ML20141H206
| ML20141H206 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 09/25/1996 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18102B310 | List: |
| References | |
| NUDOCS 9705230216 | |
| Download: ML20141H206 (133) | |
Text
17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE Public Service Electric and Gas Company (PSE&G) is responsible for assuring that the operation, maintenance, refueling and modification of the nuclear generating stations are accomplished in a manner that protects public health and safety and that it is in compliance with applicable regulatory requirements. To carry out l this responsibility, PSE&G developed and implemented a comprehensive Quality Assurance Program that was applicable to the design, construction, and testing j phases and is now applied to the operation phase.
The Operational Quality Assurance Program is described in the fclic.ing docum:ntc;
- 1. !!C."" P0.Z2 0010(O), Operational Oualit-/ ?.ccurance Progr,ar C;tchilchC th; OuClity T.CCurancc ProgrCr G-c Nuclear Administrative Procedures Manual - This? manual l establishes and documents the programs and processes that implement the QA Program.
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The QA program provides measures to assure the control of activities affecting !
the quality of structures, systems, components, to an extent consistent with their importance to safety. The Quality Assurance Program encompasses fire protection of safety-related areas and other activities enumerated in Regulatory Guide 1.33. A planned monitoring assessment and audit program assures effective implementation of the Operational Quality Assurance Program. An assessment is a direct observation of activities and review of documentation to verify compliance /conformance to specified requirements and ef fectiveness of processes.
The program provides coordinated and centralized quality assurance direction, control, and documentation, as required by Nuclear Regulatory Commission (NRC) criteria set forth in 10CFR50, Appendix B. The program provides for monitoring, assessing and auditing elements of the Fitness-For-Duty (FFD) Program as set forth in 10CFR26 and is applied to and includes non Q-list (i.e. balance of plant) activities and services necessary to achieve safety, reliability, availability and economy in the operation of Hope Creek Generating Station.
Applicable NRC Regulatory Guides, codes, and standards, as well as the policy statements contained in the Nuclear Administrative Procedures Manual, are used by PSE&G organizations performing activities affecting safety to prepare appropriate implementing procedures. To assess the effectiveness of the PSE&G Quality Assurance Program, independent auditors from outside the company audit the program every 2 years for compliance with 10CFR50, Appendix B, and other regulatory commitments. Reports of such audits are made directly to upper management.
17.2-1 HCGS-UFSAR Revision 8 September 25, 1996 9705230216 970516 PDR ADOCK 05000272 p PDR
Quality Assurance (QA) policy statements are issued by key management representatives, including the Chairman and Chief Executive Officer and the Chief Nuclear Of ficer and President - Nuclear Business Unit (CNO/PNBU). These policy statements are mandatory throughout the Company for nuclear facilities.
Key policy elements, as they apply to nuclear safety, include the following:
- 1. Nuclear safety is of the highest priority and shall tr.ke precedence over matters concerning power production.
- 2. The public's health and safety is the prime consideration in the conduct and support of Public Service Electric and Gas Company's nuclear operations and shall not be compromised. All decisions which could affect the health and safety of the public shall be made conservatively.
- 3. The Operational Quality Assurance Program is an essential part of the PSE&G commitment to safe and reliable nuclear power operation.
Applicable program requirements shall be strictly adhered to in the performance of activities covered by the Operational Quality Assurance Program.
PSE&G requires its suppliers and contractors to assume responsibility for establishing and implementing Quality Assurance / Quality Verification (QA/QV) l programs, as applicable, to meet 10 CFR 50, Appendix B. However, responsibility for the overall QA program is retained and exercised by PSE&G. QA reviews those programs and conducts appropriate monitoring and auditing as required to assure that the suppliers are properly implementing their QA/QV programs.
Thel Operational QA Program verifies that requirements necessary to assure quality are properly included or referenced in procurement documents. In addition, these suppliers' procurement documents include applicable PSE&G quality assurance requirements for items and services provided by their suppliers.
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l 17.2-2 HCGS-UFSAR Revision 8 September 25, 1996
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17.2.1 Organization The Operational QA Program, referred to hereaf ter as the QA Program, assures that l adequate administrative and management controls are established for the safe operation of the station.
Implementation is assured by ongoing review, monitoring, assessment and audit under the direction of the Directs . - Qua.lity .'.ccuranec/"uclear Ca hty nctic.:,
Nuclear: Training,iand Emsrgency; Preparednessi;(DirectoW:;-[ QualityhNT,Tand;EP); who reports to the CNO/PNBU.
