ML19296D668

Requests Onsite 800206 & 07 Meeting to Discuss Responses to Encl Info Needs Re Inservice Testing Program

ML19296D668
Person / Time
Site:	Point Beach
Issue date:	01/03/1980
From:	Schwencer A Office of Nuclear Reactor Regulation
To:	Burstein S WISCONSIN ELECTRIC POWER CO.
References
NUDOCS 8003120734
Download: ML19296D668 (8)

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[d'f s- "i NUCLEAR REGULATOR COMMISSION 0,

UNITED sTANs s

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,,.J s w/j sanusry 3,1980 gv Docket Nos. 50-265 and 50-301 Mr. Sol Burstein Executive Vice Presiden-Wisccnsin Electric Power 00:cany 231 West Michigan Street Milwaukee, Wisconsin 53201 Ocar Mr. Burstein:

In conducting cur revies Of / cur inser vici testing program fo-Point Beach Nuclear Plant Uni s 1 ar.d 2, we navi determined that we sill need the additional informatior identified in :ne enc 1csure :: : an-i nu e the review.

From past experience wi-h similar reviews. ee have found t :at a meeting with the licensee is ths most efficier: ritrod to review resp:nses in detail and to seek clariff rg informatior that usually becomes necessary i

frcm our evaluation of jo.:r ir.itial respc ses.

Therefore, rather than ecuest a written esconse at this cirr.s, we would like to meet with you a the Point Beach site on February E a-d 7,1980 to orally discuss your resp:nses to the information needs ide-tified in the enclosure. The :u c::ce of this meeting would tner. retsemitie what additional infor:na-ion wculd need tc be sutrnitted.

Please contact us if you as e any questic9s concerning tr.is rsouest.

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Y A. 5:hwencer, Chief Seriting Reactors 3ranc- #1 Tivision of Operating Reactors

Enclosure:

Recuest for Adcitional Information cc: w/ enclosure w s w a[' L)I See next page D

s 80031 e o 7 3'/

Sr. Sol Burstein

'isconsin Electric Power Company January 3,1930 cc:

Mr. Bruce Churchill, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D. C.

20036 Document Department University of Wisconsin Stevens Point Library Stevens Point, Wisconsin 54481 Mr. Glenn A. Reed, Manager Nuclear Ooerations Wisconsin Electric Power Company Point Beach Nuclear Plant 6610 fluclear Read Two Rivers, Wisconsin 54241 4

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Tre folicwing are c:- er s and :;uestions on ne se-vice esting Programs (IST. su: '- sc 3 ne Wisc:nsin Elec--i: P:wer C:r:any for tre ?oint Beach Nuc:ea- ::' ar Plants, L'ni: 1 on May 19,1977 and

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' regards to tr.e :5T s :T.' tais is civided int: 'ou secticns :

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1, 7, anc : :.=s =n:cn are :r:vi cec a -- an emergency ecwer source are su:'ec- : inservice test ;

A -a :nere any puros in :r.e :lan: :-ovided wi.a enerese:v :ower that are n o # '. n C '. L d =.~ ' a..... =.' S. r r- ;.,.- ?

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to be iTeasu-e: 3r a varia ie speed :u :.

Tne licensee does not lis : : 5:eed as a est parl eter to be reasured.

Are all :ne p.::s 'isted c:nstant scee: :ur:s ?

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. 2.3 Ser ice Water Pumas (? 32A, 3, C. D. E. and F) Page 1.5 2.3.1 Are the pumps located in a fixed resistance system?

2.3.2 Will the pumps be tested individually?

3.

GENEPAL 00ESTIONS AND COMMENTS - VALVES 3.1 For all valves, provide information en the normal position and the emergency position of tne valves.

3.2 For all Category A and 3 valves, lis

ne limiting value for stroke time.

3.3 For cneck valves tested wi n ne :umo :es t, exclain how it is determined, folicwing ne cumo es, that the valve flac:er has returned :0 i s seat? Aisc, d:es :ne test provide a full flow est for One valves?

4.

SPECIFIC CUESTIONS AND COWER 5 - '!ALVES 4.1 Category A ' Val ves.

Provice exercise fre;tency for the folicwing valves listed in :ne !$7 program-Val ve Vaive 316 DI-9 31 3 DI-10 Containment permanent tes: ccnnection ( A-E)

WL-1755 WL-1757 3est-accident vent system valves 12 and 13 ( A-E).

Permaner.t test connection valve "B" ( A-E)

H -3 containment samole line (2-E) 2 H -9 containment sample line ( A-E) 2 Post-accicent containment ventilation valve No. 4 ( A-E)

Post-accident containment tentilation valve No. 5 ( A-E)

Post-accident containment eentilation valve No. 5 (1-E)

?:s -accicen containment ventila:icn valve No. 7 ( A-E)

Val 19 VaI Ve in-::n IA-35A 32'5 632 759 u-r

,,C l'7M Od 3212 7595 3213

. 4.2 Cate; cry 3 and C Check Valves.

The folicwing valves are listed in tne.nt: 2 IST prc; ram.

They are, newever, not listed in :ne Unit 1 IST program:

Valve Val ve 842A and B (Cat. C) 6675 (Cat. C) 853A, S, C, and 0 (Cat. C) 889A and B (Cat. C) 554A and 3 (Cat. C) 852A and 3 (Cat. 3)

Why are these valves missing frca the Unit 1 IST program?

4.3 Category D Valves 3 ace 1.11.

Are nere any explosive opera:ec vai ves in ne IST ;r: gram?

4.4 Valves 352A an: 3, Centainment Sorav 3umo Suction Check Vaives ( Drawin; llDEGi7)

The licensee states uhat it is impractical to test these valves as One piping design :ces not allow design ficw thr0ugn the vaives except wcen :ney are actually spraying into the containment vessel, The containment soray pumps P 14A and 3) are tested monthly during periocs when ne plant is aoove cold shutdown conoi-ions.

