ML20214N757

Forwards Request for Addl Info to Continue Review of Rev 0 to Facility Pump & Valve Inservice Testing Program. Notification Requested to Schedule Meeting to Discuss Responses

ML20214N757
Person / Time
Site:	Vogtle
Issue date:	09/11/1986
From:	Oconnor P Office of Nuclear Reactor Regulation
To:	Conway R GEORGIA POWER CO.
References
NUDOCS 8609170016
Download: ML20214N757 (15)

Text

.

11 SEP 1986 Docket Nos.: 50-424 and 50-425 Mr. Richard Conway Senior Vice President and Project Director Georgia Power Company Rt. 2, Box 299A Waynesboro, Georgia 30830

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE V0GTLE INSERVICE TESTING PROGRAM The NRC staff is continuing its review of Revision 0 to the Vogtle Pump and Valve Inservice Testing Program. To permit us to continue our review we re-quire that the additional information contained in Enclosure 1 be provided.

We have found from past experiences that acceptable responses can best be arrived.at through a discussion between our staff, consultants, and your staff. Please notify us when you are ready for us to schedule a meeting to discuss your responses.

Sincerely, 1

Paul W. 0'Connor, Project Manager.

PWR Project Directorate '#4 Division of PWR Licensing-A

Enclosure:

As stated cc: See next page i DISTRIBUTION: -,

l 2Doctet111e; - NThompson Local PDR JPartlow NRC PDR BGrimes PWR#4 Reading EJordan

-BJYoungblood Reading OGC MMiller MDuncan l JThompson P0'Connor l .ACRS(10) i-i f

( PWR#4/DPWR-A PWR#4/DPWR-A l P0'Connor/ rad BJYoungblood l 09/lo/86 09//o/86 l

j 8609170016 860911 PDR ADOCK 05000424 A PDR.

I I

i Mr. R. E. Conway e

Georgia Power Company Yogtle Electric Generating Plant cc:

Mr. L. T. Gucwa Resident Inspector Chief Nuclear Engineer Nuclear Regulatory Comission Georgia Power Company P. O. Box 572 P.O. Box 4545 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Mr. Ruble A. Thomas Deppish Kirkland, III, Counsel Vice President - Licensing Office of the Consumers' Utility Vogtle Project Council Georgia Power Company / Suite 225 Southern Company Services, Inc. 32 Peachtree Street, N.W.

P.O. Box 2625 Atlanta, Georgia 30303 Birmingham, Alabama 35202 James E. Joiner Mr. Donald O. Foster Troutman, Sanders, Lockerman, Vice President-& Project General Manager & Ashmore Georgia Power Company Candler Building Post Office Box 299A, Route 2 127 Peachtree Street, N.E.

Waynesboro, Georgia 30830 Atlanta, Georgia 30303 Danny Feig Mr. J. A. Bailey 1130 Alta Avenue Project Licensing Manager Atlanta, Georgia 30307 Southern Company Services, Inc.

P.O. Box 2625 Birmingham, Alabama 35202 Ernest-L. Blake, Jr.

Bruce W. Churchill, Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W. -

Washington, D. C. 20036 Mr. G. Bockhold, Jr.

Vogtle Plant Manager Georgia Power Company Route 2, Box 299-A Waynesboro, Georgia 30830 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 l

l

EncloIura 1 VCGTLE ELECTRIC GE.NERATING DLANT, l":71 IST R ROGo;7 i:.E/ISION 91- PE's !EW CUES"! N.S

. I I. Valve Testieg Progran.

A. General Guestions and Contents

1. Are valves tnat perform both'a containment isolation functic e ;

a cressure coundary isolation function leak rate testea to bc.-

~

the Apoendix J ano Section XI requirements?

2. Are all valves tnat are Appendix J type C leak rate tested,

, incloced in the IST program and categorized A or A/C?.

3. How are valves inside containment fail-Safe tested quarterly?

a. Dr: vide toe 14 .iting ialue of f s!!-strc<e time for all pc-e-operated valves ir tre !$' pecgram for the staff's re.ier..

5. The NRC nas concloced t,at the acclicaole leas test orecedures and requirements fcr containment is lation valves are determinec by 10 CFR 50 Appenaix J, newever, tne licensee must comply witn tne Analysis of Leakage Rates anc Ccerective acticn Recuirements Paragrapns of Sectian XI, IWV-3426 and 3a27.

I b. Reactor Coolant System

1. provide a more specific tecr.nical justification for nct-full-stroke exercising reactor head vent valves during each c:lc shutdown.

l

2. What is the safety function cf v alves LV-0059 anc CisC?

i

,c, , . . .

