ML20195F938

Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Palo Verde Units 1,2 & 3, Informal Rept

ML20195F938
Person / Time
Site:	Palo Verde
Issue date:	02/29/1988
From:	Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML17304A788	List: ML20195F938
References
CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7432, GL-83-28, NUDOCS 8811220443
Download: ML20195F938 (21)

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'D-V ENCLOSURE

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. EGG-NTA 7432 February 1988 2

INFORMAL REPORT a Idaho National Eng/neer/ng CONFORMANCE TO GENERIC LETTER 83 28, Laboratory ITEtt 2.2.1--E0VIPMENT CLASSIFICATION FOR ALL OTHER SAFETY RELATED COMPONENTS:

4 PALO VERDE-1/-2/-3 Managed .

by the U S.

Depenment .

ofEnergy Alan C. Udy i 1 i

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w DlSCLAIMER Tm,s eCet *as creca'es as an a:::wet ef *0ri s00msorea et an egency Of tme ust+s

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3:es m01 hectlla'4v CO*lt twie Or FD'y sta Sm00rlement, feCOM%et:Cm, Or fav0nng Ov t*e V4tta $14't9 GM**4*t Of smy 4;tmCV tF9'90f The vt*14%$ 0060PS Cf ast*0rt 9 D't45e Fe't>m 30 m01 *0Cellarily State OP f ft 4C1 thCl4 Of the VMt3 $tates Gove'eme*t et 4*y 4;eacy t*4't:f e

EGG-NTA-7432 !

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TECHNICAL EVALUATION REPORT i

CCNFORMANCE TO GENERIC LETTER 83-28,  !

ITEM 2.2.1--E0VIPMENT CLA55!FICATION FOR ALL OTHER  !

SAFETY-RELATED CCMDONENTS: PALO VERDE-1/-2/-3 l i

i Decut Nes. 50-52E/50-529/50-530  ;

i Alan C. Ucy [

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i Ab11she: February 19ES  !

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ano Natienal Engineering Laboratory EG!.3 Icaho, Inc.

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Prepared fer the U.S. Ny: lear Regulatory Commission Wasnington. 0.C. 20555 Uncer CCE Centra:: N:. DE-AC07-761CC1570 FIN Nes. Cf.001 and C6CO2

ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from Ur.it Nos. 1, 2 and 3 of the Pale Verce Nuclear Generating Station for  ;

conformance to Generic Letter 83-25,' Item 2.2.1.

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I Oo: net Nos. 50-525/53-529/50-530 TA N:. 5916 11 i

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FOREWORD t l

This recort is supplied as cart of the program for evaluating {

licensee / applicant conformance to Generic Letter 83-28 "Required Actions  !

Based on Generic Imolications of Salem ATW5 Events." This work is being conducte: for the U.S. Nuclear Reguistory Commission, Office of Nuclear (

Reactor Regulation, Division of Engineering and System Technology, by E i Idaho, Inc., Electrical, Instrucentation and Control Systems Evaluation Unit. ,

t The U.S. Nuclear Regulatory Commission. funded this work under the  !

I authorization E!,R Nos. 20-19-10-11-3 and 20-19-40-41-3, FIN Nos 06001 l are C6002. l

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l Oc:(et Nos. 50-52S/50-529/50-530 f TA: No. 59164 {

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. CCNTENTS O .

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l A B S T RA C T . . . . . . . . . . . . . . . . . . . . . . . . . . 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11

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i i FCREWORD .............................................................. iii t

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i l 1. INTRCCUCTION ..................................................... 1 l

REVIEW CCNTENT AND FORMAT ........................................

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t ITEM 2.2.1 - PROGRAM .............................................

3. 3 3.1 Guideline .................................................. 3 3.2 Evaluatten ................................................. 3 l 3.3 Cen:1usien ................................................. 3 1 .

