y Ik,UL t e '-{' - 'jj Q '. , i j ,. ';

.

.

Docket No. 50-346 TOLEDO

License No. NPF-3 . EDISONSeri . No. 702March 31, 1981 a.c-e.nc p cac se

. x yn,h

.

' 'vw ,

s,.t pi me .nEi . . , , / ,.

Q '. , i j ,. '; .

y Ik,UL t e '-{' - 'jjDirector of Nuclear Reactor RegulationAttention: Mr. John F. Stolz

Operating Reactor Branch No. A _j , c g 'g - -Division of Operating Reactors j [.5 _ b # T

'

,

United States Nuclear Regulatory Commission kyy v.s. q"'g,ic,.,

,

Washington, DC 20555 f ., -

/ -

% )/./4 {T/-

Dear Mr. Stolz:

This letter is to transmit editorial revisions to the Inservice In-spection Program for the Davis-Besse Nuclear Station Unit No. I whichwas submitted by letter on May 15, 1980 (Serial No. 616), and revised onDecember 15, 1980 (Serial No. 671). Please find attached five (5)copies of the letter revision delineating the editorial changes to theInservice Inspection Program. The editorial changes made in thisrevision reflect the results of telephone conversations with Mr. A. J.Cappucci, U.S. Nuclear Regulatory Commission and Mr. T. Cook, EG&G Inc.This letter revision depicts the editorial changes showing by pagenumber the changes made.

Any additions that become necessary, due to modifications and changes tothis program during the course of the remainder of the 120 month inter-val, which do not meet the code testing requirements will be implementedas needed. U.S. Nuclear Regulatory Commission notification will followthese changes.

Very truly yours,

RPC:TWH

ds d/1

Attachment r

poolcc: 3Luis Reyes - DB 1 Resident Inspector

i I

|

THE TCLEDO EC:SCN COMPANY ECISON PLAZA 300 MACISCN AVENUE TOLEDO OH10 43652

0 7 () {'

.. - . _ _ _ _ _ . -_ .__. .

.

.

.

SUPE.ARY CF

REVISICNE TO THE INSERVICE INSPECTION PROGRAMFOR THE

DAVIS-BESSE NUCLEAR STATICN UNIT NO. 1

Page

I-l Changed start of program from June 27, D 77, to November 21, 1977

I-6 D. CCDE EXCEPTICNS changed to RELIEF REQUESTS

! I-7 Code Exceptions changed to Relief Requests

I-8 Code Exceptions changed to Relief Requests

I-9 Code Exceptions changed to Relief Requests

II-l Changed start of program from June 27, 1977, to November 21, 1977

II-20 Test Frequency changed frcm Q to C for Valve Number CV187,Cvl91, and CVil7

II-25 Test Frequency changed frcm R to C for Valve Number RC10

II-32 Max. Stroke Time (Sec.) 31 for Valve Number DH63

I!-33 Max. Stroke Time (Sec.) 18 for Valve Nu=ber DH64

II-50 Max. Stroke Time (Sec.) 70 for Valve Nu ber SW1382Max. Stroke Time (Sec.) 67 for Valve Number SW1383

II-57 D. CCDE EXCEPTICNS changed to RELIEF REQUESTS

II-58 Code Exceptions changed to Relief Requests


II-60 Code Exceptions changed to Relief RequestsRelief Request Nu=ber 4 added, "The reason for not full strokingthe check valve is that the auxiliary boiler will not provideenough steam for the pump to spin fast enough."


II-62 Coue Exceptions changed to Relief Requests


- -__ - _ - . _ _ _ _ _ _ -

_ _

.

.

Scamary of Revisions to the Inservice Inspect .on ProgramPage 2

4

page

II-64 Code Exceptions changed to Relief RequestsRelief Request Number 14 added, " Cooling water to the reactorcoolant cumps is required recept at refueling."

II-65 Code Exceptions changed to Relief RequestsRelief Request Number 15 added, "Coeling water to the reactorcoolant pumps is required except at refueling."


II-67 Code Exceptions changed to Relief RequestsRelief Request Number 19 added, "when an adequate expansionvolume is available."



II-70 Code Exceptions changed to Relief RequestsRelief Request Number 26 - removed statement pertaining toradiation and added, " Loss of pressurizer level control cancause reactor trip."

III-l Changed start of program from June 27, 1977, to November 21, 1977

| III-66 D. CODE EXCEPTICNS changed to RELIEF REQUESTS|

| III-66a Code Exceptions changed to Relief Requests

.

IV-1 Changed start of program from June 27, 977, to November 21, 1977'

|

|

|

!

I

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w, w -s ~-,v - s- , - a.e -a ,. ,, - , e-s e

_ . , _ . . _ _ ._ _ _ _ - _ . . - ._ . _ __ _ _._. - - _ __ . _.

!

!

.

J

4 .,

i! *

4

. PC.'G TEST PROGRAM;

i '

- ;

!

{ A. PROGRAM ST.'?.ARY

"'he P=p Test program identifies test requirements fer all safety I

related p=ps, either these that are tested in accordance with the,'

requirements cf Subsection I*a'P of the ASME Boiler and Pressure vessel .

Code,1977 Edition and addenda through the Su=r.'er 107s Addenda er ;

these for which the Code requirements have been fc=d to be i= practical.The P'. p Test Program will be applicable for the re=ainder cf the

; 120 month interval which started en November 21, 1977, after which the gprogram will be reviewed and updated as appropriate with that editioncf the Code and Addenda ~in effect net more than twelve =enths pricr

i to the start of the next 120 month interval.