'o

3. The NRC staff's position is that the PORV's function is to protect the reactor vessel and coolant system frcm i low-temperature overpressurization ccnditions anc shoulc te exercisec prior to initiation of system concitions for whicn vessel protection is needea. Routine' quarterly exercisir.g of t t PORVs during power operation is not required.

4 What is the safety function of valve Va-020?

~

5. Should valve U6-ll2 oe categorized A/C? Is this valve ever ocer during plant operation?.

6. Review tne safety function of valves HV-8145 and 033 (P'&ID No. IX4DSil2 D-5) to determine if they should be incluc.ed in the IST program.

C. P;uclear Service Coolino '.;ater Systen-

1. Are valves HV-2134, 2135, 2132, ano 2139 leak rate tested to tre

] Appencix J recuirements for containment isclation valves?

2. Review the safety function of the fcllowing valves tc ceterrir.e if they should be includeo in the IST program.

P&IO No. lx4DS135-2 Location t HV-1207 E-7 i

l HV-1809 G-7 t

HV-1823 0-3 l HV-1831 0-1 i

i f

P&ID No. IXaOS135-1 Lccation l HV-12C6 F-5 HV-ISOS H-5 l

i HV-1822 E-2 l'

u HV-lS30 G-2 I

2

. O. Safety Injection Syster 1

hnat is the safety f unction of valves dV-09:3 ALE and valves I HV-2375A-H?

i

2. How are check ; valves U6-079, 0E0, 081, ana 082 full-stroke exercised during refueling?

3. What is the safety function of valve HV-SS43?

4 Provice a more specific technical justif.ication for not full- ce partial-stroke exercising check valves96-013, U4-C26, 027, 023, and 029 auarterly during pcwer operation.

5. Are valves 8802A&E required by Technical Specifications to be cisabled in the closed positicn during plant operation?

6. a rceice 3 ore specific tecnr.ical justificaticn fcr not full-stroke exercising valve HV-8E06 cuarterly during plant operations.

7. Provice a more specific technical justification for rot.

full-stroke exercising valves HV-3809A&B cuarterly curing acwer

~

operation.

I S. Would f ailure of valve HV-8313 in the closed cosition durin:

quarterly testing render an entire safety system incperariel i

4 7

9. Do valves HV-3814 anc 382C perform a safety function in F.e c rer i pcsition?

1 i

l^. Provice a mcre specific technical justificaticn for nct full-stroke exercising valves EV-?E2ic, SE21E, at:c $535 cuarteri during power operation.

I t

3

4

11. *a ould f ailure of ' valve EV-EE40 in the oper, pcsition curing

,. Quarterly testing di/ert low pressure safety injecti:n frcr tne

{ ar.aiyzed flow patn?

12. Provice a more specific technical justification for not j full-strcke exercising valves HV-69234&B Quarterly during power coeraticos.

1

13. What is the safety function of valves U4-016, X165, ana x444?

-14 How is each of the following valves full-stroke exercisea curir;-

the refueling outage testing identified in relief recuest RR-6?

Valves U4-143, 144, 145, and 146.

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15. How is each of valves U6-129 and 129 full-stroke exercised duri".: _

cold shutcown?

16. '"ca i s eac, of v alves M-ia7,142, -129, anc lfC verifisc tt full-strcke curing the cold shutdown exercise test?.

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17. What is the safety function of valve HV-E924?

18. Hoa i s each of valves HV-083, 024, 085, ana 086 full-strc>:e

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exercised during cold shutdown?

19. How aces the ECCS t'est line subsystem indivicually verify leak i

tight integrity of series pressure' boundary isolation Check t' valves (i.e., U6-123 and 124)? -

i j 20. Review tne safety function of the following valves to ceter-'  :

if~they shculd be included in the IST program.

1 i

i I

C l

yrr- e w- ,re- -- w g i+m:w- - - , ,-y-4 gr m e ,

e-e yq-m----nwtmwr- -

r u P--ct-+-TT

D

. kV-SE77A-0 (P& D ?;o. 1XaDE120F

.. WV-S379A-D (PLID No. 1.X4DB120)

HV-86S94-D (PLID Nc. 1X4DE121)

-iV-2803 &B (D&!D No. lx405119)

HV-8870A&B (P&ID No. IX4DBil9)..

HV-8883 (P&lD No. IX4DBil9) 041&C42 (P&lD No.1X4DB119)

HV-8882 (P&ID No. IX4DSil9)

E. Residual Heat Removal Systea

1. What alternate methods have been considered for verification tna:

valve position is accurately indicated fcr valves HV-8811A&S?