During :nese tests water is passed from :ne refueling water s:Orage tank (RWST) througn the valves 858A and 3 to the spray pumos and returned througn a test line to the :WST. Why cannot the valves be tested together witn the cum:s ? What percentage of full flow would pass tnrough One valves during sucn a test?

4.5 Valves 262A anc 3, Centairment Soray Puma Discharge Check Valves.

4 Drawing ilGEDi 7; The licensee states nat is imcractical to test these valves other tnan :he leakage test new being performed as the piping cesign does not allow design #icw tnrougn these valves except wnen Oney are actually spraying into the containment.

The valves are Categcry AC valves and C:V's.

The drawing lice 017 shows na: a :es: if ne is located u; stream of :ne valves 352A anc 3 be: ween :nese valves and :ne normally 3:en valves 155A anc 3.

To tas: :ne valves 352A and S would recuire :lesing valves 553A anc 3 anc caening the ncrmally closec valves 36aA anc 3 in :ne :es: line.

Thi s can only be :ccc at refuelic; cutages wnen the system is no: neecea.

Why, :nerefo re, canno: the valves be at least par: strokee curing refueling cutages? What percentage of full ficw wculd pass nrcugh the valves during sucn a test?

- Tne licensee snould also provide infor a:icn en now the

.alve leakage test is being conducted.

4.5 Ya!ves 242A and B, "A" and "B" Safety Injectic, accumulator iscnarge Checy valves ( Page i.li) 2e licensee should provide additional infnma:icn en why it is impractical to test these valves, ard justify the basis for requesting relief from full-streke exercising ne valves.

4.7 2n:ainment Isolation Check Valves he licensee should provice infor a-icn or :ne radiation ex:0sure received curing testing :f ea:r :# re #cilowing val ses, to justify the imoracticali:y :# nat tes ting these

.al ses more nan once a year because :f radia icq execsu re.

Va!ve 757

- C::::cnen-2 iin: 5/ stem 755A and 3 - C:mcenen-2c'in; 5/ stem 304C and 0 - Chemical ar: 7clu e Centrol S/s tem 370

- Chemical ard Volu e Control Sys tem 523

- Nitrogen Suo:ly Sys tem 529

- Reactor akess Wa e-Suoply 4.3

' al ves 33A and 34A, Ins trument Air to ne 2n ainment, Centainmen: Isola:1:n Checx Valves t 3 5;e

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-me valves 33A and 34A are not in :ne lis-ing of ca:egor/

A ::ntainment isolation valves (CIT s' On : age 1.7 of ne

IT program. The valves !A-35A and 363 ara, n:uever, lis ed as instrument air to containment cneck va'ves,

cate;0ry AC valves.

Should the valves 33A anc 3 3 have

een listed as I A-35A and 35A valves ?

4.3

diticnal Containment ! solation Valves (C:V's)

Jai.es 2017 and 2013 are main steam :ned val.as and snown as ::V's en drawing M-2Cl.

Dey are :: 'nch:ed in :ne

'is: Of CIV's sncwn in : ages i.7 and '.i :# : s :57 Oregram.

as -ec : mend reviewing :nese valves #:r ir:lusic

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-::itional Category 3 Valves ne re::c: end rev1 ewing the follcwing va:ves f:r inclusio.7

'n ne IST program:

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'/alves 326A, 3, and C (.0 :r ::s-sted boric acid tank isolatien valves), snown c

raaing 110E017.

'/alve 2033 (Supply trip vai ze), shown on drawing M-201, sneet 1.

'/alves 1000' (2) and 4001's (2', (Motor operated gate valves), located in the auxilia / feed pumo discharge lines to ne steam genera.;rs a.d shcwn on drawing M-217.

'/alve 595 (gate valve), ic:a:ec in the nitrogen supoly to

ne Pressurizer Relief Tar < anc sncwn en drawing 541F091.

Are the above valves safe y e:itea? :# :ney are safety related, ney snould te ir::.ce: in :ne :57 ::r gram.

4.11 0-her Catecory B '/alves The following valves are 'f s e: as category 5 /alves:

'lai v e SA-9

- 5 ea. 1.o:iy to racwas te system SA-10

- 5 21 I.coiy to radwaste system Hcw are these valves sa#e /

-r teo? If :ney are not safety related, tney coul: :s.eleted from tne IST program.

a diti:nal Cate;0r/ C '/al.e 4 12 r

'We rec 0=end reviewing hs #:11: wing valve for inclusion in me IST program:

'/alve 857A (first off hig-sa: safety injection check valve), shcwn on drawin; 'l:EC 5.

!s the accve valve safe y rela ?d? If it is safety related, i: should be incluced in ne !!! orogram.

?.13 acciticnal Cate; cry E '/al.es A: =cugn 'W'/-1300 of - e T i:itien of Sec-icn XI of ne A3ME 5ciler anc ress. e 'isssel C ce excludes valves

.s e: for c eratir,; ::nven er :e inc -'aintenance cnly from

es:ing re:ui rements, 4 - "I s s afs coinion and recem-encation tnat any sucn vi:.e 4-icn is in :ne normal or a::erna:e ficw pa:n :f ::: ; ea er of :ne EC'S system,

1. "Om ne source to ne rei:::r :: clan: 3ressure boundary, sncula ae incluced in te talve esting program.

f :ne talve is nor-ally 10cke: ::a. :P closed, it snould be reflected in the 3r: gram in: :ssignated " Category E."

Tais recom.encation aisc ao *is s :: engineered safety systems wnich a, designed to rem ve cs:ay heat from ue reac*or

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