*.

_

LONG ISLAND LIGHTING COM PANYT... : fLC'OC*faggsfgsfg SHOREHAM NUCLEAR POWER STATION

P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792, _ . . _ _ _ _ _ _ ,

November 21, 1979 SNRC-450

Mr. Denwood Ross, DirectorBulletins and OrdersU. S. Nuclear Regulatory CommissionWashington, D. C. 20555

Shoreham Nuclear Power Station - Unit 1Docket No. 50-322

Dear Mr. Ross:

Enclosed herewith are six (6) sets of Shorerram-specific systeminformation in response to those Bulletins and Orders TaskForce long-term questions of July 13, 1979. These responseswill be incorporated in a pending supplement to the genericdata presented in NEDO-24708, " Additional Information Requiredfor NRC Staff Generic Report on Boiling Water Reactors."

Very uly yours,

mJ. P. No arro,Project ManagerShoreham Nuclear Powe.r Station

JPM/cc

Enclosures 13Qj |gcc: J. N. Wilson

J. HigginsW. Kane

Goob.5

ll260 3VD &A, c..m

.

', PLAflT .5//e8f/M'1 UtilT(5) /-

,

ABYPASS CAPACITY

,

Plant Steam Sypass Capacity, % Rated

1 N1 196

.

-

.

PLAtlT JNMENAd**

8SYSTEMS Att0 COMP 0t:EflTS SHARED BETWEEil UtlITS

PAGE C0tlTIriUED PAGE

Single-unit plant check here do not complete

Shared BetweenSystem or Comoonent Units fiumbers

1701 197

.

4

.m.me.---

-

PLhNT $ 80/?f # @ l UNIT (S) / ,

cPLANT-SPECIFIC SYSTEM INFORMATION

W]kIdd s'

;fkgk N3Genera 1 Water Sources _ Instrumentation

and Contro1 Frequency cf

Safety Seismic Safety Seismic Safety Seismic System and

System Classification Category _ C_la ss i fica tion Category. Classif. Categon Component Tests

1. RCIC 2 / 2 l J6 I (dN O)~ ~. - ib ~ [ [N ~ ~ _~ U 3)

'

li) _ (1) L il)~~

2. Iso 1ation Condenser' ~

'~ ~ ~

3 itPCS -

H "' I (O2. @ .-_ / - -

2.-- -- p) gy

14. tiPCI-

6 LPCI 1 / 1 I #

__ 6 -[0E |/ / / I

.7 pg, - - -

g. snr., / / / I l6 I [0 . .--9. Rl!R (including f) [ yg [ g)

Montdown cooiing, . _ _ _ _ _

C

__(2)

,2 / 2 / _f6 | t

sfalm_ condensing,_ ling.sup!>rtgjort_ poolcoo 2_ / z t __ __.T gN) 1 i_ __

)_

) ._ _ _contairc:.ent spray modesl 2_ l 2. I E dd _ (

510. ,NS.u.

3 I 3 I_r 6.- | \ ~(l[

- -.

| f()A 11. E';Ctt! RBCLC W 3 | 3 I [g |o a, f g j yt,y , gil712. CRDA. , g-

13. CST (Q N,, ci) m-__

ggg 14. nain Feedwater 72) ciy ~~

N4 NA .[6 ) (0g (3) gy )

[L_Recirculation15. '

Pump /Eutcr_ Cooling (0) 3 I 3 ) y | q_

Uotes: See attached sheet

i

. .

PLANT-SPECIFIC SYSTEf INFORMATION

NOTES

(1) CST suction piping to UFCI/PCIC is safety Class 2, seismic Category I.The bottom portion of the CST containing the volume (100,000 gallon)dedicated to EPCI/RCIC is encased in a seismic Category I outer con-crete vall.

(2) All feedvater piping inside the reactor building is seismic Category I.Feedvater piping downstream of valves F032A & B is safety Class 1.

(3) System not applicable for SUPS-1.

(h) All safety systems vill have some non-ensential instrumentation whichare used for non-safety functions (i.e. annunciators).

(5) Portions of the system which constitut<a reactor coolant pressureboundary as defined by 10CFR50.2 (T3 are safety Class 1.