Individual pu. p test requirements are presented in Section C bya coded P =p Test Progra= Table. ~he codes used for this ableare defined in Section E. '!?.e Pump Test Program Table of Section Cis arranged in numerical sequence by Inservice . Inspection Instrument;

Drawing (ISID) n=ter. Section T. prevides justificatien for theexceptions taken to Code test requirements as provided for in.

10 CTR SC.55a(g) (5) (iii) . Justification for each request for reliefis general in nature and pertains to requirements fcund to be impractical

'

for all pu=ps. Relief Requests are numbered and referenced by nurieras Code Exceptiens on the P M Test Program Table.

).

B. P:!.47 TIST PROGRAM TABI.E FCRMAT

-"'he Pu=p Test Program Table has been ceded to provide the folicwinginfer =ation:

.

1. System and Drawine N eter. System the pump is in and the ISID, s

n=ber.

2. Cocrdinates. Ix>catien on the ISID where the pump is found. .

2. Pume Nu=ber. . Unique number assigned to each pump..

4. Speed n*. These parameters are addressed with one of thefc110w:.ng entries which indicates test interval er applicability:

,

4

NR - Net Required. .:

NA - Not Available..

M - Mcnthly.Tast-i ...

Ouarte-ly' Test.:Q -

- ,. _**

Rev. 2-2/61.

*_-uw w- L-- - . _ * _ _ _ _ _ _ _ _ _ _ _ - - -a-____.-___m---._-..--___-.____a_ _-__________.-_____.._.m __a __-_ _ - _ _ ____ _ _ . _ -+. _ _ _ . _ _ _ _ . 2... . _ m __ -_.__m-_.

.

.

.

.

-r...r ..r.~g w-=e e af-.e . *-3

his se: icn provides jus ificatien fer the exceptiens taken ::Code test requirements as provided for in 10 CTR SC.55a(g) (5) (iii) .Each Relief Request is identified by a =irce n=ber and identifiesthe pu: p(s) for which the Relief Regaes: is being taken. Chespecific Code test reg; ire =ent found :: be i=eractical is defined,and the basis fer exclusien frc= code require =ents is presented.Any testing performed in lieu cf Code reTaire=ents is spe:ified.Felief FeTaests are n=bered and referen:ed by n:=ber as CodeExceptiens en the P. p Cest Progra Cable fer specific p =ps.*his section als: resents a s--=ry of . ast .:. n. testing.r

1. Felief Pecuests,

a. Felief Re uest ! =1er 1

C:=penen s: Auxiliary Feedwater F. ps P14-1. F14-2.

High Press = e Inje::icn P. ps PSE-1, PSE-* cw Press =e Injecti n P*...ps 742-1, P42-2Contain=ent Spray P. ps P56-1, 756-2-

C =penent Cocling P=ps P43-1, 743-2, 743-3Service Water P=ps P3-1, 7 3-0, P 3-3

F= icn: E=ergency core cocling.

Safatv. related eTaip=ent coclinc..

Class: and 2. .

Ces: ReTaire=ents : Menthly inservice test.

Basis for Relief ReTaest: Mer.thly Section X: cperability.

tes ing has been a Ce hni=al Specificati n reTaire=entfor these pu=ps since April 22, 1977. An analysis cf

! the results of these tests and := parable data fremether cperating plants have shewn no significant changesin perfermance. Based on this analysis, the continuatienof Seenien X =cnthlv. testing wculd not significan:1v.increase plant safety. "'he Auxiliary Feedwater, HighFrassure In;ectien, Low Pressure Injection, and Centain=unt5rray ?=es are standby pc.:s whose centinuous Opera i:n.

is ne: reTaired. '"he C==penen: Cocling and Se:ticeWater P=ps are c:n inueusly ru .:.ing, and any significantdegradatien will be detected d=ing ner=al cpera.icn.

I-6

., /ei.. e r.t 4 .

_. . _ , . - - . , . . _ , , . - , .. _ . . _

.

.

?cnthly pu=p testing requires a total of at least 270hours per year of pump operatien; at least 714 man-hcursper year for data acquisitiens at least 60 man-hoursper year for data reduction, analysis, and recordkeeping. This amounts to a total of 774 man-heursper year. At a conservative total cost of S20.00per =an-hour, this amounts to $15,480.00 per year.Based upon the average exposure rates in the areasof the Auxiliary Feedwater, High Pressure Injection,Low Pressure Injectien, and Containment Spray Pumps,the total man rems exposure per year for pump testingis approximately 2.0 man rems. At the presentconservatively estimated cost of $10,000.00 per man remto plant personnel, this exposure costs an additionalS20,000.00 per year. Total cost to our customers isapproximately 535,480.00 per year for no significantincrease in safety.

Alternate Testing: Pu=ps will be tested in compliance, .

with ASME Sec-ion XI once per quarter and will bejogged monthly and flow measured. This is in agreementwith present changes that are being knplemented inSubsection IWP of the Code.

The revision to change pu=p testing to a three monthint eval in IWP-3400 has been approved and will beinc.luded in future Addenda. See Minutes of theNevember 28, 1979, meetinc of the Operating andMaintenance Working Group - Testing of Pumps andValves in San Jose, California, dared January 9,1980.

| b. Relief Request Number 2

i

j Compenents: Auxiliary Feedwater Pumps P14-1, P14-2.

[ High Pressure Injection Pumps P58-1, P58-2

| Low Pressure Injection Pu=ps P42-1, P42-2| Containment Spray Pumps P56-1, P56-2! Component Cooling Pumps P43-1, P43-2, P43-3I Service Water Pumps P3-1, P3-2, P3-3|I.

