identified., an- un-
- - resolved item and a -violation as discus:;ed in subsection:.4 '
at WBN and subsection 5 at. BIN in 1982. Also the, CAT
identified the same problems at BIN in 1982 which is dis- d. I.
cussed in subsection 6.
Based on TVA's response, NRC Region 11 reported -in--1984,
"that TVA had contacted various cable manufacturers -:-by.letter to determine if the 'as-installed' cable bend.'radius.1ý?.,
would be damaging to the cable. And that the manufacturer,"'.'i
reply indica ted the as-installed cable bend radius.-,ýwa11*v -:'' ,.--€
I
I
58
M ,
satisfactory And that TVA' s specificaition was very consterv-ative and EN DES had accepted the manufacturer,'s 'reply.Also the fact that a task team had been composed .of EN DESand CONST personnel who will review all identlfied'cases.where the bend radius is less than specification and willdisposition them. on a case-by-case basis. All .futureinstallations will.comply with the established bend radius."
The investigators reviewed the manufacturers' documentation,that FEB cognizant personnel provided to support ,EEB'sposition which provided relaxedl R TI values for mediumvoltage cables (shielded). .Deta1 l' "of this review arecontained in table 4, and are highlighted here.
The investigators concluded that:
'~4.,Al
K,'
(i) There was insufficient manufacturer 'sdocumentation, Lo substantiate the relaxatifor all cable types and-sizes in question.
(2) There were a number of inaccuracies ispecified relaxed values which were lessapproved by cable manufacturer.
(3) TVA's specifications in regard to Rminshiedled cables were not in fact conservatime of G-38 violations, rather they wereminimum values recommended by ICEA.
The investigators reviewed all material/documents prowhich were to have been justification for relaxativalues if they were discovered to he less than thvoltage cables. The -result. of this study was tabula4 and is summarized as follows:
(1) Therf was a total of 21 cable manufacturersupplied cable for WBN and RLN. FEB's letter ofdetermination of consequences, and shorter servthe result of violation of ICEA values for R_mitted to 18 manufacturers. Only 10 of them rewhich 5 did not approve violation of ICEA R ,the other 5 that approved, the relaxation, Te aci
qualifying statement or conditional. approval.
(2) G-38 R3 (effective from September 27, 198September 26, 1984) provided a set of instructionpulling activities including a table of a setmended" and "minimum" installation factors to beby the cable OD to determine the bend radii fornonshielded cables of all type used by TVA. AG-38 was silent as to whether the bend radii inR or.R nontheless, since the table wasTmin. p Pm inwi pulling activities, the inference was that
R values and not R. values. The minPmin Trnn
59
support t, orion ofR'R
n the EEB- "than those
values fortive at theexactly..the
vided by. EEBon of R
In
ose for. -owted inTable
s that hadinquiry for
ice life, aswas trans-
esponded, ofvalues and
n provided a
12, ,throughns for. cable
of '".recoin-multiplied " ,7
shielded and,Ithough the* '•'' ""'
question is.:.associated .-- ....these wereimum 'values
-J ,. ) *• . i .. . : ' - '•.v :: .'
La
~.
~
~p~' .',---
5-;.
U.S
Table 4
.5.-
. CableManufacturer
ReRelaxa ionApproved
No Yes
ICEART min
ConservativeYes
Manufacturer'sReply Date Comments
12345
78
910111213
American Insulated WireAnaconda Ericsson, Inc.Belden Corp.Boston Insulated WireBrand Rex Co.
Carolina Wire and CableCollyer Insulated WireDelco Wire and Cable
Eaton Corp.ITT Susprenant DivisionOkonite Co.Philli Cable CorpRockbestos Co.-
8/25/839/9/839/12/839/1/838/29t83
No reply.No replyi.8/31/83
10/13/83No reply9/29/83
9/8/83
X
xxx
X X 3 x ODNot less than 10 x ODFollow ICEA RT m.Indeterminate for abnormal
service condition
Expect response from.their-.- technical. department .
O3xOD when Psw 700 lbs.
4'x component DD, unshielded8.x cable OD, shielded
Should not present a problem
X
X
X
11.I
I12
2
.5.
4
.5"-
*55<
4 Rome Cable Corp. 8/24/83 X5 Teledyne Thermatics .9/7/83 X8 Tensolite Co. No reply7 Thermo Electric No reply8 Triangle P & C_ No reply9 United Technologies Exxes No reply..0 Times Wire & Cable1 General Electric
Side Well Pressure-Psw
-NSRS i nvestigators -could-not locate EEB's. letter of inquiry to this-...EEB did not consult with this manufacturer since "it had supplied sm
manufacturer.all footage.of cable."
.! i '' : :• • :.
;' ~"'.>I~,
-".~'
'2..
0
.
0
0
0
~"&-' ~.
I isted in this; table:,. .3.2-1.2-1 of t -38 R3 for shield€dcables, vere in fact ICEA HT. values. The investigators Y,
could not determine the bastilor e;tabl ishment of some. of 4.
the minimum Hp values for unshielded cabie as wellMMasalrecommended R values provided in. this table . 4P '.' ". . • ,•.. . " .
The present Electrical Design Standard DS-E12.1.5 RO issued
September 20. 1983, Table 1, provides ICEA R. va Ieus -
although the ti tLIe to this.table d i d not a,1,quatefly ,lescrlce i .•,..
that hese values. are R values. Based on interview with
EEB cognizant managemenlinmt was revealed that FFB considers
these values to be applicable to R u. as well asR., It
must he mentioned that Electrical I ,n Standard DRY3. 12,RD issued on July.f21, 1976, contained the same table, as inG-3R R3 with the -same installation factor values and were -'7;
provided for the purpose of calculating the cable bending q;
radii for pl II ing in conduit. This standard was superseded
by DS-EI2.1.5 RO issued on September 20, 1983,. and DS-E13.1.4 Rlissued on August. 24, 1983. It msut be emphasizcdthat R T values were for zero tension and ICEA stated very
,Ttnexplic itl that H , values; must be greater, thtan R Tvalues. DS-EI2.1l• not~ed that. "This design standard oum- . .
lines the minimum Uending radii for pulling cable. during x *. .
installation and for training cable after installaLion."- ''
Since there was only one table which defined installatioli d 21"
factors for cable bending. radii, the implication'was~that:there was no difference between R and R which waswhat FER intended. but was in violate, ion of TN" standards.
It is r,oted from subsection 7 that a year had gune by since. ..
WBN and BLN. had both become aware of bending radius.viola ... ,.
tions and apparently the problems had yet to be resolved,It was noted that "from an EEB perspective at least, there,...does not appear to be a fully integrated effort to resolve.'-/all aspects of -this problem (cable bend radius)- for all Mprojects." - . .
Delegation" of the lead responsihility to EEB with certain JAQ7
action plans assigned to WBN and RLN management 'for execu= ............Lion by a given dale was noted in subsection 8.
Subsection 9 officially named the OEDC members of the team .--.with the charter of developing the program for defining the TON- A,
nature, extent, and implications of the cable bend problems.
Subsequently, as the result of act ivit is ties ussed in
subsections 7, 8, and 9, HEB took the lead and conducted twoseparate meetings with BI.N and WBtN personnel. The purposeof these meetings was to discuss cable bend radius, problems(at BLI, and WBN).to determine extent and severity'of prob-:
lems and to explore methods to resolve them as discussed in"V..:,
subsections IW and 12. . ,6 0. ' , ,'
•.,.,. .;. > . .!.. "" " .. ,>,
6 0 : • ,* " .'
.. ..; "• "z'/ ,.. . : ., .• . ,., - . •. :.',.> . #,. . ."A
" " " ....."' ::;" ' ' • ":: .'". '
4'~-* 4*4'.4
'4 4. !The NSRS investigttors determined that:
(I) The OEDC terim had not. documented its evaluation results or
conclusionsirecommendations; for either or both plants in a
final report. Information obtained ','as used to. justify
dispositions of individual NCRs.
(2) There 'was no evidence of the OEDC team findings as the
result of survey of industry for:
(a) Cable failure history as the result of violation of
RTin (SEP 83-08).ý
(b) Raceway system design methodology Lo avoid violation of'
The two pnges ofinformal notes of i-rnversations with four
A/E or utilities indiciate.d raceway system design method-,
ology that was not the iaue as that of rVA.
(3) The OFDC team had set Iup cutaway model condulets and had
pictures taken in an efforL to il lustrate the "worst, case"
conditiol;m. These were subsequently seuiiL te, cable manu.-
facturers te, determine if training bend radius violations
would be approved by the manufacturer. NSRS determined
through review, of the correspondence and photographs that.
there could not have been sufficient information for, the
manufactutrers to provide adequate engineering basis to
approve viclation of RT ..' if it were possible by looking at
the pictures of the mlmo up. Of ten responding- vendors,
five did not concur that relaxation for ICEA requirements
was Justified.
4.~4
4~4.
4-44
44 ~-4,-N,-.'
44
4:4
44.
4'-,
4 .4~4.4.
A
.4:
4"
444: 4:
444 4
(4) The evaluation methodology selected by the OEDC team, which
appeared to he random sample of 2 percent of Train -A cable . .
of 600 volts or less, was concluded to be an unscientific . -,
evaluation. .In particular, there were no statistics main-
tained of t.otal population, sample population, population
that did not meet ICEA RTt'n values, as well as~population
that was found to be acceptable. The investigators did not .
review the result of low voltage sampling inspection as they :,
were told by EEO personnel that records were not available. 4.
NSRS . could not determine how or ' if the result of the
sampling program was applied to the total population atBLN-
as well as to WBN. - - - .
(5) There was little documentation provided by FEB as: to the
records that were to have been generated as the result of a ..,
sampling procesS for inspection of medium voltage..- AIl:,that
was provided i-as a listing of how many cables did not meet
the relaxed RT [vies.
(6) The ,-valuation process ins;pected only installed cables under ., 44':•..
the assumption that, when the, cables were pulled R was
61
9 0i
satisf ied and that only while training were R problems;generated.
(7) The evaluation included class IWcahlrs, although criteria dfor nonclass IE cables were identical. Nonclass IE cables'n 00may have been just as much damaged and/or overstressed as :those found in class I.E. "'•
Overall Conclusion
The cable bend radius problem has not been adequately resolved. .The specifications, standards, and documents reviewed led theq: ? i,:investigators; to conclude that. the major thrust of ove efforto ,was to justify the "as-installed" condition at WRN unit I rather _,.7.1than develop acceptable criteria that are endorsed by industry_,,-practices and standards and provide adequate engineering justi- v A-a"fication for, or identify and correct, subst.ndard installation,. ,.) v;The inappropriate approach to resolution of bend radius pro- :. J"P2cedures concisely summarized and noted by the investigators to bethat TVA had to be prepared to defend the I icensabiI ity of WBNunit I using the as-installed configurations because there was.,.not time for accomplishment of major modifications.The investigators concluded that Lhe cable bend radius problem Se:-was known by management to have had existed at least since the Llate 1970s but Iad never been.e fectively resolved ,to "achievecompliance with TVA's commitment to industry standards aswell.as .1MYconforming to accepted industry practices.
vFurther, although throughout this evaluation OE continued to".require OC to follow relevant G-specifications and, other OE-initiated documents to avoid further noncompliance, NSRS con-cIuded that had OC .omplied with OE's established criteria and .§II", Qinstructions, the final as-installed cable system would have been7,',J.-:Y Ain violatLion of industry standards and practices anyway. ,; g-. 5Finally, a problem of a more subtle ,iture may have been :.generated. From the treatment of the bend radius problems, QC . ..-. ,inspectors and others could have perceived that it did not.matterwhat the requirements might have been, OF. could, somehow, alwaysjustify the "use-as-is" disposition if they we're -vilated, whichwould degrade the authority of specificatiuns,There were no indications as to whether the cable bend radius.issue was considered by OE for BFN or SQN cables.
'.D.:. Generic Applicabiiity of INPO Find iT. to WBN .. .' .,Introduction
'This section provides a brief summary of the INPO findings at BLN '?
as outlined below and the subsequent development within. OF to •determine the applicability of their findings to WBN, in particu-" ,* lar, those findings that were deemed to be within the scope• ofk W"'TTthis investigation.,
I ,
62".:
g'•
* v;.
AAA'
I. INI'O Finding.; at ItLN.
2. TVA' s Re:;ponse to INI'O Find ings.
3. F-rmat it of BEE 'Tleamn and Object ivvs.
4. BEE Team Findings.5. Format ion of Action Teams.t. Mini-internal INPO Review - WBN Unit 2 Only.
Specific Relecv.tnt }indiqgss
I. INI'O Report for BIN.2. BEE Report for BIN.3. Mini-internal INPO Review for WHN-'Unit 2 Only.:
4. O1 Action Team Plan for' BN Electrical Correction'.and
Imp row'ment s.
NSRS Evaluation
I. The Inst it te of Nuclear Power Operations (INPO) conducted
an evaluation of the Bellefonte construction project and'the
design offices in Knoxvillo during the week of February 20-
27, 1984, and presented their findings to TVA management on
March 15, 1984. This ev;,luat inn determined in part that
"The electrical portion of Bel lefonte project needs& to be
upgraded. l'roblems were noted in au'h area evaluated in-
cluding procedlural guidance, crafL pefnrmance, QC inspec-tions, protection of equipment, d,'sign, and qualityrecords.''
2. TVA's respuuse developed as a resiult of INPO and TVA re-sponse meeting of May 10, I984, And published on June 5,-1984, by iNPO (EDC 840608 701) was that:
TVA viriws the QNPO-perceived overall weakness in the 'electrical portion* of the Bellefonte project. as very:serious. A collective evaluation of associated:find-.'ings is needed to determine the total extent and va-
lidity of the INPO general concern. TVA will evaluatethe process for design and construction of electricalsystems utilizing internal or external organizationsfor assistance- as necessary to ensure an independentevall at ion . The evaluation will he complete by August1984, and corrective action will be implemented on a
schedule that is dependent on the extent and nature of'
the findings. 'Corrective actions will proceed. as,
indicated in the responses.F
4,
3. TVA OE and OC management. subsequently developed an electri-cal evaluation plan t.o " determine the extent and
validity of the general concern raised hy INPO regarding the
electrical portion of the BI.N project . . . ." This elec-
trical evaluation plan was officially issued on Septem-ber 12, 1984, with the following objectives:
63
T.-'r~ ih~t,.ri if u I,, j't:iea i i-.Y;y t,m daeign intllt , a.
criteria, and st and, Ia'd:; hIiv, been adequat elydetermined and specified to govern the detai la'd.•design,
2. 1o determine if electrical sy-tem design cri ter r I.and standards have been adiquately i n'orporatedinto the fi na I design', and that necessRary design "
ve r i f i cat ions hav v* eeri .adeh a iately perfor ern d and -•Pdoclimen ted, . ::. ": . :••',
T3 dr e t.ermine i f de s jing reqali rmnts ald guidance . ,,
for electrica Ifaturer. have been defined suffi 'Cient ly and cleear ly tn ouppoa ,t const ructiion andoperation a cti vit <.. .
4. "r dletermine if' const riict i on p,'•a c it:es adequatelyncpo-l)rate des i gni reqj I a• ement s and gui dance itSIOhte const. ruct ion i)1 a in rfg , ie r formance, anspec-
t inn, and Let .Ling c 11nt ,r0 pr -. " t!s '.F.
S. To determine if electric;al features have been and
,1re being i nst.a 1led, prote(cted, and maintained inacc'ordance with design requirements and guidance. .
HLN elect rIca I evalIiat i,,n plan estahil ished the formation -. A:;n evaluation Leam whose membership consisted of- indi- -
als of demonstrated technical competence and integrityhe electrical discipline who were sufficiently indepen-.'of the BLN project.
BLN el ectr i cal eva I iat, ion team pub I i shed i ts f ainalrt in January of 1985 . riis report noted that:
T hv i n tentI of IFLhe v va I n atLi on w as t o jaijdge whether.the HeletIIefo rit plaIn t velect r icalI systems could be.-shown to be adequtate. , w'he re 'adequaaa " was def ineda Sd ae S g 1e d arniul co 11t r u cttcd s o a s t o 1 e:
'S~a I--As es;t.aOl) i :;led by conflormanace toregajlIaItory r vq u r emen t s, i nclu id ing thereq ani red d oc aime i Itat. i o n to r.u pp o rt t !-cdc'si grs and d es ig n implementations,
aInd
ke I a blIy Opt!rabl 1e - -As estab.' ished] by * - 9 'a d hvr en ce to TVA ;anad inadast ry standards, ~.by test ing and by timely upgrad ing of
The Iof aviduain tldent
4. Therepot
.3.'
plant features when needed, as indicatedfrom TVA's or other industry experi-
" • : •'~~nce.. * '" "-'" '" '(
The evaluation team for al I practical puarposes substantiated.:the .INPO findings, and determined that " . . the short-.p,".
64' .", i ... . .:{:..!•".:::.. ::• . *.:
7 -7- 7
Z ,•
. 4-". 4• • v ' :'•. . . . . ,..
coming of the process t.o provide sufficient documenta tion to"Osupport t tic licens ing process and suhstantiate t echnica k ,adequacy, anl the ineffectiveness across organizati onl 'ion.a "interface to carry through original design requirements, .- y; : 0effectivvely solve problem:s, and. consistently make appro-...priate use of experience gained on other projectsi",were the root. causes of the RILN electrical problems, .o. .t'
Additionally, the evaluation team made some geLeral recomi " -mendations, such as performance of a systematic review of ,all "electrical, regulatory, and technical commitments to ,.ensure that all are being met and that the Suppor.ting work "is properly documented; establishing She clefinition of theminimum seot of required electrical ralculations; and placingmore emphasis on upgrading design and construction standardsand practices. .
-C..
TOO
The evaluation team noted that B[,N project has generallyfollowed the same basic design and construction . to meetsafety and . reliability""requirements that TVA has used onprevious nuclear power plant's tOlectrical systems."'--The.evaluation team did in fact confirm the INPO findings as:well as confirming the existence of some additional designand constrmction deficiencies and concluded that additionalcomputations and redesign are necessary in order to meet the-licensing requirements.
5. The Offices of Engineeriung and Construction Lop managementreviewl and discussed the findings of the HILN electricalevaluation report with the evaluation team and subsequently,estahlished two action teams, OE and OC action teams, toreview each finding and recommiendation and develop plans andschedules for implementation of the required corrective.actions, as well as determining generic implications. Thiseffort was to have been finalized and issued by March 1,1985. The investigators oht.ained an advance copy of theOffice of Engineering Act ion Plan -Fir Bellefonte NuclearPlant Elettrical .Correc•tinns and Improvements from the OEpersonnel who informed the investigators that due to budge-tary questions, the report haR not yet been approved. The OEaction team had taken the . lead for / of the general . recom,.mendatinns and 24 ,f the findings.- Overall the OE action-team concurred with the 7 general recomm,•nla tions and 24 ofthe findings with partial agreement, on 4 findings.:The OFaction team evaluation of the findings for generic .applica-hility to othr TVA facilities was affirmative for most of,the findings. The OK action team developed recommendations.of implementation of the corrective actions for BLN.firstand then consideration for other TVA plants,
I
00a,
W ' A
jj.4
.....
The investigators made no attempt to review the status bof MAthe OC action team report..
6. While the HIN evaluation team and OF action team-were in:',•:":.volved with their tasks , WIIN OC management deterinined thatl
65'
IF
ýz -
~2
0
it would be appropriaLe to re vi ew 1I.N INVO f indings fo r tL
purposi, of identitying applicability to WItN activitiV .;
Such a review was performed by WBN personnel who concluded
that " in the vast majority of areas no indication of
similar programmatic deficiencies were found at WBN."
WBIN OC management, in pursuit of maximizing the experience
gained at BLN and capitalizing on the positive approach that.'
BLN had taken to prepare themselves for the INPO review,
felt in early August 1984 that performance of a minjinternal
INPO review at WBN would he desirable after unit 1tfuel,
loading (scheduled at the time for mid-tall 1984). A mini-'
internal INPO review was performed by nine WBN personnel in•
December 1984. This review was limited to WBN unit. 2 only,.'-
The investigators noted that I finding among 17Mfindingsy ..
identified. that: "Increased management involvement "i•s'
needed in reviewing potential problems andi monitoring:in-
process activities. Specific examples cited were:.lneffec.:
tive review of Bellefonte findings; ineffective :trending 1.
program; ineffective work control; insufficient.control of •
hazardous material; and lack of managers in the field&I W, N
OC management in their January 16, 1985 response to the" 7
mini-internal INPO review noted that the., review of BI.N INPO '•
findings was in process and could be submitted to Knoxville .74
OC management on January 23, 1985: (NSRS investigators did.-:
not review this document). A"
ýpej~ific,,_elevant Findings
The intent of. this section is to identify those electrical items
that were recognized as items of concerns that were within the.!:j
scope of this investigation and those that were believed by the,
-investigators to he appl icable to WBN unit I. The investigators""
review of those documents discussed here briefly revealed the ;
following:,
1. INPOReprt at RlN
a. INPO Findi njZ DC, 3-1 .
S,m, electrical calculations were not performed .and
o hers did not address all design conditions .. These
calIculat ions consisted (A standardi zed processes ýand:
use of tabulated data to establish cable sizing and
equipment capacity capability. Examples include the ''':
fol lowing:
o Calclat~ions toa show that equ ipment cTapaci ty
limitations are not exceeded.
o Low voltage cable sizing adequacy.
o Inclusion of the effects of conduit grouping onp
cab l e capacity, ..
6 t,.. ... ,; .- . .. . ,.: ,Ž 2; :
" •.";a:::'• • • •2 2"' .
.... :•¢: ) • .• . -:{ .t- 2
-.. ,,,
.~..
-.4..
b.
C.
INPO idnD.3-
Improved control over t.he 1rep;v rat ion, review,. all(Iapproval of elect rical and pipe stress ca lculationsi 8-needed. Some calculations and analyses .do noot contain.appropriate references or input data. ;5", . 4
INPO Findinl DC.4-.
The implementation of the verification process needsto -ihe imp roverl . Some studies and load lists were notverified prior. to incorporation into the affect'eddesign documents. E.xamp.l .s of some design documenLt "
that were not verified are low voltage power distribution study, station auxi I iary ac load list, and -:,,
instrument and cont. rolF power' loads. Some as-built,-S,,ca l) 1e vlengths have not. been veri fied against maxi- .mum/minimum I engt h cr ite ia. C I
d. INPO Finding CU.5- 1
Irncro.sed attention is needed to ensure that electricalcable pul I IinR requi rements are met and electrical.cahles, and equipmen t. are prote cted from nearby con-struction activities. Cable Iplling is not alwaysaccomplished in a manner that. minimizes potential cabledamage. Equipment and installed cable are not always.protected adequately from damage by work activities.
r
I
2. Bellefonte Electrical Evaluat-ion Heprt
I
Vol tago drop anda shortI ti rc it al cal Iat ions were not Ldone for voltage-level V3 cable appl ications to verifythe cable's capacity *to perform its intended function.n:
b. BEE Findi-rn2 C-7 IInspect ions of cable and conllhiu it , ist a I laIt ions revealedseveral areas where thl instal led conif iguration (lid riot "sat i s f y de s ign reqh i rement s or good i ndu(t ry practices.As an ex.imple:
Electrical cables for tit(, EHRW pump stationar' routed throogh condi it banks that term-inate several feet below cable tray stacks.The trained and common cables are intermixed --,and exposed for several feet before enteringthe apprnpr i ate t rayA, . No ,ep, rat.ion between _t rained and common cables is provided, andthe cable routing program. does not recognize - <
associated cables. Design drawings require.':'.ý:ýconduit s from thie terini Ilat i on of the duCe.bank to the appropriate. Cihle trays.
67 - " '. , •i . .,' " . /. -
... •.*. & : '-•!•,~ '. 4, :
I
ton V
; . .JA. . -0
1,-.'-
BF1I. Findin nC-8
Although many improvements
have been. incorporated into.,%§
the cable-pulling proRram,:
, A ilnwing are areasloflVIA1C,
4 444
concern:
1. During non-QA- cable pulling activities,.
thv oh-.i.
server noted that the maximum pulI- tension"
andf "0",.
minimum bend-radius
requ irements were-"obtained
from an appendix to FCP. 3.4,,1 HI which was can-%
.
celled 18 months earlier.
2. For QA cable pulls, ins;pectors
must refer to-..
Design. Standards to calculate
maximum: pull tein-
sions and minimum bend-radius requirements.
Based. >.,
on discussions at the site, no record is main- o Zn
tined of these calculations or tLhe actual
mon
toring devices employed.
d. BFE General Concern 6,1.1 .
TVA has not defined the required minimum set of c.a I c. u-
lations and studies (or the Mlectrical systems -r!!quired
to. establish technical
: adequacy and the4- design basisij&
0",.
e. Excerpt Frm BEE Report Section •3.4
.
the issues related tu cable pulling.,. were"...
still unresolved,"
-..-.4 ,
3. Mini-In ternal INPO Review Findints (Limited
in scope to WBN
OC unit. only)
A .,'0411 W; 4-
V7 W
ANA444444
a.
b.
Increased attention
is needed to ensure that electrical
cable pulling requirements are met and that cables are.>
protected from damage during pulling operations,
Defi'
ciencies observed
include: failures
to follow proced-> 4 -
.ure by not using a break rope to monitor pull% tension;-
using an incorrectly sized break rope; pulling cahles.la
co
across sharp edgesi walking on cable during pulling.:,
operations; failure to check cleanliness
of cable prior;4--'
to beginning pulling
operations; and failure to. use. Y.
cable lubricant.
':. "
.7>
3
Some portion of the quality inspection are not, bingw
implemented effectively.
Some i nspec"to rsnot 'n a r4e"
remaining independent
of the production functionANot
all required attributes
are always checked -by. inspec .
tors. Observation of deficiencies
includei-consis
.
tent use of fillet wild gauges; failure of.electricalk,!•
,h'.444.4
•
-. -V~i•Z:.7&
•>~ v:.(; 7 :' 4g<4
' .
. " .4 :'• % J . 7':• -4' 44';i444..: '{!
p
,,.ie',ctors t o verify proper aL, t r ihutes during 9 611hl .i+cpulling operations; attributes incorrectly verified on 4- l
hngers and snubbers; inspectors relying,; on C raftguidance cou.serning proper completinn method for ndocu.-meutation and proper application of pull ropes ;:inspec"tors advising craft on work needed to bring items intocompliance; inconsistent documentation of IRNs; and
inadequate documentat ion of on-the-job training of01 ".
inspectors.
r_'LL ~n..QA. 2- I : • .... •>
Increased management involvement is needed in reviewing ýpotential problems and monitoring in-process activi- V':'
ties. Specific examples. cited wc're: . ineffectMiveI 0review of Bellefonte findings; ineffective trending Z
program; ineffective work control; insufficient control.-of hazardous material; and lack of managers in the',
f.... 1(1
thon Hlan for BLN Electrical Corrections and.mvenents
c(.
4. OE Ac
IMpre
OE management had reviewed the findings/recommendations, of'""'the BEE team and had reached certain conclusions,, excerpts -. . ,- ,of which are as follows:
a. Exer'pts.-rom O.E action plan2 for general recommenda.... ..... . .. ..... . .... ....... .. : - . , .• , --tiens, sections 6,1.2I a nd 6. 1.2,2: .
1. BEE Recommendut.ions: A systVmatic review of allt. e(hn1ica I and regulatory elec.trical ý.ommi tmentsshould be made t.o ensurO all are being met and allsupporting work is properly documented (6,1.2.1)
The minimum set of required electrical disciplineq%{!.calculations should be scoped and documented to: oinclude description, purpose, timing, and respon7, ,.-sibility (6.1.2.2).
1I. OF.A, Team Conclusion: Agree. .
IMl. Scope: This act ion pla n includes both of the.above general recommendations. The overall aim ofLhis plan is to perform a systematic engineeringp.evaluation of the electrical design in- order to 0 . Ndetermine the minimum (i.e., necessary)l setof"calculations and studies needed to .substantiatethe design. 'This activity should begin; with thepreparation of a Special Engineering Procedure,. . M(SEP) to govern the overall effort.. The following.:xpresents tlhe scope of act ivi t ies that. .hould: be&inctluded in t.he SEP with the detailed procedures:j. , 'I
. . ...........
1 . Identify tie design basis for elecatriLd <?V
sys Lems and equipment in t he following a reas f
a. Power distrimiitI MIon
h. nInstrumentation and controls
c Swiwt.chyard hrd
d. Light ing ...
e. Commun i catL 1ion .
This activity will include examining electri-.,.... .". ..ca einriteria. to id,:ntify. design hasesL"-.i,•cal design c nh .
and design basis ev,.nts. (For the p dirpost .:"e .""
this action plan, it is. assumed the. designbases are known and understood; however, if.'.-they are .notr (documentC:d, this must. he done as
a part of tlhis act ion plan.)
%
zlýeý .4t
2. Using the. steps in. the design process, typ"cal ly fIl lowed. to irmp I nw',nt the. design basesident i fy tie, Lypes of calculations ." and l
studies needed to s:upport the design steps in
each of the four electrical areas,":Identification of steps in the design process were
addressed in the BEE Team plan dated Novem-
her 27, 1984 (TAS 841129 001).]
The purpose of this activity is to determine-,.
the minimum set of calculations and st udies a?. i.which are needed for a given electrical s y s-tern or componndt. The e firi ltrion c and guide-"•
lines for what constitutes minimum should be-ý
included in the SEP. .
3. l)evelop an index of the speci fic calculations: ,
and studies requi red for B.N by, electricalsystem or type of equipment. .
4. Review the index tro verify that the minimum m um
set. provides the needed support-for, allI
regulatory commitments. •h i s -"activity- ,-.
includes identifying all electrical-:. regula',tory commitments f rom the FSAR 'den' d
criteria, appropriate. NUREGS, and `responsesAil
to the NRC. If any additional 6alculationsX",
and studies are identi lied, they.: should beI& •
inciuded as a part of the index.
S. Prepare and issue ,:lectricalV "'•:•discipl,ine
guidelines to document the minimum" set.Vto
tic I ude
/0q
KJ
,.,;. "Y~
-V -
- Descrip Libor i (fdcl I
- Purpose of' eact' "IN' -:
- Appropriate timing for preparation andr...:X;
updat infR
- Responsibility for doing the w'ork - -
6. Review Itel lefonte to determine Athe status of-
the minimum set aId ident i fy any addi tionaltVTO.?work that must he done in order to p rovide:::iicretrievahle documentaLion per TVA's estab- : M
lished procedures. . -
All the above activities will he accomplished 1 e dby the electrica I branch core groups. except.-.: ..:
item 6. Item 6 will be accomplis~hedbythe,•- 7 KIM,
BLN electrical design project. -
It is reCommndemhd thi.s action plan"be a ccomp-lished on Bel lefonte first and then accomp- ,
lished on Watts Bar. After completing Belle-f-'J.:':'fonte and Watts Bar. a joint evaluation with 'Ol:-
NUC PR 'oresentat ives should be done to.:-_."determine the need for similar review efforts O-f
for Browns Ferry and Sequoyah,.
b. Excerpts From OE Action Plan for E--4
1. BEE Finding and Recommendation
Finding: Voltage drop and short circuit calcula'i-,-Lions were not done for voltage-level V3 cable
applications to verify Lhe cable's calpacity.tperform its int.ended function.
Recommendation: All cable applications should be
verified to be adequate by calculations' and docu-',mented in a manner such that the informatioin isi,ý;
retrievable.
I1. OEA Team Conclusion: Partially agree- All cable---applications are accomplished in the samemanner.'-, -
IE cable applications will he verified to, be-ade-. r.V
quate and documented in a retrievable manner,. If
problems are found with IE applications, the
non-IE cable applicat.ions will be .=vrified and :1 X
documented.
II. Scope: Verify all IE MCC's voltage level 131 loads-,:by calculation;s and issue these calculationsA fo r Q
entry into MEI)S. This will be accomplished under t.
activity D-g88IVERIF'YR6 by the system..iengineeringZ-
11
la.yout sect ion of It LE P. Ve ri fy .i I I~ I 1&C iondsby caicitlatijon 111(i Isstso Llthr's oakuflaion's lent ry int~o M t'.I; This work will bt- flccompli ishf('dby a 11 sect Li onl 0f IILEPI The act: ion plan -is, r'com_niended f or t rail) use oil BLN boefore expanded. use ontot her TVA plants.
P~ ~.
NSRS Evaluatioi
The OE's program that controll) Ie the idesign pocesses and -Coilstruction act ivi ties was defi ned ini General Cnst ruc ion Speci ji- :.'3ications and FI.ecLrical Desi gn St anda rds , drawifigs, etc. Geni'ally Ispeaking, the same engineering basis and methodo logy.. had beten.•appi Lied and ut i I ized for tie design of, IN (both units)t, as well •14"" *as WRN (both units). The fo llowing oxcerpt from BEEU repoort....:Section .7, "Conclusion," confirmed this fact:
The iel 1efonte project ha!- geteinally II yt eI I owl the saint! :.'•.b.asic til,; i gii and const. ruct i ) t) t oil ',r .s to meet safety . ."an(d re I ia'0i Ii ty relu i-meLts t hat TVA has % used oil -pt-eViOUs 11uWClAr POWi~l p1ant eleCILri'al ' systxms. nf
.~-
addition, efforts iiav,' bell made Cf) improve the diesign "process b)y) preparitg ,'xtpautltd ies igni critit'ria to clar-....ify t.he ,th'; ) gn bhas is n, I by tak iiig acrouinI of design.antid cons t ru il. ion expev ' i ence Al so TVA h,)s a I outa ., d.. othe electrical systems usigi z onal svpara tion . prin-ci ples that minimize comnon exposurt, %f redundant andi ndeprident. ci rcu its to Pot tnt i a J damage from adverse .accident condii tions These all indicate that: ift iproperly imp I emented , the !I.N ,ldesign shoul d(I be more ":reliablo . than TVA' s previousiy, engineered nucle .r -electrical ::ys t elms.
Hiowever, the HIEE .Tea)' rev i ew ha . con i i rmnel vhe find ing sof INI)O aundi other reviews , iniclitli ag ti,,! ex st,'nce of . . ,
some deh sign and constr,,t. ion ,lefieni,,,,'es . These ,wnteed man.agement aLtent ion. • .
11n ortle I te) mee t thev I i "'ens rig 0q iti reinent, , L somealdi t iOfd i comptjtat iolts and redefs igou are necessary..:. A .review of thi' F.SAI. will I lso he ri•e'ded -in order to - .. Westablish a cOmlplete Itst of licetnt, ing tommitments inorder Io ,'etrmine it' th(!r vie ctri(:1l design •ork 'is ;needed Ii these are p)roperly itle)t i iied ilftol the worki; ch'hulof , I t , there is rea;son to exp.ct that thhey can be . '. , Ž
:'ompletetl in adeequate t ime to satisfy the licrensingschedule. _F
As stated alwov, the f-'E rep,1t. coni'ud,,d that add it i ona I compiuttation ant) rede(si;gn were necessa ry to he prformed so that Ill N - ...
could meet the I meatag reIu i renment it alo' cotf i rmed t.het*f act tht e ffort hlint] been reade to) itlroi tile desig 1 proce s 6Y. •preparing expaldtedd de, igr) cri teri a anti cdartf Yin th -t dfe rignLbos is as we II as taking into acc'umitt t it des i g, and COil ttruction-
'12.. ...... ........... ... . . .
• ' -•:-:°" 3'.
rý:, F,1,17,_;Fwlý-,ý
KoYUK
pol
, XW
experience of previous plants.: The invest igators concurred With. II ýM.
the findings of the vBEE team which determinned that the Bellefonte,''lplant electrical systems were inadequate at; well as subst ant i aeLin the extent and nature of INPO( findings regarding the electrira ,z-
cal design and installation inadequacies at Bellefokte,.•. ... . .. .: .-• ...........
The OE action team confirmed the generic ap plica|hility'of'manyf,,n+ p
electrical findings to all plants wh, ich included :,Watts ' Bar ý*Q no .0Nuclear Plant, unit 2 as wel I as unit. I. Although.' the WBN OCmanagement ,; intention for requesting the onduct of a mini- i '
internal INPO review was thought to he an appropriate step in the.uy'•0proper direction, NSHS concluded that excIlud ing unit I from theqi"'.scope of the mini-internal INPO rview was inappropriatej;Specific conclusions related to the calceulations for voltage dropYT!"and short circuit currents are detailed in section V.B. I with:JJpul ling forces and sidew:l I pressure di;;cuts:ed in section .V.1B, 2. ; -The investigat ors concludedf *that the, design and constructtionI: -programs that controlled these activities for WBN were of similarv"source and natire; therefore, based on the precedin, discussnog onthere was re.asoninable doubt whethher W,'N, uitt I could be showntmeet the licensing commitment for full power operation it'"it werso challenged. . .. ..
.qi~a litAs,;i•ragcE': ,ano! tat.i:i V• r~l fite i on o f Ca. 1 Protram) I aE4Activities
In addition to the. inve.stig.ation of Ahe routing, instal at ionn *+v, 'and inspection of cahles, NSHS reviewed thhe .Applicable QA organi-h"'"z.|tiion activities i n their reSlr eCtive a rp'.s. 'rht. investigators"'AG 4 Anoted that the D)E Qua ,lity Man:agenment Staeff (QMS) had responsi-k,hiility for QA verification of WDBI)' and EEII cable' design act lv-'vities and th;it Oit" C:orintruction.-Quality Assurance Branch (CQAB) Yhad QA vwrilf i'at, inn resplnsihi lit y fur cable innttallaitiori and Ainspection act iv rste. -
NSHRS requested a list• of', audits ani -urvvi I lance reports performed by QA organ i za t i os s iin, I 9RO thhat ,on" ll' have. related toC)the scopje of' this invstigatlon, Each of the audits and survet I,.'~lance reprit:s Ii,5tetd (or prmtvitdd) was review.ofd to determ irne th at.1Lthe Acope ia bluded review of the apprplriate activities, that.1W -deficiencet , if oI e qrved, we re identifield and reported for man-.}agemr'uet attrnt ion, and that for audits the .va luated' program ,a .•j:,
assessed with r.',ar'd to the' nature of any finding. .' -
,. Q~u~a.tIl..t t'ren Staff : :
F..