(6) Frequency of tests vill be identified when the Technical Specificationsare developed.

(7) Insert and withdrav lines as well as scra= discharge components.

(8) Same system as item 11.

(9) Scram functions are IE.

(10) Containment isolation functions are IE.

17,0i 199

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T S B uaahi ol aet oaxt iCC lart 'T N A n BBBCDCGGR. SSVEO n AADI PO n AMSON O o : o oA C E i = = = = = = = = = = = = - i = = = = = i = = = : ~ -

t tL G t N6 (1a aP Y A a K V V

l 00OHl CC 1 ( FR P l CLKC BTVCVBVA o BGBCD GGRSSVX 'v )t o AAD1 P o AMS )M s s s

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m e eoo e e e l l

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b b b a al a a t a e T To T T tnt dr ne o n n

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t a oCt u is Ms ai su tF n t s s c C s t t ee v s

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ed s A mprt r nP se ry i te s snct t cr r mrr1 di r oreoe a I

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at&l ACtAOPPOnut l linot i ta OE i

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: V V = = = = :V = = =r = = =d = = I === = = = n n PFM l n Ie o I0 o AORR eo AC0?r NY n 0I N ASW i ie o i i

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g s u o o on o l s s _ , c gnE P "' I I L

CCDN

.

-

C7Vv-,

ISOLATION SIGNAL CODES.-'t

SET POINT 1/DESCRIPTION.S_I_G N \_L_-

7

' A* Reactor vessel low water Icvel 3 12.5" *

B* Reactor vessel low water 1cvel 2 -38"

CA liigh radiation - main steam line 3.0 x Full Power Background

D* Line break - main steam line (high steam flow) 106 paid

E* Line break - Main steam line (steam line tunnel high temperature) 200 F

F* High drywell pressure 1.69 psig

G Reactor vesse] low water level 1 -132.5"

J* Line break in reactor water cleanup system - high space temperature, high 30 F dbove ambient, **

differential flow

f 248 H 0,110 psig,10 ps tgK* Line break in steam line to/from turbine (high steam line space temperature, high HPCI - 30 F above ambient,

steam flow, low steam line pressure or high turbine exhaust diaphragm pressure) RCIC - 30 F above ambient, - 105 H 0, 57 psig, 10 psig

L Reactor building standby ventilation system initiation System initiation

P* Low main steam line pressure at inlet to turbine (RUN mode only) 825 psig

**R Low chndenser vacuum

50 F above ambientT liigh t emperature in turbine building

U Iligh reactor vessel pressure 109 psig + flood level stetic head

W* liigh temperature at outlet of cleanup system nonregenerative heat exchanger 7" lig vac.

X Low steam pressure, drywell high pressure IIPCI - 110 psig, 1.69 psigRCIC - 57 psig. 1.69 pain

Y Standby liquid control system actuated System initiation

Z Low level in RBCLCW head tank i 5'-9"

RM* Remote manual switch from main control room Not applicable

* These are the isolation functions of the primary containment and reactor vessel isolation control syrtem;other functions are given for information only.

** Not yet established.

If Set points are preliminary. Final values will be documented by the Technical Specifications.

s

\ .

Y cci _c e-

1

- cci ces ye e ,'

'~

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q q

. . . . . - " ' " -_. _ 2g .m,

X2 A FEE 0 WATER LINE

7f' f}- u. u,on,

x2B FEEDwATER LINE -r. p 9 d e

c;x cci sc.cce . co e _

b: **' ','x20A CORE SPR AY PUMP DISCHARGE TO RPV

" b * **[0 L

x200 CORE SPR AY PUMP OISCHA9GE TORPV-

TO 1111 *

" ' ' " ' SUPPRESSION ,,,DPOOL y .L_ bh ,

"X36 STANDBY LtOUID C6 C1 LNT TO RPV [ V[[ } . __

- p# VESSEL j fREACTOR i

''

, , , , , ~ ,-

"

x30 SAMPL E COOLANT FROM RPV-

- ey t e.

'- REviRCULATION SYSTEM RETURN LINE~ ' ' L..