Function: Emergency core cooling.

Safety related equipment cooling

Class: 2 and 3.

Test Requirements: Measure pump bearing temperature.

yearly

i

1-7

Rev. 2-2/81

,. - . _-. - - - _ , ,

. . _ _ _ _ - _ . .- .

.

.1

r

Basis for Relief Request: The referenced edition of.

the Code requires bearing temperature to be recordedannually. It has been de=cnstrated by experience thatbearing te=perature rise occurs only minutas prior tc

Therefore, the d'tection of possiblebearing failure. ebearing failure by a yearly te parature =easurementis extremely unlikely. It requires at least an hcurof pu=p Operation to achieve stable bearing te=peratures.The 'small probability of detecting bearing failure by.

temperature =aasurement does not justify the additionalpu=p cperating time required te obtain the measurements.

Alternate Testing: None. This is in agreement with.

present changes that are being i=plemented in SubsectionIWP cf the Code :: delete yearly bearing te=perature=easurement. Celetien of bearing temperature has beenapproved and will be included in future Addenda. See

'Minutes of the November 28, 1979, =eeting cf the Operatingand Maintenance Working Group - Testing of Pu=ps a.dvalves in San Jose, California, dated January 9, 1980.

4

c. Relief Recuest Nu=ber 3

Compenants: Auxiliary Feedwater Pump ' P14-1, Pli-2.

High Pressure Injection < umps 758-1, P58-2Ica Pressure injection Pumps P42-1, P42-2Centainment Spray Pu=ps P56-1, P56-2Component Cooling Pumps P43-1, P43-2, P43-3Service Water Pumps P3-1, P3-2, P3-3

]Function: Emergency core eccling.

Safety related equipment cooling

Class: 2 and 3.

Test Requirements: Observation of proper lubrication.

level or pressure

Basis for Relief Request: The observation of lubrication.

level or pressure is a =aintenance function not anoperability test function. ' Pump lubrication requirements

'

,

are deter =ined by the pump manufacturer and plantoperation.

I-B

Rev. 2-2/81.

__m___ _-__. _ _ .-.--._-_u._ .-. ._ ., __--___.-____.._____...-_.__-..m.mm. - _ _ _ - - _- _ - . . _ _ _ _ _ - . _ _ _ _ _____m ___u-_._

. _ - - .

.

.

Alternate Testing: P=p lubrication requirenents are.

part of the plant maintenance procedures rather thanSection X: cperability test requirements. his is inagreement w:.th present changes that are being i=ple=entedin Subsection I*a'? cf the Code. ~he revisien to el:.rinateobservation of lubrication level or pressure frem theCode has been approved and will be included in futureAddenda. See Minutes of the Nove.ber 25, 1979, meetingcf the Cperating and Maintenance Working Group - Testingof Pumps and Valves in San Jese, Cal.fernia, datedJanuary 9, 1980,

d. Re.'.ief Recuest Nu=ber 4-

C=penents : Cc=penent Cocling Pu=ps P43-1, 743-2, P43-3.

Service Water P=ps P3-1, P3-2, P 3-3

Function: Safety related equipment eccling.

Class: 3.

Test Requirements: Operability testing of installed.

spare pumps

Basis for Relief Request: Any ene of the three ec=penent.

coeling or three component service water p=ps is anins alled spare. One pump is nor= ally runnir7, theseccnd is aligned as an aute=atic backup to ne operatingp=p, and the third p=p is electrically discennectedand manually valved out of the system. In the eventof failure of the operating pu=p, the second autceanicallystarts, and the installed sp ee is * electrically connectedand manually valved in as the reserve pu=p.

Alternate Testing: The ner= ally operating and reserie.

pumps will be tested. The instal'.ed spare needs te betested caly when it is connecte?. to the system.

2. Past Puen Performance

*he following infernation is submitted for your review:

a. P=p Past Perfcr .ance ::ata

b. P=p Past Perf 3r=ance Statistical Ar.alysis

I-9

Rev. 2-2/81

____ - __ _ - _ - _ _

- . .. . - -. .

II. VAI.VP. TEST PROGPM

A. PPOGPM S*|MERY

*he Valve Test Progtem identifies test requirements for all sr.fetyrelated valves eithar those that are tested in accordance with therequirements of Subsection IWV of the AS.5' Bo'.ler and Pressure vesselCode,1977 Editicn and addenda through the Su=mer 1978 Addenda orthose for which the Code requirements have been found to be impractical.The Valve Test Program will be applicable for the remainder of the120 month interval which started on Nove=ber 21, 1977, after which theprecram will be reviewed and updated as apprcpriate with that editionof the Code and Addenda in effect not more than tv41ve months priorte the start of the nexs. 120 month interval.

' Individual valve test requirements are presented in Secticn C bycoded Valve Test Program Tables. The codes used for these tablesare defined in Section 3 and su=marized in Figure 1. "he ValveTest Program Tables of Section C are arranged in numerital sequenceby Inservice Inspection Instrument Drawing (ISIO) numbet. Section Dprovides justification for the exceptions taken to Code testrequirements as provided for in 10 CFR 50.55a(g) (5) (iii) . Twotypes of justification are provided. The first is general innature and pertains to Code requirements found to be i= practicalfor all valves. The second type is used to justify requests forrelief for specific valves. Relief Requests are numbered andreferenced by nu=ber as Code Exceptiens on the Valve Test Progra=Tables for specific valves.

.

B. VALVE TEST PROGPRI TABLE FCRMAT

1. Valve Number. Unique number assigned to each valve.,

t

.C.2 -,1.as s . ASME Class.2.