The QIS hacd pe r Ioriead twn ppert i nn1t and it s ( RA-04 WRDI' andT"85-05 EEI ) and a sur'vei I la er of t he cable Wchedule; which •were reviewed by NSRS. * Prior to the establishmentof,QHf ýS,Qthe Office' of Quality Assuranc& .(OQA) had responsibility. -orW >iZthe QA ver,ification of de'atkn act ivit ies; however, tha''i~:le 7investitatig :,re• ,id not olentify any catblIe (de's. I gnt itie )4 >Ye r i i t', i ont e r formled by .(OQA. The' invst ai~tors revieweQ,,the .audit and nturve l lance reports iy noeit, and NHPS notedthe (#f.lo.wingK problem
- 'Y
to ;4
" < ' i > .::, .<> 4\
a. Audit R'eport QMS R5-04, part. V, ditwinn stLted 1a .'I I
pirt pos. of the andit. waS to evaluate a! I' major Act.ivll".w
1ties; performe:d by WIRDP whi h :rb I•:-tL safetIy-relitlld ,"' 'e
S, t. ructures., systems, awil .ompoirtent.s, N SHS rev .,wed (. -.
t dhe i-rctnten ted aud it p Ian aInd report a ltd d t.e rm i nued t. he.1
audit plarn as well as the actual athi t conducted to. he
essent ia I ly a sha I low and superfi c ia I rev iew of admit .-i -
s ,rt.rattiV requirements nou OfE doctimenti, Prhoblem" Altea8 .(4~.*,..,,.., i•, ~ u''discussed in the report but not.. ident ii , . de.ficlen"44 4
c 'ivs requiring correct ive act i|on inclded: (1)f di*p-
crepancies between the project NCR li)g nad 'TROI , (2)
* - the project ConniLtMe|nt Tracing Records (CTR) log wads
not current,, and (1) an unu.sed .lroject procedure. was,,s t,.i I I isted as act ive. Th.. repeort suffmarized that.i> '4
"design activities in Lhe audited areas were generally -. 10
• .heing conducted in accordance With. procedural rq||ire- -•:. >.
ments." No cOnclIs iot was stated regarding the" . ..
*.adeq'utacy of the progam be ing imp! emented by. WBDP,.a 1t. hou gh a (Ii st r i hut t. on memn r a ndum foot no Lte h h I i ghtetl
Lhe apparent need for specific definition and clar
fication of: project, branch, and project engineer.A ,
responsibilities.
b. Audit Report QMS-85-04 reported thaL no deficiencied ewerre identi fied ltrom.any of the 11 project activities
reviewed, but reported 7 "problem" areas and pirovided .7" Y4:i,'
recommendaLions for cortection. The failure of 1the..
anudit report to dlocumnent the "prob lemm" areas as defi- Q,ciencies requiring res;ponse and resoltLion is adevia-
SLion from a TVA ,eRe IatI,,ry comnnitment to ANSI N45,2.12 .1'ý;,ý
Th i s identical problem was adhlres smd in NSRS' Report !,..*4f_,J
R-82-O2-•JBN, "Major Management Review of Watts .Bar,"
but- corrective action was apparently ineffective..
c. Significantly, audit report QMS-AS-O4 identified that .... •,the OE review of OC QC0Is and QCPs was untimely and ,,
largely ineffective. Though• not identified as "a' !
defici.ency requi rirg response, a WIDI' engineer stated,by way of response in a memorandum to WBDP files, that
"The OE review of' Constructinn QCIs and QCPs is func V..
tioning.as planned." 4
d. A QMS, surveillance report (t"n-numtbered by QMS) "toevaluate the process of it i I izing a fully automatedqv,
computerized system to route. and control Cable tray,:"
fill for electrical cables at Watts Bar ....... "datedlSeptember 17, 1984, identified only that the (ECt&D *,
User's Guide was an uncontrolled document referenced in :i• >}--
.a controlled EP. In a memorandum dated November'13,
1984, the WBDP Projecrt Manager recommended a meeting'be
heI d to. resolve the issue. Heetings were held.on
Febrt,:try 8 and Fettruary B5, 1985. As of March 22, this• o.Uissue ~had not been resolved and another. meeting was'4,4:444.43.4:-
planned to hbe scheduled.
7/4V
.,444.. . . . . . . . . . .. . . . .... ..,' •,,: .. ,.:/,:.•..*,. .
,4 4." ', ;.'( •':'", ';': > ,:-
Q<4 V 4 ACT,
-~ r ~
2.
Th, iirve ill lince v :. II eil to idlE l it fy thAt t he pr,'efsgs
wlfivr',hy the n ite lint if ien WIMI)i of' f II ld I ray,;aynild Ilene'-
t ratios itS ge'ngerally nlot l'tfoct ive, :itoroginwerinR. " .+
pe isoiilel lh ad not bee'n c¢ot¢Aet etl by Ithe QMIS evalualr:
Co'nstru:tion eng ilie ern i lite IvIew'i by NSRS -4ndicite -I <;
that inbility to puitI cable rs riginally. routetd Ky.:A.:
the, cable scheduIle, due tn f i I led t ray -ind penet rat. in•tn s ,:i
'Wit I itluled to be a major problem re tll ting i t tlay i a+ St,.
flow of 01C FCRs One cone tirut:tIion eing inee r hail I ra 'it+"d.
apIIroxiinately 115 unit 2 calbles and nit 4ited. that .Ise i87 p r
cent requi red r-routIn in iu td o unrieotled, iill .s -AnI ..
associated problems. In i on g oe ras< , the engl.ne.r i ne r
stated the cahlet; had to be riitouted more 'than Otice .
In s ummary, Lhe. OE QA veril icat ion program for elerctr-i
cal design activities w-*as dt, v vrmilted to .be totally
inadeqiiat e . Auditi ,it etl to pro p rt I y report de(i-
c iPlCie r,, Ps ai Ied t o requi r, s;,,s of' effective
res'ultit ion%, and ackeul sutI ii'l.nt qtope and depth to
meaning, flully assess pr ograf i de ahlije y rinid effectiveness . .-.
The emphasis nf atl i t tnd '11141 S ill ances during per- i',-,
foinin-e appeared to t,, onl almi nist tat i611 Of- documents
rat her than on process capabi I it le and results. .4
ConstructionQ A Branch (C) " :" (.4
NSRS reviewed the reports of three audits performed by the.+."'
Watts ,ar Construction QA Unit, two ot which pertained to .
installation and inspection of class I , electrical cable.,-
Audits WB-E-81-03, issued July 27, 1991, an,! WB-E-82-02,.-
issued April 27, 1982, reported observations of cable pulk ." -
and terminations and reviews of associated documents., Poth "
audits reported no deficincn(ieq although during W--I-8 • '03
work was stopped for two ulays linti I a procedure for :cable
installation was issued. No audits of (able installation. .
were pertormed after WH-E-92-02, sinr-e work activities of <'i>.
this nature wire considered better reviewed by the surveilo.• v .
lance verification method initiattd after formation of OQA.
Twenty-four such surveillance reports, 14 from 1983, 9 from .,
1984, and I from 1985, were reviewed. These surv.illance,.
now performed by CQAB, ident if led a variety of, problems
associated with cable instal lation. There was evidetice thaL" .-
action was being taken to resolve some of the problems, and
CQAB evaluators were performing follow-tip surveillances in .
problem areas. However, there was also evidence thAt. defi
ciencies identified werre inconsistently documented -'and ' -:
reported and that L fol low-up veri ficati on of resolution was.
not always • performed. The following examples typify the
inconsistencies:
a. Report tB-S-8S-(-O0 dated November 5, 1984i identi-.,
fied that QCI-:3.05 lacked suff icient Rguidance for W
pe rformi ng muIt icable pulls aI l that the method de-
mcr i hed by SRN-G-8:i- 4 wag :mb i gnous, A deviat ion*.
7 t.:".: .%. .".
....... ................................. ... ... -Y)t,
'&
I,.
~,. ~,
report wa 4 not gnera I vd,, however, and t he surveC I I aiice-~:•report was closed a.;e-d oi) t he (event 1uaI y sincorrect)aslimpt i ni that t he procedure would 1e. changed '41 On ,clarification was Obtained via FCR E205 16,
Report CO3)840275-COO.. dated Atigus t 9, 198A4, ident f iedthat EEOI was not specifying informat ion required byhQCI-3.0.5 on the pull slips., but would change the pro-ceurq' to permni t F.Q( to enter t h ne inlet'marion, A t., I ..
fol Iow-up1 veri fi cat ioil n i. ,1iI;1re! the .han e. cwas .made
'V
V
b .
hadnotI,'? lt m .1w -nlh Jil-1* - .4,1-..p, # , I -t n
. . . . . . . . . .......... = 1 ' ' ' ,,•,.,- = ... :.•••':,;;;•"•••,,.,•,[
c Report Lsl-83-205-05 dated June 24, 1983, 1;tated thait tprrnh I ems had been i uIenti f id wi ttI bend radius requi r- .mernit n and I nsta I Itt ion.. Follow-tup eri ficat ion wanspecified, perforiuued , and reported July /, 1983, andthe sturveill ance report. apparent ly ,•as closed based onan ()C engineer s statement t hat a s tidy of bend .rad i us.was being made and act ion would be t aken.. No, addi-.:Li onal fo1 low-up has 1uevn r, pii red. I,
In summary, the CQAII sturvei I lance program was effect i ve I yidentifying problems with the cablie. program, but, was incun- -.sistent in assuring that appropriate, effective resolutionwas accompl i shed, ' thereby producingR ineffectiveness' of the."--,conduct ed sit rwe ill ances
V. DOCUMENTS REVIEWFI./REFFRENCES
1. NUREG-0653, "Re'port on Niuclear, Industry Qua lity Ansuirance Proce-.dures for Safety Analysis Computer Code Development and Use,"August 1980
2- Watts Bar Nuiclear Plant FSAR, SecLion 8.3.4,f .
3. Construction S',e;ification N:3;-88I, "Identification of Structures,Systems, and Components Covered by the Watts Bar Nuclear Plant.Quality Assurance Program," Rc-vision 3 and Specification. Revision,Notices SRN-N3G-881-3, -4, -5., -6
4. General Constrwction Specit ication G-38, "Instal I ing InsulatedCables Rated Up to 15,000 Volts," Revision 5 and Specification,
.Revision Notice SRN-G384
S.. Watts Bar Nuclear Plant E.ngineering and Construction Monitoring,,and Documention Program User's Guide, Revision 3.
6 General Construction Specification G-40, 1InstalliIRg ElectricalConduit Systems and Boxes," Revision 7 and Specification Revisionl ..Notice SRN-G409
7. Watts Bar Design Project Engineering Procedure WBP-EP43.13,"Cable Schedule !fandling Procedure," Revision 6
J76
4..
An.
,C
F nVM
........
8. Division of Eng i nee r i ng Design Eng ineeri•g Procedure EN DES EP -'-W
3.10, ''Ds igrn Verification Methods and Performance of Design ; ,...-@.
Verifications '" Revision 6
9j. Division of Engineering Design Enginceeing P'rocedlure EN DES03
EP-4.03, "Field Change Requests Initiated by Construction CYR-
Unlicensed Nuclear Plants," Revision II
10. Electrical Desiga Standard DS-E-12. 12, "CondLct.or Cuirernt.o-v
Carrying Capacity Cross - linked Polyethylene InsiulatLed Cable.
(O- 15000V)," Revision 0 . ,- . : Y."
I I. Electrical Design Standard l)S-E12. I 4, "Conductor Current Carrying
Cpaci ty Ethyl-byl.!e - lPropylene Rubber Insulateed Cable (0-15000V), ____
Revision 0
12. Electrical Design Standard I)S-E2. .5, "Cable Minimiun Bending - '
Radii for Field Insulated.Cable;s Rated 15,000 Volts and Less,Revision 0. ....
13. Electrical Design Stahdard DS-E2. 1.11, "Power Cable Conductor
Data, 3-Phase Cable Voltage Drops in PVC and Steel Conduit,'. :
0-6000V Phase to Phase," Revision 0
14. Electrical Design Guide DG-E12.6.2, "Selection of (onductor SizesW ,:-ý
Based on Fault Current Criteria," Revision I)
15. Electrical Deisgn Guide DG-EI2.7.2, "Cable Schedule Development,.00:•i
Revision I ":"'¾.
16. Electrical Design Guide DG-E13.1.1, "Conduit Cable Pull-Point, .
Locations and Support LocaLions," Revision I y, """" "",
17. Electrical Design Standard DS-E 3,6. I,. "Raceway Conduit-Box - q. .J..
Design - Minimum Requirements," Revision I ....... .
18. Electrical Design Standard. DS-E3.6. 1, "Boxes, Cabinets and .
Enclosures Conduit Box Design - Minimum Requirements," RevisioniO 0. -
19. Electrical Design Standard DS-E13.6.2, "Raceways Use, of Conduit.'.. .•!
Bodies in Conduit System," Revision 0 . ...-
20. Electrical Design Standard DS-EI3.1,2, "Conduit Sizes for Cables 0,... ',of Various Diameters and Cable Bending Radii " Revision 0 03.,."
(Deleted 8/83) ' . :!,"'T'
I
.21., Electrical Design Standard Drawing SD-EIS.3.2, "SwitchboardPanel, .
Wiring Methods," Revision 2 .
22. "Watts!Bar Nuclear Plant, Minimum Cable Bending Radii for Field"
jIlnstalled Insulated Class IE Cahles," Revisions 4 and '
23.,Division of Construction Quality Assurance Procedure QAPI
' ' "Field Change Requests," Revision 7 .2
77
3- 3' .4
FM
-~
24. Divis ion of Construct ion Qual ity Assu raice I'r,)g ram Pol i Cy. QAPP3,"Inspection," Revision 3.
25. Watts Bar Nuclear Plant Qual ity tControl Instruction OCI-I"Preparat ion and. D)ocumientation of Fieldl Change Requests,"~.Revision 13 " - .
26. Watts Bar Nuclear Plant Qulait t Control Instriu'tion QCI-I .40 . .."Records Accountabi lity Program," Revision 6' .. ,..
27. Watts Bar Nmucle,ir Plant Quality Control Instrul't ion QCI.-3 Oi.,"CablIe Installation," Revision I
28 . WatLs Bar Nuclear Plant Quality ControlPI'roce't|mre QC10-3. 0,0 5"Inspection of Cable Installation," Revision 22
29. Watt-, Bar N ci clv:)r Plant Quality Control Procedlire QCP-3.03, "''-•. '-
"Inspection of Eliectrical Conduit and .Junction Boxes," Revision-•.-:•'17
30. Watts liar Nuclear Plant tlodi fic~it ions and Adidit ions Instruction.%MAI-3, "Insta I lat ion and Insp(;ct ion of InsulIated Control, Signaland Power Cables," Revision 3
31. Insulat.ed Cable Engineering.Asuoci:mtiron (ICEA) St.,nflards S1981"S66524, S68516
32. Memorandum -from W. R. Brown to Those ILi:sted, dated *Juine 8, 1984,"BLNP-INPO Const rumct ion Eva Iuat ion Report" (FDC 840608 701)
33 . INPO report of RLNP evaluation, June 5, .1984 . ... ..
34. Memorandum from 1). R. Patterson to Gaily R. OPwens, d(ated January.-,,,'7, 1985, "BI.NP Electrical Evaluation D)raft Report,' (WEN 850107101)
35. BLNP Electrical Evaluation Plan, Septemler 12, 1')84, approved byR. W. Cantrell
36. Beliefonte Electrical Evaluation Report January 1985
37. Memorandum from R. W. Cantrel I to Those Listed, dated January 22 ., ,1985, "BLNP Electrical Evalujation Report" (TAS 850122 001)
38. Office of Engineerring Action Pllan for Be l leforintc Nitrlear. Plant . ...Electrical Corrections and Imp rovements, March I, 1985 (no fi nal Iapproval for publication at this time to due budgetary coordination)'i
39. Memorandum from Guenter Wadewitz to Those listed (lated August-.' 131984, "WNIIN-INPO Evaluation" (WBN 840813 008)
40. Memorandum I rom G ;.. nt er Wad(Iw t z to R. A. Peedde , aat ed Jan uary ry16'.-.1985, "WBNP Minrilnternal INPO Review," (WfIN 850116 010) - ,
78 ,. '- .. . * 2•;
**'1 .44~
'¶4...
A
41.
42.
43.
44.
45,
Letter from I.. M. Mills to James P. ' RI i Iy dated.J.16ndary -19"
1984, ''Fina I ReportL - BeI lefont.e Nic lear P ant , Shielded Power .
Cable Bend Radius, Deficiency - BLIiRD-50-438/82-56, BlRD-50-439/k
82-50" (A27 840110 018)
Memorandum from .J C. Standifer to Guenter Wailewitz daLed Octo-
ber 14, 198:3, Watts Bar Nuclear Plant Units I & 2 NRC
Unresolved Items 390/82-27-08 and 391/A2-24-08 - Reinspectionf.
of Cable Instal led Under DIR No. E-9 Prior to I s.uauce of::
Revision I" (FEB 8:31014 936)
Memorandum from It. J.: Green to M. N. Sp)rouso d;v ted August 4,
1983, 'Sequoyah Nuiclear Plant Unit.s I arid 2 - Nonconformancee
Related to Betial Raditis of. Mediuwi Voltaýre Plowtr Cahle in Diesel'ý_
Generator Cont rol Cabinets - Nonconformance Report (NCR) No.
2053 -Bellefonte Nuclear Pla1nt" (DES 830805 024)
Memorandum f rom F. W. Chandler to Those listed dated August 4, `
1983, "Watts Sar and Bellefonte Nuclear Plants - Implementationý
Procedure for the Identification, Evaluation, and Resolution.,of
Cable Bend Radius Problems" (EEB 830805 292) ... - '
Report from 'TVA, Division of' Engineering Design (EN DES SEP
83-08), dat.,,d AuigustL 4, 1983, "ldent, i ficat ion, Eva lation, and
Resolution of Cable Rend Radius Problems it Watts Bar and,-,',
Bel lefonte Nuclear l'larits" (EEI WV30805 941"
Memorandum from .1, C. Standifer to GuenteVr Wadewi l, dated July 28,
1983, "Watts Bar Nuclear Plint Unit-, 1 and, 2 - NMinimum Cable Bend
Radius for Installing, Insulated Cables". (EE 830729 926)-
Memorandum from It. L. McCloud to Electrical Engineering Files,
dated August 4, 1983, "Bellefonte Nuclear Plant Units I and
2 - Cable Bend Radius Problems" (FEB 83080S 916)
Memorandum from 0. G. Frye to Electrical Engineering Files dated
July 22, 1983, "Watts Bar Nuclear Pl:ant Uinits, I and 2 -- Cable .
Bend Radius Problems" (EEB 830725 916)
Memorandum from Lonnie S. Cox to W. R, Brown, dated July [, 1983,
"Bellefonte Nuclear Plant *Cable Bend Radius P roblIem" .
*(BLN 830705 086).
Memorandum from F. W. Chandler to M. N. Sprouse, dated :July I, 1983,
"OEDC Prograin to Identify, Evaluate, arnd Resolve Cable Bend Radius-j '
.Problems at Bel lefonte and Watts Bar NILclear Plant"
(EEB830701 940) ..
Memorandum from Dwight R. Patterson to Files dated June 21, 1983 -
"Timeliness and Responsiveness - MeeLing with Involved OrganizaLions *".O•
on June 20, 1983" (EDC 830622 008)
46
47.
48.
49..
50.
52.- Memorandum f,'on, Dwight R. Patterson to Files, date'i June, 13, 19tj83,
"Timeliness and Responsiveness - Meeting with Electrical Enginee ring
-Branch, Divsion of Engineering Design - June 9, 1983" (EDC. 830613i030)
79
" •:;•~~~~~~4 'V,:. "'• <••••••..; :••
W
NO silt? V
lot
A
.53. M'emorandum fromR H. W. Cant el II to 08. J. WiIkins dIed May 18, 1981, A _N
"Watts Bar Nuclear Plant - Des;ign Information Request (DIR) No. -9 1' !'K.{!Revision I" (EEl4 810519 93R)
54. Memorandum ,rom Thomas B. Northern, Jr. to M.. Pierce datedApril 30, 1979, "Cable Minimum Bending Radii -Design Informption.'Q-Request (DTR) No.109" (WBN 790430 114)- &
55.- Letter irom James Kusher, G. W. Collyce In•Iated Wire, to James ,
Wagner dated Jlanuaary 24, 198:3, "Contract 775-822173-3' , .4Q 7..r
(EE~B 830202 040) ..
56. Let icr from Q E. 1ubIernan , ['owe r kaibp Enigi neeir ing Center, to F WChandler dated November 19, 1982, "Watts Bar I and 2/Training/NCR4I94RI/76K5-8?7365" (EEB 821119 021) .
57. Letter from A. J, DeChiara ,The (Okonite Company, to F. WC Chand ler"Yý.2jx"dated November IS, 1982, "Watts Bar Nuclear Plant -. Units I and 2• !
CEEB 821118 002) ..-
58. Letter from A. .it IDechiara, The Okonite Company, to F. W.' Chandler• '
dated June 7, 1983, "Contract 79K5-82-5903'' (EEB 830610 .014) ..
59. Letter from 'eter Deschner, 'Triangle, PWC, Inc., to F. W. Chandler,.'.-.{' ,
dated Novembhr H. 1982, "Contract; 74C7-85069 and 72C7-75228-I"(EEB 821116 024)
60. Letter from Peter P. Deschner, Triangle PWC, Inc., dated Febru-ary 18, 1983, "TVA Contracts 74C7-85069-2 and 72C7-75228-1". ,
(EEB 830228 014),". . • .• ' .4.
61. Letter from P. C. Moody, General Cable Co. & Research Center, to '.
F. W. Chandler, dated December 3, 1982, "Contract 71C7754762-3"' .. :(EEB 821210 001) .
62 Letter from J. I. Steiner, United Technologies Essex Group, to ..
F. W. Chandler dated November 23, 1982, "Cable Bending RadiiNCRtI94R" (EEB 821130 018)
63. Letter from J. I, Steiner, United Technologies Essex Group, toF. W. Chandler dated December 28, 1982, "Cahle Bend Test"
64. Letter from J. A. May, Rome Cabl!le Corp. , to F. W. Chandler, datedJanuary 3, 1983, "Training Radius of 8-Kv Power Cable" . .. .
(EEB 830106 013)
65. Letter from J. A. May, Rome Cable Corp., to I"..W. Chandler and. ,w,,,Kent Brown dated November 12, 1982, "InstallLion - Using Less
Than Minimum Training and Bending Radius' (EEB 821115 014) . -
66. Letter from F. W. Chandler to American Insulated Wire Corp., dated" August 19, 1983, "Watts Bar Units I and 2 and Bellefonte Unitsl1
and 2" (EEB 830822 939) Y- ., ..
80
A
-y
67. Letter froJ m Aram Madoaiat, Amer ian 1 isulated
Wi ri Co .., to F'>W,
Chandler dat! d August 25, 198:3 "Your ,et ter Heqlfutl or
dAugu 5tjyu
L 19, ,
' 1983" (FEB 830,931 '013)
.. :.;,>•>:•:68. Leetter from IF. W. ChWndler,
t o fl.Pdl Cardel lo, Aamonlt'-Eritts :(m,
Inc. , dated A uust 19. 1983, "Contracts - Watts iar Nos . 81K7-828633,
80K8-827380, 76KII-87232,
80K8-827337, 7WC7-85861;
hIellefontC Nos".
80K6-827454, 78K,-824447,
80K6-82 7254, 80K6-82599 1" (EEB 8"0-it22s 2-9 3
69. L t tet vr on|i hiu I 'S. C'arde I lo , Anacowldi - r i c,,:mt, I 1( .,, t )' , W,,.
ChandlIe.r dat ed September 9, 19A3, "Your Le tter Dateld September
91.:tl
1983" (UPl 83(0915 0 10).
... :
70. Letter from F. W. Chandler to, Be I dn ot 1,(i rat ion, dat od, August 19
1983, "Watts Bal Nuclear Plait On it ; I and 2 Special Cable Cont rac{t,:i
74C 7-8$25911 (!}B A30911) W 42 )71. Letter from B ill King. , Belden C(orp. to F, '. Chand ler. dated Sep-
t-ember 12, 198I , "hvnd Radius o)f l,.4w Vrlt;,, , Cabhler Installed i 1t
Crouse-ll anals Co.iluI ,t s'' ("Elt 8IO(12())Jil 9312. Letter from F. W, Chanil ler to lr',st, on I ns w ah td W i. & CabI(v Col,
dated August 19, 1983,. 213i.1 lef.lut' Si gna C(ablel, - Types"lS M irad
KXPS.J - Contract 77K5-82099
1" ,EBIt 8:10819 9,, 073. Letter from J. R. le,,arni, BlW Cat, e System:n,
i:tc., to F. W tChatdlcr r,
dated Septeomber I I1983, "8 lB .f'on t.e - Signal Cable Types PSand
MXI)SJ - Cofnt ra t. 77K5-820991" iEEls A10907 005)
74. Lotiter from F. W. Chand llr to fira)ndl-Rx ( ilmpany,
late d August 19,
1983, Types I-SF, MXI'S,I , ,lil )', Cont racts 5 79K5 -1
82500" and 7•KS-824279" (EB 830819 9,3.)7. Letter from intephenI..
Saaidor8,, BrSAawl-Rex
fCo to, . W. Chandler. "
dated Angust 29, 1'83, "Brandid-1ex Hesjo.)I.<;(
(EEB 830906 006)
76 Letter frosm F. W, Chandler to C, r-. I i ni WJ mre ,iwl C.IIvle , Inc.
,dat e it
Auga•st 19 , 1 983, NWat t.• Ba r - Clint ract Nos .. 8 -8291074, 80K7!-
827381, 8OK8 -A2650r, 80K7-82,4:138,
7K13 - 82322" (3EE 1930822 945)
7?. Letter from F. W. Chatdle(Ir t.o CiI I ye, loiin.IittI
Wk I ' Co, "ConLtract
740C-RS448" (EEB 8310819 941)
.
78. Letter from F. W. Chavnler to Dvoho Wire ;ind Cablie, tn; dated
August 19, 1983, "Watts Bar Nut' ll;r Plant tin it ; I and 2 - Inst)la at
ed, Conduct(o r Type S1 I font. rar t 7 ?KI I1.-A22 7 I" (FEB, 830822 9(43) .
79. Letter from Tomn Finnegann, leelco Wirre and Cable, Inc. , to F.,, W.
Chandler date,! August 31, 198U, "C;onttrat
71KII-822175"
.
(EEB 830907 OIl)80. Letter f row F. W, Chandletr
to Et. ton Corp , dated August 19,, 1983,
''Wattq liar and 8ý! lefonte losiulatel Conductor
Contracts"(EEB 830819 947)
- ,,;); : :
>4Ž
9,
-4. 444.4
iii iiil; .... .
8. 81 Letter from All en-P. Clement-s, Etoll or1j, t W -, W.("IhandlerI
dated October 13, 1983, "Watts, B,.1 awl lil li-fontt Insula t1.ed
ConducLor Contracts" 1'.F.B 8H 210 19 0 C,'"
82, letter -irolnl F. W. ChaoIh' d r to ITT Suip ,t|" t, at lPivi!.inom dated Augr'qt11),
1983, 'Watts liar Nuclear Plant Urnit; I and 2 - Instilated Conduicntor --
Type SIS - Contract 78K)3-822912" (EFP 830822 942)2
83. Letter from John I. Reed, 0 Kon i te Co to V. W, Chandler dacetfAugust 29, 1983. ''Watts Bar and Bellefonte Nuc l(ear Plants . .: .
Ins ul a ted Conduct or Coot ractLs" (EH 830001 001)
84. Letter from A. J . D[ech i a ra , 0 Kon it , Co., tL, F. W. Chandler dat ded
Sep.tember 29, 1983, "Wat ts Bar and Bel lettntv Insuilated Conductor<
Cont racts" (EEB 831004 003) .
85. Leetter trmo F. W ChanIdler to Rocklbestos to, dated August 19; 198 3"Watts Bar ariAd Bel lefonte lnsu laited Condiwtor Contracts"
(EEB 830819 945)
86. Leter from 1t, BRoque., Rockbestos Co,, to F. W, Chiandler dated- •
September 8, 1983, "Watts Bar andl Rell lfontt ltsul ated Conductor->
Contracts"' (EEB 830913 008) .*
87, Letter from F. W. (handler to Romre Cr.i,' Corp. latel August 19 "1983, "Watts Bar ard Bellefont e Insulate, Conductor Contracts"''(EEB 830819 948) !
88 L.etter from I at J. Marwick,, Rome i :, hli, Corp to F. W Chand Ile ri . .4
dated August 24, 19o3, "'Cable Installat ione, at. Watts Bar and , .1>,Bellefonte" (FEB 830828 024),
89. Letter from F. W. Chandler to "re I iyyn m'hermatics dated August 19 ,:1983, "Watts Bar .ind Bellefoantt. Nuclear 1'l ants" (SEEB 830822-:940) 4 .
90. Letter from Will iam Strickland, Ifledvne Therrmat ics, to F W.
Chandler dated S'jptembe r 7, 198.9, "' eird Rad i 'is Sw i L chboa rd Wi re.and Signal Cable" (EEB 830913 012)
91. Letter from F. W, Chandlert L0Teisol ite Co. dated Augusts'%19,. 1983,"Watts Bar and Beliefonte Insulated Condutor Contracts",: 7
(EEB 830822 941) .4
92. Letter from F W. Chandler to Thermo-Elect ric dated August. 19,1983, "Watts 1.r Inn ,.ated Conductor Con- t ract hC7-85!8i ':I . .
(FEB 830822 9,~4~
93. Letter from F. W. Chandler to Tria ngle-Plastic Wire & Cable
dated August 19, 1983, "Watts Bar indl Bel lefonte Insulated" --- Conductor Coit ra:.Ls" (EEB 830819 944) .J-"-5 .
94. Letter from F. W. Chandler tLo n it eal ''echnologes, dated AugustL 19 } -i
1983, Belle I fon Le - Insulated Conductor Conrtracts' ....
(EEB 830819 940)
82: ?- " , . j4". .... 4 " .977 .4.97.,'([ 4
k~A ~"*~
96. NRC Re'port. No. 50 -438/H12-17,
50-4 3/82 -17
)7 NRC Report No. 50-4 3A/82- 22, 50-.439/82-12
q8. NRC Report No. 50-19q/82-27-08, 03l8-iR,
9.Lvtter US roor
p L , Ste~i ner to Chief, FF Support rifi
ite
Julne 17, 1981, ''Report o ,Sp-c ial Bend Tc~ o KIe
~~~'
(lF.R 830620 001)
'
1001. Statncard Dpert.
lg I'rocodure, S01P- 14, I't!' 1 t I I a~ lI. iou ')It I pec t iOil,
au I 1et d Tv iII ug o c cK tcl r i ca I C a I )1 aid I .IIi juuI t I ''e I v vI ; IOU11 I , ,,
'01 St anda rd Ope rat i AM Procd ~1re 0"ElI-' SO "!"scu ri t
y Sys Im,"
A
102 Mod i f i ca t i mi'. mitt Add iLi iOunuI nt:: t.r uc ,i con:; MlA I3 "I us t ala t .i on
anitd I nspec-(t i on o't Cal) le Teriii I uat ion, Hev i "i 41
103. WO1N FCR K- 20" l (WHN 8410A :300)
104. W.IN F CR F. - 15 12 1. IN 814 o5() 1 ýt8 6
10.Mr-moraniduin f rcmn .1. C. S L a n'.i f vr L' o6 Wa dt'wi I z tlati ed 1 Juy. 2 8,
1983,- ''Watts ~Bar Nui: lvar H aruLs; uniit. I anud Z - Ni nimianrf C~sble 1k a
Rdus for I Ost al I r ig Itnsii at~r t'1 ablos" (FEBI 030729
91 2 6 )
106. tc m, or aI I (I III t oiti IC ,St1 ari tIer t'o G. Wardc-6 z dait- 01octoher `27
1982 , 'Wa t.tr liar Niuc Iear Pl ant - NkCs tinreso I viol I Iemq
390/82-27-01, 3')1/82-24-01
, 390/82-21-03, and 191 /RZ-24-011
(SWI' 821101 010
toJ
iii EEI F, O 4Fs n/2-19/, "'Guide~
for the lox~ign and 1Nista iIIation
of g G
Cable Systemsu in) Prwer Genieral
i ryg SI.tt rolls "
1)08. 1 IEEE STD) (90- 1984. ''Standard I or I lie I).'i go arnd I Wsit I Wat iolitof
(Cah 1e SyntIeni:, for Clziss Il,, C ircuitI I;
ii3 Nnch- at. lowt'r Generat i ng
Stationis''
109. M(-rt:i.nitciranua froin J. CSt rnd ifo te , 3 (itiviit.ir
Waiew iLt d atedI Jwit 130
19 8 3, "'W[I N loui i I !; arjidii 2 - N t) ~i i c iiio t iii e Rt I a t- t e'- I a 'o i BI.- II di I Ig
Radius of iledi in 'Oil Lagc Power
(>,lu e i n QV1, PIrays . - Nonconformnx
o N
Corndi tions~ Report~s
1.Rs)41901 .iui' 4191)4k RI' (KEAK 830630.910)
110. A tt a chItmen1. A 1 r) W BN (C I -1 .0, Rv i o I , da td 1 ctri, hecr 2 2 Igo; ~
"NCR 4191IR," kovi !; ion 1 (WIIN A2 1029 IVS)
I II >AtLta hmen L A t c) WIIN QC I - 1 012, Riv I;i on'1 , 'dated Juily 221 1982 '
"Nonconforriiinrg (:onli t~ion Report 4 190"<' (WBtN 820)726 100) ,
112 . emorandum i rorr V1 C, Standi1 1fer to0 Guienter~
Wnuluwi tz? ae ui 0
1983 ''WON In its 1 and~ 2 -Nuitu:
iOrrmniice RelIate~d
to lItndigPnyWg y
rI-A.'
Radius of Meliun - Voltage Power Ca 1) l e in cameb : Tiyi:Noncon
forming Co. di t ion Reporth (NCR' s) 4194R an,,I 4194R Rev s Ion . :
(EER 830610.910) 1
mi. :," Who r
, . , -.
' I1.S. Memo randum from F. W. Chandl I er Io .I . A. NHall I on ,Iat e(.d July I1 ,:
I.J8:, "'WiN I and 2 NCR 4194R, Revisll i I, H,,rdinug Hadius"of
Medium Voltage Pcrer Cable in Cable Trays - Supplisi,'rnt .to Report,2'..
ber 3 (Fina 1)" (A ,30718 913) .
114. Division of Construction - WBN QCI-1 .02, Revision 3,idated July.2.
1982, "Attachment A to Noucnnforming Condit.ion Repoet.h4194R .i'o...
(WBN 820726-100) . .
115. Engineering Change Notice Cover Sheet toir -.CN 4612.-dated July 7, .i -
1983, (WH'l 8:1071.5 539) . ' -.•&'.
116. Memorandum from T C Stand i fr" to Ghtrite' Waewitz ated.June 217y''
.1983 "WHIN - NCR 4274R Revi:sion IK. (RE 13 8306 29 905) .
117. Attachment A to WE1N QCI-1.02, Revision 6, NCR 427hR" ".!. ""
(WEN 83051? 12H).
118. Memorand.n from R. M. Pierce to T. $, !Northern ,Lat.ed"July lS:18, I919
"WBN Units I and 2 - Insla t"ed Conduytof RSpai,"r of1 lamaged Outer.? 2
Jacket" (SWP 790723 008)
ALtachment A to WIN QCI-1.02, Revision 4, d'ated August 1,. .1982,."NCR 4272R" (WBN 820916 184) [ , .
I 2o'. Memorandum f rom Cuut, e r Wadewi it.: Loa. C. .quti itfer dat~ed Sept emQSK
her. 15, 1983, "WBN ,.'Non- ASIfE Sigi Lficant Nonconiormance Report:i'.
"4933 Revision 2" (WBN 830915.007) . .. :
121. Attachmt(nt A.Lo WHN QCI- 1.02 Revis loll I dated Set.emberR, 1
". NCR 4933 Revi;ion 2'' (WRN 830913 106) ,: '
"122. Memorandrum from I. C. Stand if Or t, Guen.ter Wadlewitz dated-July:28.d
1983, "WBN tUnits I and 2 - Minimum CaOWI Bend Radiuns.for Instaliting,
InsulaLed Cables,,;" (EEB 830729 926) .
.lemoranhiim from F.. W. Chandler to J. A, Ranki;t n" datLed Septembetr ,lf
1983, "WBN Un itHS I and 2 - NCR's 4`133, 4933 Revision. 1,49337'
Revision 2, Bendding Radius of Medium Voltage( Power Cables .Reportl p
2 (Finual)" I EEB. 830921 903) " . ". >
124 . Memorandum fri ,m F . W. Chandl .r to, ,. A. Ran: Ilstun ,lated,, -S " emberN27
1983, ."WRN > Wits I and 2 - NCR's 4933, 49933 Revision . ,.1 - _
Revision 2, Riendinrig Radiuls of Med'liuim - Vnltage Power Cahles? OA}ff"i i Q "ti
Report 2 (F inal)"' (E 8027 90'Y) :7
125. Memorandum frm J C. St a•id i fer r i tc ('; ,,Ilt r W:idlewitz dated "SePt i-.her 20, 198:3, 'VIN Units I aid 2 - N r nhcou n ,rm anc e ReIatLei .ted to
"ending Radiis of Medium -VolLrge Power Cabl, es Nonconforming," .
Condi tion Report, (NCR) 4933 Revi;sion 2' (EEl 8309921902)
844
: " :, i 'i• , -'-: 5..
zi .
1 2 6 . A t t.t ac i m e n t A L O W B N Q C I - I1 .0 2 , R e v i s i ,,n t, il at . d J id yy -2.3 , 1 9 8 1 , .',.; .
. . ..NCR 4933 Rev'isiont. I" (WBN 830803 109 ." '... ..- i:•.{-'
127. Attachment A to WBN QC I - I . 02 , Rev is i of di tited JuineI 22, 1983,.
NCR 4933 Revision 0'" (WRN 830624 10(0)
128. Homorandm from .. C. Standiftier, to FI. w. t•h inmflr dated Ituly 17,
1983, 'WBN - NcR 493:3 Revision 0" (WBN 81070/ Oi) .7 .
129. Memorandum from F.. W. Chandler to . C. 5fr niif.r datted.'Jill y 19.,.'.• ,.
1983, ''BN - NCR 4933 Rev.is on 0' 8..)10 Q05 zandWBP 830726016) .