-- E

XGA EriR INJECTION LINE TO & I - S -

1 loccl ccf

i i: ' N -

i iX4 RWCU LINE FROM RPV

w x --

}9 ' .--,

Fil RECIRCUL ATION PUMP_ r .

==---- REACTOR --*'

SE AL INJECTION RECIRCULATIONPUMPS ces cc

V . :so- CRD INSE RTlj ^ W (T YP. FOR l37

DRYWELL l

SUPPRESSION CHAMBERWATERLEVELN AIR SP ACE y y y,.

~~

1111 -~,~ SUPPRESSION POOL ,-

_

' N1 207'

.

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9

LEGEND

Siv-L E AK AGE CONTROL STSTEMVF1 CAL ARRANGEMENT FCR >=s-GLost vat.t Ictostol

OUT BOARD Msty*S):=2- GLest vaLvt torthi

X1D M AIN STE AM3MPetl$Unf

MPC -m'cha47 INJECTIOND4 GAT E VALVE (OPE h!

- M AIN STE AM LINE DRAIN C

!>4- GATE vaLvt (CLO$t D)RCit - mL40TCR CORE '

- xlC MAIN STEAM CM - catta vaLvt (c et N ) iSh afiom toouNo

- M AIN STE AM LINE 0R AIN g,,,, , ,, ,, ,

R-MOTom ( Pt aaTon a rv .et a;*ta PatSSJRY VESSEL

atB M AIN STE AM g~MAIN STEAM LINE ORAIN

' ':

- $4FEYY /atLit F vaLvt nec;. At a*TCA e&T ER CLtahu#

puum usu.ua.=sTEau-

XtA M AIN STE AM- MAIN STEAM LINE DRAIN h.taptosivt vaLvt

b-L Eau f tsT CON 4t CTION (L i c]X3 mal * STEAM LINE DR AIN

X12 HPCI TL' B6NE STEAM'

INLET LINE NOTES

X16 RC6C TURBINE STE AM i waim sitau pipams up To tSOLafit 4 vaLvts~

INLE T LINE .ag ev cansto Tc sli 1 aso am Lvueato asut m tem class 1)(ccTXG8 RHR INJECTION LINE TO ,

RECICUL ATION SYST EM RETURN LINE 2 aLL L Tc watvts itiTMER Gaf t on GLost)aND List $12t 5 aat 3/4 im M.alut C CC2 i

ahc wave aT LEalT 0%E OF TMt T*0 watuts i

Im Sf mitt LocatD CLottD.

X 5 RHR SHUTOOWN! t-

COOLING LINE FROM RPV; t

F 10 RECIRCUL ATION PUMP '

SE AL INJECTION {,

|,

fy}gf SHW$0& Ggjf __ ;}THOR AW LtNESi 4

FIGVAE A \ ,

I j

CRITERION 55 Cf'NTAINMENT I

ISOLATION vat;IES

!i

*

.

a

1701 208.

b

9

. _ _ - .

1

i- *D**]D ]D 030'

"

@'

cwM oJuUSUkInl.a ,. y'