3. Drawing Coordinates. Location on the ISID where the valve

is found.

4. Valve Categerv. Valve Category as defined in Subsection IWV-2200.

5. Passive. An 'X' in this column indicates that a valve ispassive as defined in Subsection IWV-2100. All other valvesare active valves as described. These valves mechanicallyconstrained to prevent changing positions are designatedas 'L' in the Test Requirement column. Those valves whoseposition is controlled by plant administrative proceduresonly are designated as 'P' in the Test Requirement colu=n.

II-l

Rev. 2-2/81

, .,. ~ -. -

. . . . . _. .- . . . .. . _ . _ . _ _ _ .. --_

F

DAVI S- DESSI: NIICI.I;All I'ONCit STATION IINIT NO. 1 l'ago 2 of 3VAI.vn Tl?sT l'ROGitAM -

'

System CONTAINMEffr AND l'ENETPATIr1N POOHS Drawing flo. D29A Ile V . 24_.

' 3 E .C*y valve g 8 k yy*

5, e_

ga Cat. g 3 .j ;! ag g #5.,4 'd

<a >. 1.,, l. ... .. o .o.

- u . . . : o. . o .r. . . .4 as

Valve Ntrmlier [j $ (gj A R C D n". M l*- 4 (g M(g 0. N O rI O rU NO O rU 3.[. Rem.u k nce vi es c a es e a 17 o se n m

4 +,

i

SW334 3 G-14 X X 1 Gl. MA In I. R

SW327 3 G-14 X X 1 GA MA in I. R

SW330 3 11-14 X X 1 GI, MA in I. R:

SW32R 3 Il-14 X X 1 GA MA In I, R

j CV26R - 11-10 X X a' CA MA ID 1. R

L! -

i e CV266 - 11-10 X X 4 GA MA ID I. R' uo

CV152 3' J-3 X X 2 GA MA IC I. R

I Cv60 3' 18- 3 X X 4 DA MA 10 1. R '2

CV61 3' 11 - 1 X X 4 DA MA In I. Rii CV196 3' G-12 X 4 CK' SA S R S C FORWARD FIOW TEST WITil llYdPOGEN--

DIIAITION HIOWER TEST.

CV187 3' 1I-12 X 4 CK SA -- S n S C rOnWAPD rioW TEST WITII IIYDROGEN I

i Dil AFTinti HfDWER TEMT. I;

*

CVl91 3' 11-14 X 2 CK SA -- S R S C FOftWAftD FIDW TEST WITI! IIYDROGPN ri DIIAITION IIIDWER TEST.

I CV117 3* f*-14 X 2 CK SA -- S 0 S C rORWADil FICW TEST WIT 11IlYDPOGErlDITAITION IttDWER TEST.

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e 6 5 4 3 1 3 3 0 0 0 0 0 8 O 9 8t v O D 8 O 2 1 1 3 3 3 3 3 3 S 5 Ss W W W W W W W W W W W W W W W Wl

y a S S S S S S S S S S S S S S S SS V

_

.

D. RILIEF .8.E;CESTS

This section provides justification for the exceptions taken toCode test requirements as provided for in 10 CFR 50.55a(g) (5) (iii) .Each Relief Request is identified by a unique nu=ber and identifiesthe valve (s) for which the Relief Request is being taken. Thespecific Code test requirement found to be impractical is defined,and the basis for exclusion from Code requirements is presented.Any testing performed in lieu of Code requirements is specified.Two types of justification are provided. The first is generalin nature and pertains to Code requirements found to be i= practicalfor all valves. The second type is used to justify Relief Requestsfor specific valves. Relief Requests are numbered and referencedby number as Code Exceptions on the Valve Test Program Tables for

! specific valves.

1. General Relief Requests

a. Relief Request Number G-1

Components: All safety related power operated valves.

Function: Power operated valve timing requirements.

|Class: All.

Test Requirements: Section XI, IWV-3413(b).

|

| "The stroke time of power operated valves shall

| be measured to the nearest second or.10% of the| maximum allowable stroke time, whichever is less,

! whenever such a valve is full stroke tested."

l Basis for Relief Request: For valves with stroke times.

| of less than 10 seconds, this would require measuringi stroke times to within a fraction of a second. Valve

timing is performed using a stopwatch either by directlyobserving valve movement or by observing remote positionindicators. Neither method can be relied upon to yieldresults with accuracy of less than a second.

Alternate Testing: The stroke time of all power operated.

valves shall be measured to the nearest second.

!

I

II-57

Rev. 2-2/81

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. - .. .-- . _ _ _ , _ _ _ - - - - - .-

1

.

b. Relief Reques- Nu ber G-2

Ocmponents: All safety related pcwer operated valves.

1

Function: Power operated valve tirdng requirements.

Class: All.

Test Requirements: Section XI, IW-3413(c).

"If an increase in stroke time of 25% or more fremthe previous test for valves with stroke time greaterthan 10 seconds or 50% or more for valves with s roketime less than or equal to 10 seconds is observed,test frequency shall be increased to once each month

until ccrrective action is taken at which ti=e theoriginal test frequency shall be resumed."

.

Basis for Relief Request: Cperating experience has.

indicated that individual valve timing is influencedby many factors such as changes in temperature, humidity,fluctuation in power source, li=it switch adjustment, etc.Because of these outside factors, timing data can exhibit,

scatter which exceeds the Code criteria but which is still'

less than the maximum full stroke time. Iacking in theCode requirements is any provision for verifying testresults prior to placing the valve on an acceleratedtest frequency.

.