130. Memorandum ftom .J. C. Standifor t o ;'.ttii ntr W.idewitz dated Nove,-her 10, 1983, "WN NCR 5062 Revision I" (EE 831109 .919)
131 At.achment A 1u WBN QCI- 1.02, Rcevison 0, i,'ttid Oc 1 19) .3"NCR 5062 R.evi:sion I" (WON 83 10 11 103
132. Division of C'nst ruct ion - NCR ,tted F ', rliary 2 5 19'84, NCR . 465 5Revision 0" (WBN 840229 102 and WBN 840424 102)
133. Memor.'indum I rum I. C. St:,ind i Ir tLo Gunit r'r W.Vhi wa t dated April 1 019 84 "'WON - Non; in if i cantL Nonveon Ir n, c R,' tt i i•4 ' c e'16 11t(ECE 8404411 ')31
1.34. Div'isionn of Constrction N EC d.lt,.d A\ri 1 24, 1984, "'NCR !592'Rev is ion 0" (WON 8A40427 104, ani WIHN 840142710 ) 1 o
135. Division of Construct. ion - NCR dated Otctther 5, 1984, ''NCR 5932,Revision 0" (WHN A4114 100 and WhN 850110 101)
136. ,I,,mor.,,,dtai, I rom . C. Stntud 114, to ,,t ,,t r dv W.,awi t dated Decem- .he r 24 , 194 , "WBN - Non - ASME Noris i yni if i crant Nonconformance
Report 5832 Revi:ion 0" (F.f 84E210 907)
1.37. Division of Construction - NCR d.atefd Octoher 18, 1984 "NCR 5840Revision 0" (WOiN 841019 106)
138 Memorandtm fr,'mi r , C St.andif,' 1r)o Gu,.'Itler Waýh'witz dat.ed e .,cv i .l .her 24, 1984 , "WBN - Non - ASIE Nons a ',ni•t;,nft Noantrnformance ,Report 5840 Iv ,i son 0" (EEEl 841227 t12)
139 iavit;infl on o Conis;t ic ton - NCR dat"L . lay P2 , 9. i ' "'NCR 2372Revision 0" IlN A31026 112 andi (:0 8A5011 1 I !
14.0 MiN moran iijin froia R. . . (H8dgc-; t, I. ... (Cox datel August ,10,, 1983 ,"'I' N - NCR 23/2" (EI:( 830812 9.210)
141. Memorandatm fr'm R. M. lfodge; to I., S. Cox tated Jitly.29,. 1983 ; ;>"bOLN Un i t 2 - N,,,'itcon fo rmin,,an Re I :,ted t , l• d . if Ra td iu; o f Mled i urnVoltage Powor C:th Ic at T'r.,a:,; iaL on of 'Irv Ri:;'-t to r Class s.Swi tchge.-, r NCR 2'1 72" (EF0 830128 . 26) .' -.
'4 . '", "•
•.• ;. ,.I;
Z4 ' , ? "
.?, ;,.2
,1421 F'ailure Evalu;ation/Engineer ing Rport from A. A. RanIsLon" to, H. L'"... '
Abercromhi e dated March 19 , 1985 ,. "Knv i ronment-a I Qual ifi (.i on-"t.of Elect.ri•ial Cable Not. Val idated" (Ht45 850319 251
143 flivision if Engineering' Design N NC R dated February' 19 18 >IkSY' M,.444,.
-"SQNEEB85O"" (EEB 85,0219 918)
144. Mefo.radum from R, Pierce to W" N., Cuyr dWted O er t. , r 98,4"WIBN - NSRS Rout inv Review of the Response to NSRS RpAssessment. of Lhe Res'tl s of the:.B&iV I ndeprndeut Dis igpooRviow 'of
the W`BN Auxiliary.'FeedwaLer System - NSRS Report R-84-2 .-WBN,(EL-B 84100Q0 23) . ":'
145. Memorandum from R. M. Pierce to IH. N. C! iver latewl October-3- 1984,<$S Respons.e • Recommendation R-84- l9-WBN-07 (('at euot', y 3b ) * ' . A'. '"4'..
-(WBP 84I010 021) : .. .. .
146. Memorandum 1.r om H. N. Culver to R. M. 'i'',e dated S(.ptt.ember 5 A
19,4, "WBN - NSRS Rout.ine Revvi,,w of thhe Respons; to NSRS'Report)R-84- 19-W RN" (ONS 8,40906 101) 1..
147. Memoranuhrn from H. N. Culver tj 4. W . Will !; d;ted Septembe -. S ,
1984, "Response to Board Comment - bN - ,opnse to Board
Quest ion on Power Re:sponse to NSRS Repurt R-84-19-7WBN"'(GNS 840906 i1O)
I48 . memo random ftrom i. . Plarri;s to If N. C'ulver datedi .July 31 198"NSRS Assessmsott of tfht Results of the Black & Ve.'atch (B&V)Intdepende.nt lDes i ', Review% of the WBN Auxilita ry Fedwate.t zSysUe r-:NSRS Repo rt H-84-19-WIBN". (EIC 840801 (60I Andi A02 ,40731g016b j) ,,
149. Memorandum Ifrom, 11I. . Culvver to J. WK, Atndrýot dfated September. 15, ,1983, "WBN - Breakdown in QA In.,spuvlc1t.L•1t" 1 u ,,ment s of:-CI. .-'r s IE"--(As:soc'iated) C.'ables" (GNS 8 l0916' 050)
150. Watt;s Far Survv i lance Repott s• - WH-S-H)08-0:f)0, WB-S-85-35 CO0,CO3S840108- COO), W1,-S-85-79-COO. co( ,O, I2-n 0i, CO S'84018')-X ,I! . . ,..
C03S840094-C00, C'03S840275-COO, CO.,,840 1151-8)I , WB83-20.5-1. r,4
WB-83-20.5,-, WOR•--20.5-3, W&,l-g3-2015-t4, WR-83-20.5-61W14- NO20..5- 7 , Wlt- 83- 20 5 -, WA -A3 - 20 0 - I0 C A4 3- NE-25-1 1 '
W3-83-20.5-9 , WRI-83-20.5-12, Wit-93-20.5-_, IO0StR400002300,.Wli-3'3-20.5= 13. WlB-SI-,8)-9"1={?o0
151. Memorandum from F . IBea s l ey to, .1. A 0 S ,itatf i er ,Iat eel ' '. ... C4(
.. tJanuary 14, I9M5, ?'Qual it.y Manttagementl SI.aIf (Qp5) Atdii85-04-Watt' Mat Fng:incertng l',,jo t ," ).MS 850114 200)
152'. Memnra hdumn Ifrom E. HI. Cole o Wat.o ta L Rar EI•,ugin,,,ring Project .;4 Filaes dated February 13 1085, "Wattst Bar E' ngineering Prnject -
I Response to Quality Management. Staff (,QMS ) Aoult t 85-04," (WBP8V150213 006) ..
I03. Mlemorandumft I r ... Standli f(r to T. C. CrV"i no dated February 77,1985, '"T'ransfIer of' Reslonns ihi lity for N:Rs; ,hIt: to I)ictipil Wit!' '
Staf fing, ((41W 850207 1 5)Sa
• -8 6 .... " ......
i; i 4l
'14..- M iem(orandum ft .tr I. J . )tadif er t r O I , K; Ha t I , fl t i ttd Febirary 7
1985, 'Wa It Esii ne 'tri g Proj.evt Transfer of Responsibi liLy I oor
NCRs dine to D)iscipline Staffing,'' (WBtA850207 IbO)
155. Momoiandum tfroim J. C. Standifer to P. D. Mm eto' If dated February 7,
1985, "Watts Bar Engineering Project - Transfer' of Responsibi lity
for NCRs due to Discipline Staffing," (WBP 850207 1§1).
156. Memorandum Ir on J, . Stard itfer to R- R. Reeves dated F ehiuary 7,
1985, '"Watts Bar Engineering Project - TranSfer of ResponigibiitIy
for NCRs Due to Discipline Staffing,' (W'I' 850207 ,2):
157 M(Memo randum f rom J C. Stand i fe r to .J. A, Ra, tc tn ds ted n f e d: uary 7.'A r.y.7
- A1985, "WHN Units I and 2 - Handl ing of WIpP 1r)pt-id IQraw"ings.:Whi ch Are Used As F i gu res i r the WBN FSAR, (WBP 850207.61•,. .
158. Letter from I.. M Hill.s to James IV. 0' HRe il v dated February 7, -,")
1-MRV "W,' Units I and 2 - NRC - 0IE Regio,'u 11 Inspectioitn Report;n50-390/82-27 , 50-391/82-24 - Suppl IemenL to Revine'l Res pons. to
Deviations," (A27 830207 029)
159.. Leetter from 1. M, i I Is to nJames P. (0R10 ll v I ,Iy t,,dl. January, 19;,
1 983, "WBN ir (it s I and. 2 - NRC - OIE Region II Inslpectiul. Report,. <c,50-390/8R227, 50-391/82-24 - evised Rspnnos' to, Dvviationis."2'(A27 830119 023'
160. L.e'tter I rom I. N. M I Is to James P. 0' He liv ,ditl., PCIE'rner AI.
1982, ",'WN Units I and 2 - NRC - ONE Region IH Irnspect iOn Re"nrtL
50-390/ 82-.27, 50-sDl!/82-24 F nal IRe'sponrse t,, l)viatinns,"''kA2.?821201 016).
161. Mernoranduni from. B. A.. Costue r to M. N, Spi Is,' datet. Imarth 13, '
198 ''EN Dus Internal Audit P-81- II,' (O)AS H.!0112 021)
162Y Memurandum from . W. Anderson Lo M. N. Spi, s 'Le ed Mht r ch 4,
1983, 'Audit;. 1)83, 'Thermal Desixn andi 'idpinit Analys isIa( Suppor"Des ign," (OQA 830307 502)
16 3. .Memorandum from .3 .. Audhrsonn to N M p1, Sipu.rc dateu( AprLril .i)91983, "AudIit D8 1-4 Des;ign Chanige Control I .u Devl ation.,",
C "iLt rn i," ()QA 8 i0,429 504) ,
164. Nmn,)rrrujdnn froin R, A, Costrier t.o L, .. ConWley datetd tay I. .. 1 1 19 1 ...
Review of Quality Assuring Iocumvnte'nts by the ()l i(e of Qual .it atyAssurantr EN DES - EP 3,10 Rev r'vision ji, "'•D•i s i •l V r i' f ation
eit~hoAs and Performance of IDesign Verif vit orn.;,'' (OQA 9840611
165. Memorandum from R. A. Cos:t mr t,, R. .W Catit r 1I 130ted Augus't 1-1 '71984, ' (litie of Quality Assurrrmrc, Audit Rel,,,rt 1- )1 - A 8470006j
Program Marnag•ment and l)emiju Control Art iviti s Associated With
0V Discipir:e Staffing Revision 61' Major Provcidures• " (OQA08408- 503)
. ". >'
I166 Memnorantdumn f rumi A. W. Andi. ron t o M1 Na
ell'~ *IjtI r iue '
193,'Auq1 t. 0)375
Mv- 1)e Cont. ot I 0)()QA 00 14-504 1O
167.. Const ru.t i ou ,ua i ty A•siur i. Ie AI 1 Wl /1 F Wit (W0A 8.0427
00 1
" 168 .Coust ructbon Qua lityAssurance
Audit W1- 81 03 " (WQ, 8 1072 7S169.Nmoralrtun
from K k.,Chandler to Q .0 Peasloy dated tl.'rch 21-
0.199S "QS.Anjit
85-05 -. Electrical
Engineering Srmich,, :1(343'•
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8$0321 929)
... 17(, Nmuanduni I rm 4 (. 8easI'y to FP. C•htl P,
dt ePd fr A I nrary 28,
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171. OEDI)C 2QAI -2 P, vji to i 1 dated-' Febuary Q, .1984, 'En;tallishment.
of y
I. i m im t ed QuaI it y Us;turance Proitg , rn QA 4,022f 1]) .
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1984 "V0- A.' r'ssm•n of Rcnuwit
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so .t ud'' iln te S6 Cr- i
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S. 85022:A-I?, HmPoranimh
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1904 ''WRIN - Surveillanpe ,Report
on tLn' h .Umlt o! i *'zed System.l for1 _4.;I i- DC -30 - I , "WhSI? II&Qgnri
ter a jfor: Vmorgmuy Atfx di iary' AC_ Powet
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............
V~Vt -
rVk't~VWV,*.
Vt
00Q1 'E
TENNESSEE VALLEY AUTHORITY
NUCLEAR SAFETY REVIEW STAFF
RiPORT NO. R-85-07-NPS
SUBJECT:
DATES OFREVIFW:
TEAM LEADER'"
FOLLOW-UP REVIEW OF QFB RECORDS INVESTIGATION I
MARCH 18, 1985 APRIL 15, 1985
R. D. Stri>"
R. C. CLITSHAW " "-DAi
07 0 51:-, 152,
-83-13-NPS :
rE'
z4
'"4 ,
4> t.Cf>
TEAM MEMBER:
APPROVED:M. S KlIDD
-~"~IV.
VV
vI.
TABLE UP CuCNTEXNTS
Background ..... . .
Scope . .. . . . . . . . . . . . . .
Conclusions/Recommendations .
Status of Previously Identified Open
Details . . . . . . . . .
A. Corrective Acltion Management.B. Quality Engineering BranchC. Sequoyah Nuclear Plant ....I). WaLts Bar Nuclear Plant ....E. Vendor Manuals ........
Personnel Contacted ........
References .... ..............
Items
page,
2
2
54
7
10
4.. 5 '4
44 .4
4 4 4
44. ~4 A
4 4
'Ton
MR,.
"a' '
BALMJNUUNUJ''g
"rhe original. Nuc lear Safety [Review Staff (NSRS) investigation >h'vo"
1-83-13-NPS found that vendor records assembled by the . Quality.' i'
Engineering Branch (QEB) were not being transmitted and incorporated
into the construction records for Sequoyah Nuclear Plant (SQN)..as -
required by TVA procedures. It futher found that construction records": ,
associated with QEB source inspected procurements filmed and trans-, y2':, ;
mitted 'to the Office of Nuclear- Power (NUC PR) at SQN, -were.,not,",
indexed to a level sufficent Lo allow easy retrieval, and the com-.
pleteness of records at both SQN construction and QEB was in question. i!-. o&
As the organizations involved in the collection, transfer, and receipt
of the records exhibited interfacing problems at that time, it was
recommended that an interdivisional task force reporting to, the ýt. Y;I f:
Assistant General Manager (AGM) (Technical) be formed to correct the
problems identified and establish an effective records system.
The implementation of the above recommendation was delegated to the"
Manager of Engineering Design and Construction, further delegated.-",;
jointly to the Project Managers for Bellefonte Nuclear Plant (BLN) and
Watts Bar Nuclear Plant (WBN) who established a task force chairedby ;
the Assistant. Manager of Construction. Through the efforts ofthat, A. PAP
task force, which was in existence between December 1983 and'April
1984, considerable progress was made toward improviqg interdivisional
communications and the improvement of a records maintenance., and "
retrieval system.
Of significance, the task force brought about a cho.age in the require--., "D'
me-t that QEB records be incorporated into construction records and.
transferred to NUC PR in total. NUC PR identified those records .Wit 7
requited at the site for immediate access (e.g., construction records), Q 5
those that could be retrieved within a few days and located elsewhere
within TVA (e.g., QEB records), and those that co;uld be forwarded.Lo a
Federal records repository (e.g. vendor radiographs). OrRahizational" lot
assignments were made within the task force to effectuate the changes,'
i n record locations and ease of retrievability, procedures were'pre- "'
pared, and the task force disbanded. UnfortunaLtely, the corrective
ac(tio s were nuL totally effective. .... .
Since disbandment of Lhe task force, individual organizational efforts .:
were underway to. implement thei.r assignments, and improvements in ,
records. were seen by NSRS during this follow-up review;: however,... T
records retrieval systems were not yet complete. QEB records forSQ '.!':.".
NSSS and principal piping contracts remained unveerified for complete-.VP
ness and lacked easy retrievabiltiy. . Information retrieval continues "
to be very dependenL upon the memories of people at SQN,. WBN, and QEB. r
Open items left by the task force were bein; followed as an ancillary ;
function of the Office of ConstrucLinn (OC) Quality Assurancie ranch ,Y".
(QAB), Management oversight of all individual efforts was not seenn.
.. '~ ~~ ~ . . . . .. ... .. :' ,-• ' :. . '• .,.
y,.
II. SCOPE
KI
I
, TV
LII
TNSRS conductd a follow-up corrective action review of the find -"
ings and recommenda ions associated with NSRS repnrt I-83 ,P "
This review covered the activities of the Office of Engineering (OE),.j "
OC, and NUC PR regarding the acu.tmulation, storage, transferring, andKQQQ
retrievability of vendor and construction records connected with pro-
curements requi ring QEB source inspection. This fol low-tip review ,,: ',,
inrluded discussions with personnel and the review of selected records"ý.
at SQN, N, and EH.
CONCLUSIONS/RECOIMENI)ATIONS
R-85-O7-NPS-O1 Manager of Power and E•.inepring Ajppointmgnt of aI
Records Manager
Conclusion
.Throughout this review no upper management coordination entity-was,)identified as a focal point to resolve programmatic problems or to ,
establish priorities and schedules for completion. It appears that
the upper management involvement that. was present during the task
force era has been lost through reorganizations and retirements. It
is essential that upper management become involved once again and to
continue its involvement until such tire as TVA's tremendous volume of -, 0
0old vendor records are in retrievable order and the present, sysLemof-:,,.
placing new vendor records into the appropriate records retrieval"
system proves itself effective (see section V.A for details).
Recommendat. ion
It is cecommended & h,.t the Manager of Power and Engineering appoint an
upper-level manager impowered-with the responsibility, authority, and -!
orgatnizational tfreetdom to assure that records associated with the 00.00
procurement and installation of QEB source inspected equipment an!d-.i.
materials are assembled, verified for completeness, -indexed, a nd
stored for retrievability by present. and- future users of hose'ý
records. That apointee's scope should include all past and future QQHEV am
source inspected procurements for SQN, WBN, and "LN and the establish:
m.nt of a schedule for completion of past records. .
V. STATUS OF PREVIOUSLY IDENTIFIED OPEN ITEMS i*. ̀
The memorandum transmitting report I-83-l8-NPS to the AGH (Technical)
* contained one bromd recommendation. To provide ease .-in addressing R
each of. the issues still - requiring action, that recommendation has.i
been divided into two separate recommendations as follows:
I'
2
A. 1-83-13-NPS-01, Examine Findings of NSRS Report (1-83-13-NPS)
and Take Necessary Steps to Identify Actions Re uiredBy the Line .'
Organizations (POWER, OEDC, OQAu.and OGM) to:
I . Develop_ an lntegrzted Records System for QA Records that
Will Satisf_ the Needs of NUC PR and OEDC
NUC PR has identified the records required and subdivided,
• them into three categories. Those subdivisions are docu-.
mented in procedures and supplemented by memorandum for
site-specific construction records. Assignments for records:
* responsibility have been made by procedure. Rerords index-
ing procedures have been prepared and are in various stages"
of implementation.~ A TVA task force• was working on vendor'
manuals. This item will remain open until the conclusions'ý_
and recommendations of the vendor manu:Al task force have
been evaluated by NSRS and more experience is gained by the,''
Office of Power and Engineering .(P&E) with the records'j
indexing system. (See sections V.A and V.E for details.),
2. Correct Implementing Deficiencies Identified in the
Exist intSstem
a. Most of the major problems were found in this area.
QEB records were not adequatley indexed and thereiwas
some concern regarding their completeness. Efforts
were.under way to place completed contracts into the
established indexing format and have them filmed by
RIMS, The more voluminous NSSS and principal piping
contracts were still unorganized and unverified' for.
completeness. QEB stated they would receive .the
highest future priority; however, no schedule for•com-lý
pletion had been developed. (See section .V.,B for.0K
details.).
'.. ...
b. All construction records for SQN had been transferred.,.,
or were in the final stages of filming. A Records',,.
Retriev al Indexing (RRI) system.was prepared but judged
not totally effective because it did not preclude the
need to rely upon, to a large extent, the memories of
key individuals to locate records. (See section V. C
for details.)
'.~ A ~
~"
c. Construction records for WBN were being identified-for
transfer to NUC PR. An RRI had been prepared and coam-
munications between OE and NUC PR at WBN regarding
records and indexing was active. The mechanism for
selecting OC records systems for transfer, establishing
transfer priority, and records acceptability was. less,,
formal than it should be to be effective. Records
requested during this review were retrievable but this
was dependent upon people's memaories. The, level of
3 _''½
indexing and cross reference capability described for,ý`.
the records when ultimately transferred to NUC PRshould reduce the people dependency and provide a very
usable set of construction records. (See section V.D...,for details.) .
d. Continued upper management coordination involvement at
a level capable of crossing organizational boundariesis considered. necessary until the problems are solved "
and records systems prove effective. This item remainsopen. (See section V.A for details.) .. /" ,!
Provide Documentation Records to Each of the _OpratinSites as Required by.. NRC Requirements and TVA Commitments ,.
QEB records are no longer required to be onsite. TVA proce-dures and the Topical Report have been changed to reflect
that change.
An NCR (GEN QEB 8401) was written for WBN and BLN identify--ing noncompliance with 10 CFR 50 Appendix B, criterion.lXVII. _'k....and ANSI N45.2.9 regarding QEB records indexing and retriev-ability. NSRS found the specified corrective actions for '
3.
1~
LildL.. ., idU U e'I acIcLomII shJ d .I , " .. ;....
Procrcures exist to accomplish the transfer of records to.
SQN. These records are now or soon will be transferred.The retrievability of records is the subject of item V.A..
above and will be followed and resolved through activities
associated with that item. This item is closed. (See
section V.B foi details.)
4. ClarifyOrganizatiuaal Responsibilities j
With the exception of a clearly defined system for vendor .. ..
manuals, organizational responsibilities have been defined.
This item remains open pending the resolution of the vendor ,j"-"
manual issue. (See section V.E for details.) . .
B. 1-83-13-NPS-02, Reportback to the oGM on the Planned Actions andt
Schedu l.e for Corple tion of Actions
Two reports were made by the Manager of OEDC to the G .GM F4' :
(Technical) regarding the implementation plans and schedules of'!
OEDC and NIUC PR. The pl,•nn were predominately procedural iný,
nature and the schedules indicated when the revisions were to be ".11
c~ompleted. .The corrective action was less than adequate in~thatno schedule was provided that established when the records them-
selves would be verified-as complete and indexed for retriev-r=
ability. At the time of this review the OC records transfer.for:,
SQN was essentially complete and, therefore, no schedule is .t
required. WBN by procedure has until six months after commercial"-
4
"a.A.
IwA.
.operation offrame is precompletion.indexing ofa schedule fV.B for deta
rAILS
untit 2 to tran:.fer records; however, a shorter time-",;;'
•ferable by NSRS' for those records Systems that reach ..7",QEB, however,' has not completed verification -and
their records for SQN and WBN nor has QEB established t,"
or doing so. This item remains open. (See sectionils.)":
" - . •
Corrective Action Management
As the original investigation found interface problems between .
OE, OC, and N11C PR impacting their assigned responsibilities, it
was recommended that an upper management task force capable of
crossing divisional boundaries be established to further.quantify-.', k
and solve problems identified in NSRS report 1-83-13-NPS. It
was further recommended that the task force report to. the AGN.lI,.
-(Technical). Through a 'series of :delegations a task force or,,:*,
committee was established under the chairmanship of the. Assistant.:i
Manager of Construction with the task force reporting to the"Q
Project Managers for WBN and BUN. . . .2
Representation on the task force included a good cross section of .•
personnel from OC. and NUC PR and included representation for
Office of Quality Assurance (OQA) and periodically QEB. ",'"
Through that task force NUC PR developed a three level system. of.,.i,
records which was incorporated into procedure ID-QAP-l7., and
formed the basis for dividing records responsibilities. QEB`'
would retain, be responsbile for, and. retrieve information from JPý
vendor records under their source inspection program. Construc
tion would assume responsibility for construction records asso ..... 11
ciated' with vendor products after the items were released for.
shipment by QEB.
In addition, the task force developed art indexing system for',"=
records to be transferred t.o NUC PR by each project office..' That- .-ý,t.,
indexing system was. called RRI, and generically proceduralized:.",n!
with input "from both OE and NUC PR in OC QAP 17.2, "Records !2IŽ•
Retrieval Instructions." Each project (SQN, WBN, and BLN) ,was to .:, Y't
develop their own site-specific RRI. ' , .
In April 19.R4, the task force held its last meeting'thus termi-. .
nating its existence. On June 8, 1984, by memorandum, the.:.
rbroject Managers for WBN and BLN requested the Manager of P&E, to !'
reassign responsibility for follow-up of R-83-13-NPS findings to (OE.'. The Manager of P&E did not concur in the transfer and
further upper management involvement in' this issue couldnoti~be.i'
identified. Since there was no further upper management atten-•
tion given this project, it appears that' schedules for completion 'a>',
of QEB records, answers to programmatic problems, and follow-upl,,A-
of task force open items (which were being tracked as an ancil •..•, ,
lary function by the OC QAB) remain unaddressed. ,'
With reorganizat ions and retirements, the initially involved.upper management personnel are no longer in positions to. assume.responsibility of this important task.-' While the Project,"-iManagers for WBN. and BLN -are still concerned and involved with .the records associated with QFB source inspected vendors as they.~,,pertain to their projects, their positions do not cover the-,.:¼..•.'entire OE involvement in all nuclear plants. It would be appro-,,,priate to.-reassign the overall responsibility Of vendor records-I'to a manager organizationally capable of assuring that. theefforts of *OE, OC, and NUC PR are coordinated and accomplishedboth timely and effectively.
B. uality Engineerin Branch h.
Based on NSRS report 1-83-13-NPS a generic NCR (NCR GEN QEB 8401) :was written stating QEB vendor records were ni, easily retriev-,.:.*:ii,:
able and that Lecords were not transferred to the designatedpermanent storage location. The corrective actions specified for .,_
that NCR were accomplished, namely, procedures developed, people`... -
trained, and permanent storage locations redefined. However, theoriginal problem regarding retrievablity was not solved.
QEB developed an indexing •system suitable to their needs and.'defined it in 3QEB-EP 24.7. Work began on processing approxi-Imately 650 ft of compLjted nuclear contract records in ,M..arch 1984. A goal of 5 ft' per week was established and highest "priority placed upon SQN and WBN. records. QEB employees were.ibrought in from the field offices to assist in the effort..' .-7
3At the time of this review QEB. had processed 126 ft of records,..,through February 28 • 1985,. reflecting a processing rate of
3approximately 2.5. ft per week. Of those processed approxi-mately 37 percent were for SQN. and WBN, 28 percent for BFN and.•BLN with the remaining 45 percent of the processing effort goingtoward records of deferred or cancelled nuclear plants and fossil-.plants. While the.statistics show original goals and prioritieswere not being met, progress was being made. Two of.the five', :T,-0QEB sections have completed almost all of their records, onesection han its records in order in hard copy, and another is.placing its priorities primarily in the WBN, SQN area. Of con- .. '
cern to NSRS are the major NSSS and principal piping contractsfor SQN and WBN which have not. been worked on since the originalNSRS investigation, QEB management stated that increasedpriority would be placed upon those contracts and a new addition i:-kto the QEB Knoxville staff was coming from a field office to help ..in that area.
3:2Reasons were given as to why the processing. rate was not 5. f tper. week (e.g., lack of personnel, other priority work, RIMS notable *to keep up); however', no information was found that,"ndi :cated OE management was aware that QEB processing (verification iVZ,of. record completeness,, indexing, and entering into RIMS) would'A
6
0
take twice as long as anticipated (i.'e., four to five years) orthat they concurred in the increased time. The original estimate'wplaced the processing effort at about two years excluding any.--,increase in the rumber of completed contracts. In addition,there was no TVA upper management official (discussed in section *--•'
V.A above) to oversee progre3s or provide added impotus...
To evaluate the retrievability of records by QKP fnr SQN, QEB was.,requested to produce manufacturing data for a flow element in the 'ýunit I reactor coolant system. That information was produced in..,.about two working d:-ys and, considering the type of information ! .
requested arid nature of the request, NSRS considers retrieval of•,"that information to l.e outstanding. Unfortunat'ly, the retrieval'• .
-of that information was not due to the QEB records retrieval sys- -tem. It was retrievedbased upon-what people (both present and,.,.former TVA employees) remembered.: That exercise highlights three. ,
points:(1) the records are currently retrievable but dependent - -
:upon people, (2) people should not be considered an integral part.:-of a retrieval system, and (3) the development of a retrieval .system will be di(ficult. ;
Considering all the above, QEB should take steps to assure that .the NSSS and principal piping contracts are verified, indexed for,retrievability, and stored (either hard copy or RIMS) as .soon asis reasonably possible to produce a quality, usable end, product.','ý,
C. Sequoyah Nuclear Plant
OC at SQN had completed processing all of its records.: The gen-eral records (training, certification, etc.), had not been pro-cessed at the time of .the original investigation. Since that
:investigation, the SQN RRI was developed and the general records ' ,..
were indexed to it. The records previously filmed on plant sys- ,-:-i""-tems remained as they were found during the original investiga - -
tion with some additional indexing. .
An RRI had been prepared to enhance NUC PR retrieval of:OCrecords. It was reviewed by NSRS and judged to be a good J-•-{description of the records available, but of little value in,}locating the records. Various pieces of equipment were selectedby NSRS to demonstrate their records .retrievability. It wasfound that records retrieval was dependent upon the collective,.<memory of four individuals, a lot of searching, and not theretrieval system. Two of those people were NUC PR employees and •two were OC employees that would not have their present jobs in ---- >
the near future. It is understood that since SQN plant systems.records have already been filmed and the hard copy:. recordsdestroyed, the task of developing or retrofitting an indexing.--.system is- extremely difficult and in some- cases may; not'be*justifiable. However, the future usability of those .:.recordsa 4is dependent upon just.such an effort -'(probably in some -.cases.amanual indexing .on a frame-by-frame basis). As SQN is down todý -
four knowledgeable individuals, it appears imperative that. addi-•tional personnel resources be devoted to the indexing effort."..
7
" " . . .. : . . . LII"'i : :fi l:"! . ..
The system for vendor manua ls was reviewed and found to be i n
good condition. The manuals were indexed, systematically revised,.,
and.controlled. A question was raised by NSRS regarding whether..
or not any of the manuals were considered one of a kind, and ..
therefore, in need of fire proof storage. SQN agreed to evaluate-.."
that concern.
D. Watts Bar Nuclear Plant . .
NUC PR and OC personnel at WRN were in the preliminary stages of .. .. ..
developing a system for the verification of records completeness, ...indexing, filming, and ultimate, transfer of OC records. At the
time of this review very few records had been filmed and trans
ferred and most of those were being redone based upon the direc-
tion given by the task force discussedin section V.A. and the:,'
RRI developed by WBN. The RRI .was understandably not complete
and will undergo revisions as new systems of records are preparedfor transfer; however, the. format of. what was prepared appeared •
descriptive enough to .allow' retrieval of information cataloged
and filed under that system. Both NUCiPR and OC personnel were
communicating about specific records systems and the level- of ''•*'
indexing required. Current plans and estimates include 100 per-•;L,-
centverification of records completeness and computer indexing
of about three million entries on both document and folder level .
indexing. One problem identified with the current approach was
the apparent informal structure of the transfer process with
regard to identified interfaces, priority for transfers, and for-'..
mal acceptance of the records for completeness, readability, and .: '7:"• su:s:
retrievability by NUC PR.
At present, through NSRS requested OC documents on QEB source.`ý "
inspected contracts, the records retrieval system at WBN con-"
struction was determined to be very people dependent. All docu-"
mentaLion requested .was. found indicating the required documenta-.4tion was onsite. Based upon the future level of indexing in the
RIMS system, people dependency should be greatly reduced andtime
for retrievability enhanced.."
Vendor manuals were controlled very well. They were adequately C:.
indexed and revised. One problem regarding the lack of as-built-' .:
drawings for the solid state reactor-protection system had been -
identified and was in the correction process. No other vendor .
manual problems had been identified, One enhancement to the.
vendor manual maintenance program was the identification.of those -,',.
plant procedures wherein the manual was referenced in the front
of a manual. The supervison of document control and vendor
manuals section identified several, areas where the section-was
trying toimprove its programs. .. .
E." Vendor Manuals
The currently applicable procedures. for OE, OC, and NUC.PR vendor."',
manual control were reviewed. .They were found to be selectively'.,
.vague in that implied responsibilities rather thaný specific
-. . . ,A.,.: ~ .... . " .:.........,.....-....•' ' : . . . " ' "i::•i~i: -•: .' :::: ': -•i
'*..t~
-3~33,.,
-3~3
responsiblities were assigned to each :organization to perform.
the same functions. As "a result it was unclear: as to ýwhich •
organization actually maintained control over vendor manuals.. .
A task force was developing a new procedure regarding the main" 'j
tenance of vendor manuals which should correct that .. probl-em.
V. PERSONNEL CONTACTED
A. Office of Nuclear Power
1. NCO
G. Cannon Records Officer, Document Control Unit
.. M. McGuire QA Analyst., Quality Projects.Staff,
R. C. Birchell Compliance EngineerD. L . Cowart Quality Surveillance SupervisorJ. R. Crisp Administrative Services Supervisor,*- ::p.,
MZ.H. Kabiri Support Services SupervisorG. B. Kirk Compliance SupervisorD. 0. Lockmiller :Document Control ClerkS. B. Miller . Regulatory EngineeringL L. M. Nobles O&E S'uperinten~denLP. R. Wallace Plant ManagerN. M. Welch Information Systems Specialist'. ., ' '
.3. WBN .
.R J. Blevins, Jr. Information Systems Specialist,ýR. T. Chattin Administrative Services SupervisorR. L.L Hleatherly Drawing Unit Supervisor -
R. C. Saner Compliance Section Supervisor,B. S. Willis O&E Superintendent.
B. Of f ice of Enj ineering
P. D. Andersmn Document Clerk, QEBE. G. Beasley Assistant Division ManagerM. D. Conner Materials Engineer, QEBG. F. Dilworth Director, Division of Engineering and Technica I
Services ,
W. C. Graves AdministrativeOfficer, QEB ,
If.. W. Knox Materials Engineer, QEB -
V. Koger Information Systems Specialist/, RIMS. ,
J. F. Lewis Materials Engineer, QEB -.
C. L. O'Dell *Chief, Information Management Systems StaffJ. W. Oravitz Materials Inspector, QEB -
J. L. Parris Chief, QEB0D. E. Smelcer Materials Engineer, QEB'J. L. Snyder Section Supervisor, QEBJ. M. Winebrenner Materials Engineer, QEB
9*.. • • ' ' : .. .. ?3 :
C. Office of Construction
1. Central Office
A. C.J. T.R. A.J. E.
Kel leyMcGheePeddeWilkins
Assistant ManagerUnit Supervisor, Quality AssuranceAssistant ManagerRet ired
D. A. Bat.eson StaIff Supervisor, Office and: Civil>i;
Engineering Branch
Engineering Aide, Office and CivilM..C. Shivers
3.' WBN
Engineering Branch .; .:?,
Supervisor, Instrument Engineering Unit.
Supervisor, Document Control Unit
Engineering Aide, NS Unit
Supervisor, Document Control Unit
R. W.M. S.S. A.J. E.
ForsterJohnsonLuckSmith
D. Office of Qua lity Assurance
J. J. Knightly. Supervisor, Documentation and Data Management
J. A. McDonald Chief, Quality Improvement Staff
S. L. Patton Records Officer
REFERENCES
NUC Power Procedures
1. NQAM ID QAP 6.2, "Vendor Manual Control," dated December 31, 1984
2. ID QAP 17.1, "Transfer of Quality Assurance Records," R4, dated
VI.
July 10, 1984
3. NQAM ID QAP 17. 1, "Transfer of Quality Assurance Records,".dated December 31, 1984
4., ID QAP 17.2, "Quality Assurance Records for Design and Construc-,ý,Lion," RI, dated June 8, 1984
5. NQAM ID QAP 17.2, "Quality Assurance Records for Design and,>
Construction," dated December 31, 1984
6. N-OQAM, PART III, Section 4.2, "Transfer of QA Records from OE.
and OC," dated October 12, 1984
7. WBN Administrative Services Instruction Letter D-18, "Retrievall
of AS"E Code Documentc,' dated January 9, 1985
10
777-77 -7-4 .7W 10-7- . .........
8. WBN Administrative Instruction 4..1, "Interface Responsibilities, ;
R9
Engineering Procedures
1 QEB-EP 24.37, "Prod~uct Compliance Data and Quality Engineering,;
Records - Processing and Disposal," dated January 22, 1982
2. QEB-EP 24.58,- "llandling of.Supplier Records," dated February 9, ..979
Construction Procedures
I. OC QAP 6.2, "Vendor Manual Control,. dated September 3 1985;
2 OC QAP 17, "Quality Assurance Records," R3, dated October 1, 1984.
3. OC QAP 17.1, "Quality Assurance Records," RIO, dated October I, -!
1984
4. OC QAP 17.2, "Records Retrieval Instructions," RI, dated Octoberll.i
1984
5. WBN Quality Control Instruction (QCI) 1.08-1, "Records Retrieval,'._ ,_
dated May 15, 1984
6. WBN QCI 1.40-3, "Universal System Program," R2, dated October 12, Q
f.. . . -:
l orrespndence
1. Memorandum from H, J. Green to Ch- cles Bonine dated August O,7
1983, "Bellefonte Nuclear Plant - Microfilming-and Cataloging of-
QA Records," including attachments (DOC 830811 007)
2. Memorandum from C. L. O'Dell to Those listed dated October 4,
1983, "Vendor Records Study Team Meeting Notice, Third Meeting"
3. Memorandum from M. N. Sprouse to G. . Kimmons dated October . 17-
1983, "Draft Vendor Records Study Team Report", : ,.%'
4.. Memorandum from R. M. Pierce and W. R. Brown to Those listed
dated November 3, 1983, "Meeting on Vendor Records" (EDC 831103 701)
S.' Memorandum from J. A. McDonald to Those listed dated November 16, )!
1983, "Transmittal of Revision 1 to Quality Problem 83-25'!,`."
6. Memorandum from Charles Bonine to L. S. Cox dated November 17,.
1983, "Transfer of WBN and BLN Site QA Records to NUC PR"
JDOC 831117 001)
7. '.Memorandum from J. E. Wilkins to Those listed dated December 5,-
1983, "Transfer of Records from Construction to NUC PR"1 Y
(DOC 831205 003)
8.
9.
10.
12.
13.
14.
". . 16 .
17.
18.
. ..... " " 1
19.
20.