Implementation fore the'non-QA'areasiunder the1controUfofftheiDirector-Quality!
x NT and EPfis assured;byf the;Managef-;[Qualitp;;? Assessment!)
Company organization is shown on Figures 13.1-1 through 13.1-10 and 17 . 2 - 1.
Responsibilities for activities affecting safety are described in the following sections.
17.2.1.1 Nuclear Deoartment The CNO/PNBU is responsible for managing and directing the nuclear activities of the company. Overall duties and responsibilities of the Nuclear Business Unit l are provided in Section 13.1. Vice Presidents, Directors and General Managers reportingtotheCNO/PNBUareresponsibleforimplementationofQArequirementsl by their staff. These QA requirements are contained in the Nuclear Administrative Procedures Manual and in individual department documents.
The CNO/PNBU regularly assesses the scope, status, adequacy,andcomplianceofl the QA program to 10CFR50, Appendix B through:
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- 1. Frequent contacts in staff meetings, QA audit reports, audits by l independent auditors, NRC inspection reports and department status reports.
- 2. An annual assessment of the QA program that is preplanned and
- documented. This assessment addresses the scope, status, and adequacy of the QA program. Corrective action is identified, and tracked.
17.2-3 HCGS-UFSAR Revision 8 September 25, 1996
17.2.1.1.1 Quality Assurance The Director - eAfNGR Quality,[NTi and Ep Quality ".ccuranec/ Nuclear Cafety ncricu l is responsible for defining, formulating, implementing, and coordinating the QA program. He has been delegated the authority and has the independence to ;
interpret quality requirements, identify quality problems and trends, and provide locommendations or solutions to quality problems. He is responsible for approval of the QA/NSR Department Manual used during the operations phase of the nuclear stations. He also is responsible for verifying compliance with established requirements for the QA program through document review, inspection, monitoring, 1
assessments and audits for.a111 areas ^ except1those nonfQA7 areas.lunder hiafcontroli j QA provides a centralized coordinating function for QA/QV activities applied to
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the operations phase. l
.. ... . I The Director - QA/NCR; Quality,.'NT,fand-EP has the authority and responsibility '
to stop work, through the issuance of a Stop Work Order, when significant conditions adverse to quality require such action.
The PSE&G policies and organization structure assure that the Director - QA/NCR QualityRINT,farid1LEP has sufficient organizational freedom and independence to carry out his responsibilities.
I Responsibilities of the Manager - Corrective Action end-Ouality Cerviccc include the following: !
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- 1. *dminictration Of the Nuclear nepair Prograr G-1. Review of engineering documents such as equipment specifications, .cld proccdurcc, :tc. for inclusion of QA requirements.
Gj2. Review and approve specifications for Q-listed materials, equipment, and services.
4}3. Review of procurement documents for insertion of QA requirements.
- 04. Conduct of supplier surveys, audits and surveillances.
(5 . Evaluation of prospective and existing Supplier QA Programs.
E 6. Administration of the Corrective Action Program.
B/;7. Performing statistical analysis trend reports for management.
17.2-4 HCGS-UFSAR Revision 8 September 25, 1996
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@8. Monitoring / auditing of nuclear fuel fabrication and installation.
Mj9.. Review of NBU fuel specifications for inclusion of QA requirements.
Mio. Perform material evaluation activities on items subject to the QA Program.
- 12. r rferr Ced: related insp : tion: and test performance.
- 12. Perferr de ig chang: pacheg: pr impl;; ntation r cicu and closure r cicu for : mpliene :ith Incpection Held reint: !!Mre) li Performing perfer= n: b : d insp::tien (!Mre)
Responsibilities ahd(authorities; of the Manager - Quality Assessment include the following:
m11 ~ ,^ s.Theias_th.o.. r. i..t.ip:.T.mandTr. espons..i..b. i_l. .i. tpI to.l sto.
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.m w.orW..t...h. r_ong. h.... %.. ..heiissua. h.ce fo....f..f. a Sto@6rMlOrdefy9henis ignifibantiTc6hditilons[advesse i t'o[qua Kitp]iequirsh such:!^actiont ~
27 ~ $Thelfrssdoni]andTauthorit'y}tol'[directlplichess]thelCNO/PNBt$iffths[nesd[for a dch!acce s siesis t si fo r'[angis sue ;;undeg: his;yespons ibili tp{includingitholse rslat's_ d.%dinosf0A.?arussTunder,
-. ~m o- ? theThontifol?;of?