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,

i

ii

stSS-ROCLCW-FRCM ORYWELL UNIT COOLER $ *

,( ' LEGENDM24E *

se - s60st watve ICtest*,1,

so.e60s va6v e t omt e t 29CLCW TO CRYWELL ug|T COOLERS d

I24 Mpg . satt va6vt IC605t03

Cm0 * Gaf t v4Lvt ICDst) M 2461 *

g = a#SLt watut EC605t0}

est . CastCe ta6vt (CL0ttel3322.CQtTAinutmf VENT TO RBNv5 -

C:4 - Csetta vahv t 40PE#1 .b

esg - Suf f t eate vatvt (CLOSt o s4

g{ * ptLett va6ve ITA RwR.CONTAl%wE47 Vaaf ORY * ELL -'~

A.u0 foe Opteatos,

x320 ComfathwENT ATwCSPwERC CCNTROL -e n, ,

x113 CCNTA'hvf 47 Cav 4 ELL*

RADeATICM MONiTCaiN3 Si.35fsTEM _@ -Lt as vest C0==ttfionis f C i

i,,,C...... .e tomt

Co0L aef ig4ECf'04 139 ORYWELL ?ERVICE AIR *

# Cec-eeatfoe Coat-e,.

isotat:04 C00Lete

esos-ett,0Wh est af et esovat 327 PURSE AIR FROM DRYWELL +

@ * II* A "I' R4S CONTL4WENT ATMC$PNER:C CCNTROL -*-g - seneste XS8 CONTAiNWENT Af rCSPnEPIC CON 1 ROL +

se e4 h . FLamGE CohetC T104 ~

E 32 FLOOR DRAINS FRC4 CRTWELL -*-6 - es st eiCrime 0eie iC E %mettCo-etactos eviLO'=e CL0tto 600* @ x297 URGE AIR FROM $UP9 PES $lCN CPA43ER

+coolies saf C# | 10 A RHR-CCN'A NUrNT $PGAY

SUPppE55'ON CHAY9ER _ 1'6C-LOCat0 CLotte $

I5 *6 W8EST'3 PCCL hCLE ANyP/ PvuPCCe N

II* IO V" UU 'U"'O'IE"A'OESUPPRES$104 POCL -_

?. ?, aCLEANupRETURN

' '

RNR STE Au CON- M_ |CEN5thG OISCmARGE

R42 RCIC bACuyM SRE&sER,w %

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I 1214 CORE $ PRAY PuM' SUCTION +

CORE SPRAT TEST Li4E~ ' '

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> RDC.* e 'O 087ef LL ymi? COOLERS # ",,', 'g'es". t r e' " sic.i * *Y. '.f. a . . .|,,Qf -| | Q,| -u.C

*

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R AOI A 0% = N . . + suksysT[W

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, j '|' j ' i i ,--- .is ,C ,e .s. :, ,

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ISOL ATION VALVES--- !,T,'j|','|C .'i , n ~ . ,. .- , u . 1.A- ,.

4. O }I | $ g u*lc ., .,, -

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$ | i

X 2 2 A-RB CLCW-TO RErlRCUL ATION PUMP -

._

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AND MOTOR COOLERS B "%

AND MOTOR COCLERS'

ffi

X23A-RBCLCW-FROM RECIRCULATION PUMP ',Q_

X37A NITROGEN / AIR PURGE F OR TIP~'

X378 TIP drive GUIDE TUBES - - h S5: kX37C TIP CRivE GUIDE TUBES : :

X370 TIP DRIVE GUIDE TUBES- -- h k: : * O:X38 TIP DRIVE GUIDE TUBES

CRY

SUPPRESSI

X45-DRYWELL FLOOR SEAL PRESSURIZ ATION- E AIR^

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Dee - GLOSE valve (CLO$EDI >3 - E E PLO5IVE V ALV E

pet - GATE WALwE (CPEhl h - LE AR TEST CCNNECTcN(L T C)

>4 - G ATE VAuvE(CLC5EDI

R - MOTCe CogmATom meCLC a-mE ACf te est- Di%GCLO$f D LTP-COOLINS EATER

-PUMP-CAveELL FLOOR SE AL

NOTES

1. ALL PEhETe AY10NS, PIPi%G 4%3il0L AY'04 WALW ESARE ASME = CODE CiAl$ 2 4CC2)

2. ALL L.T C vaLvt$ (EiTHE4 Gaf f on GLCBEi ANDLitt SIZE 5 AaC 3/4 thCM,45 w E : CC2 AN D ** AW EAT LE AST 0%E LCCREC CLOSE D wa6WE. ,

. . ,

s-

' p5 $ Mj-i r .t _

x 2 2 8 -RBCLCW - TO RFCIRCUL ATION PU MP

~] % '~ }l

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A%3 MOTOR COOLER

ecs~

1_

ANC VOTOR COCLERSx 2 *S- mBCLCW- FROM RECIRCUL ATION PUMP

t'' -

IREACTORRECnRCULATIONFuMPS

PLI)NT SHWMR IUNIT1

_ flGORE C-E L'. g

yi4~ 4MHEH ,,

A CC - 4 44-CRY AELL FLCCR SE AL 2RESSU RIZ ATION= - ' --

ISOL ATION VALVES

ON ?OOL__

?