*** ,.' . , 21
.I22.
st ,,-4
':,' .
ac 0AA :i" " -W, _X. ,•!¢•
Memorandum from. J. E. Wilkins to Those listed dated December 22,;1983, "Transfer of Records from Construction to NUC PR"(DOC 831222 005)
Memorandum from G. H. Kimmons to G. F. Diiworth. dated January. 5, -;; s ?1984, "Vendor Records Interim Report," Administratively,-Confidential . .
Memorandum from W. R. Brown and R. H.-Pierce to Those listeddated January 10, 1984, "Vendor Records -. Interim Report,".Administratively Confidental "
Memorandum from R. W. Cantrell to W. R. Brown and R. M. Piercedated January 26, 1984, "Vendor Records - Interim Report,".Administratively Confidential.'". " ,
Memorandum from J. E. Wilkins to Those listed dated January 26,..1984, "Transfer of Records from Construction to NUC PR" , .
(DOC 840126 002) .
Memorandum from Vera Koger to KEDS Files dated February 17,1984, "tEDS-QEB-Supplier Record Files - Meeting Notes"(?fED 840217 005) ....................-.:..... ......
Letter from NRC Region II (Verrelli) to H. G. Parris dated ..
March 13, 1984, "Inspection Report, WBN and BLN" (A02 840313 006). -
Memorandum from ,J. E. Wilkins to Those listed dated March 16, .. . ,A1984, "Transfer of Records from Construction to NUC PR"(DOC 840316 006)
Letter from I. M. Mills to J. P. O'Reilly, NRC, dated March 29,
1984, "Retrievability of QA Records, WBN and BLN" (A27.840329_006) - -
Memorandum from J. R. Lyons to J. E..Wilkins. dated May 24, 1984,"Vendor Records Requirements" (OQA 840524 402)
Memorandum from J. A. Coffey to C. Bonine dated April 13, 19R4,"Transfer Request for Duration of Construction Records Generatedat SQN" (DOC 840416 002)
Memorandum from J. E. Wilkins to. Those listed dated April 13,1984, "Transfer of Records from Construction to NUC PR"(DOC 840413 005)
Memorandum from J. L. Parris to C. L. O'Dell dated April 16,""1984, "Processing of QEB Suplier Records" (QEB 840416 004);:!.,
Memorandum from J. L. Snyder to J. L. Parris dated April 24,.'.1984, "Monthly Activities"
Memorandum from John A. Raulston to L. M. Mills dated March 28,-•1984., "WBN and BLN Retrievability of QA Records (NEB 840328 280)
: : >:i•.4,
2'f ~
12
:23... Memorandum from J. P Darling to W. R. Brown and R. M. Pierce
dated May 8, 1984, "Vendor. Records - Final. Report Action Item"
(EDC 840510 701) -
.24. Memorandum from J. R..Lyons to J. E. Wilkins dated May 24, 1984,
"Vendor Records Requirements" (OQA 840524 402) .
-25. Memorandum from W, R. Brown and R. M. Pierce to I. G. Parris 7
.. dated June 6, 1984, "Vendor Manuals" (EDC 840607 702).
26. Memorandum from J. E. Wilkins to Those listed dated June ii, 1984,."Transfer'of Records from Construction to h1JC PR" (DOC 840611 004)V
27. Memorandum from J. L. Parris to J. A. Raulston da.ted June 25 1984"2',f•2 c
."SQN, WEN, BLN - QEB Vendor Records Nonconformance Report" .
(QEB 840625 003)
28. Memorandum from James P. Darling to C. Bonine dated June 25,
1984, "Transfer Request for. Duration of Construction Records,,
Generated at WBN" (L68 840524 823)
29. Memorandum from J. L. Snyder to.J. L. Parris dated July 3, 1984 ,"Report of Activities"
30. Letter from L. M. Mills to J. P. O'Reilly dated August 1, 1984,
"Retrievability of QA Records" (A27 840801 012)
31. Memorandum from J. L. Parris to Those listed dated August 28,
1984, "SQN, WBN, BLN - QEB Vendor Records - Nonconformance .. :..:•.• ~Report" '(QEB 840828 005) -,s
32. Memorandum from S. A. Burt to Files dated November 13, 1984,
"WBN - Microfilming and Indexing of QA Records" (WBN 841113 151) :V
33. Memorandum from S. A. Burt to Files dated November 19, 1984, .
"WBN- Microfilming and Indexing of QA Records" (WBN 841119 151)
.34." Memorandum from S. A. Burt to Files dated December 14, 1984,# " --.
"WBN - Microfilming and Indexing of QA Records" (WBN 841214. 151)
35. Memorandum from G. Wadewitz to C. Bonine dated December 21, 1984,-:
"WBN NRC Exit Meeting Notes - 390/84-86" (WBN 841221 014).
36. Memorandum from M., Conner to QEB Files dated February 26, .1984, I
"Meeting Minutes - Vendor Information and Configuration Control" .. -
(QEB 850226 001) >,/. .!,'
Miscellaneous ~-~
I. Data Package on Item No. 1-068 [.227-0002, Reactor Coolant'Loop
Flow Transmitter and Associated Assembly (WBN) ...
1. 3. .. : !. , . •, ,,... .:, ,!
1 3 . .. "• . ", •" "•- = •,
jg!kýl
• n
2. Data Package on Item No. TVA MK-68-7, TVA B/i-41W465-3, Orifice'Plate and Transmitter for Unit I Reactor Coolant Loop (SQN).".
.3. Informal Note from J. L. Snyder to D. Smith dated March- 27,
- 1985, "Recap of Study on Vendor Records"
4. Contract Inventory Worksheets from QEB .
5. QEB Computer Inventory of Vendor.Records Completed
6. PRIDE Data Description Form •'...
1. Miscellaneous Component Records Retrieved upon InvestigatorRequest (SQN) . -*.."
1'4- -.- ... . . . . . . .. . . . ... . ., . ~ ~ ~ N
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001 '85I 0605 5 0
TENNESSEE VALLEY AUTHORITY
NUCLEAR SAFETY REVIEW STAFF
NSRS REPORT NO. R-85-08-OE/NUC PP
SURBECT: SPECIAL REVIEW OF TifE OFFICE OF 1. EN(INI.ERIN( (OF.) ANI) "OFFICE OF NUCLEAR POWER (NUC PR) ACTIVITIES ASSOCIATEDWITH SEQUOYAH CONTAINMENT PRESSURE AINSTRt14tIFNTATION
DATES OFREVIEW: April 3-9, 1985
April 10-12, 1985April 17-19, 1985
- OF, Knoxville- NFUC PR, SQN- OF, Knoxville
REVIEWERS:$G. iE RANTar""l D)ATE
W.---D. ;ý4-TES 4-- --- 651ý- DATE
APPROVED BY:l. S. KIDD
S4:S-DATE
,.,,•
,° ,
TA\ [H 1,EoV C ()NITNTS
S I. IHa;ck, roiittd...................... ;,; ......
II . S , . .. . . . . . . ..
I Il Conclus io'n; anjd IRc.commcndat. ion:.; . . . . ..
IV. I. ta o 1; In . . . . . . . . .... ...........
- i s. l ; of er P.ict sonume. rl . . . . ..vi d.
"i . VI, References (lDocumemts Re:viewed) . . . . .
2
35-
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E EEQR
EN DESFl'
FE/FERFSAR
J C 0)
mOA
SIR
" NC'R 'm
N ILS
QMl
,::L•NRC ýNSRSNSNSSS
... 010I!( PR ,
OFS0* .O'DC
OQA
*PAM
QA
NHRS EP
SqNASi'
WBN
ACRONVMS
Civil I Eng ilive eri ng Branch (ON)t.ontainmienI. Pressure 1)i fferreut ia l Traimi QM
Compliance SC.t. Ion Super'viso.r (89QN) 7
Des i gni Bas i Avc ideLt.i)esi gn I>gn j t P mManag',er (!QQN)Enrginfevri inK Change Wot ieElectrical Equipmen t.l Efnvill'OllilfflLM I QIli l i ",i it ) H1 tM11Division, of Engineering. fesignI in' P..CFii nen:r i nig ProceluresSQN Equi piment QuaIi fi cat i on' sheetFailure. Evaluation/Engineering Ne-port
Final Safety Analysiis ReporAHligh Ene rgy Line BreakInstfrumrent Matintenance Ilstruct.i ilon
Justification for Continued OperatiouLinimitingi Condit.ion for Operat ionLoss of (,ool ai Accident.Mli I I i a mpe reMaxi mumI C red ib I e Acc i denl t
a i tt enialCe Request
Nonconformance ReportNuclear Discipline Projeclt Eg rneer COE)Nuclear Engineericug IHranch (OF)Nuclear Licensing Staff (OM)NEM Site Project EngineerNuclear Quality. Assurance ManualNuclear Regulatory Commri ss ionNuclear Safety Review StaffNuclear Safet~y §taff:(NUCPR).Nuclear Steam SupplySystlems Set lou (SElt QNtWIiN) ;.. -
Of1fice of Nuclear Power-Office of EnineeringOffibce of Engineering Misn gnand (diostiintloci ('irganizaition-
was the predecessor to OF and the Office of (ouistL rid'L. iA.:
Off ice of Qual ity ,M 'isrance "
Operat ions Support Group (OE).Post a.c i dlnt Monitoring Inst iiirumn atiOffice of Power (This office has be in l a il ihed)
Qual ity Assurance
Quality ControlUnit OLf Rad I it ion DoseRegulatory EngiineerinRg Sert ion (SQN)
Residua Ilea t.L Remnova I-Safety Evapiat ion Report,Suryei I lance Instruct.ionSequoyah NucI ear Plant
SQN Technical SpecificnUtionsWestinghouse
"Watts Bar Nuclear Plant
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g~il gre I 9SQN -St ýe I ,oiltd a mell Ln VC S S ~ r V I and (O~rýe~Re~act"h, Shibl'BIUfIhiLd in
Fi gure 2 "Loca~tioni of the Foxhoro CPAit in th? rAtiriull 16 I fill
figure 3 "Foxiioro Model~ KI~I vF'rld. ialand P'ressure) eri ~ U'1%
[i 0tr 4 Woho&~ Made! EI~IGM Force Ba lance Presre e Thif'li I re~iial Ir in 1m mit t.e r '(Pr inc'i ple of' Cperat ion Tri
jigr 5u'e Graph ic Ill us~i.t ioi' of Annul"; l irgio *'ft " MIp too AQ sk 1.* Wo~~-rse.C.3eJiA
5SQNNEIR8niO
1, 1 ST 1) P Ar A CI M F NT,
I1ý SQN Iqui ipmt'n QualifUi cat.ion Sheet. (EO) - .E(S No. SQN-NEii-30.-2t.Revision 05
2 OE: En~gi neerring Procedu: e I.26. ( R8) Flo I h ow .
3 OE Engi neer inrg Procedurd 1 48 (IN) Floiw Chart.
4- NUG PR Standard Practice SQAI18 Flw Chart
Vol
ITT!Aoki W
A
* iACK;GR( )UN 1)
Eight ( tour for~ eaCh "nAL) 'Modeli ElICIi Fonx 1)r.6 to r, hv b-,ance COntin aiimeni pressure di I ferenLial Lr;nswittes. (CPIAR) were being usi, I. ti
m"nr Lo r the pressure di fterential between di. inside of the s I , .containmenL ves.sels surrounding both Sieqnoyli Nui Iear I'lant . (S NI ,. ,
nuclear reactor'., and the annul'us regiots betwee'n the l. teel V 'I .v ssel s ai Hd.,t he, vrnnrot, riki~or shield huijidings (sev I iuriesh I a " d 2). 1 Iu W.(two for cach uni it) of Lhe C(ldts were aSsoc iaLt I' with LlI. prsta'cidh it-
.monitoring (PAM) system. During evaiat.iLions o the L hability otf Lhvs, ,-.,.n
transmitters to perform their inttended saf. 'ty uiv I, i ons Ai their• "
insitu environment following a posLul ated ei a'isn Is c.is c i1.dnt ( IIIIAOffice of Engine ering (OE) engineers railsed ,puest ii.s aleiut the change i.• -
in accuracy of the t.ransmiLters following th posttulatedu ac'ident. ..
Specifically it diid not. appear thhat diis t.yfpe t rinsfliL tters had lice .i -Les ted to derions:.trit(e and document their accut racy fo: tLhe postacucident.-'eniv i rnnment,
K..UN",
. .I. ... 4
A norinconformance, report. (NCR) ildent i fyi ii H h, i ,pot enit i a-1 accuracy'inadeqrlacies of the transmi.tt.ers war sisue, b.y KIE in .Janmiry 1985iandthe assOciatded Failure Evaluationi/Engiineeriing N•eo,"rt (.E/ER) fWr theNCR was issued in March. The issiance o.f tih NCIR-.FEiR was report 1.,lby, the news medi a and investigated by the N"c l ,;i r Regiiulatory Conimmis-si6n (NRC). The NRC expressed concerns (primairily inIvolvruig timel i-ness) about the manner in which the NCR-FE/ER was i ssu•ed and, subse-"qicenutl,, proccessed. These concerns prompted I he.Nn i'I ,ar Safety Rev i ,w
tiall ('NS1S) to coinduct a special review ini Aptril lN8•N o. the cirnum".stances su, rroundiing the insuancie aiid hiandlinig of th' NCR-FE/ER, antieLhe resul ts of tfit. spec iaI review are, aidre•.sed in this rplrt.
ýjv 01
I ,I . SCO :PE
'Thi s review was coniducLed to det.e.rmine thei fol lowinig:.
A Were the transmi Lter accuracies aciiiiatae fir i",,tLaciAient. idi-'LIi onris
11. Were, the transmitLers enivironmenL.aily qunlif,,l -...
C. The ,iid qiufacy of tihe OE and O)" I ice .of Ntil. I , l rw.r (NIJC ITR) pro-u:oiirs for in itI i taL iing and re•r sn i g NCRi -FI:E /10s (01AtLai )Iishied ait.ihe Ltime, of tht! occurrence) low
•). If the NCR-FE/ER (SQNNEB BuI5 0) was i nii t iat d and processe I''ini
accordance wi Ah the es tab] i hslid p'ironditire .;
F1, Past identified problems wiLth the NftF•-FI/ERi pro ,e.ss . ': .'i .I
F, Act ions t;akeni tLo alleviAte tie rioriconi 'frmi iiu l t Lionu *sp. ci I iedl .in the NCR-FE/ER.
The review consisted of intervi ew, wi dh West. ii,•,ghil,,,, (W), DE, and. N .I, H.It per sonl; inspect. ions of Lthe Lransini tes andi evaluatLion u I jl."VA 0related reRul atory, indutLry, rnd TVA dcumenLs , . .
1'
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in111. C;ONCLUS IONS AND RECOMMNENDATIONS
A, Cidi Accii rjic I forle)tiC d't.orl
W'-
Conc I us ion
The CPdi.t;i accuraci es wAre adequal. ti' prov I & I he . rfqui ired
safety .functoions fell.owin g. the DPA. Thip conclusion was based
Upon the fo I lwino : - .
0. The CPdts were designed J.t fneL ioro i th environnie.nlal.
conditions that they would ,xperiQ cv Ife : the I)BA.h . -
0 The CPdIts were designed to provide a,:crurary we ,ll witlhin thUC.
require;d after the DRA.
The scheduled 18-month sh;rve ill anrf test i ug of. the CI'dt s androut. i ne ca I ibrat ion had .been performerd ., r,,n i red.
hr e mainn rterance history indicat.', that th, C idts ha&' bvl.
reliable since original installati.n.
o Measures were being taken t0 o N'o.Scv' the i•cv i r o i!imei li a IiLtegrity of the C I'dts during IF ait. t it e I 1 a iv:111v a, v i" i e s
(See sect. ion IV.HI for deta ils.)
Hi. Envi Ioneta iuaIf icat ion Status of t he (1lldt s
1. Just tiCat in I~ Cioine WQ I? t I I~ Vt 1i lnn( ýal die CPdit L s
Cunclu s inn
Thl C I'd t,.: id i l.I Ihm .I oe .#Ii ., i',' I 'f*qt i r.'ment s I r i
environmental qua Ii ficat i n. Ins! r"ii s of .he same t ypv.had not heen tested to drtnonAi;Lr'a te tihat Ihiy would performin the envi ronmencal cOndif. ilonS t.Lhat they would experienceafter the DBA, and the. qualifiCat,.on hy "similarity' provi .
sion allowed by IOCFR 50.49 wan imirproperly performed,However, adequate just. ification wan provided for continuedoperalion (see sect. ion II [ A aove) iuti il r'.liacemnt tinstruments could be insiltlI I Il hat had i,•fci•u ntod tesi data
to satisfy regulatory riequiremlnt.9; Irnr ,.ivironmental qual i -
fication. (See section IV.C for ,l, .ai IS)
.4 ~
2. R-05-08-o0-/• 17 PH-o0 (o01) Iacp3t,' .IE .En', i,-nn.,o!Ita.. 9uli 2'ica.Lion -lrocedtsre , .mgnt. QuorI. fi'at.i Si mil -t.i
The OF proced(re for environmental qua I i: t i Ca L ion of SQN -eleCtrical equipmentV aI Iowed qua! if i cat i•, by "mimilarity",as permitted by IOCFR 50.49. Hlowevr, tUle procedutre ronj-,tained no definit.e criteria ,i•rfitting what Wotst Ltnted .."similar" item. As a renult, the SQN (Vldts were improperl:y,..i
1)
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MIT >
C-. . -8
Conc'
NSRSNCR-p rocfolI
ilnl i ifled fol. a peri'od 3-, 1~il1 112 yognr'. j
s'ct L oll I V. C ['ori t lt a i I
IMtAM ish criteris t~hat IiProperly doinesii' what coIskL hutes t:1. ON
"'sim iIa r"' i tem. Inwrol aeteciei,~i' tifni anTY....
into TfVA p ocedures gove iii i ng env rijment i ia I ii I f i cat. loll 'II'
i' ev t ri'ch I equipmnentI. a ni rrev:aIia fumin i I li new. i ~the qua! itf i ('.1 ion statii, nf P!lev ricn! ~ mit r~OI y
-09~-OE/NUC l'h-02 , Iaei el ;udNVCT PH Prc.tv''iuu's i 1
Q!t nland l'roc0pEM its. off:FE/st......................
.'o~c~l ield that. the OE and NIAC PH pi-Au~tlnir e l i provee'si"FE/ElRs wtýre i n ad equatLe It',' r A ii iriny t i mi'I y i t iI.i at. itlil Andess i g of- IN(R-FFERs . '[h i sco"ciunio;in wa:s hased upony thikowi ng: q......
[Threr was no central resporishibility or loimal act ive' aiig ky~teii to asmure the t imely j'i'rvess g of NCH-FE/Ilsthrough OE, the OE N('iP/lER prycess en uro~rges mint ime-.
Iii ss and lack of priority in that, it is balsically.aiunromwarli ig process tWile ~ prucessur , hag Ai leiast- 14 intvr- myface pni nt-s between perni)Imn I or oI'gdI1i?.'it ionsl5, amni NCR.
FEU/R work i s nunu I ly , a ri- I at er~lam t, :i;' gunw nt 'rhie rterature; tan hie Mefte:ive Writoir'ei Lio [rii iity and .i, [jwl i-.n
The OK' ind i'JH' FIR proci'itiirv:: to noit 1 I It. r' ait .I)l p pri J.
oI if0 and SIIC PHI organli z-;mLuionf inariii Ii cm it td i on, t nWIJC IT by OF by phone of' a condit iion dt.eun.'. to he a AigIi .
c'ant imrmnedi ate' th reat. Lo the heralth and lat Iel t ou. orpe re I n-"nii its aildresxed i n tlio NITC PR pnroceureP huit not ini the' npiroieduire , la;ck of NUC IT ci'i t.ni a I ni i-t. ermnnuing .i f anNCR- F1'/ ER is adiiI aLxa and , h I r 1O rvi~a lvgC o amssul'i L i me I y reprilcess in ng ft nadvyi~iqiueI NCH-F'/lRI .,,
r'etuirnedi to( OE by NU(. P'1. Atiet~uatc. and mtinadequmate~. FE/1;I(S -ar'e adidrtased ini 'IIC ITl.buit not OE pri-poeritres .
TIhr. scope' of the FE/ER process waIs OaLt wfe I I ief i nled te X.1rulding component. vernus system/plant 'appl irabiliy V I......
T lI I NIX T' Er proccdure at I I ow.ed' up; toi I I i'a Indeir, d a ys r.I
I,
C)
0
dr termine report i bi lit,' of andi I inal i ,e i tt ,'nildd cI orrec 1 ivi-act:ion for an NCR with a .cmttegioiry III FE/ER, 1lThe 1-I 1daya lllowabl, tLimeframre coul1(1 occur it" ti II/E/FnIE was received on '
ae Friday anidi there wanI a holiday 06 hlie IllO ,ing MIluittuliy ,c '-'.
(Sep, secttion l.V.D for deta tiIs .)"
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_
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11 rev ewe•d inh,+pth by ti~p r TV Oirem 0<, )(,-.iivo+ 'It'l loll s o l -
.bebe taken teo re~v 1se the, s•ys ( 011,as fwOt~e's,-A y i, 14 i.,u + .+ ro t, 3 .11.11;. •
f ,f' c t ive ( III , it eeni t c<.jntxcil I r n.ý .+J t I+I I !-i, t imi j 1 1 "ilivfI t vd;"!•'::
; '4
T..[hese (.ont~roh;+ :Ohotld {ilkchldtl, h~ nft wii.: . i I , v • lv I•, lm It+, t o'ý11 !¢>-?••! L-o.+
thl~e fo4lo
44 41)I 1:" F im"II d ( il ,'- i i tim o f all till -t• - t•' ;•, 4. 14 1 ý-f , i~ I vv i, l. It IJ ' i, '.: .. i .•
u I ilv
" he tw~I v l :I I " pa rt- p•iia t i TV A o.vl',,•i i atiz l i~i,, .it,, i.;.,•,••'.+ E s'.,tablis•hlle•nt , ) o , " cv~[a r ). n" s .11 o~ll I b vi '1114i 1 o rll III.'I I 'iy'1-1.1+
f f t, t ra lk i i g NCR - 'FIE/ E i n c+'li.ch im1ijor•i ý;jI, t iý'ii• a l =im VA , !
'... 4.'".
attnsmessdd
I.
r is4I a444
organ rza m i o r i dea, O1 f y e ,iO4'4544'5 m J,,., 4:arsl, stg
o. e.
V'4
• .l5 .If c h or is trt.t ion In i a I I(• , I gt'5'. r) . Il 1 \u' r4•l4. l 'p44 s lY ti i ;I " I
wi th !; pe c i fc ied t i meb rane I rom ide n lie. i• I (iii (po1 o I;t4I Ih A4w
t.'li~~il) i 'rmr',f) to cc)rrec
t, l on l'h . ..sil~, y:;[++i t holim I • ; ::
aIctivo "Ind not Pass w .fvt NC -FF/. R'. s :hoit~ -Id I o be trL 'kr~lc
• across major Org~an izaL iow'i I iitrerf ýi:e..
-n
b ltaik tea s to r sslir'4E th(at Whol4 4i s ll_-,ory v M ýsK'4r' i:tl v 1,W +
t' miled ed , t' i-. n pn romptIy nt r d fI ormal I Iy 1.4.414.4 i 4l ;is'4I s 'j I vt 'i'ait l
[e. w m ltot 'N I an1 ( 4 Id j on ce h* 4 54,44 Sd'
r'eThv4 i
4ro y V t iow.,'(
1 ..4
I) n it.i itt, ioni awl P-ro~cess-ill o R Q N I•5 i, the A o iat.e~d.•
R' 45454.51 ' If' I CISI 44 4413( F. I. ack rd4 ~'i' 141 sli '1 44 I S' 5c /i 4
11 i i t '
alt iI o I I
t'he; t.il ue
...
ask4 4 i i lli. s 1; to .It i v ,:,+++ -'4 I
"Ir C r-,t'C k is g r) H f t e /EQ ts in iiI I.~c 444ifi NCR 4 w ri pa 4i;je ' It o
"org . pr3t-C obab .l e aus of" th s ilt- 's'3 i a the 440'
l i r i t5-; 4"w i the t i he I 11voivm e ( ;Irnos li r fo 1*10441 *lip,1 Itr, th Ig t < i, , ,I
4: .
I t L tiar .i s rig t he d QNr Cnt Ii s 4t)51 in4 .f i(i l ie.r 5 1,.4), 1 t'lh,
:4 c~ rol e ad w44)1 p3 S iVt'. Nt.'r 4Ir .'1440 ' th 4, 4'iv ,) t 1wa i~ -rih d I I
WBN) (See section IV.E. K m IX n : I •l+ ht~is )
' t+t')Re o,4 n d '.s t i oc nt
'
,.
t 1, 1.E/Ll. s•; .1* I
• Def ine andil doctiment. Of., Ok, [,'itlicy to Issits-e that.L h c~i je op ra t.- • •+.++<:, l
•- rig p l. 3t a re
g a .(nt
sa f fo rded th e p r oj wi r p -t l i i~ l t) r i ,rt nl~ w o rl, -++ '+•++• •+",,.:•.,-+>+
ac: L IN L it.fi; r vrIl a ted Lo an• e I ot.yV a n Id ti'sI iL , Th pol I( cy shouldj41 1-,
he t et ffect+je. t IY COnmuIIr, i ca te d t (I a I jjev#,:+ o I '!' OF MAtlgemletit. :-..•
.and employees. A me Lh od o 1, oiy V;i
i'fll; I (1 41 S I ta I ished to -
4~4
_ " bast .
. •,hi ,.l's:'
• h, .,
I 44' 1h 34 4454 ;5 044 4 44Is t li' .'i'f4 .5 y 44
,, +,< - t 44'4's' sf t e S N C 't .41 .s' N. ''0 544401
1
.2
f
A. ~.,.
3,
R-85-08-61111411: I'R-04 (0101), Q!,~ 1o: i itrAw e~.~o
t~he NCR-FE/11R Pro~oss
Con clin I
~'~Some OE engineers were iinfarni Ii a wit h t.ht' NCR-FE/R prcb"s
as a wh I Wh e and t. hle I I I nWAIII v' 1. :iw t'i-amn-s rss ib I igivd t
accomnplish the related activit.ies;.
(Sv an,. t ion IVEJ. aqd,_
IV V. F . foi- det~ailIs')
Recomrnenulat i o
Es tablIi sh a formal and e ffeit ives W aini pi~ro'gram on the W."
procedures for WinhaLing
Anrd .proveQs ing NOR- FE/Eis,
r ;tn t thre trabiiing LO all DE marig.;, enginieers
, anrd io
t~echni: ioirs that wouldl have occas ion to 0"! r ath andi prvmss4
NCR-FE/Efs . Reqniire deosr~o
61 t Olrstanrdinrg o, 11w,
key po ints.~;, concept s, anid requ i rcmen t s by te:stin. i. *
US-05(8-01F/NI PR705(OK)
, lack of-TJ umcQ nentys.s i-n 11nlil tip~i~Con clIus ion
NCR SQNNERRS501 wat, not procsstcd by OFl withini tho t irefrannts~
sperf i i'd lyMA esai hed : proceduriesi . Al; .1tinalIy , it, was
evi dentr that OE. f reqric ~ 1y exceeds jhe :;pvv i Ii ed L.imeri rt' -
q u irerneun s for process i ngNCIR-FE Elis' .(Ser sec .trio MV0l~3.1-1
,4 anid _' arid IV. F for del a, ..
.Recornienda
t io~n
-
Kmupha s iz to alli OE enuployee s invol1vedl withI thle NC'R ~rovcirs
that compl iaince with thm erp nrrso ptC.,111rf5
)')vpvrn
rig the ili t iation indl prort ss jog of'Ck-V/[K/Rs; is. uieessar Y
to assure that. the proess works ,. Make it v ~ar thai 6n
vompli ance with establIi shed reqir i remeniert ;rat, I cvid to re~gt lu--
tory violast ions 'and nunafe .courditi~os
and Cain=o he
;QN processed the subject NCR-FR/ER in accordance
with their
sstabli shed procedure. Al though an SEM wag not, prepared,
he ogi ner ogev 1 atonfor the SEKR was pet. o rndb h - ~ ,
~egulatory Engineering
Sec'tOnn. The FE/FR was declarvid
nadequate and OE was inforrmed . of the inadequacy
before. the
sLAbl ished time limit Kcpreparationn of the* SER hyQd
xp.ired. (See section MVE for deLp , )
4.
tRi
C
......................................, , ...
5
'777
Q_ I
SAW
, iTy
'n' ,
. -. .- . . .:.il ; :••<:••'•" •• ..
.•?U.;•<>::•'.::>:2;i •I• .•:' " .... ; 2'• ... 4c'VN
With Timel iriess aini RsolV(o'ý'rvl n heNRi~FRP' rro c fo S s
LoneI II.ifll ..Colic I us i oil. . . . , ;- .:,;• :
Pro"'blemt, i L h ,i COr.t'Ct rriiicOlIOi'nli fl cu ii t elr- ,idiVert . LtjO.-.
qualily rpres(-.iit a long a. nni , g . pt~do) er. "feY h:iV, ,bt*r C I " n( i" tifired by audi it organizaLion un .ra.nd o n 1 nizo by 'IVA malige lmhlit ; -.-'
:a pro ter a:; ar bac~k ,as O9M hit at,.- v,,t ,, 0 , Oe rec•t d ,•p~~~ rot I c ;Ifa, bFa""lre of management tod. M isily rorroct to peroblems h.'t:-,'i.":CnL minae itte: n a vi 'oe; . i ai i ted av inst ; i o at , iN r .iAry_1985 and".more rvicentlv advwrs. |pubIjcii y for "]VA. Iru,•,'tv, c, moreir( mlj rnl .
tLant to nnclear safety, is Lhe need ftor-lhe iureiinclat '•tl .iNS,
ment. and i mp I emen t a I ion f ect ie lnag•,,.mrn Vont rvl. I :tOr.. lrmp 't y ide nt f ,t 'ocur.d o t. and coI` re:, a :ndit ion 11 h tonAiyM
J.m p a (t . L hI -I q u a; I i tLy a n t . a f d t y r ' Tf O l,;. r a l. ti• ' 'i . Tf V A ' s. : n u c¢ l 1 'i
plantS, tSe. 'ete . ion IV,' f i, a ),; ii .S .
Establish imprnnved mnatgagermn kt con' ro,;l qh Jn-l lt.s y (,i lt d hpthii ....freq =ency) tLh v' :ar'li t aCtivi t &A in thi A:.e art,,; I, , a2,;nre.. n 1 i -n
ance with NO.R-FE./ER' ,rocedureI s Take prompt ,eml al( I isi , .' ig ,-m nenL :t iriOns Lo correct. Any identified ,eaki1,.,;a.-s T t rt.asu .andit act iv ty should be maintained nut; I t i'. f, , c j:learlI-
demonstratend that a Qqali y 11rogray ham been i,:ta;blished aud.impI lemenLed. . ...
F. Act ions "'ak,,cn to Al levi t'te N, ane'onfo1 kiil ,( it i 1. I 5 0 tlheiF1it.Ii. l the NC'R-FFt -.. , :.E! E..-
Corir I us ionj
Tlihe ,S N CPdtH.s associaL .. i'd t w htPh' po s,•- a ';. aidnl "Ir llit le r fg ;VYSL.O'iI`,.-ýi`(PAN) were rep llaced wi dh itartLoe prressu;ire- t ransa:li t. cers that . hdocuimen ted t.e.s t result.s to demonstrate ac:e.pe ta;i!hle ac cura cy. an II
operability duoring postacciderL. condit. iOn. The' vreplacemeMli ..accomplished using estabi ished diesigni, Colitrois ;and the.4.,istrm-.Wments were Frun'tionally.tesLed liefoi'r ing ple vi'Upda te of th,.,environmental qua I tnition eiia. r . , Is I ,,' the new PA' !,CPdts was in iprogress by .•y E. -(See set, io IVY t'or..detuail.• AS††††††††††††††††††††††††',"'"''""N K'::•
DETAILS
The followin g i nformat r ion, is proviju..nf to fii c iI f Ltatv an understwl uIgtof ,1he.design , Lesting, envirnn•enmLtal pualifIcfm vea 1 l nll CHl in1eeiiti.e ;iim:ruodifiAalion acLivi Lies asb';hiatLeaf wiLh Lhe SQN re.actor' nlinit ;L
arId associa ted CPdLs ; the N.- 'F!ER pirocesS. del i ,ea Lted .by esta L isJ Q iOE and NUC PR procedures ; Lhe - specii fl i iclun LtanceR; sur&u"nidi ngoissuance, processi.ng, and revision of NCR SQNNEIBRSOI and it.FI/ERPA!past. identified problems.wiLh Lhe NCR prnces , and the ciirrenqt., itusy,of the CPdts installed at. SQN, -
• • ., .,. ¢,, :, . * c
.. , ,.6 -• ;t,
-- .. low
A.
Th iolta rmc i ve f gi"' 1 "I Ca h 1 11!t~ ~,-.-,oj
ah (I raI ira oac 'a i~t~ s:Lc re '~ f ae r rod ItI a' akt laai it- 'llifil I a~t I igj;'1a' ai` .'t
L`0 lowin Ia a dItsin of I hv !&A. I;I.~ I dots si go fa t a' r: I' ' I lit, cont t a did Iit
So t eow a l"l t a Ii I~ c aa it t a vo a- v 1 n h t~Iaa 'I I. 'n it~i
St t I S L 1 0 a aarit n. Va r ..a l dq ~ "jI
ho~ La t tom' s .I i: l nta a' r i t , Loi St ve r'Ia
s; ~ ~ 4 1 a tKc'I tai Or k ,a I ho v ata L I d it aa I a ;a vs at'ta ;aea.i (u I v rafl I s r I ait a a ~ I / at~ aaa, ' '. H t ' . , I
It,.' dl'a ta v.at It-, aa f it ii~a a:. Ir:a /I I'a/ I(ia itarj if
'I 't a 'I I ;I rl 1) 1 1 f L. I I'tt aI a ?,:I t I,,a at illt' a;
''iiiIn ofi a'val~ \Act'tiiaa hiaa.: rltt , iha k tand Isolaa I
and i rnapt.-ra ;tiaaare~S s tall! a Ing i roma Ithe NtA . Ii' h v l A\ :i a Ia:
I -t i n tat a aca:i dlaia ( 1,C)CA ) I a'aa a a ai i aaI (aa-
bret'ak 'it th at itrga'st. rt~lcit ora a'aan I iaall 11ai at.'. ,rAll Ia'a' condfcalso I-.'
p~~~ na'a' t as i det hA' s I cel Ht I to ! I aavt vv Nt ',a': : ,c tatI.iit .;
posMit av pr' eatsaat't Lu'a vita leat sI~s I tAnit I.' 1 2,,a ( 12I',/a I'~
It " t da a v a at n ad A f I v. t' a t ,'aA
'Ita' t I'll Il:a' a a . 1t Y fi t aj'I i rt 1:tn , hi- tt i I 1a alavn I .t I av be'. a' ta I t.fc.
at' he pal a' ;'.' a ajatat wit ha i a t ho At' vl I a nt at .1 a ata'at vissatI :anad
thae :cifinu I an'; e i onart 'l A c i N ma 1t nLa aa'i ;c at A i Wit I y, U.SS 5,.
a a 'ta' at 'at a.it! I L! o I, Ite nt t ca I tad. sai a' I on ' ti a':a a, h r a i~lI
A a.'aatlaIatnrieta'a !;pra':y syst-t'ta a I t, raaoaavaido I satIap It:iaawtat LlwI cf!..a
ataaatc(aaaae'a aIn I artat Lin III' ( Id'~aac !-aot a at:; provaa'idi e bug -If roia
cool ing o lo 1awinag a oraul A ld I.tOCAý A a afi a itiarntfi M ')a acaion q, ;
syaastema is Als Ir p J vidf~ae' tat a ol at.. th (-'l ta a aaa~ hiilc'1aa1,11L, -fl r at'
t:I(:t' i tleft( I a 'la' i LI = iTha eI'a. vhra~ a'a vaa I I of s s umta Ats, Ita n 't' haIt.l
lia , av< artiao I iit'assort tao I het' an I'a m~ tiatioraa I'S;' Vese dna"uthwL
r d Itaci' doas i gno sgaaaa iv prva'r ta''~aa ' 5I 1t I j it "-'g I " tic
vtavttttt rel' at f n',stt''t o eal i oh~i a tao at tl ai . ai to' I Itaw M uafti - ife
4it 11 c i tI I iat-I It vvss' I I't "it t~ Ionliarat I "I: vvgi i Pan huts jaiev itt i "g.
Llat' preassu re a ais i do L )I( ta' va''s I - ttarlfl ttt'a'Iant Iip.g (-XC(j''. a Vt I Y
I owet' I- ttha" thea ;at; lS 1 tS 'at,~ t ~l alals pr n o p h c i ght:.. t~l 11itaj1"lla a
(at ILite! a''a V essel
Tlia SQN 'att' i , coritat ,rmaat vesvt.Is weret atvar P'~~ir 'ttd.Lt 13. MtIN/iTag at ter Mya' werea roatlas UV MaaI addt aare '. t rio
at:a v cstt'i fora teatk~tam Iat 12 lb/ut p, i.'~;~' ttdut a
51,ya'aifi~a':aiias f(STO) rstacl ist tdu aII tawatala aijr' 1Laa oa'arge. ot "0. 1 La 0.3 [1Ib/it n a g l AM' a'aanrv I a L ivvtrc' I_ al a. at ,
Sthe ;artaaaIni s reg~io ra pri';Sa a'ti
-Q
0,C
~'
Thec rimcrete mcaLor
shaied Wiln ding i;a 'trilt(t'f
u: i
cr ct est sit r act'l re s )r rou llo 1Ag I hi si te I ol 1-s iitittt'at ve sq!,w anit
Ithoi' 1ei tLtr Cooliant- Syste
dneltcinag Hoilwtit
li~~ I Itt Iia " . ..
p rot ot: t it on o t he s e I ow.ia i'intivni Wn n v m w I iaipi 4-a
E its r ! "Idvo tso i Laniisplir I o t, I'S..
snot' 4" tP I Il
M i sst i S
3 Anitu I ut.; N L'~fnit
The ar<'s i s refornt is t he gpare QW-i~w t Wi SWIp iyaatlt i
ment 'cse and the iam. rete reautor
shil -d i It g.Th
Wei (01jbntXflita~e t\ 375,0 ,fOO ict t"VQ a~tnWWt
As COS~;ieic
I. v for~ : all l esakage itotta hei ;antaI";
's ojicai y" prtW de 101r
t~it," it 5i;j tfo so lt~ics o t-li
vv r~jtslt ruttt ao 1), rt~ piv i dt o ý
regio" o I Swur ptf'ss~trI' thAt vwa'
mci -t *atiwosphiteri,1
norma 1 iipu~rat ingi pre'ssure of' t ~he Anoiti n reiona'
is ntiItl
vrcultis cont rol
subSyst-em. Ac ve 0 s t n~ t h- a nut" I us rel ino s.
aviai lab le for manj nteiance
,arid i asprctti~n puaarposes
duriqQ
normal operat
iont Of thC, re'aror
IL~~~~ r vt i
11n'' .Pifc'a at r e ss u r 14orti tart1l
r it; L it~ Qumatlilt
There werce iighta CPdtn (four per unit. I *Iiress''l atoa it'he oighinal
NCR-FE/ER. U0 h CNdas were loat e-d
i; the annulusaa regi onl at
;ipprox imatLi' Iy e i va tioa 70"s feft! "tnii ' i''ý-' alutvttt til !j o tt ahe vorra t a
i'eaCtca shiel'd
httildin wall (see j
io go~tres .t' and
'They wt rc
Foxbhror Mode I FlII GM f qrce ha Iance t. rtansmli a a irn And rt.,s .ass j gined
'TVA nutmbers Phi 30-41, -43, --"4, Wt' '-I.'