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rhe.?DissctiskjM...oualitsp5.mNTf>
an. d. .S.E. P ?
- 3) " !;lThe} re spbns ibilitp;;and (suthbritpff orNe riffing lc.omplisnclejith[b s Esbiished j requirements ][of AthelQAlpfogramXthi!6ugbydocumen t@ revi(wsjjinspections)) !
EssessmentMsnd}suditis@f[nonjQAIaFuasYahdbE3theib6nti6176f Etihef Difeetoi ,
{QualitipMNT$shd{EPR iThishscidd sTths aUth0Eitiy))ltl6 int lent5keti QA
.progpamirepireme~tafduringic6nduchyofithe[abovelactlivitiesh
-47 Development and implementation of the QA Audit and Assessment Program.
3-51 Performing assessments of contractor activities and evaluation of emergent
- contractor programs and procedures.
1.
i G-C Planning and scheduling of surveillances conducted within the Nuclear l 1
- Business Unit.
I j 4-7 Performing station procedure review and concurrence.
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). h8% Preparation and maintenance of the QA/NSR Department Manual, the QA
- program description in the UFSAR, and the Operational QA Program description in the Nuclear Administrative Procedures Manual.
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1 l 6,-97 Review of the Nuclear Administrative Procedures Manual for compliance with 4
- the Operational QA Program.
-7 10. Performing assessments of PSE&G Program administrative and implementing 4
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procedures (as necessary, these assessments may also include station
- administrative and implementing procedures).
4.11} Conducting QA Program orientation for NBU personnel and administering the training and certification program for QA personnel involved in l inspection, assessments, and auditing activities, maintaining the QA training plan, and maintaining QA training records.
9 12. Review of new regulatory requirements for QA program impact.
4413. Coordination of the commitment verification program on a selected basis.
1l4}."(j[PerformXcode7Ealatsd {lsispechionsM6estjjpeffo'rmaneQ[ahd71eviduJbfjssld proceddresIforync.lssioRo.f[QK[reqsirements!
A511dPe%fprmldesiign;;l chang [packagQreffplementatidRreviewiand@lbsuse;'lfevies ox , -- -
f,,o. r...'T.:.c,s,,mpl,;iance.. 7..s.>.i. t...h. l.lIn.spe. .c. t,io. rf. C,H. .ol..d. :7. Po.. i. n.ti....m:l,.s.(.I.,H,. .P...a. .). .,!
.- . . .~,, -. .
M.{ [Perf orminsprformancej bas le.di{inspscti6ns [
17T ymplernentationj o;fithe"[onsit e71ndspsndentp rsvieV ?
17.2-5 i HCGS-UFSAR I Revision 8 September 25, 1996 i
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Eccpencibilitic cf thO Managcr !!uclear Cafet; Rcricu arc dcccrihcd in l Ccction 12.1.
Pecpencibilitic Of the Manager 1.icencing and Regulation arc dcccrihcd in Ccction 12.1.
Re spbns ibilities foffthe} Prog ssm y Manags r$ 7NdclEsr] ReviewfBoard lincidde sE.t,he follokingi li [ProVides?shpport(ltojthslNucleahRevisw:lBoardi(NRB)[tb]lensuref that the[NRB. E sa perfornitit s[f dncti;ongmanagemen t foVe raightloff the 3 NRB{sObcommittee s hnd[NRB findepyndent(seji'ewsgand %verifiss3.the }d%acy[of[10CFR50} 59 SafetyyEvaluationsyand3.that@thefpfopOsed[setidhdydoy[ndtM;isv0lvs$an l Unreviewed safety lQdestioni
- 2) [Minage's : and idminidt'ers? thef trailningj: requirements for(Nuclear;; Review' Board personnelj, Responsibilities of the Manager Employee Concernsh [th.e)[Te'chnical Trninini/Servidss( ManageQ theh operh tions straining] ManAgerf[Andj thejf Eniefgency PreparediManager are described in Section 13.1.
17.2.1.1.1.1 Quality Assurance Personnel Qualifications The Director - 0"./!!Cn} Quality @NTyand(EP and the QA managers reporting directly to him must each have a combination of 6 years of experience in the field of QA and operations. At least 1 of these 6 years of experience must be in the overall implementation of a nuclear power plant QA program. A minimum of 1 year and a maximumof4ofthe6yearsofexperiencemaybefulfilledbyrelatedtechnicall or academic training.