The present Code does not require any action for valveswhose stroke time suddenly decreases a significant amount.Any marked decrease outside the normal band of stroketimes could indicate a =ajor mechanical problem such asthe power operator being disconnected from the valve.Any significant decrease in stroke time should beinvestigated to determine if the valve and pcwer actuaterare capable of performing their function.

Alternate Testing: Maxir.sn full stroke times shall.

be established for each valve based upon requiredvalve response time to assure adequate system responsefor safety related functions. Valve test times willbe acceptable if less than the maximum allowed. Iftest time exceeds the maximum allowed, the valve willbe immediately retested and corrective action taken asappropriate. Any significant decrease in valve testtime will insnediately be investigated and appropriatecorrective action taken.

II-58

Rev. 2-2/81'

. _ __ _ _ _ . . _, , . .._

2. Specific Pelief Requests

a. Pelief Request Number 1

Ccmpenents: M5100, M5101.

Function: Main steam isolaticn valves.

Class: 2.

Test Requirements: Quarterly stroking.

Basis for Relief Request: Cycling valve during ner=al.

operation results in loss of main steam to turbinewhich causes a reactor trip.

Alternate Testing: Valve will be full stroke.

tested during cold shutdown. Partial strokingduring normal operation is not possible becausepartial stroking can only be performed locally atthe valve. If valve was to inadvertently failclose during test, the main steam reliefs would

lift. The local test station is located in thearea which fills with steam froia the main steamreliefs. Entry into area is strictly controlledduring operation. No remote partial strokecapability is available.

b. Relief Request Number 2

Deleted -

c. Relief Request Number 3

Deleted

|t

l

!

|t

i.

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l II-59;

Rev. 2-2/81'

u.

,

d. Relief Request Nu=ber 4

Components: AT29, AT43, AT72, AF73, AT74, AT75.

Function: Auxiliary feedwater check valves to the.

steam generators

Class: 3.

Test Requirements: Cuarterly forward flow stroking.

Basis for Relief Request: Cycling valve would require.

injection cf auxiliary feedwater into the steamgenerator which would thermal shock the auxiliaryfeedwater nc::les. The reason for not full strokingthe check valve is that the auxiliary bciler will notprovide enough stem: for the pump to spin f ast enough.

Alternate Testing: Valve will be partial st.wr.e.

forward flow cycled during refueling when the steamgenerator is cold. valve cannot be partial strokedduring normal operation or full stroked at any timewithout injecting auxiliary feedwater into the steamgenerator and thermal shocking the auxiliary feedwaternor:les.

e. Relief Request Number 5

Components: TW601, FW612.

Function: Main fetdwater isolation valve to the.

steca generator

Class: 2 -.


|

| Basis for Relief Request: Cycling valve during ncrmal.

| operation would cause loss of main feedwater te

| steam generator which would cause reactor trip.t,

Alternate Testing: Valve will be full stroke.

tested at cold shutdown. valve design precludespartial stroke testing during normal operation.

f. Relief Request Number 6I

Deleted

g. Relief Request Number 71

Deleted'

i

!

ii

! II-60

Rev. 2-2/81i

|,

|1

h. Relief Request Number 8

Components: CVil7, CVIS6, CVla7, CVl91, CV209,.

CV210

Function: Hydrogen dilution air to containment.

check valves

Class: 2 and 3.

Test Requirements: Quarterly forward flow stroking.

Basis for Relief Request: Cycling can only be performed.

by injecting air from the hydrogen dilution blowersinto the containment. This air must be purged fromthe contairment to the environment. Purge time is li=itedto 90 hours per year during normal operation. Testingcould cause excessive purging with resulting increasein releases to the environment.

Alternate Testing: Valve will be cycled at cold.

shutdown. No partial stroking is possible duringnormal operation without-injecting air into thecontainment,

i. Relief Request Number 9

Components: CV5080 through cv508i.

Function: Contairment vacuum breaker valves.

Class: 2 -.


Basis for Relief Request: Forward flow cycling can only.

be performed by entering the annular area betweenthe contairment and shield building and verifyingfreedom of valve by hand. F.ntry to this areaduring power operation is strictly controlled andi

limited to ent:/ only when absolutely necessary.(As per Special Order No. 84-4, Revision'4, datedJanuary 5,1979)

Alternate Testing: Valve will be verified for.

freedom of valve movement at -L*d shutdown. Valvedesign precludes partial s* ck.: y caring normaloperation.

II-61

Rev. 2-2/81_

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j. Relief Request Nur.ber 10

Deleted

k. Relief Request Nur.ber 11

Cc=ponents: RClO.

Function: Pressurirer spray centrol'.

Class '.

Test Requirements: Quarterly stroking and timing.

Basis for Relief Request: Failure of valve in the closed.

position would result in loss of reacter coolantsystem pressure control which is required duringnormal operatien.

Alternate Testing: Valve will be full stroke tested.

during cold shutdown. Valve design precludes partialstroke testing during normal operatien.

.

.

!

;.

II-62

Rev. 2-2/81

_ _ , . _ _. . . - _ . . . . . . . .. -. . . . _ . _ . . - _ . _ , . _ ,

,

1. Relief Request Nurber 12

Components: RC2A.

Function: Pressurizer pressure centrol valve.

Class: 1.