The- ( luwing 1 .1
i n f o rma t. i ol t :orns i doered pe rt. i ru'ut. to utar al: ji ol ij tuý howt a tit-, t r~aw. -
titiur were, ttin'I
tended L1 hacti jilt antI lthe nartalt of athe OE cii'-
.cerms as expressed i n t.he NCR~ awl
corr i'p S ttian;y FE R:
il 0
S'V'
1. Ctriganal !r~i'~
t~ Ih~s I ~u, and Queti it 'itt tw I
irtformcat. ion
'-ii,
In Autgust. 1967, TVA a SSteil an "I rtt inn. B id, *and Art tsp'
Lta It' (1. locument'ft ýsvv e iferctise
V! . K' I ) !or Lwo nuct(lear steaaaa
supply systems; which sitltquent l'fIy becamne
tilt two SQN units.
The docuettnet cont ained ana insta.rumnesa
anad rontro I i sectrion
that spe'ci fied criteria for the pre~ssure
dif ferpeat.ial. triins-,
mi tiers that would he utsed ini UPe nuclea r "AW i , The-e
qui red acctiracy criteria
t~hat. ias spec ifit'd tro te( r.
wia 4h i ecn or bette~r f Col 10 per(,tt
t 100 pcitea' at a .
Wt'L t . igitnuse QW eq~ui pmenft. sper it i ailo I E'Spec }4. 61462,ý."
rei'Js ion 1, Suetd int Novemb-er 1lH 1, t'stibjshut!
Lechniuat i
;atiu adtili 11i i .rit i ye rein iifli'eats covt r i ip., al I h'e It
8
T";>
11WQ n".
navy
delgnng f .a -, kio .
adel(s i c in WN bi qam LIt onnyl ils rrgio wt 'Id un ''i T
f rthe transmIit y KAý r ci veti d ( k g ý .TV -'f aiu n e vi. .',.i
an qtAhe ~adwm beenr recvie ed byVAIti "g And. I h;,tohc'ir'
e 1 ect r' ica ItIestijngT I h. re4ONJ d W tf 1.- jilt vld "yere' W
attachied Cn the eata~akiec iI~iA hmI;I~: 7 '
MUMcr~ were released& IAy th W qua lit not r il '(QC) DPhrt .
flieft. , vv-Ce ivid by rVAý, .,Iand s"Al~qciertlIy Ast a I d~ in LhtktwoSQ uinits . pdated specjificat. dionrs (lax force Iac peire.(Iii erent ial transmitters J.ticl iidiin th lC hLA~) were 'Issifflby W i n August. .I77 ttf( ence MUM8. -,J) In tli 'sspecif Rcations, W~irdicaed* hItC the wpiiud Aiccir- y" s'bt S"pe rven o f spantand:T he ills t minW0 ustjl~~ qeuit Iit ir to ..p ostalcidcent: Ardtol s Iif'IIt u výttrd"summna ry of SQN. 1om) iC 11tn n 1, i.rc ji c i f~lllA~rmeri.iLu~ond iti nsinii 11W iiilur~I iri
Ins _.§etL .ýJj~ii.ationis
J."
Thle nia"in arit "r re K m SpeC i f i raL. i OtiS for t hie Qlq nu %tpf 1. iTVA and ins; tall ed aLz SQN were Usa foillows!
a . Acu-uracy: Q05 pe rce.nt of s!pan.
1).~ Ainbi ent temperaLuire Iind f Vs "0Ool t0
1800
1 F- (. im Iiu s'~
cc(ýmponenit was ,the isnpl ffiex) . .
c. Topworks cover. Ca.tI l 1mi sumA (wilnfi L it
d. E ILe c I rival ciasA C011 C1i atoc s si' I
.3
4.k
? its
nV.
e.. FRange : .I 15.1 h/in •g . .
rilnciple~s o Operat(on Reler to Fig,.o , 1.J
She'- conta imnent. pressure .eing•monitrM.., is .apji, lied.t,
bellows cap.sule '-1This 1. M Ir#•!re exertO .• rcs.Ce on tiet-W. isulk which causes it to move. 1'.lat UK ov-ment i, hal anuiiiylan- op;os i rig force 'from :the"feedback coi I which -c•a'to -dampen the movement. These forWes 'acL through theL Kforce 6!,¢ ,and - the vea:tor.- f.cyure assembl y _']'he di aphragm bedI.,ean! .Ipoint P act as fulcrums. - The o. ,ther siie : .the be Ilw .capsule is open and venLed to thl., anrn iu,; rc6gia I tmophltherefore the pressure differential across 'th steeI con-
La inment, is the parameter a ia ymdn'
Any pressure change causes movement .61 the forte bu•b•.:l, Chproduces: a minute movement of? the detleutor-armatur.e.;;ý:Ts."•'.: i
q" Z,4
,'A'"33"' t Ic , i
subseellt I- y c curren I Q o'9 5,J 'A h, W1t Iur I' hi forcba13enc ci srcAt he" rafmpit6- slgmd aral nd Is um) 0) If. eiIy to thl,
teedbm'flek coi in't the i rCIV~ A in s ciit Rm ite ~ "
A3'33333''hi. c~ 1 h la ce (dmp Sa 1: th10 11 o t i I M6n Ih (I the In eb11'3;~~>contr I3 room. 3
fi!sWc ,1 rov3 I Td oupu' t~n'ru - con ( nuo s IA wlisi ca t"; 'ju (11 I.'! lshE ý sotc '33
d i f ra lane' isa bhetreensu :t. lie tignal ac 'i I.. m l I;0ý 1,pu' a~n d I t, h e"~ 3" ~ '
"33 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o lowing: prssre I~h I, t,~ t~jI e. Os~, ....
f Und ticaOilS (oe. d o Iac s cusune S oA w I ~iu. On In ohe usa olun
So t n'o I r Voo m. ýS y i eI r .q
l (es i td5 irV a d.n oatclu u IIOI hin'I' ui tt t ex di In t li a-'sir3 '
dii ' cnt f i gh hcontwe nmt he' 54 1 h/l Ia il gma ~ s n3',~n ;tiia -ii~n Ih tit~ ruv in ti fo Ite IoI.nn m~a Iy
fuact~~~ aol (d~ns17 e wll he onl fo u#uit
Io t of gh-~ h BA ih ;Th onic n tl: Ii of r, ' to is rei ng g
Hotaigh caauiet 1, ressuaion m et v cop4 te ii/ i lsog li 3:*n *
<3' cool~~~~~~~tantu ytman rtit phase A)o oJU~ ~'3A,3,
>3. i... sh r. m eme" I ct isowlation.L l#.!q 6ie ýdj 3 3 fl,3th
'3~~33~'3'>':3'3' ',n e 'oU - any, envig C''t roniiu itauu ._ Changs e .~ n L'..~28 he /nnu I3. k 33333333. 3
I-A ion. i i a tes Cn i u' Lhe iiBA fl. .s ;stfi III,)l's ~o
The tan phse A).iCL d 1) , oi I to f te,33o
'3 '33 lb short-ter fuac tIons :a ri co. 3 qa)~ tov tiew . nr
'dvanLe 'of an -environin hug n t nni"m~
i tip postacc idetut mot)I%,o r nag (PAH i nd icatLion'. 1Lo- ,<" '", reactou operator to al low . onr opet,'.'iti~onali ju~dgmentaP'.
de c is ions f ollIow ing ,thle a~cc j.idntL Th is jpres sure. inrd i ,'33 -4,~' cat ion. isý. used to determine 'wiuc;. to manua IIy perform 3K.~~~~~ "~"3~ sch funictions as t-he f(ollowing...,3~j3~ 3~43
J$ 11 i J tti a? tC. hr! r e I i (I Ia 1, f 11 v n'. at em I 1: M R) s~pray fra dd it ioualI ~ntLai tament L-)re P sifre con Lrol I ; < 3
~3A3~',3 '~; 3 '
•4 : : " I .. • . ,'. . .- .• ', . • ,. - ,
4 0 le~trminate7 cbant Wil asst' .4P"aY .d/aIH t
-: p r: eB5s i . . . ,, os g t ' fisg: ou Is . , ..... ..
Open'%the 'vacuumn br'iake;iI' .1i( at I Oi rVA'S1 to- o f;
4' -"" -'*•4'4'-' • " " ' : - vide :protection aga inst. negat Ive:-i r'.•sur
-A~~~~~~ (In ta i nneaat, vei( v s -b- 8 ->-- 1&
.: ....-.. - - - ° Reset phIef c t a n tsat So a t I :, t ow I 6
.t hro,,gh safe t y sy.AtLIm;"-K" . .. ,
be 1 il IVo t e, d.
30-414 a ad -45 r~ t, e' hia c t a rn- le :i.uc a ted I U I lit
I .ng t, rm " ICA~l "f rn•. t, •: ,, a t1he , 4re:i i nth Ie ` of'- Il • di ii
f inst.LrutmeIIts as- t was the- perf4) 1 M: Wan 'I II tI( f,'t C ltI i ,
: .or the:. long-term-nfety.-;/:functios that
q~uest ion.-,5 . SQ?~TIiC13.1..:.L~ I c t.jo 's (S''S ;sal ..... , 'a •'i .., . A.Y. -j° './;::
'Le ~ ~ ~ ~~~- 111iCaIS *i i Is (STS and I b a I S lvvIa t y .-
R. .ort (FSAR) u i i remen" s for PA" : . ,I'd "s 0 1 e -" ,- i'I i
a.; , STS
'.' '.O r; hnic al S1r ei a t. ' .1SIi)e h t I it f I j I's f tho I" PAl M.. . .. . I e , h 1 .,:)6 i . u i
CPdts I he ope rab I e- no rmal I y-.a nd - t hia t one.o,: tbpe ra ) Ie-
S . . .. .. ./.. .. , channel i s .the. min irnum number .a o, wed.- As speci fa -( -i( (d, i i:1
se ec t i on 3...3.. o f the STS,19 the- limi ang i.osdttoa. .
L~ o Lertio -LCOy wi th rno`chanflel-s ope rabl is4 hus f
or the tinit has. to he in:hot shut down with n-the.next2.
12 hour1, -Section -4.3. 3.7, of thfh STS r e'paire's s if.rvi aS;t .I. c Les ti rig to de:morins raI e rslhility by the..' " r
, .ornsance of a'. channe I check it It 1:atL oIln e peir,31-d ay3.1 ,V
and a channel -calibration at least once per 18 mofiths" i'i
A- channel check i.s the qua(!, i t11.: 't ive asessment
'chiane I behavior, dluring operat iom toy vi sua . oharva -
t ion. The channel check include's (compar so-l .f One'. $
channel indicatio s -atus with - t lhe of herr chati, I .s"ia
cations to- determine i.f excessive Ileviat.ion. is. ,-notL'.
'.:"".4:.i" A channel calibration is a;tit adj,:s;tmnelt., as n c.essarey -.
of the channel out psIt such that. it r,'.spoladsl wit hi tnh L -I -
- speci fied range and accuracy. The ca I it) rationil encona-,;.ý
passes the entire-- channe I . i tc I tidi.ng the sensor and
alarm, and/or •trip: functions and includes. function-l!:
.: tests which inject a simulated signal to verify ̀ 'opera .').6.bility: including-alarm and/or -trip (initiat ion fusIt'/:;i=:7.-/i:.--------: :i----------------------------------
tions. - '..5
I. FS AR -ýA
I- (1 )Envi rtimenta l.e 1 47nI r• -- -- . " . - • .. . .. . . . . . . .. . .:-' . " " "... .=
4''
'i'':Secti on• 3.11 "of the "SQN. FSAR o, rma I nfor
Sdemonstrating t".at-- the safety.related 'ect rical14" k 4-. ... ...
'-. - .- , . 4,, .:; ,! -,• ", _.:
....;. ., ,- %
L i or psA, i ~oll ftS " t., S
1" th Se.qw re ptt cit $4 atn.n I etf tQN - f3 td 4.;rsui oiia I ct at C n tLs aw k L i
(eeluipmeneft.. indujstrj ail -r~tia nj~~s md ;i i tioihI(.tcai" I. IatI.4"I&U
[Dust , in s to n) ht ý r t bin a t oat 1 t 1 nin # jvq t 3 1* 1 tnt Is t h at tOm p o Ii ew -) t~e~ Atce di., ata *1 i sit
i onh oas I t. hen IV 0i l I i tt I .'lI L vfý W# jare A rt' ) 1 1~ i;1 f.d Iis .i1
l.(,(l lit Con 1t ol rill
In tbL 14 t I 2 f ah LQ I,.H d.t Wi 0XI Ig , rhi idV~~~~~~~~~ qi ea Cc tai tci i- u t I toiala i-nn
.,-~~~~~ au u~~~r t 1! 1)n esav rom L.~ i eu ) o hu PXi
Puts wallij by 4-10u percchntL- Ig ul pi
AA
.. ,-it len 7.5ti. h t an li tno S A st ; 1)1 t~ ia, eoa i t a nf
C, ;a nd y - n i roum ri L ., vtIec.chanc(. in wacrc i. 1, hit C. r tt l1
:it;.s Vir t o~acidn . :~lti.iOS WI o .-. ~ +0 E enp: ra g a rn P C!1' 11 t P r V in tred 1) y, NSia wvus(IO r t h Qft....i ort eH I a . timt! rzas I'ig e Irm tg s L 111101 ects te jelt I I)
f jc .r o jipoiy t ion i I ere by~jig, fl manti tas1dtance I rnk to16 auu t~ac- flx ofl ' ." Ih t, icOtis co .1 Aru'iapi pf I:!r a h Us rfec uaiC the "111111 I ra y
th rsst.aa !alsoe i fs fia com one 1: 20 F IFa.)tc~ ., . L ut mput o rathie - 'txborng I feh f eca 8 a lie rtn e -I
ta ice State- tht p .c'.aa i tj nibfft est by is th re t i C1.nponen_1
cc' Lo maagnerL.iwre. fl~ I~rit *tx) to fl per n d. - filt. lhanr e r r, i s a1 crt. aertf t omeý-of Lh I age r in to pe ra u s e %, 1 W he
persuanel~~~~~~F.) coa)at.d yN ito tI aae ha.tcthane wasor Tp r h aan: I y'h ic I p.t ia. pr I021
Chagnel ch eck p rab w ri Iy tc, riot a oa ita am h' a . ý e s r ~ ~ n
(SI)e per , 1.1,aalylll,. neuý,.cfzyig, ariar aesopat.fua iy WoThe plnt opeainn staff. veiy' :NthatIn pa Lsaed indats
'ch13044 ange.-0-5 ons panelp 116 'I i in, mar 0i 0't~o Fo
(6 not deiae mor tIa Io 0.7c lbing r neanthr
hatintennchec r pequest IM isy orenit!sý pLa i r idmo e I 'Iad to Crrectsobsterve exscemossiv ted %eionsmn I(see se by'n IV.8. Sdo u r
forep discuLson1 ofn sR 'staff-ver-iy Iia taa -castryeY itdc~rQ1A channe 44 an ....)olp IcIM co o ra
(tono deibaate mon 7 pefre v y18mnh o-c'v, ~ reuln uae). ,11 ~ by' fI9 3o Coate taharLliot.4r
marnensure! ritz bine (MR)~ ie reureesar to....................f d
ob e v d e c s ie 12i~in . (e e tIfl I .B . ti I o
S
41
I"-..
.4.,F'~
A'.
Man., NO
IOWA 4170
FF."FFW
'F~.F~F9
4FFFF,,F
kyn,5
• ' ' ' " .,,,.'
NSRS rev iew Sed 1198V3 m[i ilit,,nCV' ir..re oit C *4liC
data ,h,,ut s for uni Ln I anld 2 a:d VtI I a iu E1 .hI thW ¢il. CO
c.li ibrat ions. h a beenc pepfrmed as u equ b he :iS_
4cviewu.-f the - cal ibrat ion 'recordw.u:"red S u dfo Whed . "
iL the "As found" aid .T.a u e ft.values for r I A. CPdt u
(ua itb,,F F"•0 .
.1 1arld 2) lcitt!tR
. indiicat ,d 'thatý a t r I• moi ,-'if *pe l to :
i<me' of the Lest points we,' uually found oit t.i
tA. I( "1c iw
f Led t~olurafltr' hand, Amu, not flexcitq tvv 1%. Th i' i s. , fit'! '
tinusuld :ift1 er" 18- "nuths of o 'op-irai j"..10 Ile,. inflil Ctrlb
requ i redI ýol.y .:;ýrec a I. ib ati on "AajUn
ii 1. 1 or t' 1w ng u. t, •.f''"
bha ck into ,•erv ic ol;".'i.`."-,", .•. ;',••:"•.
P revunt. y e and CO reitc t ive: : a i ntroen eii t .i C+L-'. F '. ..:L / " '!;~, i-
The p revvent iwv maintenance history "for the PI'dil C Y consiatle& ec
of periodic ca Liration"performed by the plant int r"nnnta- 40
Lion seCt toll , NSRS reviewed the'; ij;ruteiit cal ibral itC 0 10
cards for the PAN 'CPdIsW and determni ned thet. peeriod it .a ii F'•FFFF'5FF
brati ion was usnally cInncurrent w ith:.ipe rt •lmalnce with SI ' I F .
and Lh, d;uta recorded on theucards geriŽ•rt•aly reflecte tFhn 'FFl,.'
data recordted in, the S1.-98.3 dat a p~ci'kFigts, as . didase................. '........F'
NSIRS requesLed ae .opy of' all of..t he MHis, on Ci lon 4A h wtt >X'•r F '<
asSocinted with .,the PAM CPdt. -for both units.:)..irt . .
Review of the p.MR 0pies provided. Iby: tt p.p ant . sai. f ..i nd it ca-l .:I
'. ed that there had .not, been any, jign if cant :,orrect,;i ye. nie Ceý
tenaiicre prohlems with tlhe:: traimi tiersii tinci! ' they e
originally installed. ' This. was conirifid 'through discu&,i
sions with tte plant cognizantyrenginivri fr-nnlthe .lfstrtmenLt T"
Maintenance Section. Irn the opinion of'th,,e engineers, .t h
instrument ' performance had been N reliahle'. during: normaI., ' •.,..-,
plant operation. -'F,
M P 0 ' d i t i c a t W o o
?' i"
>,;.. .- ,
Through discussido s wit~h. the' pilanit., s.t f 1' f , SRS 'on Ititl e zd ;
that the CPdts on' both .pnits 1 and 2 had iint been modil iedI F.
via ,field iand design change requests "or P ng i ne er i n g' change:
notices (ECNs) since original instaillatiom. The PAN CP tn&'- ''" F
were replaced in .Ajjit of 1985., a resulttof quest on ls'
raised about envi rohlment.al qal i f ications as' a result of NCR
SQNNEU850. This46.inddfica t.on its discussed" in set i o.l IV. .'''
of this report.: c.:' .. ' ""
SMN Program for Preservation of Env i ronental qua I fIt C L Ion '..
of nst rumentation Durriuc Minne -t iviteS '.
SQN "Inst rument1 Maintenlance- Instruct joret (111) i3S .s : ....... F FF;
established procedure used by instreunent maintenance. perSon-.
ccel to maintain the quhalified life of class .iEiinstrumCenta,,
Lion that, couLd be subj ected t har hA li" vi ronemnt". NSR
ihspecLed completed daLa sheets bfor "a I ma intenance Factiiv y
on unit 2 PAM CPdtsj and veri fedthat requitredBsteps I
4a•", - F . - . . ... , . "F
F'F'F4FFF4
3-...4FFF.
'
and .. .......... , L o-1) r v ii e r III- "illa I I f I Ca L i 01
L e tj 1): e I•9 t-,%.•• (I• U%: r: i ,I L l(! itC' I_
t: 0 ••.; " • i , a, (, I., da•- 1,-, f. am 6 ,•1.J f •i
'!dmen: Y ta en pl .nt ,men~ed
;i 'A ""....
•?:.::.?;.. .. . ,-_ fication o•f -Class,1 fE E'quipmen•t. fotN110 Iea r Poe.!f• r '111,1!t• : N •!.:':
'Rego takory requ i rements:.t haL:Cst arb, hi 'h th .ase. r "It he ," environmental qua ifi t.1 of tiio1o .i • ., O 't
-- .egl..ry .. U riIrotgrtldV s t a, t,--, sh .Ir .. • .,.or .th.
'r -" Design Criteria i, 2,4, td 23 'of' App,,,lix: A and Criterib a:'
411 l a I X andXl of 'Alpp:dix B 4o IOCUR P;I ;rt '.1). R(CCitL llomtk
P art 50 :was . cvi sed t cA6 a I i sh, 'thefJ i t' I ru I'l l"i of) epVi roný
me ta I 11al..icati.. L' n::,o, f t eadl el rr I i I equi ti:..' : 0( 1OCFR Part ")0.49) Pub ished .s ,ta -ndafns '.and guide fWies
.addressing the issue i nclude lEE Standard No. 323, Regul a .
:: r' ;" tory ,Guide 1,89 IF. [ulletin No. J9-OIP, ari NURE;.- 0588.
The NUREG was the primary source docu-ment 61•rginally-uso' t0-•i., formfi late'. the O s. Q eletrica 1-'.' OqFi pmnt ' e'vi ronme.n t aq~ualification prograsm.,''
" ''Section., 2.1 of NUREG-0588 addressing ,la i firation methihdsi
.> states:.
-"The choice of the. methods selectedt is largely a,matter of teclhn'i'6'r judgement'anduivai lahi lity :
.,i n fiorma t i on that; .supporrt. -the,-'conc.l uts io"s :reached'
Experience has. shown'. thatqualfication. feCqti"imen', subjected to 'an ,acccident.:.envi ronmernt without,ý,
.:.~ ' . ' -test data is not .:adequate Lo demonstrate 1u-.ct .ional operability.J': ni:general, Lthe stLtff will noiot
.~ 1
accept analysis i S ,ie o f tLes t:,ltat, u I elss (a)
testi ng6 of. the component is impract i cal due -to . -.:-' size limitations and (b) partial' typi, test dat.,i -,
'provi d~d to. suipport Lthe a nal1 yt Li (,It I ;Is s mpt Lion s. ari d
c co n clus io ns reac-hed'.'
Section 2.1 also states'that
,Equipment that must funct ion in ord e r to mitigat "a' t'
any accident "should ber. qua I if Hed by st 0.(1-to demon-strate its operability for the time re quired, in
the environmental condli.tions resulting from that
~~ P>' ~accident. '''
These statements indicate that it:is stronglydesired that -
: 'C I a's s::, I , equiprment' be tes ted t0 -demons trate" operabi I ity
: during 'accident conditions. '. Paragriph'. f) of OCFR . .4(- indicates that' acceptable 'methdd, for(,quai fying e.tri C'
• .,.,' equipment importantO"'t6 f. (atety:,,n I C Le i ng:Ii denL i -ca i r:a similar': '.items:a long th.•.i supporti ng ana lysis to
.... K. show :that the.equpment. tobe" qualified is accelabtle No.• • 'N
ci- . Lcriteria was specified in .ny o.f the- reg.ulat~ory informationdefi n ing what" v const.ituted a. ."s imil.a.r" it em..,, ,
'- -' ' - 14
2. O " "rcedii re. .f, r Ele.c-trical, E ei it .. i ome ,,t EaN vi , , i . .o _ L a I
Qu I i:- •.'; "f i,,. • l f cat ion ,for R!.., . ":•:>...:" :- . . :.:< ,.:. -, ,:'' .i. T
.'I'l...l • . ..;.- .I e .OF, .p rocedu re. for i u'lv Iil'y gg Ail,10. 1 1"a, 1;-4•, 1.. 1 c't 1ý I• it I ..• ! .:! }: • '• "• C .!: • f ) : : . "-tu i p , n t " a t S Q N {W a s ' S ti v s , , i ii N i~ we n i c 1; . 1 ') 0 9 A W 4 ~ ~ " .: •7
:'.,k~a>:',.:vo I': ..- (I F•' , oi to y . n i net!r ing lh: kiln -SIp c ,.;),I- E,,,i ,, ig !i ti,' i ....
%-.i I il. El~ '-
!.:••:).., .0: ,: .:. .... re .. N DEFS -SEP , I2, I . eh .c L ra t, e'} F, ll L.| ti' 11fr 1|,t |.•ie i {::`.I
• , a".', ! o ..
. a i at iion.Report,.p or.Sii yah .N i t r I oi t nt - I.1) . 2 re arat ion and iii. A''git 5ht
I In .. . " r m ry s o ulr c e " d o c a m e ln t t ha t. w a s• rv G,iv iit-v(d i~lk t tht, - l; • t ~ , . <
'>•:''' .'.c,',,'- e... . I t i r e w i,,; NUREG- 0588 and (I Ia t e I- .I 0C lR 5()O 41) a fter c t, wi):.:i's sued, . l'ro ed e, rfor i: ci ay rig Ok ,. procedures P i,11111AI ly- . rv 1 i 9h!,l4agil i tale for a t ! ItreW a r i'rton ai nd ,hndl inyvenrf tht}i le , (rii l:
S)"{":'"' Equ i pment, Environment.a I Qualif I f cat i er t L EER). oil 0aort5The
..scope 'o I' h ltet I ro edu re, E N 1)i"(' F2, , S w fas e~ f a'•-
• ': • : 4 { ' " " + : ' ' ': • -. " i • . .. . e d B o m e w h a t , ' .t v p ~ r o v i d e m o r e . ", g u i d a l i C v .. o r .. t h e . p) r od c e s s . i r • -
& Ure ..~ R f)ES-SEP 8-11, ~ 1~1 ct. rfc-va I ua t if ons '.',.ak ,'t.
"u...- , ",. .rforming e fnvi ronmenp Lat foir Iqua icaNt i o'i-, ta tions ,,
:. .•.g.<•. .... . >,:.. eve r, 'Wal cr t r a}, spec i, .Jfied I~ii i '1n.!01,ll( g l)O (,u2.e fir)i1 what i onsLaitun s a im i la r" . Lin .:. Proped r:, de1 .9n.i.Lion of what co Lns itut e s a fsi l r" .t I shoild be det ir':
mint and. 'he' incrl(icr O poed u i i .'t i (f p'ii;r ypro v iires rIa
.q promentaI quaIifn cali otin of electrical H iprtn. -tit .h . -'tcL e ofn th N. Il to SKe 8 (-11 N:oil i, 'n i-I :'- Anpu."i"" " "KaEyp<',.
;.,../ •:-,•5,". . QuaIi fi c,, Lion| Sheet C (EFQS) whic:h" ',. the. i :heckl Ist" iised t.(.:::,!': :a :....•..ensure what. al Iprequired data has been recorded for inputce t o, •,perfrm":the EEQR. The (see att, I c lime n1t)- orves as.aCOW. e,-
"''ik'" " " " s eet "for .a p n i e h t conta in add ti citi Ii gtiif, iat ().i -oil ,-: _x<•: ..
j,:...{•:',,ver, nA l ris t o -e quia wa ' tpci'tired "in .inr-o h,, ORs --wi the.tlnreN• .
A o.f k4 "in g hat fon Iuts ha '!mlan vi ters, rkr ..... a,,
tin of what conrs. L u), "oirni Jtr" tern sioIdhder'"
vr A snre nary oft qa ia us of l , Oc ii h ,q uaIi Ii (;art Iin ,-
Atta hm" "N . I o"S f' 2- 1 c....... 'a -'Q I', ap r . i - t
i-..n. .i r p onpr S ee t' .aQ) hich il tL ispoc h cfl ;t vi id , A1:1
*~~~~~ f&... "' enur 1h) al pri red if (J a hr lie tn reide f1 4nut1the SE~Q Th QS(L atirhet )s'xe a cv
A.- :. f o i fication ...... nfor c:ton Ldid ii o1r . C ... .
- -c o m p o n e n t s -n o t : " f u l l y ' q u a I t .f i v , l . - -- . .. - .i ' ._ , .
4 . .' -, '.' *"r
, o A quaIi.ficaLi.onI for interim 'operation for t'hose' c(:,-4 40.A.ln ... L f.ts quaIi' fivI o ly. for inte I fise o with Li m L t L H
of intierim operath o ,, ..r .o a " U •0....
& A (u a r i f e ' , t usi( . ti e.-I .I iu f ei l ifI- .'N•i I' fa
,.:,"<:"'.'•" ':• .."3,:,--"Test ..... ji.._g of Pre:ssure .Transmi t.Lers .Lu' Dc:m n ra e; d" t~iv rotf-:•.,:,:.,.. .- ,I. u ipp icat ti re .p.. f-. ' i '._. if:.m na iA . ...Jf 1 Jii. J .>,
S. t,.n -"'It gtio f pressure tirnh t)iai t t r. e . i Lc, o-dv ,i:cii tr ate . , ira ilio t y
, quI jiIg.a tol for J ritet code tions was coprditieo y ant Foxht',roir0g A i r f ...m en"t-al< •'' " " ' i :" • 'i•ca't •o r • "-i': " ' .. '>.">. . :./" ,
,..-, :.•.....•,> . tin... of,,,> , pr..... re , trau: ri,..tti i . t o. il., ,,.-<, ~ 014 abi•:•• .Ii.ty-
"A.- "I I " ... - - .ý" 11 7-1ý77-=ý
V.. .iii i:
6 a. "n. I re- nriil ( .dt:A / (ri . "v pi "u' Ir U ... .. '' W n : Il f)/I
-. iIW 1l54 I ( refe-rence V F B '8.. & ih W It: re por ted tLhe Vnly doounent . eI ti•, ergp ti, sl. itt II I t,' 4 y (
"rn ,,e iqF:" iis IKr r fKi l. I es li hI I-a:i ..11ii,', rod i f i pd Wt) tlnabime. them to hji telif ih sland cnd i* i, o
-. ' . i'. e d d t ie oi t ii n.fl .i Th.e" : mi oig m ht I aI I i ni u•. t' , ill .p rit,,r ii ,.,i I rd
Is .ax imaXi m Cnre'dible 'AiCdihn: (MC A)Aj "tye' .PIi~ rmki ni au *,[ wei.
dos' i giied ,i It vr mlod f (-at at oi k in ; . it d d I ie' ow1 I',i If
- ... . aCcie L induced condit toi•..
Humd i :itoY (iota P ne(C i t"• '-" ~Radliatin,(ToLal.al Lgatedj~lnseY).72 "a i0..,,s ." "•{
nt.". ii (I i' a .t i o. t .s w" c r t ma (t" ' I .I 5 tw ';l o. ?In I I h t. I
S empe 'i Liitre• , pressure, :An riI d , i in I r' I s ýafd, iii I .••'I
... ii lowigfi" t:ypes::of a vir• QTaig'e :"
Pe s r Se !s~semi I y .. . .3
0 mp I ni. fir
Cover 0ring.'lCY Zero 0Iring
betectorasury
Cover'., .. ia. t. io re sisa nt ,i rink
"Th modi f ied MCA-t ypeW.Wt r ansmi tt erd l 's I .ed r" I•:a tied o f" r;1 I d iII
tunder, t fe-'. nvirunri~nenai tesýt miodjatintt' s~poti j i ed *rhontyS.Ilwever, a changein -accuracy . f t.e g d ivt 14,*7,. percent of of
fi Il span"w:;'measured for the modQl I- I I(bM ciuispped.wit the t ': !S10-0 mA' ampl i fier when sil, jctI .d t0o lit•h . o•,l-envi ronie.tLa I -.
- tIs esL. conditions- (niteamrt,"Li mpe aiire, ridiat.d W , and pes -'sire) . It is imp6rtant to notu e th.La vit ,,t; .chta in'g i- "
. -c Ided a .n:.t.ive 7W5 pe-rc 0,t that wi, added to. aqcotnIL. '"...........
a 90" . Lhs/ina g hackpressurei' through the. openvent' i th, .i-t ransm i te ( - However , the CPd is . SQN .Will Iit not hi suhe j '
to any changes due: to. Wackpresiure ',s the pressure in. theAV 5 annuilus remains relatively constant !at slightly .less l h;n-
;'Qk tmosphere.. during ;and fol lowin g"f, " the A..T'li ....'1ia(re fo iiS)NCould expect, a manximum change of 'negaLi[wv 1.25-p'rerc n t i'"..thin transmitter had ' been'inQutal led 'inside "'contLainmen t
" .owever,, he actual Ichange-would,; b"Iess at.. SQN ast'4j'.'ý'. '4-transmitters are insthlled in. the• annul uISr 4 i0 on whher, the
. '' ;. :..environil et is less harsh dur i -qaWITfnL t1'lowing, au•i'hnt .
conf. it Li oris
'The "onl y docume lted ,tje. Lng o. nor -MCA, t yp(' L ra nsm L t, v -er. <,
Ai. 0omponents" was .irradiaLion, on- hree..Ltandjrdet-4-20 . mA, . I(). .. v.series:!. amplifiers. (the. PAM ( .ds.are-ui pped.lip with 10"50 mA-i !7 1.setries ampifiers).i.The larges daip ki r put bhiht 1.":-
"' durig- t hhe Le I ng wa Sa .fnegagvs .1 e219 pe rc:nt Ljfo'r f one Z1.
- -. ,-I..•?i "• 3 ,," '0
'. ii i i ei at L1 I x .. Ts hi es t•: II s .iS-1) r oilteis '"ii
,' WCA --854 I in .Ju ly 197.5., OE p r ) s ifne i f iii o 1i 1#- Ns s, t ha t C hu
Oial I y lit f('r en CP 1.11 L WO 8tn ;I 1141 l ~ji ht
(4720 niA/ 10-!.imA) was: .5 res i S Ltor to Ila 19.IgIIIfl tu opu trn
TheV.re have. beenrnoil)-dot.rinented t e strc. r(I Is• t1): re ented (It. t I A '
t demom's t-rate .ope ra b lit y duri r potA, twca (lidt , 'o-'i i i on o0
thle,; iioiitlLA F 11 GM t y Ii-a 111.1111 LI tr' c e'd or t i e, VH O' st
that, were in stal le at, SQN
. CIroI In o I ov of t he Enyv I org nitn, ii a I I I IZ.' I *Jii t, .' ýSi,)N "v"% i
The i ol lowing is 'ia ch-onol oI y o of. I'' t f o 'ti 'i r mment 'IlI (a I -,.. i ..... i•oils of. the SQN PA IM C tdLs .
EQkS Rev i sioil 0
,ht 'original EQS wa .i i u Su d i if) 'S pj t; )c r,. 1981. .1 tii
E 0 S was" infcluded' in tlhe I.t, QI Th, 'i i i'oiitii . )l "i. Analysis ": attached to the KQS i(Ik, I ! 1, th,;t tl- Cu,!t
w. e( r c-, q ua I i f ied 1)y. the W. t Fe;t to t hi# env i ron 'ncii t Iconditions Airside contai n , men, 1( 1 1 I mwng t hIe DI iA t srepo rt.ed by VCAP-854 1,. This an.'l I vs i s i nco rr Iv t a Nt. .-the CPdts were non-NCA type I Isisi. rnnm nts a nd thostested were- MCA type. -,Qualiafi6at ion hy similarity witlh
*;i:, the tICA type Lha L w re, tes Led .wa s novddressed ,n lb
'~ ~ FQS.
TI. .The EQS was- revised il may l'J82 ,_i ijdlc,tc- tha t 11..'CPdis were Ii. a Ii fi ed of' the has/., of b ila r it y t yt I.iMCA-type transmi tLLers Ltha t, had l Iei tested lby W fy 1114
ii!•:•: ii•:, , -. F'oxhoro. The:-justi ficatiol at t;trhed to the FKQS loO
quiial i f ication-,by. simIlarity .,rmdi , i atd that the aIlil m-,Oe1ji.. . ... . iers of t.he no, .'MCA t ran m It 1 er s.h,1d.tI io n- te s .l t.
-ads and performance to mhat ilos.: wai "c epiahe I ''
While this is true there: waas a, s I xlat. ,1 I fe renlc, ii tlic,•::">;:< • '"' ":irnl lifi ers test~ed and thi yp :-ml if(• O t e ',Iq•;!:;'I lthIe typ ip ie rsr If the, Cldtstý
T That difference invlved e th .otput, resister whicllchanges the i output Irange from '20 mA Lo 10-50, mA
""T1: .. i'tw justificat ion for. similarity jim a i ii ic.tjon inlicdI t.a-d, however,, Lhat the elecLronli(i ci I uity anl .O-riiigs
r * were susceptible-: to degrad.it ion w'ithill If 10. yIl .3"F environment arid therefore .concled thatL LIhit-
transmitters .. had a;1i.1 1 ;if ed life .l only re8 yeArs
c e vQ ei s ion .STh1 "lth re was- no. Rev i's ion -,2 t. he' I(;- . i 1 'S v I '')o I eve I
-nadver tenL I y went fron Revis on Io Revis oo A dhii to
._all.admiiaistra Lv..-.oversight .