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-.

:' PLAtlT Shorehan Ut!!T(S) 11

*,

E..

DESIGil REQUIREMEtiTS FOR C0ftTAltit1EilT ISOLAT10:1 BARRIERSa

#

$

$> Discuss the extent to which the quality standards and seismicOuestion:-

design classification of the containment isolation provisionsgfollow the reconmendations of Regulatory Guides 1.26, " Quality'

,

j Group Classifications and Standards for Water , Steam , andRadioactive-Water-Containing Components of fluclear Power Plants",

; nd 1.29, " Seismic Design Classification".d!,

.; Response: The quality standards and ceismic design classification of the

]{containment isolation provisions follow the recommendations ofRegulatory Guidos 1.26, Rev. 1 - September 1974 and 1.29, Rev. 1- August 1973.,<

il7" See also response to Question G (Codes and Standards).is

3,

<,

1

4

1301 213s.

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4

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..

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PLANT JNutt/M M UNIT (S) /'

f

PROVISIONS FOR TESTING

Question: Discuss the design provisions for testing the~ operability of the isolation valves.

Response: In general, Peactor Coolant Pressure Poundary Containrent IsolationValves (Figure A) can be tested for operability by stroking the valves(one at a time) during normal plant operation. This testing is accorp-

lished by remote ranual operation. The following exceptions to thisgeneral rule apply:

1. X5 - RHF Shutdown Coolinc Line from RPV

Contairment isolation valves in this line are nornally shut, and

cannot be opened with the RPV at full pressure. Operability maybe demonstrated at any time, provided stean done pressure is lessthan 135 psig.

2. Eirple Check Valves Associated with X2A&B, X-36, F-10, and F-ll

Inboard rain feed water check valves nay be demonstrated to shuton reverse flov when the reactor is shut down and feedvater issecured. Standby Liquid Control check valves may be deronstratedto shut on reverse flow at any time, by means of openine upstreattest connections. Recirculation Pump Seal Injection creck valvesmay be demonstrated to shut on reverse flow when the reactor isshut down, recirculation pumps are secured, and seal injection issecured.

.

With the following exceptions, the balance of the containrent isolationvalves (Figures P & C) nay be tested for operability at any tire by meansof remote nanual stroking of the valve:

1. Figure B Containrent Isolation Cbeck Valves may be demonstrated toshut on reverse flow during integrated containment leak rate testing.Inboard RP.CLCW check valves may be tested when shutdown using ventand test connections.

2. TIP Drive Guide Tube Fxclosive Valvns (X373. C, D & X38) may betested with the TIP's witndrawn. However, there is no intentionto perform this test.

3. TIP Parco Check Valve (X37A) is tested for operability duringcontainment integrated leak rate testing cy exposing the valvesto containment pressuro via two-way equalizing valves on theTIP indexer units.

h. Figure B Pelief Valves ray be den.onstrated to be seated for con-tainment isolation during containeert integrated leak rate testing.

'49i 2l4

.

.,, .*

..,_

PLANT CHcar m UNIT (S) 1

G -

CODES, STANDARDS, AND GUIDES

Question: Identify the codes, standards, and guides applied in thedesign of the containment isolation system and system

,

components..

#

Response: The containnent isolation system consists of the mechanical componentswhich establish the isolation barriers, and the electrical and control

components which are used to actuate active rechanical conpor.rnts.All conponents arc designed in accordance with the applicable ecdes,standards, and regulatory guides established in the FSAR for engineeredsafety features.

Containment isolation portions of rechanical systets penetrating primarycontaingent are designed in accordance with PeCulatory Guides 1.26(Quality Group Classification) and 1.2o (Seicnic Design Classification).The principal code for the containment penetrations is A7SI B31.7 (1969)based on purchase order date. For piping and valves which constitutecontainnent isolation conponents and are, in additien, part of thereactor coolant pressure boundary as defined by 10CFR50.2(v), the prin-cipal code is AS'f? III Class 1. The major exception to this is nainsteam piping and valves out to, and including, the cutbcard isolationvalves. Based on purchase order date, the principal code for cain steanis ANSI B.31.1.0. For valves and piping constitutinc containment iso-lation components, but not reactor coolant pressure boundary, the prin-cipal code is AEME III Class 2.