Basis for Relief Request: Full stroking cannot be visually.

verified on this valve since the valve mechanism isall internal. A test can be performed by clesing theblock valve and seeing if RC2A solenoid energi:es andde-energi:es properly. Stroke timing is impracticalas the valve mechanism is all internal and the valveis pilot actuated. You can =easure the position ofthe pilot but not of the valve itself. This is nota motor cperated valve. There is no fail-safe positienof this valve. RC2A is tested in PT 5164.02, PressurizerPower Relief Valve Periodic Test, in conjuncticn withST 5030.04, RCS Pressure to the RPS Refueling PeriodCalibration Procedure, at least once per 18 months withthe unit in cold shutdewn (or refueling mode) . This testverifies that RC2A will cpen when its associated solenoidis energized and will close when the solenoid isde-energized. This test is nor= ally run with theRCS pressure at 2155 psig but can also be perfermedat <[2155 psig but )>500 psig in the RCS. This test

also verifies that the sciencid associated with RC2Awill be energized at a signal equivalent to an RCSpressure of 2400 ; 16 psig and de-energized by asignal-equivalent to an RCS pressure of 23501 16 psig.This phase is run by simulating output signals fro = theRPS to P5HL-RC2-5 in the NNI cabinets and verifying

proper cperation-of the solencid at RC2A. ST 5030.04will verify that the instn: ment strings for the RPSpressure transmitters selectable for use in the NNI>;e calibrated from the pressure transmitters to the

output of the RPS cabinets.

An acoustic monitor is used to verify valve openingand closing.

Alternate Testing: Valve may be effectively part.

stroked during normal operation in response topressurizer conditions. valve will be full strokedat refueling during performance of plant procedurePT 5164.02 which also verifies pressure set point.No valve timing is possible.

II-63

Rev. 2-2/81

._ , . - - , - .

m. Relief Request Nu=ber 13

Compcnents: MU33.

Function: Normal makeup water to the Reactor.

Coolant System

Class: 2.


Basis for Relief Request: Failure of valve in the clesed.

position during tt.t would result in total loss ofnormal makeup to the Reactor Coolant System. Makeupis required during normal operation.

Alternate Testing: Valve will be cycled at coldshutdown when makeup water is not required. Valvedesign precludes partial stroking during normaloperation,

n. Relief Request Number 14

Components: MC242, MU243, MU244, M"245.

Function: Reactor coolant pump seal water check valve.

Class: 2.

.

Test Requirements: Quarterly reverse flow stroking.

| Basis for Relief Request: Reverse flow cycling during.

' normal operation or cold shutdown would requirei

stopping reacecr coolant pump seal cooling water flow.Cooling water to the reactor coolant pumps is required j

( except at refueling. This would damage reactor coolant 3pump seals and is not permitted by plant procedure.,

!

|

| Alternate Testing: Reverse flow stroking will be.

| cycled at refueling. Cooling water to the reactor ]coolant pumps is required except at refueling. System 3

[ . operation precludes partial stroke testing during! normal operation.

:

II-64

Rev. 2-2/81

< _

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o. Relief Request Number 15

Components: MU66A, MU663, MU660. MU66D, MC59A.

MC593, MU59C, MU59D, MU38

Function: Reactor coolant pump seal water isolation.

valve

Class: 2.


Basis for Relief Request: Cycling valve during normal.

operation would stop reactor coolant pump seal coolingwater flow. Cooling water to the reactor coolant pumpsis required except at refueling. This would damage Ereacter coolant pu=p seals and is not permitted byplant operating procedure.

Alternate Testing: Valve will be cycled at refueling..

Cooling water to the reactor coclant pumps is requiredexcept at refueling. Valve design precludes partial 5stroke testing during normal operation.

p. Relief Request Number 16

Compenents: DH9A, OH9B.

Function: Containment emergency sump isolation valve.

Class: 2.

.

Test Requireme,ts: Quarterly stroking.

Basis for Relief Request: Cycling valve would introduce.

borated water from the borated water storage tankdirectly into the containment emergency sump. Valveis interlocked with DH7A (DH73) and can only betested when the borated water storage tank can beisolated.

Alternate Testing: Valve will be cycled at refueling.

when the borated water storage tank can be isolated.Valve cannot be partial stroke tested during normaloperation without injecting borated water into thecontainment emergency su=p.

II-65

Rev. 2-2/81

t

q. Relief Request Number 17

Compenents: CF28, CF29.

Function: Core flood tank isolation check valve.

Class: 1.


Basis for Relief Request: Forward flow cycling cannot be.

performed during normal cperation or cold shutdownwhen the Reactor Coolant System is filled andpressurized to pressure greater than that of thecore flood tank. Full stroke is precluded bysystem design.

Alternate Testing: Valve will be part stroke tested.

at refueling when the contents of the core flood tankcan be partially. dumped into the Reacter Cociant Systemwhile monitoring core flood tank level.

r. Relief Request Nu=ber 18

Ccmponents: CF30, CF31, DH76, DH77.

Function: Low pressure injection check valve.

Class: 1-

.

Test Requirements: Quarterly forward stroking.

Basis for Relief Request: Forward flow cycling can only.

| be performed by injecting water from the Decay Heat|

System into the Reactor Coolant System. This can only|

be done-at cold shutdown when Reactor Coolant Systempressure is low enough to permit injection.

Alternate Testing: Valve will be forward flow cycled.

at cold shutdown. System operation precludes partialstroke testing during normal operation when ReactorCoolant System pressure is greater than the Decay Heat

|

| System design pressure.|

|.!i

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Rev. 2-2/81!

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s. Relief Request Number 19

Components: HP48, HP49, HP50, HP51 HP56, HP57,.

HP58, HP59

Function: High pressure injection check valve.

Class: 1.

Test Requirements: Quarterly ferward flow stroking.