1 7
.9>
e9was9 ga- ri, rey~*999 i''A~ s .,9.-i99, ay9 'T re i ":oil'
als. in i a e 9V i" C~ s U9 it9 ita I>9~* I' 9l A w9.9
3s I 9. s ~ i .. m r 99~.9 i 9. ty .t-h th C ->.v f riiis vr
I9YA, le9 +:Sj~ilifed e pi ovii
L he F.Q it c Le (I )e. y . a9us 1.11 .S, Ill
Lal 41 i at i oll .10se o fI x rad9t
a"T Lo .Y9te9k.9t.9 99 .0 9 1
:,o Con toS beeso ca1 1 of iXIrlolt9999*i~ de9 r99, it L
th aV91 L ieM 111fa r v r's e t'i £Pf iv&de w( g.fil. eilt l"' 1 ' II of .A9~
I o0 F , zm 1ug h r"withy Lhe oporht'n hI - vp s t o ihie tye r 11,i ,
~ 999';transm i tter ion I omr i ha! api i ca A it ti on 'Il w~ i l s je ~e .ph IQv Thd e su f f iet.1e i~ denl Lfl(i~i AI. te di v hriAe C vs t iý
c~p b I h e Of'C Q W9 11 I' I u L o its pe ra L C~ A? oa 6 a -L1 V i' r ed (to~ eelT I .
aýS Retv i nerdd s a 4AtCA aIs of (1, -5.I
'o Ma~ jIcth 18A 198t. : loll-he rv ii l di! I~I ch P et Ii tf l'' ie(. tWO
9 tween the not. ICA.$atvd. with te PAM~n st ys L. em Bot h re ci -I '.99.9.
sin weem re fo n iae Lhai' the e;t CA C1ts I ha bcnn 999v** 9
(I*i a Ii f ic d ,,99 th .MA ip ntg Lshic tes In relain typeLod btemphatur Li( orlresul nts considred to h, thabey. f wer miqua I hat Ie con te'' L s
(see MAL typent-) -,-,NCR SQNNR8r0 wasw e , waf povinted and ~LI~ he he mas nufactre`-*,,nr's~r I ei fi j 't' L and'AI ' tetiICOi We~ eI
in.4 I le (I0 i d not:,.r with th op.' t it env ho w-isto in wh i b
~~~~'~~~~~~~'~e trn mitr in co mecia ll airs, ws pe
9.999100F arnid . ha sufcethev amlfers of the' L es tI. .d MCA- i erwe. c'99''999 mibicr ofd othe.nuonuCs' were sliti r tt. (te Amp i fe io AIA.
the acmotaenst LI to
~ e E~Reison 4 opoe an -s e. ra L..
I~9999 L99999 99s9n d d h 14Li ation I r c n i
opera~~~~iorn ii Lh h ' dLS ,; jr vi(e .b p d
Th n o n- MCAS were marke to' irecgned tha the iOl Ch"It ealv het'e
.9.. 99 uamfend using the sinu aerý itha -,theu tactithnt tiond re.9~9999.9~~9999~ .rs lt L iondias to", h acW t hey, we '.'unI ua I ion e oJcIi'ii
(see Attachment~~l).+"NCR SQNNEB8SOIXarlrrci 1 ai ' ~~ 9 ~9"'h raon'for;noqai ~i a in' a' [ IC e8e
ri irt - mt h ty fo t "i. vv Vi d- v'.f I It1
igli fici a it 1 L ct woul h a ll go-j ifdi' 11 i i'1111
~ *'4'~ .'. "''Ili~ long-term na ft-Y, f idi ons Pu (lA 11) 1~t~ d- 1i- va ilIab le. bt!calnSf the ('11Vi ronniffo-ut ' Ii ("ill It I I WI -tIe .",
no L F' ~e v re'ýts ht" 1` i l SlWtei I it i '1' ill fit If he
0 Ihie i i t a I ldI ra Iis illi 1,ters' W,.ot 1d ~.1 1,iv I 'wvd- ,- wi ItIIIqual i fied' t, ranA m L tr s t hat hL t 'let I itowns I rateLd ~.':A1,1t iocumen~ Led 1t 1-. ra ( s I a it tt. 1L I lit, FSAIreq i~reme uits
" ~ NSRS (I i:;cussed 'Aheý envý, roniffnt'ii 31 'pit I i. cI r i L ;til at 'itof th.e CMdt. with the- vt'iiincters;'aildIi a l I. , r " a ' s fi'I.t -II
t)1,he quatIltf i c a L (il -)V~cori andi~ Llh.. tini t. tt i ()i1) iTcess i ng of: the"ý NCR -i /H E In itAtit",'r 1-1 th l itvnýi llfevrsind i ca tell thIat the Ce It L h Li L thle- _~i ti I. itiien Ls wv r' ni I'envi ronmentally' L qai fiedl w%; the icetiraci .s fIt r-i ( (,becit. demonstLr~ate~d by Lest tL ti riger wet-i' t 'iji) fit\'d i'i (fe rences inif thle -1~ A lgn o ýif the, MiCAS'. ,ýidm o tAThey. indicated jtha t comp Ii ;n r& wi hNUL-T8
sect on I. C. ) wg bein it. %(s.l by, thbe NRC ;iiil I ho ~.cur rent regul a tozn pol ic y ws W i.rejiiii rie tnon ie
'4~~~ aco:itra ci yteting. Tecvethat .the jntrumernts :-o i iIfeell1 i
`acc ident. ant that ýoadcuatsu Jiist it'. c~atLio n had INvilp rov i (left for ct nidopraon
if geniera I,'te m,,niagers 'i' tirv ewof greed Lhat tI. Iltint.riumensw not j uiyev outiffellta Iý I q tua I I'i 14'l
T'Vhey i ridi Cated, thlat pa ragraphi <(i), of, I CFR50.44) It owodII. hem to p)rovide, a ,.uf L i f i ca t, ion, fo r .coiit ntriled nite r;. t i (11with elactriCal1K;etpuipment tht.isntý fullly q11,11 iA icelOE mala giment:7i ind i~cated that Lie. t 11,011 pja ra g raph Iis. not. applicable, to *'SQN ývi~ntage!,p paf-ts, the NRC hI ia(IIIthe n)ast allowed tiem , to otperaii. fnr ~i, i .... ;
''-4
'4- .4
I4 '4'4-4"4'4 44
44~*44'~ '4*4~~4
.*.~ .~-
4 '4--'
~4~~'4-' ½'-
- '-44 4
-4...
$1 ~-4- 4.4$4i¾~C,-44>~''"-" 4".4-4 ~
wit h tiiqual i fied (qn i ;)ment itf ;trOtip'r iu.t. IIi 4%t, it(ll • 0colit inued opera t iol was lprov i de•, |'Ihir efore , OF maii-agemlent fell. . that CPdts were, i.' (pa I i f I ed, for mit Ir I mopera t ion in accordance with. IOCFR50 49. OE ilflaxillontuilt
`.f i (cat,(r.tha:( the U:;t a- of ipararaplh (Mi) of IOCFR15n.4',).which i .not..appl icable for.SQN -vititage' pi. tll o .provide for interim operationh with uinqualI i fed (!#ll I .tmerit , is'. an' inforina. I agreemenlt.: btweerin, .:TVA'_ and NRlwhich has not been (-conifirmed' ini wri Ling..NSRS concu rs that the instrument qua lifi ciaion (101,:; lot
appear to meet t.he intent of sectionl.1 NlIREG-O5M-:and therefore the' CPdt~s were not.'!c'nvi rotnnient~alIly juii-. ;I.
fied, However: NSRS a Iso concurs.;thiaL, ' a iriTa uate j't. i-fication..was. presented _. for, ¢cntiin e-dloperat ion unit If "'the- PAl CPdt.s- coud il. re 'eplaced "wi t C IFu yt I I i fit (17t~ransmitters ' ;,7].:.'... " ... "'<"'. :-
"''44k
'-4
~'44
)77
19 '"
* ) ' 'land N I. It A."- Nt C d Ii (. / k Pr I ~e~s
Clrite ion XVJ Qu'None f frinf i rifg, Asto aINPil~ e t~steflb aid i Cittv ric XVI "WrreffIt i'AtI j(i i,'ito Alfepe teI x It
G- a~ t4L h lhe I hat..tiii. on Ki i con'; ell\'e' on~ (e i I Aty. ' I .if up VI ICk
., .. .Thcesmtirs' ar'pomt rieiidv f ivAIand' e "rryCvdcie
HRegaurd li lt'i famng it £ ifiS I ht. iLOW'ejit In e'easI iiti~it. lu yie
~e~i~drop ft -Ir. Lli ftllwui
I -tei L i f t a it I.Of a a nhe oiur6no(ot a iti i. g Hemi.
.5.'.'for in I,,ndi ijt' ItT .ro
TRepmeineg i r re t. v i'.eyv it lul A I An ite ca.<, I .id gel I it grItI
U06? iie t L j iiS- aueve i''.t t o q"A i~i ty, inewistirie,. -I r I to lo-, I
I i shed tia.ssuiir(that p~romplt, act ioll i: t.i~ee tee
0 l~etemitt ire c i'Caus O f the Conid jition.
n0aK)0ueenitiLYAnd rq~ prt. Lhi, eC~ii-t Ioeiin to Liii : oproprei e
-.Iv I b f tnanegtm~fltý
TVlA IMPt I menit Sthe regrl atory rf~qui rke~A~s' throughi t-he v['ot'ak eprt IV [' /1) NtJI>PH and QE, irnjemoieer Lhqyni
,jeopi cAl .Rport.. hrough. the, Nuc lear QAi;.Iity Asfiranifl Mantla 1
.4 u g' Troceditrs;1.E~s) uari the.: NUt; 'PH 'Area PI Kjn" Artý .A rýjaPln procedu rK was'proy Weed . by NLIC! PH f or add res s i tIng L h1K
1), , r ce s:, i ri f. .N FE/EFRs "ricpe i ve d t rfrm s[' e ve rt e re r v'Ikie! spec c'f i c' OF a id~ SQNý i fpjimenlt'tiptg % prnrvdn6ii it! iit
offec t. 'whve `NCR . SQNN'EH&RO anid iV Ls. i soce.iaC ed M'EN HW½. p('tire'paq ýanti prpcs%'d t di stishede iii thv tn! kmw le:
.5. ., I ) NCH Proceduit rt
~ '; ~ . heOE procldirrejurfornfset t 'si nl NC~s was Ep, I .26Nnnconformanen. lq ye ' eot t~.te lni!in
and Idept c. ed ri Att~chtiient. 1, Lto ti ireport W;R' I~ i.,.
qpiat.e in t hlqflt iihertwmirelsomi- Oh e rved .prelreit
U a ii r~ tat iu li enou ragi! nt mi fle I i norue itack ofpri ar -~ -r rePsti :Tae.ta ~e
''f k5.'.'' we4 r ant followntwee'a"ryiI .
i2f
.... .....
... ... ... .. .. .... . . .. ... ..... .... . .. .. .. . .... .. . .. .. . .. . ... ... ....' ¸ I ~ i... .. .. . . ... .... .. ". ... ... ... ... ... .VV<'<*' ~ N
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N. ::" ],V• V, -; " '- /," .¢,• •:•,:•2•;:*•• "" '<V• • ,,. ,, -. ,,•• ••• .'"",".."."•, % ' "
-iN -• ., t ,•-;'"VV, .V4VNV , -• . 4 ' <K•'•, :• ¢. -,-,
N" 4"-"
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NCR work was" ,rI. ol, c t .rt ta it ,hl I fir It t1 ' OK
.emnployees .. and whrilewrzk ug Iua ,t NCR L htay
might, have hdJ tLo-neglec't ctri tid path wIn'k
as'sIgrime nts N
The' NCR" process. wasi;ý art ' l iart' t'ir iag IgIy't he -4 iCte 2 L...i V l'• f : • . tio t:ro rtit f n aoI I Ian tpi.q
as,kSiL. mayý
NC r ca t c mt) e a k o I .u2 I.h u12 y Ill)• iii) I oy(,
Cc hJuse% lle, empfIOyee to, hiv•e,'u , a hI ti l y(:-" i t ."defic2i, ipes ini hi:sl/hetr own work or the(:-work of o I eng]Iet'!us- 1r 1. slt-latu vi:,,. .... "
C. r-CreilaLec a vt 2 v L eedIIack t.o tha, 1 ,"l, I,,Yr'O .. '
A'i' i f hi/h ei deut-if Ii i t t il ii ti2 opii I ,r i' t iiow
LIthat woul d1 iifI ln tlice .'•flctial all t ,,1 hc'On Ii ticllLion )i 1- ýe" .•i.I' i tI oI I1 ,
The(re are atL Ie,lst iglit i t ,i'.Ii' 0pt4'.whI re" the NCR coil :. ti alallgeo haIii. s .-1u1d IhIdele a yed heLweei the, idenlti lyi ng ntp I noyu Cfsupervisor, resiponsible rig;lftlniz tiOui, 2)1,.
clerks, '-branch -chi4tf/pr iuJuct, irhlfl; •r, or I'C
Nuclear Livat siing Stat f (NCR iq hnridlled tll) i'4l
than "once lay some part, ie)
"'here..was nie 1et, ira Iizt7 I s, pinin i h1i I it v til'
t racking the pirogress oIL tht., NCR t hr, Iuh I hieproces-s. Responsibi lity kta trat-kinag rng ,s Il vwith tht,. emplo.yees antd. Slupirvissirs i nv,)la I ve :.;
- N ,,..;'.,U' ,• . . - . - .. . . .
Tliie 1r ý was -iio foriil"Ito prevent the NCRspeci fied t i ilref -amesthrough I I of the"i amely IaShi () 1.
'i(ct iVv ti r ckiilg it t' " ,
ri'0l l llI a i I i rg tao 2i(,vt
ra " I;i i I i ),, a o t. r;uIs I a-Ii L v r t;ita lea' i n 2s i2n a
NS R S interviews W.ith ()F'. eniginarrs ;uii nd ,l2i .gers conci.erning .the Lilt cvst,,;' -.tin i lI Itawai I I ItimeIramin os indicated. thila tL h iI the nitit r-viewees were knowl ed "geablIe of .. the spec I f i cNCR' functi on they were aeccustomed to pert Iorz-inR, some engineers w,,,!re tilifamiliar. with theoverall proces s Ia 'whoale: arnd wiLhi. the f,a llov, h e t i mefranies-. (th re workiriRg lays tram.
{dentjil i (at ion Lo prepirait Ib, n at' the NUI, anmdei ghtl :cica lenda r t:d y .n iv ,de' t e rm Ia t it 8 i'll I i
• u.. ce),7:
-, V"' <N<~i< 14
j'~4.N'N
Li
N~f
(2 EJE ER MAKINurr
Thel~ OF p r oCe d u 1x fo F pi ro in i - Si ng l'E/I-Hs wh ilt wai
US ed Loto evUa IuLa a' di gnl if Iat LnlotIin
~~ condit ion :1denLi f fed on ,n WAR 'i in a oleviLiinn
report for.an pperating nuiclear planuit wa', Elf I It:i,.
.0.. . .of "PreparatAi n Io I ai lIure v" Eva I uat. i on /l:,ni -,''i ilto I '', "-,L . t i I ' II i1 I oilA,. • .• . . . . H e p n i t ~ S o f '. C i ~ i c e n l. : , .j a in l i L , l
, .. .. Nuc IcarEY Plants, '," Revis ion: I II-iEIs ,and Sa lII y:•.. evaluna~t ion "repo rts (s R~( S ) wwhich were. t . hi' pr'ýidlI
ed by O:-.weriiin tended iaole ly to p invide NU.: I'wi Lh. informatiorn tA be uned- I or ,peratl thin leti
sions .such as impact on opigrat iolr,, app] icat ion ni
the techniclla 'speci Cat ion Q.COs , anid tfor r'ep",_Ling to Lhe ,NRC -FR/ ERs wre L'o he pireppar,.I I ,r
.. ... ` : ,. all significun .de, ficient. ui, di .ions as q ic-k lv y as
.. ossibl.e by properl y quaI if Ied ;ier.moniel IlO. N1;i
a q , ,: - " . ... -.-. ... of Lthe po s a Ib le impact. on tLic, l alv Ly of a n op , ra t. .. ing plnt. " An SER was normal Iy to ho prepa1) d by
I" NUt PR,,but .may-hbe p repami, .z by O aLt N.I IT' s
>- rleques C-"ý .0i¼
In genera] -. the FE/ERi mu;t h,, iss!ted wi. ht i I'lcale ndar days nii Hter re' i pt oi hle NCR or dvi,-- ion r•port. by ,the,: respo-ns i. i v organizali"n-,"
. .... - ",nles ,-one or more . of tle f-ol lwing appl ievs
0 An exisLi nR agreementet with lhe NUC sel- i a
different ischedule .c
So NUC -PR a, rees to.: op.r re,,,Utit a di tfet tinl
.schedulI -
0: The respoion; ilhie E orgar i zit init, hl iv,! :
C ti i'l't I g M ex ist - .w ,.h ioil ipl. l ;ts ; i , ii It i -
.,..•...i. .. -cant immediate threat toli h ;iLb and , ail, i V. . . .such that the 15-calendar-daiy g"ui lin•e wouild
lead tLo a major increqs( in risk. In :;xsuh
va.s•e .the l1rW () ilhirlt:- il,,i be pex id ji ;,':•..,,',:.:.. appropri ate..
,Te procesi G pp:for lirtJ ri fig :ild handlin gig FE/EI; awl
* the transmitLtal Lo NU? PR is sil.ci fied in El' 1.48z " . is summarize d anrdt depicted in AttLalimenL. 2 of tlhis
report, . NSRS con,,iders..Lnia-P d1.48 was ainlad,-
' "quate In -thaL there were ,omy .nhgervred procedn ra I.- t ,. -features thatilike EP 1,26 could encourage iuiL i m,-
- Iiness in.- the processing.,Thos, feal.ures are as
W fol lows:-'•';'-•':'*7 -": : - N o k : i" a c-. . o l a tEL.- i- u I i .n c Li ni ,.
0.There.- , a1 t I tARL . even iierfiatrW ie n L i
c- . where "hie.: FE/ER.co I Id c ha inge hands a11 In 1delayed. :
Z0. " , • . .
t VIA.-'- &
n J n<0,
Any IN an
'V '0ý -
Q~o
J,
•" ' -• .• •/ . " ,- •'4,; -'44
iil
.4' "[0Thetre"',waS n1o at. I Vt rick iII
;,- ,/vent tilnt.imeIines and an C'":•:'>:!•>t OI"Y t 11. 0 kiiiit,'•:( t e tha Ir ; I
.theý:FE/ER) tor tracking th
FF/ER "Ahrough each i it erl aI 10 toted L+ IiL -:the FFI/F. i, t
f•rom t3 -") .... ef ore fo rma l. issu .
: -: . NXII( ' PR ir ctedthjei a i1 ow ml I'' ""-'4 ' ' 4n . " + + L mint d rla:ina eqiiate" .irt ryet
'",Ž . ,'v ..::" ".. ..".. ':<. O( ? rn edures dO riot atd ress di
. . ,:nor .do r ` they ll Ltibll i s h - any'4 .< f rajfrl(! • 1r t racking syste
turned lK/FR is prompltly ru't
- ~ L "'"' b . WiG PR (.SQN)' Aear • P I an Proc0dure .O04.O1 p ro Vti(!s
4',. 4of thL TVA oPeratiut, nol r pf],,,t,NCRs i ind is imp lmented at SQN in. -SQA:II 8,. 'Hall IIing o f Nonc-on forivrInctce k
,hii, i s tanda rd pracL ic out I i nre t III A2--.k.444' when anh official NCR andd FE/ER ar re s'
IQ E., O and: spec itfies the t inme framets that. ." '"''4" gu i de I i rnws. that ':undi r., no rmal eci rIuIns
44 4 . -........ fo ii owed 'D Dev i a L i on f romi tLiv Lime if r al
:A), by S QIN I 18 uI ld&le. I spec i a I ('C idi tcim.
444.4.. , pr r.iat e by a. respoisi H e ma narager.4' handlr.ding r an. NCR-FE/ER at SQN as spec;:.J *".'4 ; • sirrunrarized and dep Lcted in AtlachUent
After recei pt 't 'the SQN', SS i l)i v1) c- NCR and FE/ER was."to .be immediately
'," .'' latory Engineering Section (RES) whou": ,y of the FE/ER. .OE..,"would dbe milreli
nv '. -. inrdequa te4;I FI ER and r,.f., her
"FI/ERs -would be' retLurned 'o' 0Efrf'1'',• ._' :".' The" RES would contact . OF-NFB if t.h
reqtu i red SER. 'Adequacy oi' the FE/ERmined, the SER was to be' prepared,
and SER were to be transmti t~ed to thnSsection wit)h i, dire working. dys
- . RES. , All NCRs were to be disposi4"'4. - conjunct ion with theC plit co Iirpa I ce''." - t.ion was t0oinclude:,
4'4•444'444.4.:.i Completing an SER_,Lo provide a
-" -".r' a c r r, o n v c ,o to b r ing t hIt
ance w i th STS,• FSAR, o, ot he r lii
Comp I '4 o Completiing an NCR record sldeet,
'4,.'," 444<'.-:">:=. ..
Ig l I 't.'t'!s ." t,, ji -?:':
'lit r'a I i Zetll I'(*sjiir v S 4o -,
' zat il i,,,Iltd tr I ng
r ~ i:m ;t i t I t it .lit .. ,!,.i;>
v~ I intl
'I,'/I:, l lI t 1w l .11• i r'i'it,' t o I ill': '•;)' •'., :'"
nm riricqir4 I t. I 0 1 hLit O ,;t - r .1i
gt( 1 dt(. I vtl
p•uj l,|iui(t e . fr ,l]
epor i,,,. t t tt i
ib•mit t l,.I t S SQN I,'''
t,:iit*eS a re' t , I .s-
oi i ri SQA I1 8 is .4 cof* thi s r-el ort.
toPrs of f i cv,, hei,, yen LO t, Re pRtj- I
Ietermi nes .adtlej.-;ately no1 t i f it'd o Is;;a r .y i- r;im qi i.'r I t ' '
Irt h1 evIr tv im:i ti li.r(,y azre t0 dii tO I-
aind the NCI-'./I . ,
pilant, ..comnpl i ant:cea fter rece ipt by ;-i olled by RES il 7
utaf I D iisposi -
(1.1 antI dletCrotniuilm " I
mliant e ibito Comp I - "' ' ". '
"ells 'i fig dotilmltit S
'44'9,
~ ..........
0 Completing an NCR NIC itsit u shie't wllii h I r;a k: t or-
, . .: re Live.act1oin Laken by OE., instruct ion i(Wi&
, 10 s is a lid cl oI sure dat'.. Of -Un.' NCH.
cpmple l .. ce A lt a l f i, sr i ii' ,I'' l , I ,.I A iw P1
millning'.:. Lhe"' rtportal)i i ty asipects id NitA-FE/Ei ,i It:•7' ;•• U;. ... thesp. deterini ir Li .ols 'being madle, withiii In i -,. u". , king ,
7'i: ddys ofreccipt ctt i N R FE/IKl SI ~lRPat ki w I
Y-NCR-1FE/ERs 1 Welre f orine r Ly rt vi'kid hi h0 t Itil hp ;Ii10P0§. Director's adminisltrat ive suihI and the RES. Ilowtv,'vr,
" NSRS considers SQA 118 to be ina iuqlelUitv init tlia i t hr ",
OAK O.. were -some.NUC. PR intprface disconrict n wit the Al pi 6 ,-cedures "as d sculssed in. sect i.ni IV.i). 3 lhe'low, hI
,addi.tion, the .st.andard practice, does not, ;assiire L i-i.e j yprocessing in that itW allows six workli n,. days I ro, Ihlet. , Ll
time RES receives an NCR-FE/ER tLo. ithrln in' i( report aiI I.-
. -- i. ity- and finalizek correct ive act i in. For a worse-ca,,:scenario if, aQ.NCR wiLh cCa ogory III I.TK/ER i: i err i vd"on a Friday* in the Site Direct or's (if f ie inv I.aid:Orr isa hol iday , on tire next Mionday , A wnuId he~ ail Wwed by
."Xprocedure to take 11 days fromi tnhv t im, the NCR-YI"/ ER.;. ,... -... was . received Aunt i l +repo r tab i it yi s ty is tW e ril i nreal dintended .corrective.action is final ized. This i. .
A .-. worse case-,scenario and is not intended Lo imply tha;t..it is a commnon-ocelrrence.
3.. '{. [nt~erfac~ Between OCE adNUd.PRforIrn'es-;il.ts N ,I:".
. "_The N lc eI. ir Qual i ty- Assu rancee Manna I I NQAI) p re:enLt y ii "5. e-5Lffect states - that".'thcre is no oi'gaiiiz.at ional iitei '; .: ." "
- . : :. currently needed for..his criterion." No controlling.jitpir-l,
-,- ' :": "•>:¢ face . docum.nt wask:in. place ,hduring- NCRI SQNNER85OI aid l i,.", ... " -" ""'"..."": associated FE/ER prepa ration" by OE and suhise rirent, issi;itir -,-!
t WNJC: P . . - -P...
A comparison .of the NUC PR and OE prorerhir.res by NSRS r0--.......... yealed the following .interface de, ficleric ies hrLweeni SQAI18..•;•;,::•;. .•: " .:" :" an l Ell I.,48 :" ".. . :
.5.,v.. . . .:.._ p SQAI I L ,tates,- "for NCRs L f i ta t li f , ol IE ig ir, r I r ... ;
(010) deems A~ be ýa sig gi fif cant u iririediaL ;e Liot Li r; tobhealth .and safet.y ' for operatLin ig units,, tir Nicl,,ar:.jj"- ,.,
.Engineering Branch .(NER) .shall ininmediately notify theRegulatory .Engineering Section (RES) by. phmne of t.•i,':"
- NCR, O." F OE. doe "oLt addrensh this not if icat. in" iii tL i rii ._;'.:'4.4 proCediures and.OE Iicens ing personnue I indicated Llijit h ri
.... sucprocedural requiarement kxistLs for UE-NEll.
•.."o.i'. 0 SQA118 istaten ':thatt any. FE/R determined to he inar,'l -",quate by NUC PR may be.returned to OE. A. det-ermin<tionr.
for adequacy iAsIto be performed I mnied i atly uipin Co i n i i .
.; h receipt o the ?E/ER :'bby", RFS ' No de fi iLion . n what ,
45A y -L' ••'
~ 5.(. ~ '~4. 5..5.5.5. ~ ~ ' ~ ' . 5. o . 5.5.~.55'..
Ont Lte an'I 1inad equate
F'JJLR exists
in MIA I.(r
ýn .. pos...hijeconseQuel
of.this. lack 6f inter)P rc IavI'*
.' .t
&b i %"NUC P Hand OE is ttt
a s iwi ri-rntt rIssm.e"Irmn"ier
i ,
could be diwerted
from resolutiop.r0
. 1.) po cedur ef .doI not recognize thatL a I"'R
•.'' an ME
a
Vonsidered inadequate
or tht it. might Ia' rtrirnl
Iv by
NI1C PR. As a. resut of this oE pOE a,'iw r•ni r h" t I i ( yV
a returned FEiER
Wiightnt not be prmi•iii; ,p i, s,!',l ,N ii .
Lime limits s are pre llent, Lo entlti- i ite ly reo l tt il*n ; .
E. ;].l rone I21&y,,-Lf
NN!: EB85O1 _and Assocyitpe2 FE/..Js';
It'p.t.i m.
'and ,ttland I i n
.'The fol lowing information
reltLes the listory
atI an i rctitensL;il-
associated with
the subject . NCR-FF/ERH
coat'.'niillg tLhe SON PM)
CPdt s tIic I nuld in the discutss sion are UhPi'.'ei'tll;
i l itll i~ i -_
identificatioti
(it the n sic'onformi.ng cnditl
i.n ,aim the . it"
taý'.ken by OE and NUC IPR.':.Only
the major event, thatL iirqte.vd
the. .
-:NCR flow process
will: be" addressed. Other
act ions nd t hli Mails
pertaining to Lhe event
can he found in reterieucc
VI ,EK 12, whit- li
is a chronology of events
,sent to the NtC by TVA.
.-Figure 6 is provided
to facilitate 'an uhderstaudiri
of the inter- -
face of groups within
theO1 organ izaK iorn anid thiO tiE tntcivtac
e -
w with NIJC PR as related :to,.thisevent.
.Bckgrounj Prior
too Pregaration of Lthe NCW.E/k!
(Pehniiar y
* ~1984 to November 15,__1984Y
During an, inspection
by Lihe NRC in Fe'biriuiary 4, TVA wast,
asked to explain
how accuiracy reqt
einLr ls t Ot' pqli liiiir-'t...
Q 1 qualifications weref(demonstrated
on certain sal'ety-relatetd
-instrumentaLion.
'Asp'a result.
of these quesLions,
OE per--
sonnel began
a review'ofj Lhe accuracies
t'or the. iris trueiinaitta-
Lion in questionrw
Duri ng the review OE discovered
that, the Watt--s
Bar ISAk 1
Table 7.5-1
connitsto provide
rAM1 inst runutaMatio o tLiot i -
tor containment pressure
differential withino
ar atccuraiy ofl
t4 percetr t, The CI'dL0
insLalled at WBN couln
nd S notsuipport
that accuracy requirement.,
An NCR wais prepared (W1BNNEB841/.)
on,' October 26, 1904,
to document this rioriconlorming
condi--.
tion!
Since this was a potential
generic conccrn
irvolving SQN,
tn .. i
,:;,ny assignmenL
was made.to an OE employee-.n
Novermber 15, ' ItA4.,f,
to investigate generic
applicability
at SqN-
.2 Time Interval From"Assi
nMent Until SQN NCH Preparat~iott
S November 15, 1984:-January
1,,19WI
".
After the assignmentiwasamade
&in'November, the OE emplyee
a a lgn ed to evaluat~e 'Applicability:
to S(,N requested infoirmaj"
it Ion from,;, SQN 7•.to0r•lVerify
model and, seriI
•numbers or the
7.
S "'3 + - • 'i ._ . . "-4,,' , k ' . '-' -'.
n•Lua Tl Its is.• J L it I Ied , 'I' ll i is. 1 l11l14 l1 1 ,1aI iBit W I , Ioul, ivo*,l
: .. id-I)ecemher, It C-p ei r,; that lit) tIrI ht ,I wolk W.!;i ISfn i the assgiimen t. until Ierly or iiiid-(Jani~iry
The .SQN NCR wa . nit iated by OF: on .Jrinuairy lb, 19R, . T' ' :i . .f afcLors Lhat :caused~t the delay it! init iat.ing th "'ON,- :i1.i1 ir+).ilit)y i vestig ition Lbait were relvtate o ' t,:' N. kS by ,h
1the folI owing:'0'. .'"Del ay in recei v i nfg requts eL it i I ormit ion item • SN
Work assignments' Ainvolvirig SQN/WIIN NI.I)-. 8p nv o-, ,ment a I qua I i f i ca Li onn ,
Apiendi R... (Fire Protect ion Ptrram •,;,rk Ir .,N/WIIN
En iine eri.ng work asirgnrments on nulear s;af.ty s ;ynt ,mnon WIIN ' ' "
Pr i rity,'givento, WBIN wo r k it ems: ,ovi- S(JN it L-
The heavy. overall workload' dnri un thi s t i mI ic r i .id
A review of the work records for he t imeti r,,ne of Nh,;(i-her 12, 1984, Lo :'January 20, 19- 5, (il' I hlit , e(l),: yuep Iinvo I ved in the prepa rat ion of the NCRs (W!WN/SQN) i nil i ca:tLedthat of the total hour-s worked on SQN andI WBlN, 90 pcr nt"were spent on WHN projects.
Regarding priority .. given to WBN work it.oins over SfiN it, mssome engineerr; and: managers int(crviewod infli r'ttid thit hllvyfe.lt that. the work priori ty was on WtIN. lhiring interviewsw i.th some! OE manage rs. a '- referral was made' t oe ,I nmon rIlii 1h )from OF i upper managementi addressing work iii,,rit y lot timeplants in the des ign/construction lphases versus the otpu'rat.-Ing nuclear plants..(they were not si,,re when it was issie.I or.specifically what it naild).. NSPS reqi-e t. ; 'd NKHB in;, guitltto identify the memo, and,,m from '4E;. upper managremuin t adi!, .s-sing.work priority. ',.The NEB management. couldI not Iocat. Iliedocument. The most ' Ii.kely cand itdate fir t Ilie it I i cy mlmt-randum i s reference VI .F. 48 which was i s stned in Aigu,,: t 984.:.That memorandum statLe"s 'Proj~cts arv to be managed such t.hat'.when there is'a conilIi t between cost or strh•eli, ind sah-ety.or' rual ity, salety.ard 'quality-are ti)o be given priority.'''Most of these engineers/managers initerviwed indicated thit_work priority should be on the olierat ing plantts when it.involved a safety question. floweve r , it is probabhle thit.the ''desired priority, message is not heing effec-tivyey coin-municated from the managers 1n the engineers.
~'"'~ I'-"4-"A ~
'Il '"
r~ ,"~<m -- '
lzAV' *~
A
3. . NCR Piepjaration arid' DetermitiaLton .f Si Uni fi:aunce-(anuary•.16 to, Janu 1985 -
a. . SQN NCR Preparation-
Ou r i rig tlhe' pr,-NCR i ,iv ga t. i rin, It' Iii',exalmned the :W'.:and Foxboro %t -t, I l I o r-mati t-or
E vomipl) (Jyi'
I discussed,
inl section C.3 -1 this report. i He ,h-ti.rrirdthere was 1io test ing do(ufCtlet t iso In 0 t -ii t:; t .1 ' I tI'
accuracies of the installed CPdLs hrI rig i•• t-hd ,,.-ditions . He noted the -14.75 percent (iarige i l in i-racy discussed- in sect ion C. 3 but fa i I., to ,'rt )gil /f,
that -7.5 percent of that change w.!; , thi , 11, i )(1
lb/in g backpressure thL at the MCA- t 'pt, t I- i t • tti.
were subjected to through their ven , t it , i, Iig tLill t.,.:;-
ing. This backpressure-itdticed r.:rrot wis ,:,,t .jp Ii -
cable to the SQN CPdts as they ise v,.ýiito.d to th i, iiinii -
I us region and the annul Its ieg I on I.i 1t.Sill i• ii .1t iiW.
essentially constant (-5 inches of watir-) Ii•rwg Ilie.
DBA. The emplovee, not recognizing this * . t . wilt,the NCR citing that document.ation o, t Lhe CI'd t s to (,i i(not support the SQN FSAR speci fied acclracy of + 10 pIr-
cent. for the PAM CPdts during postanct drt-it cor 1 I i n!;.This was based upon the -14.75 perc.uit (haifige It mf tth(,MCA tests. Subsequently the -14.75 pt1 rcrt t u ui ,,. , .iiinformation was passed on to tilt- OE mply tht th,. iprelpare the FE/ER.
After the SQN NCR was prepared, it w,.,; fi~iui,.l•i it- I:,an OF clerk for typing and assignmetit ,f a nIiirpie (riliui-ber . The clerk then returnted the tylt,,I and iiiiftf.r- r,'NCR to the employee who prepared it.
h. SON NCR Review
Three individuals, including the prepa Irt , ,II.I wI-rI lItIINCR on .January 17-18, 1985. The NCR %-,s t-th ,• , t ,i t:an absent. OF supervi sor's ma i I box ,.l J.ir t.'r Iy 1 t8 w,:-not processed further until January 31, 1985.
The branch chief (or a delegate) must rvvr,,w the NC< 1,,determine signitficance within three working t,;rv,. t IIo,,NCR initiation. It not reviewed withirnri ti ht ;r'; iii,,(lays the NCR automatically trecir)ir½:; :iT, I i .,ril it,
time limits were exceededt whenr farr'g- lrt fl, I t ,.i Idetermine signi f icance until -January 31 , 1985. NFlIpersonnel indicated that they placed great reli arr:t.r- ,,ttracking NCRs upon the clerical stdfl and thost, i,-
v6'lved in the origination, evaluatito , ;111 1-eview ,IYi
process. No formal mechanisms were in place at thiittime to assure that all of the time rcit'ii rementS Wri, Iibe met . The fact. that the NCR recamre signit ira t r,January 24, and laid dorimrant rn the, mai I rox t I IJanuary 31 , represents a signl i irrr ft r',akdtown )I) I Ili."informal" tracking mechanism.
C. Determination of Sign Li cance
On January 31, the SQN NCR was rt-viewed otr ; gui IfI -1-ance by managers within the NElB Op' rat i onis Silil,,+l,Group (OSG), determined to be sigiif i cant , ;ati was
signed by the assistant to the NEB branch ht.:vet,
27
4. Qrepjarat ion and Rev iew of the Fe/ER (F"eli nra I -M" "h Ii
198S~)
a. _r•_paQio n
'fTie Niclear li itvns i rg St atI I NIS ) ., n tI Nh i Il I'..,
Project Enugi re ( NIVE) " t NIEB -odi' 'i t tIa. ,t -t t . I
menit for the lioepahrat ion oft the. "IK/k R. Th.ie 0 ;J
selected to be Lhe preparing ii rgi nigiat ion l 1 ,. e" , lIt-
ary I.
An OSG emplJoyee was ;ss IS•n; d t o i4rcl)at t th(. Liii 1W11
preparat ion was begun on eb 'rur. iv 4), I ",. I , .
the f i rst FE/ER that the ridi vi tlu,, I ha1 I ot,I i irer .i i , Iwas assigned partially ans tIr.uini:.g x ( it n. t- imol.i i
familiarity with the preltratl i t on nl roi\'h w p;,,..4n
The FE/ER appears to hIve he•'er aul' 1, .0 l -I y vi\ . t 1 .. ,.. ..
on the information avw i labl, ! o I h. lo, .la ti vr A t h,
tithe of pr-parr t ion, i l howevtvr, it sh ulId WI-, nid ,, l iIidiscussions 'with Lhe employ.es ill NFli ,,v,.a lIdI ii i !,or no training and lack of (.overall laitiliIr. t yv % t, It , h t1NCR-FE/ER process at the engineer I eve I . Most r.. I -
neers contacted could not relate reqj~ir il tim oI tri i:.
for each stage of NCR FE/Ek prepara, 1(41. lhfow% v(,r , ,,,tt !managers at the section sulIprvi sion livel (M-¶,) aniabove were aware of Lime reqpuirements r ,;irdlin),, the, N(IFE/ER process. As there was a differirg ipet (Ii ttl ,"Itimeliness regarding NCR IE/EN preplartion ii ,twt.u th,,managers and engineers, it is probabl) e, that t bc i,. !for timeliness was not being ef ftct :vel y I ohttrll , t.dto the engineers by the manager:i.
The original draft vw rsion of Lthi wl"/Lt a, ',• ,i' i 1e•', ' n i
to be a Category II and was forwarded t, th,, !',oN :,it,NEB representat iv, on February 11.