Personnel performing insnections, examinations, and test activities (i . e . , to verify conformance) ar. certified as Level I, Level II, or Level III, as appropriate to their responsibilities, also in accordance with Regulatory Guide 1.58.
Personnel performing quality assurance audits are certified as auditors or lead auditors, as appropriate to their responsibilities in accordance with Regulatory Guide 1.146.
The qual'ificationslof personnel lperformingjtheMnsitefindependent" review; function
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a relde scribed j ihlS e ct ioh!17f2T1* ~1. 2 M]
The Director - 93r/NGNQ6alityLNTEand EP fulfills the above qualifications with
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the addition of the following: ,
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- 1. Knowledge and experience in quality assurance, andlsafety,j 1
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- 2. High level of leadership with the ability to command the respect and cooperation of company personnel, suppliers, and construction forces,
- 3. Initiative and judgment to' establish related policies to attain high achievements and economy of operations.
l 17.2-6 HCGS-UFSAR Revision 8 September 25, 1996 l
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- -. - ... -- ~. - .._~.-. ---. - - .-. . . - - ~. _-. _--- --.~ . - _-- , . . -
t 17.2.1.1.2 Operational Review ,
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,. . . . . . . . . and A1,1j. programay. .. ..., Tprocedurssj requiredy byl.Technicalif Specifications,. .,Tandlchanges i
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f i thsrsto..f.il. sil'17.be"revieaed in taccorda.n.celwit.h,Sectionfl.7.2il!1. 2 f bslow2 Three advisory groups, the Station Operations Review Committee (SORC), the Oncit; C:fety ncvica grcup (CRC), and the Of fcite cafety revicu 5: cup (OCP), the Nuclear
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RentiewlBosrd. MN.1(D)a mMand Qualitp}Assessmsht[(Qldl{:(onsitssl;1ridepsndent"reVisEQ are
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responsible for reviewing and evaluating items related to nuclear safety. The overall responsibilities of these groups are provided belos in Ccction 12. 0. %e !
". nagcr Quality Assessment is expectsd]to'be"ref iresented ~ lati invited to all SORC meetings and rcccivcc the minutcc cf the mcctings. (C)!!c attenac the mccting l
pericdically.
As part of its offsite independent review functions, the OGR NRB is responsible for selected preplanned, independent audits of plant operations ir acccrdance l with Technical Specification requirc=cntc. These audits are generally conducted
- by QA under OGH NRB cognizance.
I 1".2.1.2 "scicuccd Tcctine Cerviccc l l l l The "anager "spicuccd Tccting Cerviccc reports to the Circcter Ducinccc and '
"cintenance Cerviccc ir fcccil generation
":plcuced Tccting Ccrviccc perform: calibratienc, analyccc, and Ovaluatienc cn cyctc=c, equipmcnt, and :tcrielc, ac rcquccted by "CEiC dcpart cntc, nd T.cintainc Oc=pli nce uith :tc qu lity :ccur nce prograr l , , , , ,
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I 17.2-7 HCGS-UFSAR Revision 8 September 25, 1996
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17;211Ji?2.7 j7echnical.fReviewfand(. Control I