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4 ITEM 2.2.1.1 - 10ENTIFICATICN CRITERIA ........................... 4 l

j. 4,1 Guideline .................................................. 4 o 4.2 Evaluatien ................................................. 4 l

4.3 Cen:1usien ................................................. 4

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. '5 5.1 Gateeline .................................................. 5 ,

5.2 Evaluatien ................................................. 5 5.3 Cen:1usien ................................................. 6 i i

6. ITEM 2.2.1.3 - USE CF ECUIDMENT CLAS$1FICATICN LISTING . . . . . . . . . . . 7 .

t 6.1 Gw1:eline .................................................. 7 i 6.2 E V a l '. a ' i e n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . T 6.3 C:n:1osi:n ................................................. E i

7. ITEM 2.2.1.4 - MANAGEv!NT CCNTROLS ............................... 9 7.1 Gsi:eline .................................................. 9 7.2 Evalua*ien ................................................. 9 7.3 Cen:luli:n ................................................. C i

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S.1 Guideline .................................................. 11 i 5.2 Evaluatten ................................................. 11 l 8.3 Cen:1usten ................................................. I'  ;

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9. ITEM 2.2.1.6 "IMFCRTANT TO SAFETY" CCvFCNENTS .................. 12 9.1 OJideline .................................................. '2 I

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CONFORMANCE TO GENERIC LETTER 84-28, ITEM 2.2.1--E0VIPMENT CLASSIFICATION FOR ALL OTHER SAFETY-RELATfD CCMPONENTS: PALO VERDE-1/-2/-3

1. INTRODUCTICN On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal frem the reactor protection system. Tnis incident was terminated manually by the operater about 30 seconds af ter the initiation of the automatic trip signal. The failure of the circuit breakers was determined to be related to the sticking of the' uncervoltage trip attachment. Prior to this incicent, en February 22, 1983, at Unit 1 f the Salem Nuclear Doner Plant, an automatic trip signal was generats based on steam generator 1cw-low level curing plant startue. In this case, the reactor ,

) was trie:ec manually by t.e c;erator almost coincicentally with the i aut0matic trip. {

i Fo11caing these ircicents, on Feervary 23, 1983, the NRC Executive f f .

j Oire:t:r f: C;erattens (E00), cirected the NRC staff to investigate and j j re:cet on the generic inelications of these occurrences at Unit 1 of the j Salem Nuclear Power Flant. The results of the staff's incuiry into the j gerer4e i :14eati ns of tne Salem unit incicents are reeertee in l;- N AE3-1CCO, "Generic IPolicatiens of tre ATWS Events at the $41em Nuclear l l

=er Plant." As a result of this investigation, the Ccmmission (NRC) 1 recuestec (cy Generic Letter 53-25 catec July 3,1953 ) all iteen.ees of l

c:erating reacters, a;clicants for an c:erating license, anc no1cers of l c:estruction ;ermits to res::nc to tne gentaic issues raisec ey tre  ;

4941yses of tnese tao AiWS events.

l l This re:crt is an evaluation of the resconses suttistes by the Ari:ena l Puelic Service Com;any, sne licensee for the Palo Verce Nuclear Generating  !

j Station, fer Item 2.2.1 if Generic Letter 83-28. Tne cecuments reviewed J for snis evaluatien are u stec in tne references at sne enc of snis re: ort.

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• - 2. REVID4 CONTENT AND FORMT

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. Item 2.2.1 of Generic Letter 83-28 recuests the licensee /apolicant r

, summit, for staff review, a cescription of tneir programs for  ;

1 safety-related ecuioment classification including supporting information, j i in considerable detail, as indicated in the guideline section for each item i within this reDort. ff I

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)' As previously stated, each of the six items of Item 2.2.1 is evaluated f in a separate section in which the guiceline is presentec; an evaluation of (

the licensee's/ applicant's resconse is madet and conclusions about t,he f

j licensee's or applicant's program for safety-related equipment  ;

classification are crawn. I I

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• • - 3. ITEM 2.2.1 - PROGRAM r i