2. Do te' stable check valves U4-122 and 123 utilize a manual operation lever or a power operatea actuator for de.monstration of faii-strcke cacability?

3. Review the safety function of the following valves to cetermine-if they shcula be incluaed in the IST program.

P&ID No. IXaDB122 Location FV-0610- H-5 FV-0611 E-5~

FV-8986A B-4 HV-8936B B-4 F. Containment Soray System

1. Does the procedure for quarterly full-strCke exercisin9 Va'.ves HV-89944&B render the entire containrent scray systet unavaarie curing plant coeration?

2. What alternate methccs have ceen considerec for verificati n tna:

valve position is accurately indicated for valves HV-9002a&S?

E O

3. What alternate metnocs have been considered for verificatior ;'

closure capacility of valves U6-001 and 002?

4 How are check valves US-037 and 033 verified to close du-ing Quarterly exercise testing?

5. Review the safety function of tne vacuum breakers on the spray additive tank to determine if they should be included in the !$7 program.

G. Chemical and Volune Control System

1. How are valves HV-0190A&B utilized for safety grace colc snutdc<.n as described in relief' request RR-15? Provide additional discussion why stroke time measurements will not provide ceaningful data for determining valve degradation for these valves.

2. Provide a more detailed technical justification fcr not

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full-stroke exercising valve HV-8110 quarterly during pcwer operation. (CS-ll appears to be incorrect.)

3-. What is-the safety function of valves HV-S485A&E in the cicsec position?

4 Do valves LV-Oll2D&E perform any safety function in the closed position?

5. 30 valves U4-la0 and la7 perfer.T. any safety function in tne closed position?

6.

How are valves U6-la2 anc 149 full-stroke exercised cuartert.

during power operation?

6

e. Provice a more scecific tecnrical justification for not partial-stroke exercising v alves 'J6-139 ano 436 during cc'.:

shutcCwn. Mcw and v. hen are these cneck' valves verifiec tc CI":: .

to perice- that safety function?

S. Are reactcr coclant pumps stopped during each cold shutdown t, f acilitate exercising seal water isolation valves HV-8100

• and 51127 l

9. What is th'e safety functicn of valve HV-1521d? '

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10. Do valves HV-8105 and U6-032 perform any safety functicn' in the l open position?

f l 11. Review-the safety functicn of the folicwing valves to deterrine

'if they should be incluced in the IST crogram.

P!,:0 *.e. ha:Ella 'ec3:icn j HV-8113A-D A-6 i

355 A-7 353 A-7 L

353 A-7 4

004 A-7 i

, Pl!D No. 1.YaDBil6-1 Location i

HV-182 C-7 FV-121 'B-6 129 C-5 124 E-3

. 299 D-3 HV-S439 0-3 i u';-810a 0-1 125 D-1 o

7

)

, n.-..< --,---, m. ~ , - --,,.--------,w-m,-vave-,an,.,- , , . ,,m-,,,,,,m- n,,,,. ,m-,+,.7ms-,-,, --g,r, ,n nwr, ,---~-- -~ , , ,wn,--._ m,-

. ;a .

osIE No. IXaDE115-2 .ocatisn

[ '

M'!-5436 D-7 i

t hV-2509A 0-5 FV-35095 F-5 j

i P&ID No. IX4DBil8 Location 4

264 D-5 l 299 B-5

! H. Nuclear Samoling 'icuid Systen 1.

i Does valve HV-8220 perform any safety f unction in tr.e q?en 4

position?

1

1. Auxiliary Comocnent'Cooline Water System 4

i.

Are tne reacter caclar.t :Lmps st ::ec curing eacn colc sr.2 ::..-

oto facilitate full-st :.e exercis4ag i3'ies."V '974, 197:, 19 :~.

anc-1979?

t t

2.

a'nat alternate tests have-been considered fer verification cf s

cicsure cacability of valves Ud-082, 085, 025, and 0?7?

3. Prcvide sheet 2 of 2. of the valve list for this~ system.

4 4

Review the safety function cf the follcwing valves to determire if tney should be incladed in the IST program.

P&ID No. lx; dei 25-2 Lccation h?-19051 E-7 HV-19CE2 C-7

"'J-19055 B-2 r h7-19057 F-1 I nV-2041 F-7 k

Q

J. Main Steac System e

.l. Do valves HV-3009 and 3019 perform a safety function in botn the open and closed positions?