Basis for Relief Request: Valve can only be cycled by.

high pressure injection flow. High pressure injectionduring nor=al operation or cold shutdown could introducecold water into the significantly hotter Reactor CoolantSystem. This would thermal shock the high pressureinjection no :le. Additionally high pressure injecticnduring cold shutdown could subject the Reactor CoolantSystem to pressures higher than allowed in the coldshutdown mode.

Alternate Testing: Valve will be forward flow cycled.

at refueling when an adequate expansion volume is |available. System operation precludes partial strcke 3testing during normal operation.

t. Relief Request Number 20

Deleted

Relief Request Ncider 21u.

Components: CC1411A, CC14113, CC1407A, CCl407B.,

,

Function: Component cooling water isolation valve'.

1

1! Class: 2.

!


! Basis for Relief Request: Cycling valve during normal.

| operation or cold shutdown requires shutting off cooling| water to the reactor coolant pumps which would cause

! extensive damage to the pumps. Cooling water to thereactor coolant pumps is required except at refueling.'


at refueling. Valve design precludes partial stroketesting during normal operation.

II-67

Rev. 2-2/81

.

v. Relief Request Nu=ber 22

Components : 001460.

Function: Component cooling water isclation valve.

Class: 3.


Basis for Relief Request: Cycling valve during ncrmal.

operation or cold shutdown requires shutting offcooling water to the makeup pump coolers whichcould cause damage to the pu=ps. Cocling waterto the pumps can only be shut off during coldshutdown.


at cold shutdown. Valve design precludes partialstroke testing during normal operation.

w. Relief Request Nu=ber 23

Components: CC1567A, CC15673.

Functicn: Component cooling water isolation valve.

Class: 2.

.


Basis for Relief Request: Cycling valve would require.

shutting off cooling water to the control rod drivesI

which can only be done at cold shutdown.


at cold shutdown. Valve design precludes partialstroke testing during normal operation.

II-68

Rev. 2-2/81

, _ , .. -~ _ ..

4

x. Relief Request Nur.ber 24

Components: SW57.

Function: Service water isolation check valve.

Class: 3.

Test Requirements: Quarterly reverse flow stroking.

Basis for Relief Request: Reverse flow cycling requires.

stopping cooling water flow through the turbine plantcooling water heat exchangers which could result inextensive equipment damage.

'

Alternate Testing: Valve will be reverse flow.

cycled at refueling when cooling water is notrequired. System operation precludes partialst_oke testing during normal operation.

y. Relief Request Number 25

k

Components: IA501, SA502, NN58, CV209, CV210,.,

CV124, CV125, CF15, CF16, RCll3,

( Function: Containment isolation check valves.

i

I Class:1 or 2.

!

!

Test Requirements: Quarterly reverse flow stroking; .

|

Basis for Relief Request: Verification of reverse flow.

closing can only practicably be accomplished by leaktesting. This testing can only be performed at refueling.

| Alternate Testing: Valve will be reverse flow.

l closure tested at refueling during the performanceof an Appendix J, Type C, test.

|

_II-69

!

I Rev. 2-2/81i

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._

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:. Relief Request Number 26

Components: MU2A.

Function: Letdown isolation valve.

Class: 2.


Basis for Relief Request: If this valve were to fail.

in the closed position during testing, loss of normalletdown would result. Letdown is required to controlreactor coolant inventory as the required reactorcoolant pump seal injection continuously 'dds waterto the Reactor Coolant System. Less of pressurizer jlevel control can cause reac'.or trip. J

Alternate Testing: Exercise valve and measure.

stroke time during cold shutdown when access tothe valve is not prohibited.

| aa. Relief Request Number 27|

Components: HP2A, HP2B, HP20, HP2D.

runction: High pressure injection isolation valvesi .

-

t

Class: 2.

f Test Requirements: Quarterly stroking and timing.

Basis for Relief Request: No pressure monitor devices.

are installed on the upstream side of these valves.The upstream piping is isolated from reactor coolantsystem pressure by two check valves. Cycling these

,

valves daring normal operation may allow high pressurelwater to be released -into the high pressure injection

system.

Alternate Testing: Valves will be stroked and timed.

at cold shutdown when the reactor coolant system is

depressurized.I1

II-70

| Rev. 2-2/81!

i, . - -

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-. .,

. .., .e. : r. . . . c ., _ . . . . . .a. ., _ . . . . . . ...._r.... ::w,. . .: ., .....

.. . .. ... . ... . .......

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,.,. . 4 a.e. 4.s.4es .w-.e.w.e . el.a . S...-- a4 a. w.s 4 . . e . 4 ., r 3.. .- . y . ..a ya werv.. ... ...

n,,. A.es. ,n.4..e exn 4,a~4 ., g ..w._ , .eq' 4 .,.e e . s . a.' .' 7 4 4 a.,. aos so.. .. .... . . . .. .

.7. .y

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safety relate. systems: either those that are exa.ined in accordanced

"' * '.e .-.v '-a-a.. s ^# .C. "" e e . ..' .. -'4.: . ~~4s , . . - ~.~n, as a- ..,- .d-.a.,.. . . - . . . . :: . a

of the AS."E Eciler and Pressure vessel Cede, 1977 Editien and

a. . ..y. . s. sw,a,.e a..a -,. w,se ,w. .. . . .4 w.. -w-.ea, a e. a 3 a. .. u. .s.e .e. e so..: .a ,

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s ^ e .-'. c,ui.- * ..e . .s h. a". e *, e =... .'.-" .d. ..- he .' ..g. . a ~. ' .1.' . . " . . * M a. .i .^ .-. .

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. .

,e . . . . O.'e anw' ***C'.**.*.* *** * * * * ' dg . M_ -am w.' .' .'ic. 7, .a .s . e . w". 4 '.*.*. * b.a - * * .''