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Licensees and applicants should confirm that an equipment classification :rogram exists that provides assurance that all l safety-related co conents are designated as safety-related on plant cocumentation and in the inform.ation nandling system that controls  ;

safety-related activities. The purpose of this program is to ensure that l personnel performing activities that affect safety-related components are i aware that they are working on safety-related components and are guiced by [

safety-related procedures and constr'aints. Features of this program.are j evaluatec in tre remaincer of this recor+ f 3.2 Evaluation t f

The licensee for the Palo Verde Nuclear Generr. ting Station responded to these recuirements with a' submittal catec Novem:er 3, 19E3.2 This

. suc-ittal includec information that describes their safety-related ecui; ment classification pr gram. The licensee was, at that time, in the process cf integrating the architect / engineer's incexes into the licensee's cata case.

n :ne review cf the licensee's resoonse to this item, it was assume that the infor ation anc c cumentation sue:crt,ing this :r: gram were available for aucit y;en recuest.

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'a t nave rtviewed the licensee's informa* ion arc fin: that i,ne l

1 Itcensee's rescense is acecuate.

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4. ZiER 2.2.&,8 - 10ENT8FfCATfCN CR8?ER8A  !

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- 4,1 Guideline j i

' f The applicant er licensee sneuld confirm that tne program used for r r

ecuipment classification incluces criteria used for icentifying components j as safety-related. j i

l 4.2 Evaluation l I

E The licensee states snat the cri+.eria used to classify structures, systems, ccmcenents, and parts are contained in the Palo Verde Nuclear Generating Station-Station Manual. ine Itcensee states that the manual's procedures conform witn the guidance of Regulatory Guide 1.26 (Rev. 3),

"Cuality Group Classifications and Standarcs for Water, Steam, anc Radicactive-Waste-:entaining ;cemenents cf Nuclear Power Flants," ano t Regulatory Guice 1,29 (Rev. 3), "Seismic Design Classificatien." I Accittenal tasis for classification is based en Regulatory Guide 1.30 .

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. (Rev. 0), Regulat:ry Gwice 1.97 (Rev. 2) and on ti.e Final Safety Analysis j Re:cet, Tatle 3.2-1. The actual criteria are listed in Procedure 7N414.03.00, "Cuality Classification for Structures. Systems Cem:enents, ,

Scare Darts anc Activities." r 4.3 Cen:1usion  ;

L We fine snat tne itcensee has icentified the criteria usec in tne i t

icentification of safety-relatec c: :enents, thus meeting sne recuire ents t

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of ites 2.2.1.1.

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5. fTEM 8.2.1.2 - INFORMAT!ON HANDL8NG SYSTEM 5.1 Guideline Tne licensee or applicant should confirm that tne program for ecuipment classification incluces an informatien nandling system that is used to icentidy safety-related components. The response should con'irm that this information handling system incluces a list of safety-related equipment and that precedures exist which govern its development and validation. ,

5.2 'Evaluatien The licensee states that the infor ation handling system (the C:nstruction Quality Tracking System which is ceing replaced by the Station Infer atice Mana;eeent Syste-) is maintainec :n tre Becntel Syste- 35 QTS data base and censists of an instrument incex, an ecuipment index, and a valve incex, which were originally prepared :y the architect / engineer-(Sechtel), and tneir ewn ccm: uter-casec interactive cata base. The com: uter data was u: cates in January 1954 to incluce tne Becntel incexes.

The licensee's data base was ceveloped by a centractor in accorcance witn a [

cuality assurance Oreg an anc urce* the licensee's suceevision, are new includes the eriginal Becntel cata bases. The licensee i s engineering cecartment revie ec the cata case te veri'y it,s accuracy. Licensee ersonnel also perfor ac rancem audits to verify the initial cata base.

Changes to the cata base are veemit,tec enly nen 4;crevec Oy the engireerin; cecart ent, the cuality assurance cecartrent, anc olant m.a n a g e me n t , in accercance wit.n Statien Manual rececures. Cnanges to tne f cata case are verifiec ey comparing a :rint:ut of enanges made to a list of authori:ec changes. This rececure cule detect any unauthert:ec cnanges. 7 The nu-ter cf personnel autneri:ec to mane enanges in tne cat,a case is minimi:ed, with incividual manage ent accreval of each authe*i:ed (

incividual. Tne casa case is accessible fecm ccm: uter terminals bet.h I

cc-site (at the statien) and c "-site, a c car be retriewec in narc c::y.