During the time period Hom l"nhrtmrty I1 )ni I tI, 5,the draft FE/ER was reviewo.d, )evi set, ar)d i),I iu, i: i i
with by the NEB Nuc lear StePam .SulipIy ,s;/s t (tt•.riv i s 1 t 2
(NSSS) , NEB OSG, NEB Site lprojec.t Engi nver (NI.'. ), ,,dOE Design Project Manager (WPM) and a;ls o b)y NEI highoitmanagement. During review, the site NEB rep.resenri t ivdetermined that the scope of the FE/ER was to no bro)adand actually included intormation more app nlropriate t I asafety evaluation report (SER) whivh It.; ti rnormallyv l ,-pared by NUC PR to dLetermine impact ain plant ili"i -tions, Additionally he felt. that the FE/EI, shoul IV,classified as a Category.111 rather than , Categoryr, I(See notes 2, 3, and 4 of Attatrlne.rt !r de itiini , ionof Category 1, fl, and Ill.)
28
A meteLing was hell i i thie NEI atI*i c.. i ft Kixv viII. .I ,
February 20 wheitc the NEB sit. ,'-'l,,,r' :s.'rt at vt: stait,,
his case and it was deItidiedl that !w. S op, , I ,F K 1".!VtW,.
shotl d b e co nfinfer. to , i fa i.ite va t t.,iat ,I . tItnl Iil-
ent basis rather tLhit1n a ii ore 1la i ( s u e; t , ah.at w,, ,Id
evaluate what etfect. tLie f ai jed ( umptiit %-i, i Id havc ,Ii
plant operat ions. Wi ha this more' *r.t rro-" !.k )I)#' i1 l IIt I!
tht' FE/ER was rew orket.d and revI: I s:. ! ;i . .s It,',t
IllI
It is a pparen'Lt tL hat the :;c,,p,. i, it h, a . ir/ ,t ,.+;. :.
riot wel I deI l ined priora t o Ihis 5 v,.,t I,, thie ý;ctip(. 1ttt
[lot o'eela propt'rlv .orlrlallllart ati t-'d t L o I Iw IIl r', ' a' par 'jap).a- a
irig the FE/ER. This lifck (t deI' it I tIt 4 ,,.I; I iIst r1"mI iIt -
a I in holding up the i"E/1E it. iI agrvt' iaat' t ,,a scopt, wAS
reached (Februaary I I -Fe, rua ry 20). I I s a:; so appa rat
that priority was; not give•i to li I' h "K"/1 dui i rig tit h :
titmet raane to assu re that th' it-E /ER wa:; Il,, Ilet, tIc wit hIit
15 days as it was () days bet fort thi. t "-.ElKIR was re t ,ittit!
biy the OE s ite rv 'prtcrasenat t iv L t 1 )l.- i, Kwxvi III. I,
rew.o r k.
The r' .ev i.w j1)raoct s:; wass! ; aiaPt te r. v i' IIt itr t wi I fly, .ii-Ico rrect't i lig the errior o t hitt' -14. ") pcii ,'ht tai'ii r.• rmV
dlae to haack,)ressiattre . [ht, 0(K tataar-ia )4(- a' ; Iat t' r tr.wV I#
ind icated that the i r rev iew cr i tL-.'r a was t or Iorin.at
technical adetua acy, I i.e:rasing cais i tfra t orts, anid It,e-nsurvre that the FE/ERs are rno(t ts overly itins' rv.I atv,that they would shiat down the plant -,ta t 1 a :;s r;• Vwithout all the Iacts beai n cons aah.aer d. 'hI, Iv ,w i tt
the original. NCR and FE/ER i.oatair a 'iI six sits ,it ii•-
t i a Is or s graattra -es oil e'ach doctta rteat t ithtli t Ila rit it-primary preparer. In the c aset, it I th NCR tl,. rI-.vt ,
and approval process verat:otnp ass itI a a. attlme I rame ,II
January 16-31. TIt the case o( thae. FE/I'KE the i revjaiw art,,
approval process encompassed a t i ratm.' Ia t I ona F b .t1t• -
ary 11-March 4. Thais copious r'ev iew of t(,rt Ihdi )negat ive effect olt the t imel.im ,ss ofl t lI,, H./ER I s:.iidlid not. enhance the quality of tja I ilal.. prtlau t, I ind
widely dispersed resporasibi Tity fear t it. I irt' imii r s!; artI
qua I i ty.
Priior to March 5 the SaUN site RI.S hail tt'een i l()aIat I.rIdthat the FE/ER would probally be Cat ,.go rv I I . tn ,lara lI5 the SQN Site RES personnel rvvat-.w,•.,' •ft advaaace I tjpy
of the FE/ER and became aware tot thi, ti rst t ima' tI a tthe FE/ER would probably h,:, Categoa y III. They Inform-ally evaluated tire consequences af t a ,. If. 14 .75 7r i' ri (,ftaccuracy as appl ied to the loiag-terita sa ety r.qtk i rI-ments of the emergency operatinrg pr aredaures . I t. was:;also decided at this time that OE shttild prepatre a .J -Ifor the CPdts to comply with IO(:FR W.4.)t.
29
. FE/ER ArUva andl [ist r i b id to II (Ma ixti ')-I, IL
The FE/ER was formally approved (itt March S . iri I I Ibvlit.I? d
by the NEB organization, on March 7, 1985. HiIt!; r , ;,tt .la significant increase in time (Fe.hruary I-Meii, i ) ,,vct tv i ,.
FE/ER time requi rements of Eil 1.48 s;truei t t,:, e i r,,,t, it, t
state, in reneral, the FE/ER must tit' issuvdW tliii W 1,1 i.i-dai r days at ter receiptt by tt.he re's:Ii, ) 11.•hi ,' in i ,1)1 :uttlevss cetla iit mitigag ti Log ci rctnsttuics : ire .jpil .1:1. Ntui.0 t these c i rcumstances alppealred to exi at .t the' I lulu tI i.s
pa rt. i cular FE/ER was be i rig prepa red.
On Maarch 7, RES reC(qUestI'l ,I c(,opy OfI the' tA . I',
report from OE.
NSRS examineo 2, signti Ii cantt SQN NCR F.i/F :. I ýsuod', lv I)1Ifrom Octoher 1984 through March 19 8 '). Niiitt,,n ,itt it tiII23 exceeded some part of the NCR FH /ER t ite I.r.tmi,',, Wi t h t hfe15-day FE/ER t imeframe bei rig ithe i.n' that. we!; itst I t.ejiteti "
ly exceeded. ItL was vviden t tb t exceed . III tihe t Il 1 .11,was a common occurrence diarili,, ptrefiaratt i (,t +,tol i s:;,t'ii , +>FE/ERs. See Table 2 tot a stmmaty of th, NCt Fl- / F.; t li .Iwere examined.
SQN Site Reslionse to the NCR-FE/ER (.March 8 -1.ri -h I 'I~
Tbe SQN Site l)i rector s ul fice receivd I ,) r rmrt I t •t n.rclti I 1t ..of the NCR FE/ER package on Ma rch 8, 19X') , which wis ,Friday. The formal NCR-FE/ER wa:; rect •.• , .e, hy IS ,) ,March 1I. SQAI 18 requires that RES sih. I ,I,.t,.mini . ti I I lIeNCR-FE/ER is adequate irmmediate ly upon fI, rma I ,..,, I pt,prepare a Safety Evaluation Report (SERI) ti, ,etleriniiii, it l .(Iot plant operations, and route the NCR-F-E/ER and SER ti, t !,,plant compliance section. A]I this )ri:,t lir at,.',)m:)t:;,i.dwithin three working (lays of re'eipt by RES I) F i t, Ieimmediately n.ti fied of ati inadequate FE/KR.
Ai evaluation was initiated as requi reet 1)y I!FS ,)i March lIRES personnel stated that they contacted th,, ()F K site p,' r-sonnel who indicated that they could providte , sat i: ata i()ry
SER. The OE NEB site representat ive Fit i t atl tbh.,) ,,"formal" request for preparation of the SIkR hal ni. •ipcnmade. An SER. was not prepared for revision u of thi' NCRRE/ER.
On March I1, RES personnel discussed the NCKR-FE/ ER w ith itleSQN Compliance Section Supervisor (CSS) who, deterrnitel t haitif the NCR-FE/ER was adequate, the PAM CPdts would have tobe declared inoperable and both SQN units (which were opter-ating) would have to be placed in a 48-hour LCO as reqitiireiby the STS (see section IV.B.5 of this report.). At the tuliIof the 48-hour period if operability of he Ctldti s c)i 1d notbe restored or an acceptalplh, JCO provided, both of:I t t,operating units would have to be shut down. The CSS, HF.S
30
personnel, a representative from list; 10 th' NEB (wh, w,. AtSQN on arnuther matter), and othie s disu.i,.eI tih alt.rI -
L i VeS and opt ion ms. a.sed upon ti. ali i:;,;,', . "I t NIKI,
representaitive that tie FE/ER was wriittn wihti VXl ix ii .other possible avenucs and that the M'E/N< s.houlaId hiv, houi
examined more closely for piotetrti;l solid m; thoi' V:. ill,
and the fact that thv FE/ER was still b, rig -.,.A ,,r.di t o,,
adequacy and SER pre'paration by tht' 1d0:S, I ,. 1, '.%: ,'.:ii
not declared inoperable by the CS :a tI th.a t i,,.
Subsequent to tLhis disc; ss ion aild iii irig, ri i, nI (d th,\ A•
8541 test report, RES personnel ,ia•,'ovwr', that thrt - 14,. ipercent inaccuracy was not appliriahl b ,) o l. SQN iAMl niI'dt sbecause they were vented to the annrulu'as regioin !r. k e: 't I ()inslV.C.3 and IV.E.4.b of this re',r.urt ) . 'l'hr. .,irIp I k iallIuinaccuracy was a -7.25 percent wh i ch was w ithiu thI"- .1 lw-
able +10 percent as spec if ie~d by the SQN [SAR. This inlor-martion was discussed With NEB or Maruh 12, alnl N'LEB agre'.l t,,prepare a .JCO for the PAM CI'dts to comply wi' th I0(.:[,R 50J.4q.The JCO was prepared ainl transmitted to RES ;iand k.visi,. ito the NCR-FE/ER was initiated.
(.)On March 14, Revision 0 of the ,'iER w;a.; ,Il,, ,itrv,,I inii.,ii.t,.by RES because of the error made by OE on th-,i t , a i.l'.
statements and returned to OF t r r ora. ct i ,on ira ac(oi,:rd;•d ai 'cwith SQAI18.
7. NCR-FE/ER (Revision 1) Prepýaration andr:Ilssuancie (Marnl I')
Marc 27~1985
a. NCR -FE/R P_.reaL ra t ion
Actual. preparation of the revision to tLhe NCR-'E/.R %-!,:initiated on March 13 a1lthough the ori ginral VI 4 R 'i , asnot declared inadeqjuate officially ilntii March 14. ()Kpersonnel revised the informnrat i on thi. FE/Ilf usiagthe feedback information from RES and updated inifo(rmai-tion from Revisions 4 and 5 of the EQSs (see sect iorn
IV.C of this report). The EQS had been revised to,remove the four CPdts that were not asoo( i~ited with tin .long-term PAN functionas and to provide a .JCO . 'lrh,. Eftýalso indicated that the PAM CiPdts were anot rravi ror -mentally qualified. The FE/ER was reiassi i&Ii to ACategory I1. The FE/ER contained twv suggest iors IWpossible corrective action. They were:
The PAM CPdts be replacred with trarnsir itters that
are qualifier! for the harsh ernviroirenit 'xpern-enced.
The PAM CPdts transmitters hre relo :acated to -in
environment to which they are r.aal it ied.
31
h. NCR Rev Isio .l , IA ji rovaIs !s, a.nd.! sl:, ) !,, v (1., i,.,,
Subspiet. ecep~thy. N1U1C R
The revvise d NCR was approved I y NEP irall'1h ,[trIr t ,,It
Maarch 21, 1985, and the FF/ER was aofirv t 'i1.1, 1i [ ..
1985, and transmi t ted to SQ'N. :, Ihsi.i yert y, .h,iFE/ER (Rev is ior: I) was rt'c ivvd Ihv thI' I ;itI', v 'v I t' ,,,.
and an SER pr e.pared. Norma , t (7. r, I I Fi..f:requi res further eva luat iin to tVet, •,tv 1 .1 1Ihf.-'r Iwill become a Category I or III withitn .t') iddti t ,,jiit(lays. llowever, the four utqua I i I ed .,xh,,r. IWAMI C It.
were replaced on or abotit April I with ri tn p r,':; ,i 'transmitters that had bet'ti dtemonstratedi by t .s;t to t. h v,.
adequate a c cura'Cies accel tabIhle I(;r iist' fr t hit lipI i-
cat. ion. The process usel to replacv I ht' t rI :;nitm I I ,i:is discussed in section IV.G of this re-port
K. Past Identi fied Problems Associattid With the NNCRI Prot s:;
NSRS reviewed TVA memorindtims and rt-pttrts front iijill .. 11it , .groups and the NRC that were associatetd with II) ()Ili(*. * irieering Design and Construiction (O'DC), (IE, andi Ni:: l .N if .grams . These documents were rev i. ewed to d(, t, c rmill , ti c p , w.identified with the program prior to jit n ;t ioJ ofi I ) lie Ni'}?SQNNEB8501. The following is a discussion of the restilt.; Al ii.,t
review:
I. Office of Engi neerin_. l)esig•nr arid Ct... t.,str. .i: , (t(lIlM). 1• ., (It. ,Memo.rand•ns Act ion P. Ians/Po I icy .iLrec t iv's
Ten OEDC/OE documents issued i f rom 1980I - ;i l , 1 .f.c I re . .VI. F.38-47) were reviewed by NSRS. T'hese ,, (,,it,-tieed the inability or actions taken tLi irnptovi. Itol i .1l, t v ,,IOE ()EDC) or TVA to itihnt i tfy, reprtrt , ,tt, ii,,i.'t, ;tiii i.,,i;
through to completion in a timely hIshior at t I,,)I ts ( ti tI
conditions adverse to qualI ity. Melrr. se t ic~nl ly, tr ,doctiments addressed the fol lowing:
'flith importance of timel iness and .it't'l v I,' ir tI' t I It -
cation and reporting of NCRs.
o Timel iness and thoroughness ifn iriille),Irc it.-1 1 , I , r, 10I t l"II,.
actions and documentin g or report. irng ,,1 NiCR!.
o TVA's failure to properl y anrd pr,milt.l y re sp,),onI 4 ,
identified problems.
o Improvements in the system to taci I tate thlie t imel inss
of preparing and transnitting FE/ERs.
Of f i C e of fqu.al." I __t-ssurance (.OQA)
Three OQA audits of design control act Lvi tv rI that l-rcconducted in 1983 and 1984 were rev iewel (reIt s.rni's VI I). ,
32
2, and 4). As a result of L it' .,udits, thei, wcrt i m y,:;an11d deficiencies relating to the OE NCR p ro .:;:; repcrted t l ' yOQA to OE management. Examples ,fi thos," I indin rgs anld h-,I ' -
1Ielnc I e w•re fill fill 41W14 :
NEB Was It l, rorv'ssinig N(36, ii . 'a t t,, 1-' 1
The auditors rec.omirniled th,!t. NEB devn, ., i t I.'
track and cont rol Ltfe NCR pro e.'v !.; tic toli:, that i ,,requirements were met (defi c ienry N,. cf And1it r ',-;
March 24, 1983).
0 The Civil Engineering Branch ((:EIB) was nJt Ir,,
NCRs in accordance with EP 1. ,.' . l Ih -a llttors ,.,n
mended Lhat CEB1 develop a system tL track Lth, st:,tt.: of
the work, document tlhe appropriate iiiloma i•nl ,i it i toriginal NCR form, ard fol low tLiJ each of these 1(tlIv-ities to ensure that they were (:orpii c.tel in Lii t iriw
period speci fied in El' 1 .26 H (,lic ieo cy N•. cit ,\I A lID83-3, March 25, 1983).
The timeframe spec i [f ed ' ",' 1. 2 fi ,r -,t ,.n icll'
sigrii f icance was riot being adhered ti l y th'i ,it- I' l'if,1
D)esign Project (deit! ciency No. 4 .I Aciid 1 t -r P ,March 23, 1983). The auditors, re c'. rilliecl e, I 1-1l ,h t thL hproject initiate a training session to lamir i.ziii i i aIIsupervisors with the specific requirements (tf .P I 10.
NCRs originated by NEB revealed several instances whi,.,,
the eight-ca lenda r-day I imri tat ion for dete rmi 1i1n rg
significance was exceeded ( identified as ai1 a rea tI.inprovement in Audit DSI-A-84-0006, .July 3, 1
3. NUC PR Nuclear Safety_Sta.f.(NSS)
At meeting No. 64 of the Sequoyah Nucl :ii SraItty ]rvi 'WBoard (S-NSRB) a concern was raised reardinii tlie ahl,.,i, it varid timeliness of evaluation and disposition of EN I0IKS-
identified design deficiencies documented iri NCRs. fhi. NSSrivnst i gated the di spos ition arid corrent i on •f two) SQN N•1 ..
The results of that investigation wer, reprt.ed to NWi t'Imanagement in Jrily 1984. The NSS iden itified ori ,etecitC iii
and several areas of neilede iniprovement whi cIt inI , ii,,:
Centralizing responsibility and authority for resolii-
tion, tracking, and timely closeoutt for all NCRs asso -iated with a given plant. This action was h,. i,,v,.i,
necessary to improve the timeliness of closeout.
o Procedures should he assessed in order to reduce th,
time between initiation of Category 11 NCRs and pilaint
evaluation on plant safety and reportahility (.,!.g.20-day timeframe for reevaluation for category 11FE/ERs).
'33
Proced tre revisions shou|lo Id be coordot i l t .t) lit-, wi•. -1.
anid NUC PH to reso I v v p rocehl'tia I inlt ( s istin I-..
The NSS recommended that NUC PR assign ain imlivilltal ,,coordinate resolution of these issues with NSS al d ifi, i.staffs. An individual was aplpointed and ,:agre,:iwt.ft ,.:
reached (on November 30, 1984) on procedumr;aI ct itg.:, Ilit .,
would be drafted and coordinated with t.hti ' ik.ati :;v 1 I IHowever, the work was not accompl ished hve,.,,:.c u t hirin;4 iiresponsibilities during the TVA reorgan iz.,t ioll i-I f(,rl
4. Joint Qualit. yAssurance Audits
A joint audit (Audit No. JA8000-13) of tih' EN iE ") niF ,NUC PH program for 'DeHign Control for Mohii iij,'it mri: ii, N'isfill SON" witi cotoilis trd by ailidtI tr II i ,f I 'KN DE•i"; #, NI( hIl' f,Dlec.mher 19'j , Fninling< No, (H I from that ;tiol i i ,hi-iiit I .,Ithat there were no cuil I Ity itiniraitsrc (QJA) Ilp 1 .1ii ,e wiu i IiIet I ineated authori Lyt , and respons ibi I it i cs am;i,, TVA I I v I -sions prescribing nonconfzormance act iv ti•t ,. I t V..s I.Iidentified that divis.ional procedtres presi r i ing iio,, .,i,.activities between divisions relative to the-. o rl •,nl ,,system had not. been ap|trovev d by OA mall ,r rgi t th0 tll,,. IPower (POWER) and OEIMC. This finding is !"t.11l ,,I,,'I .1111,.four years.
NRC-Identified Problems
In NRC OI&E report No. 50-327/84-38 anld 5{)- i28/84- J8 1il1on February 13, 1985, th- NRC issujed a uvwr I I,'violation to SQN because a potent ial non conomrir e o,, ",ll -I II
ing postaccident radiation monitors which was ideilt If id IliNovember 20, 1984, and not promptly docuinenmt-., hy (.F. 1,nonconformance was docrunented by OE 16 days after ident tII -
cation. It was noted by NRC that once the respon,;II, I ,organization in NUC PR was notified, the nonconform;incte wi:;
corrected on the same day.
NRC interviews with OE employees and manager rrsplonr•illfor NCR determinations indiLated that it was clommoln pyatt iio.to allow 5-7 days and in some cases months behne a tiscrclr-ancy was documented. The NRC report altio inrdic'atv.dt th;at (Il
managers interviewed were not familiar with the lil. initi ill
of "significant conditions adverse to qual ity" which wl.i;defined by EP 1.26 and misinterpreted ste'ps which allow idays to write an NCR to a I low 5 (lays. The NRC indidcaote,that the management controls gcverning the ideiatificatLhn,
prompt evaluation, and processing of nonconformatice( wei-cnot effective.
TVA responded to the NRC violation off March 1i, 98•5 I,reference VI.E.1l), stating that the violation resuiltt'd 1rl,1,a lack of management control which did nut ensure the tI ilvivreporting of the potential nonconformance and a lack oI OFE
34
'•., i - r:: ii•. ,,• •,•:
employee'-awareness..of the process as pres cribed by El' I.
The corrective actions thnt were specifie to avoid fitrthr
violations.'inv6lved 'providing instru'rt6i` on the t i,neli,,.,;,s
ot report ing pVotent ial ,nnonom
G. Muodifications'to Install New PTarton CPdts-atSQN,-
QE informed N1JC PR engineers that fully qualifie'd 'Barton pr.-ss,,,,
transmitters (independent of similarity"analy1i• )...had .behn c in -
cured for'WBN and were available for .sQN ThW transmit"ers
were obtained from WBN and an Engineering IChange',*Notice (ECN) was
prepared' (see, ieferencei.VI.F.28). The 'four.mnewt ansmitters were
calibrated and time-'response checked. The four Foxboro PAM C11,lts
(two on each ,unit)',were -replaced with'Ahc" new.- Barton trans-
mitters. . After installation the Barton CPdHts-wre functionallytested to assu..'e operability. The old transmitte'rs were s.ca.3ed-1 to 15 lb/inig. The new Bartons were scaled.,ItO 17 lb/in g,which required,`a rescaling of the instrumenti.:loops and replace-ment'of the sca'les on the control room indicators.'. This work wascompleted in early April 1985.
The formal environmental. qualification documentation had been,prepared (EQS,i Draft, Revision 6) and., was'i .ti"' the review andapproval vycle s ' NofMay 7, 1985.-_ The.;newJBarton transmitter.;are qualified`lto' provide -a 7 percent, accuracy .ilnthe followingenvironmental onditions: 4R
Temperature -(OF) . . . 420Humidity (percent). 00
Pressure (lb/in g). 57..,..o Radiation (rads)' 6.8 ..x. ... ( er a 40-ye;,r
'. ' •. ... ' • • period)...: • <.
Chemical spray (ppm/boron) 2500.Ph 10.7!.',,.Operatingttime (accident) 4 months .
Based upon OEjI analysis the new Bar on ..transmitters are ItIlyqualified 'for i8.4 years plus. at least. 100. days'at, the postilatedDBA condition, .. ",
LIST OF PERSONNEL CONTACTED
A. Industry :. ... '
1. R. B., Milern (telecon) W" ..ing...
.. Office of Engineering -
1. F. G. Beasley OE QMs-2. A. -P. BNaEco'. .B .Knoxv 1.l .3. V. A.< Bianco", -" NEB - SQN i
4. J.. S. ColIley OE M5. J. F. CoXI "NEB Knoxville-.,'6. W.ý L.- ElIl1io '" NEll Kno x VAll1e',ý7. NathanielFoster " ' ' CEB-.'Knoxville:'
. .' , -•.* '.. ,.'3• , , " ... . . .. ...3..,5.•.
-I.- W. 37 0 , M - - . ý WT M- C I I I 1 1 1 "fF ý_, _ . 11
-Ji . '~~. , . :• • .'" .
8. P. 'G.-, loann'ides , NEB :Knoxville9. H.: L'.. Johes ,, NEB -Knoxville
10. R. S."'Ný cKeehan.'- ... NEB .'..'Knoxville11. P. D.:. Metcalf . .'.,,NEB -'Knoxvil le12. J. E. Staub ,. OE -SQN Y•13. E. R.,Ta ylor NEB Knoxville:14. D. L.' Wiilliams, Jr. NEB "Knoxville
C. Office of Nuclear Power
1. H. L. Abercrombie SQN2. C. R; ,Brimer SQN3. C. E.. Chmielewski (telecon) NSS Chattanooga4. J. P., Dalrling (telecon) ManagersOffice - Chatt;,inooga5. R. K. Glladrey " SQN6. G. W. Killi'an DQA- Chattanooga7. G. B. Kirk SQN8. J. E.,Law ,'DQA -,,'ýChatttanAooga9. D. Eý McCloud DQA -Chattanooga
10. R. L. loore',' - .DQA '-Chattanooga11. J. H. Sullivan* SQN , .12. P. R. Waillace SQN
1) Office of quality Assurance
1. J. A. McDonald QIB Kno6xvtille
VI. REFERENCES (DOCUMENTS REVIEWED)
A. Regulatory '
I. Code of ;Federal Regulations, IOCFR Pirtt 5 'cLicensing of Productive and Utilizati6n Facilities,"January 1, 1984 . ..
a. -OCFR5O.49, "Environmental Qualification of Electri,Equipment Important to SafetyJfor' Nuclear Power Plants"
.,.. ';• < , .. , ,I:,. . .:..,S:i$.',•i" '-•: ,< •
b. •'Appendxi A, -!'General Design Criteria, for Nuclear Power
c. Appendix B,ý "Quality Assnrance:Criteria for Nuclear.. Power Plants and Fuel Reprocessing;Plants"
2. Regulatory*'Guide 1.89, "Qualificati6on bO"fGC a'ss AE Equipmentfor-Nuclear Power.Plants," Novebmer:.1974.Y
3. Regulatory Guide 1.97, "Instrumentation&for Light-Water-Cooled Nuclear Power Plants toAssess,,Plant ,ConditionsDuring aind Following an Accident,"',December 21975
4. IE Bulletinl'No :7901B, "Environm'enftal" Qua1ifi , cat•, on ofClass 1E equipment, Jaruary 14, 1980 ,
36' ' " 2'r.:4 , '
-,",',"•.k" ~~~ ~ ~ ~~'.: " . :,,: . ,-,,,.
, . ..; '• ; ',• "• .' ? .' -U '. :• ••. Z.
.5 NUREG-0588, "Interim Staff Positior, on Frilonmen: IrQualifica'tion of Safety-Related Electrli'lVEqiipment,Revision I, July 1981 .
6. Regulatory Guide 1.89, "Environmental Qualification qtCertain E'lectrical Equipment Important to.Safety forNuclear Power Plants," June 1984
7. N`RC Report Nos. 50-259/83-53, 50-260/83-5'3z,;53-296/83-53,50-327/83-27, 50-328/83-27, 50-390/83-49-50-391/83-38,50-438/83-30, and.50-439/83-30 dated>Jant|ary.,16, 1984
8. NRC Report Nos. 50-327/84-38 and 50-328/84-38 dated Febru-ary 13,JI985
•9. NRC Report Nos. 50-259/85-03, 50-260/85-03, .50-296/85-03,50-327/85-04, 50-328/85-04, 59-390/85-06;,50-391/85-06,50-438/85-03, and 50-439/85-03 dated.March.25, 1985
10. NRC Reportt Nos. 50-327/84-38 and 50-328/84-38 dated March 21.",1985 (A02 850403 023)
11. Letter from Elinor G. Adensam, NRC, to.H; G. Parris,"Environmental Qualification of Foxboro. Pressure Trarns-mitter Model E11GM (Non-MCA).for Sequoyah-Nuclear Plant,"dated April , 4 1985
Industry ,, . ...
1. Westinghouse Exhibit D to Contract No.:,•68C31-91934, "PlarntTechnical Description of Nuclear Steam Supply System forTennessee Valley Authority Sequoyah NuclearPlant - Conu:ep)-tual Design of Ice Condenser Reactor Containment System,"October 1968
2. IEEE Trial-Use Standard: "General Guide fo'r QualifyingC1ass 1.-Electric Equipment for Nuclear PowerGeneratingStations,.'"' IEEE Standard No. 323,- April.ý,l971,.
3. Westinghouse .WCAP-7744, "Topical Report'>iEnvironmen talTesting o6f.Engineering Safety Featuresi.Reilated Equipment,"August, 1971 ... . ,
4. Westinghouse Equipment Specificat ion,677462,: Revision 1,"Sequoyah Nuclear Generating Station Uniits" Il'and 2 - Pro-essInstrumentation and Control Equipment %and, System Design,"Novemberi 12, 1971 . ,
5. Westingholuse Quality Release PackageNiimb"rSQR-50141, "FieldMTD Equipment,.Primarily Transmitters".--February 9, 1972
6. Foxboro Instruction Letter SI-1-00209',."Models Eli and E13Pressure::.Transmitters Modified For MaximumCredible AccidenL(MCA) Pressure and Temperature Requirements," .November 1973
-, /...'•/. . -I. ,.,.•,,'
37.9. . -, .W"., $
7. Foxboro :lnst.ruction Letter MI 20-215, .,"Model K I HG rl re;g , ,.
Transmitter, " October 1971
8. estinghouse WCAP-8541, "Topical Report .=Seisw i c andEnvironriiental Testing of Foxhoro Transmi'Itiers;' July IJ7,
9. ChicagollBridge and Iron Company, "Overload Pressure i'estand Iniiial Leakage Rate Test - Sequoyah:Nuclear PlantUnit No~i I Containment Vessel," test conducted February 19/'6
10. Westingh~ouse, "Specifications for Force Balance PressureTransmitters - Spec. Sheet 9.01," AugustK4', 1917
11. IEEE Standard for "Qualifying Class AE Equipment for Nu('(Ir,
Power Generating Stations," IEEE Standard 323, February 1914
C. Nuclear Safe .yReview Staff . ,, .
1. Memorandum from K. W. Whi t.tt to R. W. Catii t l 'I itlI 1. 1'.Darling! "Nuclear Safety Review Staff. (NSRS) Speci;a Revii-wof the Office'of Engineering (OE) and Office of NuciearPower (NUC PR) Corrective Action Systems - NSRS Report No.R-85-08-'OE/NUC PR," April 2, 1985 .(QOI 850402 051)
). Office of Quality Assurance-
1. Memorandum from J. W. Anderson to M. N".Sprouse, "AuditD83-3,1 Design Change Control and Deviation Control -Deficiency Nos..1 and 3," July 21, 1983,,,(0QA 830721 504)
2. Memorandum from J. W. Anderson to M. N.'.Sprouse, "AuditD83-4, Design Change Control and Deviation-Control -Deficiency No. 3," July 21, 1983 (OQA 830721 501)
3. OQA Audit Number D20-A-84-0002, "Design Control - QualityAssurance Program and Organization,",November 14-December 2,1983 (OQA 850104 513)
4. OQA Aud!it Number D51-A-84-0006, "Program Management andDesign Control Activities Associated with"DisciplineStaffing Revision of Major Procedures, ' Ju~ne. 18-July 10,1984 .(OQA 840801 503) :
5. OQA Aud;it Number JA-8300-O1, "Equipment"Turnover and Conli g-uration Control,"June 10, 1983 (OQAI:-,Z30613 703)
E. Office of Nuclear Power
1. Memorandum from H. J. Green to M. N` Spr'ouse, "SequoyahNuclear'ýPlants Units I and 2 - Nonconformance Report (NCR)SQNQAB8I04 - Failure to Provide Inspection Requirements onDocumen'ted Inspection on Piping Insulation," July 29, 1982(DES 82,0802 001)
382 • , -..• ,:•6 .r'r:•.7•?•".•.•,;"•'~~~
~ ~ ~ ~ ~ 5.•.;• .•7o! .. . " ,. . ..- t .• / • •
4 4 .. . , : . •:.:',
2. memorandum f`"rom H. J. Green to M. N.``Slprrous6',- "Browt•s Feiryand:Se'quoyah Nuclear.Plants - Nonconf orma'r• Reports (01l.s',"August 4, ý1983 (DES 830805 025) ......
3. Memorandum' from James P. Darling, "Seqiuoyah' (SQN) awl ,,,ir;Ferry (BFN) Nuclear Plants - Handling-of Nonconformanc(Reports (NCR)," June 26, 1934 (DES 840627.009)
4. Area Plan, Procedure No. 0604.01, "HandiingOf Nuncunl:"rman'Reports oh Operating Units," July 26, -. 1984"..'.
5. Memorandum from F. A. Szczepanski toH. L-:i.Abercrombie,"Nonconformance Reports," July 31, 1984.-(A43 840803 002)
6. Nuclear Safety Staff Report 84-05, "Investigation of Noj,-on-formance Report Processing System - Sequoyah Nuclear Plant,"July 1984 (A43 840803 001)
7. Memorandum from If. L. Abercrombie to F. .A..Szczepanski,"Nonconformance Reports," September 17; 1984 (A27 840828 Olt,
8. Memorandufll from F. A. Szczepanski tv-James' P. l)arling,Nuclear Safety Review Board's Annual, Report .for 1984,"(L42 850329 801)
9. Memorandum from G. W. Killian to W. T.'Cottle and R. J.Mullin, "Transmittal of QAB Audit Report No,. QWB-8-85-0oo0),'Ape!i1.5 j1985 (L17 850405 800) .
10. Memorandumn from James E. Law to G. W. Killian, "Correctiv.Action Response to JA-8000-13, Finding .0-1", December II1984 (L146. 841217 953) .
11. Letter frmJ. A. Domer to Dr. J. Nelson'Grace, NRC,"Response!.= NRC-OlE Inspection Report' Nos;. 50-327/84-38 jnri50-328/84 38,!' March 15, 1985 (L44,850315.808)
12. Letter from d. A. Domer to E. Adensam -. NRC;'"Nonconform-ance Report' (NCR) SQNNEB8501 Chronology' of,.Events," April 2,1985 .,(L44, 850402 807) .
13. Letter. from J. A. Domer to Harold R. Denton ,"(,RC, "Environ-mental Qualification of Foxboro Pressure Transmitter ModelEIIGM.(Non-MCA) for Sequoyah Nucler.Plant,.";,April 8, 1985
14. Letter, fr -:J,'W.., llufham to Dr. J.-Ne son':Graice, NRC, "WattsBar Nicleý'r,1Plant Units I and 2 - Environmental Qualific'=-tion of Elec'trical Equipment (NUREG-0588):-., WBRD-50-390/81-0f,WBRD-50-3091/81-62 - Final Report" ý.(L44'.850430 805)
15. Memorandutm from I. B. Rankin to J.'P-,ýVifneyard. "SequoyahNuclear Plant.- Nonconformance Report.',(NCR :SQNNEB8501,"March 22p:' 1985 (SO1 850321 941).rV
2,.: t2 ~:4 4 :r4
,A.4. '•
. :• • -' !/ •,; ,,.'. , • -. ,' " :: ' "''- •A
W
16. Memorandum from P. R. Wallace to C.. R. "Brimer, "Sc"quoythNuclear Plant - Nonconformance Report (NCR) Number SQNNEIB8501 RI ••-Containment Pressure Postaccident MonitoringAccuracy,'". April 10, 1985 (S53 850408 804).
17. SQN Unit'I and Unit 2 Technical. Spelcifi ca-ioti, Se.ctionls3.3.3.7/4.3.3.7, "Accident Monitoring Instrumentation"
18. SQN FSAR:Section 3.3, "Wind and Tornado. oadingsSection 3.8, "Design of Category .I- Structures'Section 3.11, "Environmental Design of Mechanical and
Electrical Equipment!,.'Section 6.2, "Containment Systems"'"''" Seqtion 7.5, ."Safety-Related Display Instrumentation"
19. SQN Statidarid Practice SQA1lS, "Handling of:'Nonconforman•cReports,'" Revision 1, July 10, 1984:...:,.
20. SQN Surveillance Instruction SI-3,' "Dai]y,."Weekly, andMonthly Logs," Revision 44, April 2, .1985
21. SQN Surveillance Instruction SI-98.3,`",,Ch-ahnel Calibrati,,nfor Engineered Safety Feature Instrumentation (ContainmentPressure/Turbine Impulse PVessure) (Refueling Outage),".Revison!O,.August 23, 1984
22. SQN Surveillance Instruction SI-70, !"Channel Calibration ofPost-Accident (Instrumentation) (Refueling Cycle)," Revision 8,April 23, .1984
23. SQN.Instrument Maintenance Instruction -IMI-99, "ReactorProtection System - CC16.5A - Online Channel. Calibration ofContainment Pressure Channel I, P-30-451 (P-937)," Revision, 4Ap r i ,,:3 •7.19 85, -. :::: i. . , JJ :i( J. :•, j :
24. SQN .instrimenten aintenance lnstructiorj-135, "Maifte,,,ii,,Guidelines .. for Class: lE Instrumentatlon",llarsh Device,"Revision:41` December 26, 1984. <.. ,; i.
25. SQN.IMI-135, Completed Data Sheets .for"Pdt-30-44 and -45,dated November 29, 1984 . .
26. SQN SQA1 18, Attachment 3, "NCR Status Sheet," dated March 26,1985 . . .. -
27. SQN SQA I8 •Attachment 1, "Nonconforýa'nai'ce Report Disipositi,,onRecord,ýheet,", completed April 10, 1985•,.-.
28. SQN SQA118, Attachment 2, "Safety Evaluation," completedMarch 27 j_1985
29. SQN Monthly. Report to NRC, March i985 . ,
*. 40
J ,!, ',
* " :' •i ,' i•... .
4X 4
30. SQN,;. "Management Action Tracking Sys "eri pt/Updait Form,"
Apri 1.5-r 11, 1985-
31. SQN.Computer. Printout, "Action Items',April 10, 198¶
32. SQN SI-98 completed data sheets, September 1979-January 1980
33. SQN IMI,-99 completed data sheets, Septemte r 1919-Octob,.r l10N,,
34. SQN Maintenance Requests (MRs): : -M.. 21631, March 11, 1979 ' -
MR, 21656, March 12, 1979MR 116883, July 26, 1981MRf 167135, August 27, 1981MR! 162025, August 8, 1981MH 162267, September 30, 1981"`..:1KRi 177531, August 30, 1981MR, 165575, September 24, 1981 ':.
MRk: A-015914, March 15, 1982MR A-015915, March 15, 1982M •:A-302175, December 15, 19841T A-'292770, March 30, 1985 :'.J7:-?;MRý A-292769, March 30, 1985KR A-292768, March 30, 1985MR A-292771, March 30, 1985
35. SQN ln!;trument Maintenance Calibration.Cards for Pdt-30-44,-45, March,1978-April 1, 1985 V
36. Memorandum from W. T. Cottle to G..W. Killiai,, "Watt. BarNuclearý Plant (WBN) - QAB Audit Report:Number QWB-A-85-0009,Correction of Deficiencies," May 6, 1985'.