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ec ~. *..s,ec.'c. :..- .== .='.'es,s e * *..' ~. . C ')' ceded We'.' .a..d :-

. w ."r . . . . .f.

Cerecnent Ncndestruc.ive Examinatien Tables, and 3 citing ':endestructive

Exar.ination Tables. he ecdes used for .hese tables are definedw...e we..d a..d .:"yy- - . .' ..s re ~. . .' - *. 2. 0 -. a .. *. ah .' e = c ",4 s e r. 4

.-

3 . ... .. ..... ..-.

C _, ,~.,. . e . . N. ~.d e s _" - ..' ". e _-'x = - i . .a* ' ~..S e~.' ~.. C a. e a..an ed 'v, .ev, s e. . . . . . . .,.

^ ^ ' ' ..g N~..d e s .. .c ..' ve ?.x =_- .a . 4 n '."ab.' e s .= .- e a.* .* .. e- dab .' a .= and s.. . . . o . yo.

xv. c' ass ar.d. sys.a . S e e. ..' ~. . " . c" ides i"s..''.'.a.' .. '.-. ex e, _'-ns. .

. - . . . . . . . ..

. <e .., Cca,. exa 4 a. e ,. e. 4 e._..e .. as . .4aea .s ,. 4n .m.> - ;... .. . . . . . . ..a . . . . . . ..

. v . . o a ( r ) t .c ) ( .4 4 4 ) .:. :- .

All Class 3 welds and succ.erts will be insc. ected to the re:uircents. .

cf Table r4>2500-1 cf the Cede. ''he examinatien will be conducted.o .ge ex. e.v. .ra. ..' cab' e w.' ^..' .. ^.e .' .' 4 .a.4 n.s ' .k.e c . w~..er. .. . .. . ,. . ,

cr system design and gec=etry.

.r...,. .

Fev. 2-2/El

D. FII.!EF FI;i.TSTS

This section provides justification for the exceptions taken toCode test requirements as provided fer in 10 CFR SC.55a f g) (5) (iti) .Each Relief Request is identified by a unique number und identifiesthe item (s) for which the Relief Request is being taken. Thespecific Code test requirement found te be impractical is defined,and the basis for exclusion from Code requirerents is presented.Any testing perferred in lieu of Code requirements is specified.

1. Felief Recuest Number 1

Compenents: Reacter Coolant Pumps P36-1, P36-2, 736-3, P36-4.

Function: Peactor coolant circulation.

Class: 1.

Test Requirements: Vclumetric and surface examination of.

the reactor coolant pump casing welds

Basis for Relief Request: The reactor coolant pu=p casing.

welds are too thick for examination by using present stateof the art ultrasonic techniques. For a baseline thesewelds are radiographed. However, for inservice inspecticnthe background radiation will be toc high maktng radiographyi= practical.

Alternate Testing: Surface examinatien only.

2. Reliaf Request Number 2

Components: Control rod drive nec:le flange bolts and nuts.

Function: Secure control-rod drive hou~ sing to reacter vessel.

head

Class: 1.

Testing Requirement: Visually examine (VT-1) all bolts.

and nutsj

Basis for Relief Request: _It is impractical to visually.

examine the eight flange bolts on each Of the 69 CPM.s fromthe platform of the head service structure, approximately20 feet above the flange surface. Most of the peripheralCRDM bolts and nuts can be cbserved through the twelve inch

i'

diameter ports in the service structure cylinder, the otherCRDM bolts and nuts are not accessible for examination.

i

{

| Alternate. Testing: Examine bolts and nuts en ten percent of.

peripheral CRDMs to coincide with Categt ry B-0, " PressureRetaining Welds in CRD Housings" .

,

!

III-66

[Rev. 2-2/81

. . . . _-.

- _ .

.

.

3. Relief Fecuest Nuri:er 3

' Cc=penents: Oecay Heat Eemoval Cocler E17-1 and E17-2.

Function: Decay heat re=cval,.

i

Class: 2.

Test Require =ene.s: Volumetric ex=-* .ation of shell to.

flange weld 'G'

Basis for Relief Request: On the flange side of the weld,.

the slepe of the hase material precludes ultrasenic examinatienfrem this side of the weld.'

.

Alternate Testing: Volumetric examinatien frc= ene side of.

weld only (refer to sketch).

.

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Rev.-2-2/S1

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IV. SYSTEM PRESSURE TEST PROGRAM

The System Pressure Test Program for all safety related systems willbe conducted in accordance with Table IWB-2500-1, Table IWC-2500-1 orTable IWD-2500-1 and will meet the requirements of Subsection IWB-5000,IWC-5000 or IWD-5000, as appropriate, of the ASME Boiler and PressureVessel Code, 1977 Edition, and Addenda through Summer 1978 Addenda. TheSysten Pressure Test Program will be applicable for the remainder ofthe 120-month interval, which started November 21, 1977 after whic!. the 3Program will be reviewed and updated, as appropriate, with the Editionof the Code and Addenda in effect not more than 12 months prior to the

start of the next 120-month interval. All tests shall be conducted inaccordance with the Inspection Program B of Section XI. In the eventthat no safety or relief valve is provided within the test boundary,for tests performed under IWC-5000 or IWD-5000, the system's normaloperating pressure will be used to determine the System Pressure Testand System Hydrostatic Test pressures to be used. In no case will the

maximum pressure rating (with a 7 percent safety factor) of the lowestrated component be exceeded.

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| IV . Rev. 2 - 2/81

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Documents

y Ik,UL t e '-{' - 'jj Q '. , i j ,. ';