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5.3 Conclusien j We find that the information containwd in the licensee's submittal is i sufficient to concluce that the licensee's information handling system for ec'aiement classification meets the guideline requirements. Therefore, the information crevided by the licensee for this item is acceptable, f O

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6.  ! TEM 2.2.1.3 - U$E OF EQUIP"ENT CLA$$!FICATION L!$T!ny 6.1 Guideline Tne licensee's or acclicant's description shou *ic confirm tnat their

r: gram for ecui;&iat clattification includes criteria an orocecures which govern h:w st;li v ' ' 33:#f3% "se the equip-*et clas sification iafer-atice handling system *< e e'< ' ADM Pat an activity is safety-related and what peccedur46 70 .o9te"t#e*,

• 4 1111ance, parts replacetent and other activities cafi sa " L"+ o't zcuction to 4S 7FR 50, Appendix B, apply to safety-riliti c NW **n s .

f.2 Evaluati:n The li:ensee has shewn that statien eersonal use the c:m: uter data in at :etan:e with statich "anWal CP0ce ures a*.: C.ner (i.e., work centr:I, depart ent, anc desigr. c: rte:1) c-::ecu'es to icrntify which activities are safety-relate .

T e licensee has snc=n tnat statie personnel tre re uire: to use the infer-atir4 tndling system as an sie in determir.ing wnat procedures are to to usec fe. $ne a::ve safety-relate: activities. Tne consultation of tne

, infor-atten hancling system is re:vire: by ere:ecures, in:1ucing Nu: lear Engineering Instru:ti:n 71412.01.02, "Cesign Cnange Pa:kage": Statien

• anual Pre:ecure 73AC-9ZZ11 "Techni:a1 Intus and Review"; 30AC-92201, "e:rt C:nte:1"; 73A -92:25. "$4te V::tftcations"; 3010-9I:11. "Maintenan:e w a terial ::ntrol"; 73AO-922:5, "Te ::rary V: ificati:ns C:nte:1"; at:

73AC-91204, "$wevetilance Testieg". Ciner cc::ecures an: instru:?'.cns are referen:e: in relation to the work activities Itste: 49:ve.

Pro:ecure 7N414.03.CC ts cescritec as provicing s:e:ific instructions to plant persernel to cetermine c: cenent classification basec en tne e:uir ent classification listing. It aise provices instructions for initiating a request for an evaluatica of equicment :lassdft:st'.cn an: fer initiatin; an v::ste if tre cata in tre information randling system, 7

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6.3 Con:1usion

- We find that the cescription of plant administrative controls and DrC 40ures egets the recuirements of this item and is, thereforte aC00Dtable.

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.,, /. ITEM 2.2.1.4 - MANAGEMENT CONfROLS 7.1 Guideline The applicant.or licensee should confirm that the management centrols used to verify that the procecures for preparation, validation anc routinJ utili:ation of the information handling system have been followed.

7.2 Evaluation The licensee's response to this item (Reference 2) states that aeriodic quality assurance audits an'd reviews verify the compliance with s effectiveness of the design and material control activities. These iu~ ,d reviews ursure that (a) design changes are justified and are in e with the original cesign control measures, (b) technical and

.Asurance recuirements are specified tnat are equivalent to the Mr 1 recuirements, (c) mocifications are handled in accordance with

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• control crecesses., (d) purchased items and services comply with the procurement specifications (e) the icentification and control of materials is in accordance with identified recuirements, and (f) only those items that nave satisfied their purchase requirements are installed.