2. Do valves U4-006 and 008 perform a safety function in both the open ano closed positions? How are these valves verified to full-stroke exercise to their safety related positions?

3. Provide the P&lD that shcws valve U4-404 K. Auxiliary Feedwater 5ystem

~

~

1. Do valves U4-001, 002, and 014 perform a safety function in the closed position?

2. Do any of the following valves perfccm a safety function in tne closed position?

P&ID No.1X4DB161-2 U4-017 U4-037 U4-020 U4-040 U4-023 U4-043 U4-026 U4-046 P&ID No. IX40B168-3 U4-113 U4-114 U4-115 U4-116

3. How a're valves Ua-014, 017, 020, 023, anc 026 full-stroke exercised during cold shutdowns?

. - . - - - - - . - . ..=. . . - - . . - . .. ~_-- -- -- .

[ ,

4 Why are the~ following valves included in the IST program if thei-

!L -

internals have been removea as indicated by ncte 3 on PLI3 4

No. IX35161-2?

1

.' U4-013 U4-052 ,

U4-033 04-058 U4-051 U4-061 1

5.

! Provide a more specific technical justification for not full-strcke exercising valves HV-15196,15197,15198, anc 15199 quarterly during power operation.

i.t .

o.

What safety function do valves U4-Il7,118,119, and 120 perferr

in tne open position?

7 15 the'ficwrate tnrough check valves U4-125, 126, 127, anc 12E auring pcwer cperatien creater than or ecual to the safety 2

flewrate requirec frcm tne auxiliary feecwater system?

l

S.

Review the safety function of the following valves to deter 9ine' if -they should be inclucea in the IST program.

PLI) No'. IX408168-3 Lccation-j U4-121 H-2 l U4-122 H4

' U4-123 H-6 i U4-124 H-3 i

PLIO No. IX4DE161-2 Location t

FV-5154 C-6 l

FV-5155 S-6 i a l

I i

l i

l t

10 i

l

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

K. Ccndensate Feedwater Systen l.

What alternate methods have been considered for verificatico cf

' check valve closure capability for valves U4-071, 073, 075, and 077?

L. Containment Air Purification and Cleanup System

1. Do valves HV-2624A&B perform any safety function in the closec~

position?

2. Does valve U4-012 perform any safety function in tne open position?

3. Do valves HV-2790A, 27908, and 2791A perform any safety function in_the open position?

d. Review the safety function of valve HV-S221 P&ID No. IX40E213-2 location D-6 to determine if it should be' included in the-IST program.

M. Service Air System

1. Provide a more specific technical justification for not full-stroke exercising valve HV-9385 ouarterly during power operation.-

N. Nitrogen to Accumulators System

1. Is valve Ud-017 ever open during plant operation?

0. Post Accident Samoling System

1. The NRC staff position is that the operability of this system is required by NUREG-0737 (Item II.B.3), therefore, all valv'es in this system required for operation must be included in the IST program and tested to the Code requirements.

11 I

P. Diesel Generatcr Systems l.

Review the safety functions of the following valves to ceterrine if they should be included in the IST program.

P&IO No. IX40B170-l&2 Location 044&O50- C-3 047&O53 C-4 730&770 H-3 736&764 F-3 HV-9068A&B .

G-5 HV-9069A&E G-5 HV-9070A&B G-5

.HV-9071A&B G-5

. 2. Do temperature control valves TCV-19096 and 19097 (location F '~,

have a requirea f ail-safe cosition?

f l

I l'

, .I I . Puno Testina Program 1.

Hcw is inlet pressure and pump differential pressure measured for the nuclear service cooling water pumps?

2.

How is vibration displacement measured on the submerged nuclear service cooling water pumps?

3.

Why are the nuclear service cooling water pump bearing temperature measurement reauirements considered non-applicable?

4 Provide a more specific technical justification for not measuring pump

[. bearing temperatures for all pumps as required by Section XI.

5.

5 1

Is the flo'w measurement instrument accuracy for the comp"nent cooling

) water anc nuclear service cooling water pumps within the acceptable limits identified in Table IWP-4110-l?

t 6.

P Does the pump vibration monitoring program utilize displacement or.

' velocity measurements?

7.

Review the safety functions of the following pumps to determine if they should be incluoed in the IST program ano tested to the Code -

requirements, '

i .

Diesel Circulating Cooling Water Pumps ,

i Diesel Fuel Oil Transfer Pumps

• Spent Fuel Pit Cooling Pumps

! Boric Acio Transfer Pumps .

I i.

I k e

i 12 G

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