The following standards and guides were applied in the design of thecontrols portions of the containrent isolation syster:

IEEE 279 - 1971IEEE 317 - 1972IEEE 323 - 1971

IEEE 336 - ]971IEEE 338 - 1971IEEE 3hh - 1971IEEE 379 - 1972R. G. 1.11 (3/T1)P. G. 1.22 (2/72)R. G. 1.29 (8/73)

I O l 2, l b-R.G. 1.30 (8/T2)R . G. 1.47 (5/73) -

R. G. 1.53 (6/73)R.G. 1.6^ (10/73)R.G. 1.63 (10/73)

.

PLA!IT - SHOREFJld U!IIT 1

H

fl0RMAL OPERATI?!',' t'0 DES ATID IEOLATIO:I ?f0 DES

Question: Discuss the normal operating codes and containnent isolationprovision and procedures for lines that transfer potentiallyradioactive fluids out of the containment.

Response: Upon actuation of containrent isolation signals, there are no pumps,valves, or equipment which vill actuate autenatically and allow aninadvertent release of radioactive cases or liquids out of the prirarycontainnent. There are also no autoratic ecuipment operations to pro-vide inadvertent releases ucon resetting the containment isolationsignals. Systems designed to discharge potentially radioactive fluidsfrom the prinary containment will automatically isolate (e.g. dryvellficor drains). Systems designed to transfer potentially radicactivefluids from the containnent for accident citigation (e.g. ECCS) areclosed systems terminating back inside prinary containment. Operatingprocedures for all systers capable of transferring potentially radio-active fluids frer pricary containment are being reviewed to ensurethere are no operator actions which could result in an inadvertentrelease. A brief discussion is provided below for containment effluentlines which are normally operatinc or which may be used to nitigate anaccident. A detailed surrary of all containment isolation (nornal andpost-accident valve position, and isolation signals) is provided inresponse to question D.

1. Main Stean Lines and '!ain Steam Drain Line (X1A-D, Y3)

These lines are automatically isolated during an accident and villnot be reopened.

2. FPCI and PCIC Turbine Steam Eurp1v Lines (X12Ll6)

Steam flow is automatically initiated during an accident. Dura-tion of steam flow depends upon accident details.

3. REP Shutdown Coolinc Line (X-5)

Shutdown cooling may be initiated to achieve and naintain coldshutdown.

h. CRD Withdrav Lines

Since a scram vill occur prior to uncovering core, higher thannormal radiation levels are not expected in these lines. Flovout the withdraw line is not expected after the scran.

I30} [}b

.'> *

, -,

2. .

5 RWCU Line free RPV (X h)

This line is automatically icolated during an accident and villnot be brought back on line if radiation levels are excessive.

6. Sample Coolant from RPV (X-30)

This line is automatically isolated during an accident andvill not be brought bach on line if radiation levels areexcessive. Alternative post-accident sampling provisions arebeing investigated.

7 Primary Containment Atrospheric Control Lines (X h6, h7, hh, h5)

These lines are utilized after an accident to provide a closedflow path from the primary contairrent, through the hydrogenrecombiners, and back to the prinary containnent.

8. Containment Drvvell Padiation Monitoring (XF12)

These lines are automatically isolated after an accident.

9 Eouirment Drains frem Dr: vell (X31)

These lines are isolated after an accident and vill not bereopened unless radiation levels are acceptable.

10. ECCS Punp Suction Lines from Euntression Pool (XCA-D,X21A, P, X19, X15)

These lines are utilized after an accident for ccre cooling.The flow paths are closed loops frcm the prinary containment,through the pumps, and back to the primary containtent.

11. RECLCW (X25A, n, X23A, F)

These lines are not expected to be radioactive, since he flowloop is closed. They vill be closed tanually on actuation ofcontainment isolation in accordance with plant procedures.

bL