Reference 3 describes tne construction Quality Tracking System and the Station Infor.mation Managemerit System that will reciace it. This system is controlled by Procecure 7N5201.02.00, Revision B, "Software Controls." The licensee cesce :es tne tecnnical review anc a:orovals of software enanges, d

test case precaration and verification, software ennancements, incividual system ausrori:ations, protection of the storec information, and system cocumentation. Quality assurance audits also provice upper management with verification that the procedures are followed for crecaration, valication, anc routine use of the Station Information Management System (or the Construction Quality Tracking System).

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. W: find that the management centrols used by the licensee to assure that the information handling system is maintainec, is current, and is used as intenced are acc'eptable.

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8. ITEM 2.2.1.5 - DESIGN VERIFICATION AND PROCUREMENT o.

8.1 Guideline The applicant's or licensee's su:mittal should document that past usage demonstrates that acprocriate design verification and cuaiification testing are soecified for the procurement of safety-related ccmponents and parts. The specifications should include qualification testing for expected safety service conditions and should provide support for the applicant's/ licensee's receipt of testing d0cumentation to support the limits of life recommended by the supplier. If such ( umentation is not available, confirmation that tre pre'sent orogram meets these recuirements sneuld be provicec.

8.2 Evaluation The licensee states that precurement soecifications for safety-related j c0::enents include cualification testing in accorcance with the criteria of I

ne FS/R tne "Cesign Crd teria Manual," IEEE Std 323-1974, ANSI N45.2.11-74, ANSI N15.7-76, and NUREG-0737.

3.3 Conclusica Al tn0 ugh tne licensee cic not specify the cesign criteria 4;;11ec to this item, we conciuce that the licensee has adcressed the concerns of nis item anc, tre*efore, ne finc ne res:Onse for inis ite acce:tacle.

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• ' e- 9. ITEM 2.2.1.6 "IMPORTANT TO SAFETY" COMPONENTS P

9,1 Guideline Generic Letter 83-28 states that the licensee's equioment classification program should incluce (in adcition to the safety-related comconents) a broader class of components designated as "Important to Safety," However, since the generic letter does not require the licensee to furnish this information as part of their response, this item will not be reviewed. t e

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10. CONCLUSION Based on our review of the licensee's response to the specific recuirements of Item 2.2.1, we find that the information proviced by the licensee to resolve. the concerns of Items 2.2.1.1, 2.2.1.2, 2.2.1.3, 2.2.1.4 and 2.2.1.5 meets the requirements of Generic Letter 83-28 and is acceptable. Item 2.2.1.6 was not reviewed, as noted in Section 9.1.

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11. REFERENCES .

1. Letter, NR0 (D. G. Eisenhut) to all Licensees of Operating Reactors, A;plicants for Operating License, and Holders of Construction Pe-mits, l "Recuired Actions Based on Generic Imolications cf Salem ATWS Events (Generic Lette,r 83-25)," July 8, 1983.

2. Letter, Ari:ena Public Service Company (E. E. Van Brunt, Jr.) to NRC l (G. Knignton), Novemoer 3, 1983, ANPP-28167-WFC/TFQ, File 83-056-026;

! G.1.01.10.

) 3. Letter, Arizona Nuclear Power Project (J. G. Haynes) to NRC, "Generit l Letter 83-28 Response," September 15, 1987, 161-00507-JGH/PGN, Fils l 87-A-056-026.

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%',"i d',' Bl8UOGRAPHIC DATA SHEET EGG-NTA-7432 set .ntt.vC'.omt C= f.g .g,t.se eaae' .

l CONFORMANCE TO GENERIC LETTER 83-28. ITEM 2.2.1--

[ EQUIPMENT CLASSIFICAT!QW FOR ALL OTHER SAFETY-RELATED *:. -

__. 1 COMPONENTS: PALO VERDE-1/-2/ ~ ...""3' February 1988 I

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EG&G Idaho, inc. '*"'"***

P. O. Box 1625 I Idaho Falls, ID 83415 -

06001

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This EG&G Idaho, Inc., report provides a review of the submittals from

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the Arizona Pohlic Service Company regarding conformance to Generic Letter 83-28.

Iten 2.2.1, for the Palo Verde Nuclear Generating Station, 1

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