37. SQN AI`19 completed Attachments I and"2.'"for Workplan No.11554,!"March 30-April 9, 1985
F. Office of Engineering (OE, EN DES, OED0 Purchasing
1. TVA Invitation, Bid, and Acceptance,',"'N~ii`16ar Steam SupplySystems for Undetermined Nuclear Plants,-! TVA referencteNo.'69C31-91934, Contract Date April 26,i 1968.
2. SQN "Containment Vessels Design Criteria:'. SQN-DC-2.3,"July I•' 1969
3. Memorandum from M. N. Sprouse to Those'-'.listed, "Electric;alEquipment Environmental Qualification Report for SequoyahNuclear Plant Unit 1 - Preparation and.Handling," November ),1980. (EEB 801110 936)
4. OEDC a•dPOWER Joint Quality Assurance",Audit No. JAO00-1.),"Design Control for Modifications-.BFN and SQN," January 9,1981
, 41
7,477, 7ý,
5. MemorandumI from HM N. Sprouse to Those listed, "SetuoyahNuclear Plant - NUREG-0588 - Revision of the Program Planfor the Preparation and Handling of the Electrical EquipmintEnvironmental Qualification Report (EEEQR) for NRC," May .91981 (EEBI810528 904)
6. Memorandum-,from E. Gray Beasley to Those listed, "Audit/NCR/S0.55(e) Reports - QA Review and Interface," January 29,1982 (QAI 820201 002) "
7. Memorandum' from R. A. Cost.ner to J. A.' Raulston, "EN DES -EP 1.48'- Evaluation of Deficient Conditions In an Operat itngPlant," JUl,- 28, 1982 (QAS 820628 008); .'
8. Joint Quality Assurance Finding Sheer'A2, Audit JA-8200-08,"SQN Procedure Review," September 7, 1982',
9. Joint Quality Assurance Auidit Report,' Audit No. JA8100-00,"Design Control for Modifications of Operating Plants -BFN and SQN", January 28, 1982 (QAM 820127,,002)
10. Joint Quality Assurance Audit Report, Audit. No.. JA 8200-04,"EquipmentTurnover and Configuration Control," October 20,1982
11. OQA Audit D83-3, "Design Change Control and'DeviationControl, "April 27, 1983 (OQA 830428 500)
12. Memorandum from M. N. Sprouse to J. W Atiderson, "AuditD83-3 -Design Change Control and Deviation:Control," May 21,1983 (ESB 830527 004)
13. SQN "General Design Criteria for Environme'ntal Design No.SQN-DC-V-21.0," Revision 1, December 1, 1983j!.
14. Memorandum from J. A. Raulston to L.. J; Cooney,. "Auditsand Review. of EN DES - Revised Corrective. Action CompletionSchedules for Open Deficiencies," Octoher1, "; 1983 (NEfH 811004,253) .
15. Audit No'. D83-3 - Deficiency No. 4, "Deviation Control,"March 25,, 1983
16. EN DES-EP 1,.48, "Preparation of Failure Evaluations/Engineer-ing Reports fo Deficient Conditions for Operating NurlarPlants,". Rvision 1, April 26, 1984
17. EN DES EP 1.26, "Nonconformances - Reportingand Handling byEN DES," Revision 8, June 28, 1984 ; jI[,y:;
18. EN DES-SEPA2-11, "Electrical Equipment Qualffication Report
for Sequoyah.Nuclear Plant Units 1 and 2 -, Preparation andllandling,"IýRevision 0,'August 1, 1984
42.,
wk
* 1~. ,,
* I
19. Memorandumt from J. A. Raulston to R. C.L heir, "hatts liel,Nuclear Pliant Units I and 2 -Noncornforneari e tp,,rts I(NCVt•.WIBNNEB8415i and WBNNER8416," November 14 1984 (NEH $411114256) *
20. "Class IE ,SQN. Equipment List Outs ideI t Coiltain 'ntnivt t ,ish
Environment)," October 3, 1984
21. NCR-FE/FRd (Significant/SQN) October 1984-April 198K ('21NCRs, see Table 2 of report)
22. Memorandum from J. A. RaulIston t~o Those listed, "Watt:; B.-1rNuclear Pi'ant Units 1, 2, and 3 - Nonconformance' Report (NC1,
WBNNEI1841ý,'.' January 15, 1985 (NEB 850315' 276)
23. Memorandum from R. T. Holliday to R. R. Campbell, Se~qrry.,hlNCR SQNNEB850I which pertains to "Contaiitment Pre:sear,Monitoring Accuracy Less than FSAR Says,'.'JFebruary I, 1'9W)
24. NCR-FE/ER 'No. SQNNEB8501-RO, "Containment Pressure. Moni, .Accuracy Less than FSAR Says," March 5, .1985.
25. Memorandum from J. A. Raulst.on to Those Iis+ted, "Watts 1h.,Nuclear Plant units I and 2 - Nonconformance Report (N(k)WBNNEB8415 RI," March 12, 1985 (145 850'1.12 2,41
26. Memorandum from J. P. Vineyard to H. B. Rankin, "SequyathNuclear Plant Units I and 2 - NRC-OIE Inspection Report50-327/84i38 and 50-328/84-38-OE's Response', to Violation,"March 13,11985 (B45 850313 264)
21. Telecon Notes (V. A. Bianco), March 14,- 1985:,
28. Engineering.Change Notice, ECN No. L6369, Martch 21, 198'i
29. NCR-FE/ER!No. SQNNEB8501 RI, "Containment Pressure 'ost.t(i i,,ntMonitoring Accuracy," March 22, 1985
30. Memorandum from E. Gray Beasley to J. A. Raulston, "0tI, i ,,PEngineering (OE) Qality Management Staff (QMS) Audit. K'"- 1',Nuclear Engineering Branch Staff," March 28,; 1985 (111o) 8,T)h .'8006)
:1. Draft OE Procedure OEP-i4, "Licensing"
32. Draft OE Orocedure OEP-17, "Corrective.Action"
33. TVA Drawing 47E235-47, RI, "Environmental Data Enviroann,.iiHarsh Annulus Area," May 18, 1983 .. ."
34. SQN Unitsl1 and 2, "Electrical EquipmentCEnivrronmentalQualification Report in Accordance with NUREG-0583"
35. SQN "Steel Containment Pressure Capacityc Analysis," DrafIt
* 43
~-Jt.
. .............
36. Individual Biweekly Time Reports (OE personnel), October1984-March 1985,
37. SQN Equipment Qualification Sheet (EQS)'SQN-NEB-30-26, RO-t.5,(Draft R6), 1982-1985
38. Memorandum from G. H. Kimmons-to Those listed, "All Nucl,;,rPlants -• Timeliness in and Reporting of Nonconformar'ces,"Septembe'r 3, 1980 (EDC 800904 017)
39. Memorandum from N. N. Sprouse to G. H. Kimmons, "OU)EC 1982Action PJlan for Quality Improvement," December 30, 1981(QAS 811•230 002)
40. Memorand:um from G. If. gimmons to if. H. Null and M. N. Sprow;v,"All Nuclear Plants - Timeliness and Responsiveness inResolving and Reporting Conditions Adverse to Quality,"July 21, 1982 (EDC 820721 003)
41. Memorandum from G. H. Kimmons to H. H. Null and M. N. SprouSC,"All Nuclear Plants - Lack of Timelinesss," December 1, 1982(EDC 821201 001)
42. Memorandum from N. N. Sprouse to G. H. Kimmons, "All Nu(It-aiPlants Lack of Timeliness," December 15, 1982 (NEB 8212h1253)
43. Memorandum from R. W. Cantrell to D. R. ,'Patterson, '"Timeltr.s:;and Responsiveness - June 9, 1983, Meeting with Elev(tricalEngineering Support Branch - Response to Action ItemsAssigned to the Nuclear Engineering Support Branch," July 22,1983 (kEB 830722 292)
44. Memorandum from G. H. Kimmons to C. Bonine and M. N. Sprouse-,"All TVA Nuclear Plants - Timeliness and Responsiveness:Summary of the May 25, 1983, Meeting Among TVA's Office otQualityAssurance (OQA) and Other TVA Representatives withNRC-OIEýRegion 11 Management," August ,1i, 1983 (EDC 83081r, ill)
45. Memorandum from*E. Gray Beasley to G.-H. :Kimmons, "All Nu.cle,.rPlants + OEDC 1982 QA Action Plani" February 17, 1984(EDC 840217 002)
46. Memorandum from R. W. Cantrell to J. A. Coffey, "Transmittalof Failure Evaluations/Engineering Reports of DeficientConditions for Operating Plants," March,22, 1984 (NER 840322260)
47. Memorandum from J. P. Vineyard to all Sequoyah EngineerinygProjectiEmployees, "Timeliness arid Responsiveness - ConditioitsAffecting Quality," April 9, 1985; (B25 850409 001)
48. Memorandum from R. W. Cantrell to All.Office of Engineer .rigEmployees, dated August 21, 1984,,"All Projects - QualityPolicy"ý (DES 840821 017)
-v44I 1'111 1 11111
[ABlEI.'
Summary of SQN Norm al perational and Postaccidviit
Environmental Conditions in the Annulus Region (Note 1)
OperationalCondition
,.,- Normal Day...
PressureExternal
Slightly below-atmospheric pressure(-5 inches of water)
PeakTemperature
(OF)
120....
PeakHumidity
(M)
. . .... 98
RadiatiosiDose
(Rads)
5 x o ...(Note 3)
5 x 101
(Note 4)
FSARSource
- ,-Table 3.11.2-I- -,I-(
LOCA, HotDay
Slightly belowatmospheric pressure(-0.5 inches of water)
150(Note 2)
100 Table 3.11.2-1
Note I
•NoteL 2:?
The environmental conditions inqualified to function are basedThe LOCA is the most severe forthis table.ý The PAM CPdts must.
the annulus region for which the PAM CPdts must beupon the LOCA and the High Energy Line. Break (HELB).the annulus region and is the accident discussed infunction for 100 days following the LOCA.
See Figure 5 of.-this report for a graphic illustration of annulus region temperatureresponse to a worse case LOCA. *Following the LOCA 150°F-is reached in 5 minutes,remains at that temperature for approximately 30 hours, and decreases back to 105OFin approximately 30 days.
r . ;, ( .
Note 3: Yearly dose based on dose rate of 5 x F,) mrads~hour during operation (from Table 3.11.2of the EEEQR).
Note 4 - This is a one-year -nt eg rat.,., ,lost- .,ft :- a 1.OCA A n,les n,?t inciuole the 40-vear norm.11life integrated do:..
l Ail.L "
SUVRAHY OF SQ- " NC R-FE'ERS PREPAREID UK Hkj.V ot MA---fROM OCT6WiE IF) A THROUGH MIARC1! 1985 (NOU- I
Days From NCR PreparationUntil Determined Significant
(8 Calendar Days laximumAllowed per EP 1.26. R8
Days From Significance (Note
Determination Until FailureEvaluation Engineering
Report (FE/ER) Issued(r%*lS Days Allowed)
OriginatingOrganization NCR Number
i. EEB SQNUEB8409
2. FEB SQNEEB8410 (RI)3. EEB SQNEEB84114. FEB SQNEEB84125. EEB SQNEEB8501 (RI)6. EEB SQKEEB85027. LEB SQNE.EB85048. MEB SQN.N1EB8408 (RI)9. MEB SQNIE88409
10. MEB SQNI1B841011. MIEB SQNME841312. CEB SQNCEB8403 (RI)13. CE- GENCEB840614.. CEBU " GENCEB840715.ýý CEB" SQNCEB841516.- C:.EB. SQNCEBS50117.' NEB SQM-EB8405 (RI)18. NEB SQN-NEB840619. NED SQMNB84C720. NEB SQNNEB840821. NEB SQNNEB8501 (RI)22. NE. SQNN'EB850223. NEB SQ'KNEB8503 (RI)
T TimeLimits
FE/ER ExceededCategory (YES or NO).
Designation NCR FE/ER
I N: - Ys -e
1II1 No No
No signed date (initialed on9-27-84)
75
10I
N/A (upgraded
900'00
to significant)3S
134175
26
13634018402559421013204694102416613364
*)*
23
IIII11IIIII
111IIIIII
.1IIIII'.1'1I
iiiIllII
Ii
NoYesNoNoYesNoNoNoNoN/ANoNoYesNoYesNoNo0NoYesYes
YesYesYesYesYesYesYes
NoNo
YesYes
-Yes.
YesYesYesYesYsNo
YesYs
12131
C)1"'• ; I " T 1-F I. TIS (I•Note ri. Di,,s not tn lu.1e Rv:-;t,,i , 1 \ . .'.' llig,.
Note 2. I-t.ilt-ndar i|av guirtel , in.- ii l ! from reit y ,.:. i.
(ittry. s1ginllf I,. c det.:nn .•:,,in and h.Amn,,ir:v to Nu,) . i.%1re11S1! Sta: ý,. th,.:
h n•,ni - r .ries to r.-sporis:t-'le :'. ,.!:.'- [
SNIELD 5U/L DING 'DOME
Po S/LIo
lCof IOAO/NGcrCLoNf
,STEEL, CONTAINMENT VESiSEL IN :9 0
/-175 TON POtLAR CRANE •''POLAR CRANE.
.TOP OP DECK --- 7P OP CRANPE RAIL - SP'/NG L Ijv.N AIR.r'L W . /El PI .fo
-RIDGECRANE PENTMAION HA N
SIIE ARR'JR t P
WAIAL i1INT
I I I I
e W,4EI, . !
ftWF#04 DooD, r (MISSILE SJHIELD •
.0L ?Jr.It
IO.q
.. R . I A ff # IpNOOLACH,, "T
^*D it t
V e t . S STEE C ' T. .M .ESSE .NNL RE.O .
A N'A OCTNE C SL r
Figur ST[ SEELt COTIMN VESL ANU. U,. '.'IN
"N CNkU EACO SHEL br+oLDo ,,
Am I
.9
N.:
* ';'42 *~
/'I.
1~~
.//
.of
Figure 2 - LOCATION OF THE FOXBORO CPdts IN THE ANNUI:USREGION
r i " - 1
* .*~
, .C;ý
.3IR -. FOXBORO MODEL EI IGM FORCE BALANCEPRESSURE DIFFERENTIAL TRANSMITTER
r
FLEXURE
O(~c~ropxZ
ran BAN PCIEBAWI COIL
MAONCI
Olu "Aaa
A"
Fa-ffR-
FOXBORO MODEL EIIGM FURCE BALANCE PRESSUREDIFFERENTIAL TRANSMITTER (PRINCIPLES, OF.OPERATION)
Figure 4
4~A "~<~ A~
2r
2Ml,-
gU5S
I'
iso*t a io~ vc
pwý-
1" 9? MIc SIX'
•m I i I III i
I z s
12
lose
!)0--
H
Ii I !IIIfI I I 1 iuitil I I t 11,111 I I I I I!! I-- - -- .. . . • . . . . . i I I I t u e , ,
1lA I I I I
IU 1
TIN ISM
.......... I 'S too a s I*&aa
FIGURE,5 - GRAPHIC ILLUSTRATION OF ANNULUS REGIONTEMPERATURE RESPONSE TO A WORSE-CASE LOCA
Figure 6
SIMPLIFIED CHART OF O),':,ANIZATIONS INVOLVEDIN THE NCR-FE/ER SQNNEB85OI
ISEQUOYAH SITE
IOFFICE OF ENGINEERING (OE-KNOXVILLE)
NUCLEAR ENGINEERING BRANCH :(NEB)
NEBBRANCHCHIEF
I.-[-
OE DIVISION IOF ENGINEERING|
PROJECTS NUCLEAR!
DESIGNPROJECT
MGR (DPM)
.1
1133
NUC LE4t-rPPLYWB/Q
1
SYS SUPV(NSSS)I
WBN/SQN NUCLEASTEA.M SUPPLYENGINEERS( Nss) .
.!
Revision 03 04 05 Unit Ilo. 1.2
Proparar/Date 1. A.. Pleeic 5/19/82 6/29/$4 3113/55 4/131/ TVA ID NO. °
8/21/84 3/ 13/85 eA i jf L_ _ _ _ __ _ _
Roveveo r/Date _G. J. Kfalek 5/19/82 ... 121 . / /8 /I/f .i -! . . .
Sg EQUIPMRrT QUALIFICATION SHEET (EQ9S) Ar.,.lITL.,,
Manufacturer and Model No. I'oxboro ElICVerificacion of Table Informaon -Table 3.11-4 .
x Equipment Type - The equipment has been identified as per TVA IDnumber deigntiona (such as MOV, SOy).
X Location - The location hae been identified (such at' inside primarycontainment, anruluat individually cooled rooms, general spaces, orarea affected by 1HELB: outside primary containment).
x Component -A unique TVA tD number has been ass•gned (such as1-FSV-68-308). 1
x Function - A functional description of the component has been given(sFuchi #to= lenerator blowdown).
X Contract No., Manufac!turer, and Model No. -The contract number,ianutacturear and model. number have been given.
X Abnormal or Accident_'Environment -All abnormal or accidentenvironmentail od.r•oas applIcable to this equipment have beenidentified either in !tables or by references to figures from tables.
X Environment to Which qualified - The environment to which theequipyaent ha--been qualified is addressed in either the tables orthe environmental Analysis attached.
X Cate A category of a, b, a, or d has been defined for the
X 0peration and Accurac Re uLred and Demonstrated - The operation andaccuracy required an• demonatrate have been de mned..
qualit -ication Statu's (checkifea licable, NA if not)uA ieiad Lif¢ eIf equi.pent is qual.ified, indicate the qualified
lie with a-Wiserical entry)l N/AN/A Qualificaton Reaorc and Method - A qualification report and the
method of qualification has b.n identified on the Table Input DataSheet (TIDS).
X Environmental Analysis - An environmental analysis has been done,attached to the -QStland independently reviewed by the responsibleorganisation.
x Qualification by Similarity (if applicable) - A'J ustILfiCatio forqualification by similarity is attached to theEQB considering allthe above factors and referenced to the appropriate tables.
X Qualificat ion of Several Exact Components (if applicable) - When anzQ8 La used for morej than one item, a list, of all exact componentsis given as an appendix with all references to appropriate tableswith justification for qualification considering all the above factors.
N/A Interim Qualification (if applicable) - (Open item) - Component hasbeen determined to be qualified only for a limited interimoperation, an NCR has been v•itten, and plan of action has beendetermined to yield !a qualified component .Term of Interim QualificationNCR No.
.
x Unqualifi-ed Comiponent -(open item) - I pplicable),. Componenthas been determined to be unqualLfLed; the following is attached to&Qs3 NCR number, reason for nonqualification, and justification ofcontinued operation.!,NCR No .
Z95072.05
O2_E ngin!eer.ng Procedure 1'. 26.(RSj
FLOW CHART )
A tý t~ I win
IAny OEEmployeeIdentifiesPotential
* ii>
c.~; f
:1
z
~iJ
II
Condition
(Note 1)
Employee andSupervisorDetermineResponsibleOrganizationfor Preparingthe NCR
Respons 1bi p1
OrganizationPrepares NCR
OE IdentifyiEmployee
OtherOrganizationDoes notAgree toWrite NCR
(Note 2)
ApplicableSupervisorReviews NCR I
|
I I
NCR NumberAssignedby OE Clerk,typed, ret'd
to identifyiniemployee/supervisor
I i6) To Branch Chief (next page)To determine significance
Page. 1 ,1()Efng~eerng Poceue1. .26
"'
From Page.
Branch Chief/Project Mgr
or
I)e leigateDeterminesSinificance
FLOW CHART (Continued)
Or I gi n t LI ngUrganLidt ionCannotIDete rml.:ieSignificaince
)Determined a-Signiftcant
NCR
A . (Note 3)
[1-7Jjlandcarried
Non-s igni f I.-
OperatingLlicense I1lHandles
I
Nuclear Fngg*Pranch NEP)Nuclear Lic-ensing Staff
Elni. I.4e
EP 1.48
NEB-NLSDetermines who.is responsible
for P'e rformingFE/ER
correctiveAction orCoordinatewith EN DE
Identifiesalnt Responsible
Organizationfl and sends NCR
I to them forH•ndllng
NewResponsibleOrganizationDeterminesSIgnI f tc ance
(Within 8 cal-,ndnr clavsfrom identi-fication
1-08~I.B To EP 1.48
ALt achm'ii tPa pe . of
Note I I - denotes potential interface points between OE personnel andorganizations from the point a nonconforming condition isidentified by an OE employee, to the time it is determined tLoI),,significant and EP 1.48 (FE/ER) is initiated.
No te 2 If the responsible organization has not initiated an NCR or r,,;pri,,I-ed satisfactorily within two working days, the employee who ih.iitti-fied.the nonconforming condition has one day to write the NCR t,assure it is written within three work.qln days maximnum.
Not, 3 - Sigiiificance of the NCR must be determined within eight -l .days from when it is identified by the OE employee as a p'tentialnonconforming condition. If significance is not determined withineight calendar days, it becomes significant due to exceeding the.Mpecilie'd timpframe.
A Lt .vI 11n..ni)I (i i
I ri ii I .2 b OE Enineering Procod.tire 1 ./i8 (RI) (Noti 1)I
Res ponsiblbIe:; i i l
Iccui~vi.-s NCRF'rom NI,",(IIandecnrriud)
FLOW (CHART
kcsponsihlenrgan! zit ionInitiates
†Fa i luir e!Kru', nycering
keporrt (FE/ERH)
Y9
7I
P'repa r e_ r
I.Assess facts;2.Coordinates
with otherorganization.
:3.Requests sup-port needed I
(;ategovry I
(Note 2)
Additional DIutIeS of Pr pa re r.AA ~t tn~aL..ttj..e•!.:. .. r . .......
4. Doc(uments calcLutrlat ionis, i sstfllpt i ; , t I
5. D)etermlnes if design functions rhallenwTl
6. Documents the evaluation and conc tisfotii(items on FE/ER Form)
7. Determines Category of FE/ER
Category 11
FE(/ot I
(Note 3)
Category I I I
FE/ER
(Note 4)
PreparerImmediate iv
Completes all.Appli cab l.eBlocks onFE/ER andSends on
yI-3 ~.(Note 5
ReviewerI~et ermtnes: I
I.NNature or Ideficientcond iti Ion
2.1acts andConc lus ions
$4 To Approver (page 2)
At r ,' r I mi. f
T.A.p.r ormve r .
Confirms ade-quacy of over-all evaluation
Engi1ne er in P r rocedure 1.48 0(0)
FLOW CHART
OE OENuclear Design ProjectD)iscipline , Manager (DPM)
JroJect of affectedEngineer Plant
(NPE)(At Site) [(At Sit0).
E 1' D
ENi)• I5 DAYIS
5 ...- Ilandcarried by7 Responsible Organization
NuclearLicensingBranch(NLS) 'Immediate Notification by Phone
of Evaluation Results)
(NotI: 1;)
Chief ,ReacrEngineerin.gBranch(NIC ( ' )
Sr"
1-6)
T -
Copies sent Pr eparesinformally to] nmnthly. status'appropriate report fromNUC PR EN DES MGRcontact to NUC PR
Director
C
NuteL)'FE/ER, NCR
andnttachments t:oChief NuclearEng. Manag.,rof Nuclear IPr ,od.u ct__ionl _j
(FOR CORRECTIVE. A:T I NAND R['PORTAIB I LI. 'lY)
ro SQAI18 (Attachment 4)
AL Lathintr t 'Page 3 of t
',:of I - This Flow Chart depicts the EP 1.48 revision that was in efe'-(-Iwhen the subject NCR-FE/ER were written. EP 1.48 had not bee, trevised to reflect the organization in place at th;it. time.
Note 2 - Category I. Acceptable for all modes; of operation and designconditions.
Note 3 - Category II. Not acceptable for some design loading combifilt lonor design condition. However, a functional impairment of thecomponent(s) is not likely.
Note 4 - Category III. Unable to perform its requi red design funct ion(,;unless corrective modifications are made.
N(,tv 5 -(1iN. denotes potential interface points between OE personnel arndorganizations.
:~h,., I I
NUC PR STANDARD P'RACrICa: Sa1 18
FLOW CILART
NCR FLOW CHART
+
Office of EngineeringIdentifies NCRForwards to NEB
Coordinates andReviews FE/ER
T Time in NU ('(in workit. :ys)
:ory 2 & 3 I RES
I
Category 1 RESPerforms SafetyEvaluation and Recom-mend Corrective Action
TN = 3 Days
ComplianceDetermines Report-ability and Finaliz~t..i
TN = 6 Days
REiSReviews Disposition and TN a 16 Days _•Fills Out the Status Sheet '' I
I
ComplianceFills Out DispositionSheet-Returns to RES'I '
ITN 1= 26 Days
I HESMaintains Files andTracks NCR to Closure
cm,,) I
t,, i: ..... nde not r' potential interfaice pointm bh tw cen SQN lp, or mu i,, ,I0 rganiat ions1 ..Of.
717,7 " M4~ - - -
'TVA G4 OS.-S
UNITED STATES GOVE,"NMENT
Memo ran d umdr TENNESSEE VALLEY AUTHORITY001 '85 0712 05 1
TO It. G. Parris, Manager of Nuclear Power, 500A CST2-C
FROM K. W. Whitt, Director of Nuclear Safety Review Staff, E7B31 C-K
DATE July 12, 1985
S : .1 U F'.R: BROWNS FERRY NUCLEAR PLANT (BFN) - NUCLEAR SAFETY REVIEW STAFF (NS16)INVEST1GATION OF ALLEGATION CONCERNING INSTRUCTIONS TO IMPROPERLYDOCUMENT TASKS - NSRS REPORT NO. I-85-10-BFN
On April 11, 1985, the& BFN Plant Manager requested that NSRS investi-gate aiiegations by an ýinstrument mechanic that he had been improperlyinstructed to document incompleted tasks and that his refusal to do sowas the reason for his proposed termination.
The attached report documents the results of our investigation. It isNSRS's conclusion that the allegation concerning instructions toimproperly document tasks was not, substantiated. The Office of theGeneral Counsel (OGC) is evaluating the circumstances surrounding theterr.ination of the employee and will report their results separately.
An open item involving lack of procedures for handling employee con-cerns/allegations is identified in the report. As part of your cor-rective actions, please ensure that procedures for receipt andhandling of employee concerns exist at all the nuclear plants.
The report also noted that the General Employee Traning (GET) course,GET-4, "Introduction to QA/QC," did not cover all avenues availableto employees in expressing concerns regarding quality or safety. Thisissue was previously identified at Watts Bar iin NSRS Review Report No.R-84-02-WBN (GNS 840203 050). Open item R-84-02-WBN-04, as discussedin the original report and R-84-15-WBN (GNS 840615 051), noted thatGET-4 and GET-2.1, "Level I Health Physics Training," were similarlydeficient. Please take, the steps necessary to ensure that the mastercourses, as well as revisions used at all training locations, areupgraded to discuss the role of NSRS as defined in TVA Code II"Expression of Staff Views."
Please provide responses detailing actions planned and taken on theBrowns Ferry specific and generic items by July 29, 1985.
If y,.u have any questions concerning this report, please contactM. S. Kidd at extensioný 2289 in Knoxville.
K. W. Whitt
MSK:LMLAttachmentcc (Attachment):
RIMS, SL26 C-K C. W. Crawford, 670 CST2-CiB.M. Cadotte, E3C80 C-K (w/out attachment) R. J. Mullin, 1350 CUBB-C
J. A. Coffey, Browns Ferry NUC PR H. S. Sanger, Jr., ElIB33 C-K
Bu> U.S. Savings Bonds Regularly on the Payroll Savings Plan
001 '85 07 12 052
TENNESSEE VALLEY AUTHORITYNUCLEAR SAFETY REIVEW STAFF
INVESTIGATIINNSRS REPORT NO. 1-85-10-BFN
INVESTIGATION OF ALLEGATION CONCERNING INSTRUCTIONSTO IMPROPERLY DOCUMENT TASKS AT BROWNS FERRY NUCLEARPLANT
SUBJECT:
DATES OFINVESTIGATION: April 16-18, 1985
INVESTIGATORS:
APPROVED BY:
JdF. MURDOCK t
M. S. KIDD
M. S. KIID
DATE
DATE
DATE
TABLE OF CONTENTS
I. B)ackground .............. .........................
11. Scope .'............... ....... . ..... ........ 1
II. Conclusions and Recommendations ...................... .
IV. Details ............... ............................ 2
A. Background Information ............. ................ 2B. Employee Concerns ................ ............... 2C. Method of Investigation ............ ............... 3
I. Interviews and Discussions ........ ........... 32. Docment and Record Review ..... . ...... ...... 33. General Employee Training (GET) ..... ......... 3
D. Results .. ............................. 4
I. Employee Concerns ......... .................. 42. Plant Procedures and Training for
Handling Employee Concerns or Allegations . . .. 5
V. Persons Contacted ............... ..................... 5
VI. Documents Reviewed ................... ..... .......... 6
-4-
~jv
1. BACKGROUND
On April 11, 1985, G. T. Jones, Browns Ferry Nuclear Plant (BFN)MIanager, notified the Nuclear Safety Review Staff (NSRS) that anemployee allegation had been received and requested that NSRSinvestigate the matter as quickly as possitble. The employee, wlohad recently received a notice of proposed termination for absen-teeism, alleged that his foreman had instructed him to improperlydocument the completion of certain tasks and further alleged thathis refusal to do so was the real reason for his proposed termina-tion. An investigation was performed by two NSRS staff membersApril 16-18, 1985:.
II. SCOE
The scope and objectives of the investigation were to: 1) deter-mine the nature of the employee's allegation concerning instruc-tions to improperly document task completion, 2) determine thevalidity of the allegation. and 3) evaluate the possible effe:ton plant safety.
Circumstances surrounding the proposed termination of the employee
were to be investigated by OGC.
III. CONCLUSIONS AND RECOMMENDATIONS
A. Instructions to Improperly Document the Completion ofCertain Tasks
Conclusion
No evidencel~of undue pressure being placed on the employee toimproperly document completion of tasks was identified duringthe investigation, therefore this allegation was not substan-tiated (see'section IV.D.1 for details).
B. I-85-10-BFN-01, Lack of Procedures for Handling EmployeeConcerns/Allegations
Conclusion
A Plant Notice was in place to provide guidance to employeesin how to identify problems to their supervision, other plantgroups, the NSRS, or the NRC. However, no procedures could beidentified which covered the handling of employee-identifiedproblems, safety concerns or allegations once received bysupervision (see section IV.D.2 for details).
Recommendation
Develop and implement procedures which provide guidance andinstructions for plant supervisors in recognizi-q, respondingto, and overall handling of employee-identif. .d problems,safety concerns, or allegations.
IV-. DETAILS
A. Background Information
A BFN employee in a meeting with the BFN Plant Manager citedtwo occurrences as examples of being improperly instructed byhis supervisor to perform certain tasks and of being undulypressured to complete documentation of the tasks when thetasks were not completed. The employee maintained (from theoutset) there was uo concern for an unsafe condition in theplant or that to his knowledge any documentation was actuallyimproperly completed by any person(s) on the BFN statf. Theemployee felt that his resistance to the pressure toimproperly document task completion and bringing problems tothe attention of management were the real reasons for his pro-posed termination. Since the alleged occurrences involved amember of plant supervision and potential plant safety-relatedissues, BFN managment requested NSRS to independently investi-gate the allegations.
B. Employee Concerns
The investigators interviewed the concerned employee (aninstrument mechanic) in order to obtain detailed informationregarding the concerns/allegations. During the initial inter-view, general information apparen].ly identical to that givento the Plant Manager (see paragrapii IV.A above) was provided.Additionally, four examples of improjer instructions on thepart of an instrument maintenance foreman were provid..d. Thetask.:, involved, along with names of other persons present orinvilved in the jobs wer0 also given. No further details wereprovided by the concerned employee at that time, although heindicated that more details could be provided later.
Two examples cited by the employee were selected for detailedreview by the investigators. These were as follows:
1. Maintenance had been performed on channel "A" of themain steam line radiation monitor for unit 2. Uponcompletion of the maintenance, Surveillance Instruction(SI) 4.1.A.1O was being conducted to verify prorer equip-ment performance. The foreman instructed tt concernedemployee to go to the auxiliary instrument ruom to per-form part of the SI oy obs..!rving a relay actuation andqcram light indication. The employee was in the instru-m, t shop-when he was instructed by te.Lephone to performthe task. Upon completion of the SI, ail partiesinvolved returned to the shop to complete the ta-k docu-mentation. Upon being requested to sign for verificationof the scram light and relay performance, the concernedemployee refused based upon his not having observed therelay actuation. The concerned employee alleges he waspressured to sign verification of the relay actuation
2
T MO
pý
ýt 12Qk
A"
w."
even though he had not observed it. Subsequently the SIwas repeated successfully and docu.nented as such.
2. An instrument valve alignment verification checklist wIsbeing performed in preparation for unit 3 startup in thefall of 1984. The instrument mechanics could not com-plete the checklist because two pressure indicatinginstruments and the associated valves for the oft-g'aschiller were not installed. The initial instructionsfrom the foreman were to submit a procedure change anddelete the missing instruments and valves and ý1o sign th5 .data sheet. Upon further discussior with the instrumenLme-:hanics and a Senior Reactor Operator (SNO), theinstructions were modified to complete an abnormal statussheet for the missing equipment and attach it to thechecklist in question. Another shift crew completed theactivity.
C. Method of Investipation
1. Interviews and Discussions
The in;estigation included interviews of the concernedemployee, the foreman at the-time of the events in ques-tion, the most recent foreman, coworkers (instrumentm-rhanics) in the events, coworkers not directly involvedin the evetits, co•workers of the foreman (other foremen);and discussions with instrument maintenance management upthrough the plant manager. Additionally, an interview ofthe concerned employeL's former supervisor at the PlantOperations Training Center (POTC) was conducted.
2. Document and Record Review
Plant records of the two events, BFN Standard Practice(SP) 19.19 - Plant Notice 8, supervisor logs, and thepersonnel file of the concerned employee were reviewed.A number of letters of personnel action were also rv-viewed to determine the background leading to the letterof proposed termination (see section VI f'r a detailedlisting of documents reviewed).
The investigators requested that plant management iden-tify any procedures which existed for handling/processingof employee concerns or allegations such that they couldbe reviewed. None could be identified.
3. General Employee Training (GET)
The, investigators attended GET-4, "Introduction toQA/QC," in order to secure unescorted-access badging andto evaluate the contents of the course relative toinstructing employees as to how to voice problems orconcerns with quality or safety.
3
D. Results
I. Employee Concern
The investigation did not substantiate the concernexpressed by the employee.
Because the interviews were so alike, the. following con-sensus summary is presented as a record of the results ofthe interviews conducted with the personnel involved withthe events being assessed.
a. The concerned employee is a competent instrumentmechanic, and the work performed by the employeewas generally thorough.
b. The foreman at the time of the events did notsubject the concerned employee to undue pressure todocument incomplete or inadequate work. The signoff of completed activities is an expected andnormal part of the plant activities in question.
c. With the exception of the momentary misdirection tosubmit a procedure change which was promptly cor-rected on the spot when questioned (see paragraphI.V.B.2), the foreman provided good direction to thecrews he supervised.
Regarding the referenced momentary misdirection, theinvestigators could not fully determine the extentof knowledge as to equipment status or other detailsof the situation which the foreman had availablewhen the directions were given. However, it wasdetermined that proper directions were subsequentlygiven upon further discussion.
d. The concerned employee on many occasions createdstrained relationship with coworkers on the crew byrefusing to sign off activities of which he was apart but for which responsibility was shared. Thiswas viewed by other instrument mechanics as nottrusting their work and as not participating as partof a work team. Paragraph IV.B.1 provides anexample of refusal to sign off a completed job. Theinvestigators concluded that the employee was fullyresponsible for understanding the scope of 'isresponsibilities when the work started. Further, itis customary to have a copy of the appropriate pro-cedure in hand, which would eliminate questions ofwhich relays and lights were to be observed. Fail-ure to understand and perform these duties repre-sented an unsatisfactory performance in thisinstance. This caused unnecessary expense to TVAsince the task had to be performed a second time.
4
e. The foreman was a hard-working and demanding supe.r-visor but was and is fair and not abusive in ,,i-aging the crew activities and is highly respectedby those supervised as well as by coformenn ,in.
2. Plant Procedures arid Training for Handling EmployeeConcerns or Allegations
BFN SPi9.19 - Plant Notice Number 8 encourages plantemployees to identify problems and provides informationas to how to make the problems known. It lists variousgroups or persons who should be contacted, from im-mediateJ supervision, plant management, up to and in-cluding the NSRS and NRC. It is distributed to allplant employees every six months.
During discussions with plant management, it was deter-mined that no procedure(s) existed to provide guidanceand direction to -plant supervision or others in recog-nizing, responding to, or otherwise handling problems,concerns, or allegations voiced by employees. These areneeded to ensure consistent, proper hartfling of issuesbrought to the attention of supervisors and managers.
GET-4 was observed to provide instructions to employeesas to how to express knowledge of conditions adverse toquality (CAQ) to their supervisors. It also pointed outthat employees could contact the NRC regarding CAQ's;however, no discussion of the NSRS, as provided for inSP19.19 - Plant Notice Number 8, was provided. Thisdiscussion is necessary to address SP19.19 and alsoTVA CODE II, "EXPRESSION OF STAFF VIEWS." The PlantManager stated in the exit meeting that GET-4 wouldbe revised to cover all contacts given in SP19.19 -
Plant Notice Number 8. In that GET-4 is a generictraining course controlled by the POTC, broad action isneeded to upgrade the master course and ail versions inuse.
V. PERSONS CONTACTED
J. H. Bramlett. Jr., Personnel Officer, BFN
R. E. Burns', Inatrument Group Supervisor
L. R. Hambley, Training Supervisor, POTC
G. T. Jones, Plant Manager
A. McCaleb, Instrument Craft Section Supervisor
W. F. Nichols, Maintenance Training Unit. Supervisor(former job steward)
5
T
J. R. Pittman, Maintenance Superintendent
J. N. Schmitz, Jr., Auxiliary Unit Operator, Training UnitInstructor (union business agent)
Three Instrument Foremen (two dual-rate)
Six Instrument Mechanics
V1. DOCUMENTS REVIEWED
A. Daily logs/journals maintained by instrument foremen.
B. Past and present staffing lists of the instrument main-tenance section.
C. BFN Standard Practice 19.19, Plant Notice 8, "EmployeeInitiative in Identifying Problems" dated March 1, 1985.
D. Personnel records uf concerned employee including lettersof escalating action.
E. Certain plant maintenance and p:.,cedural recorus relatingto the two examples investigated.
im1p1ii DE~ m