1 ACTIVITI.ES911llprogramsLand procedures [ requited by Technicallspecification 6(8?
and bhangesitheretMandfany[otherlpropbcedlpkocedures1.brfbhanges3theretio which i affectQplahtinuclesr[ safety [asideterminedibyJthe;[ plant?;managergbtherf than j
' edit 6ria17oritypographicalEchangesishall'be reviewedias*followsi
. PROCEDURE)RELATED DOCUMENTS M: Procedures J prog rams {and
- changes 5there tof shalll be reviewedT as -l followsi 1l [ Eachj.hewlyfereatsd(procedured program;[or;ichange{therstofshallibe. i indepen~dently}; revibwedj bpj anTindividusl5 knowledgeab1;sifini;.the isrea I af fectsd T other fthanithe findividual:?nhol piepsredi the;y proceduref program 7 ori procedure Mchangell; 1;; butfif whoNmay;[ be y;f romMthe7same i
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organization ~asl thelisdividual/ group.phichlprepsied !ths; proeddureief procedure $ change! ;(Procedures y other7than{l Station [ Administrative procedures willl:be;;approvedfbyl:.thelappropriatfDepartmentl Manager {o,r by 'the. plant lmanagerj f Each DepartmentiManager{shall?belYesponsible forfali[ predesignated (classlofL procedures.l [The[ plant 4 managerishall' approve? LStatio[rq {Administrativel (Procsdures{ JSecOElty] }Plad imple.iient'in's;proceduresiand Emeigencyl Plan: implementing prdceddresj 2'; :. Onf thef spotJ changes l1 to} proceduresj whi~ch[ clearly]do Thotishangeithe intentlof;S thsfapprosed[proceduresfshall:lbe;il approved)by;Ewo? members ofithe? plant managementJstaffif;atlleast!one ofTwhom:holdsfa" Senior ReactorLOperatorlLicenses (Revisi'onsito procedures'which; map (ihvolvs afchange7linlintentjoflthe? approved lproceduresjshal1lbelreviewedlih 6ccoYdanceIwithLitem"I'Labovel
& , JIhdividualsf responsiblei fori reviepsTl performed sin !. accordancelwith ;
item?1?above"shallibs?approYedibpfthe V SOR.C(Chairmaniand[desighated as i St'ati6n { Qualified s Reviewers? f A[ system 7;of j$ Station;f Qualified ReviewersTahal17belmaihtained}by[theTSORCjChairmankCEach:reviewi l l HCGSLUFSAR
.-~ _ . . _ . .. .
shallj inciddej[a}yri t ten {de t e rmina tion;io ffshe ther?'6rinotf additi6hal [crossidiaciplinarpj[reviewj;isinecessary] ;[IfJdeemedj::;necessarpffssch isfiew$shallf(be-{pstfokmed7 bgthe?appr6priate7dssighstiedEFssieW
@rs6nn, elm They ts tiloh;;[. Qualified'Revi;ewersl shsil[.mee tjoKexesed..@h6 g.da..l.if. ic. ati.ods.T.. descfi..b. e..d. i. i. nlSectio. hT. 4!17snd.
. ~ m ?4 M_of?..AN.S.
m - f. 3.E. C.M?i981_?
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4..'h 'j;IfsthejDepa)tment@Matiagek7 determines;$thatithes;dochments? involved re,,@ireT.a si.OICFR
.- - .n. ~- E 50 l59,? s sf. st. yf. eValdatiiddQthE[d6hdinehtsyshs111 be forwasded?;;for3SORC[reviswlandfalsoltof the?Nuclsa2SlRspieWB6sidTf6r ad@ fndepeydentWeviepst o{de t ermine} whe thew orfn6tlad]unreviewed s a f etpye st'ionTis iinYblUed O Pdradantj t6liO) CFR [.50 ~ 59 R NRCljppr6 val' of 7 [htemailinvolvingyi.inresiewed O[ safety [gsesE5ha$or QTebhkcall S@cificationfchange's);shal;11be}cbtained}priorNo?impinmentyiony >
NONiPROCEDUREiRELATED ;DOCUMENTSf?TestsJof]egerimentalandj chahgesitoj epi.pmenti cris.pstsms T. shalf. besforsarded,".. f. b. r7. SORC. 7reUisE7
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. and7s, issit67. ths T.Ndel5sriRevis. w B6ardifoF sa findepehdent9revie wJto ' de l tfurniiheiwhethe r fofi[not Ean?unrev.tewsdTasfstsp q
~ usstiion$1s31nv61vedb (The[resh1_ts?;of{the;iNuclearlRevienfBoard] reviews 10111]be' proYfdsdfto?SORC{TRecommehdati6nsjfoE7appfoOal]are]msd6}b [SORCl;t6[ths}plsht managsr@((LPdrsuan titofl0j CFRM 0 j 591{NRClapproval]of].itiems{ involving [uhrevi;ewsd
- sa f etyye a tions} orlyequiring(Te chnical?l Spe cif ica.tionfchangesi'ahallibe7obtained priorit'6'{implementstiodj V
RECORD'7S ANDQEPORTSN ~cw. Writtis_n'iEsd6d,s OfEisYisEs?.cperfd. r.med*i.d. /Ac6ofdance!{Nith iteml171boVsMinciddingyrecammendatiche?foffapproVal(offdisappfoValgkha111be .m..a_in. t.. ained.? a 17f227b HCGS-UFSAR,
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1 l l l 17. 2.121 ; 2. 21 S tation ! Operations. ' Review.. Commit' tee;i. (SORC) l j FUNCTION 3 The Station; Operations.ReviewlCommittee?shall function to~ advise the plantjmanager odiall' matters;related to nuclear safety. l l COMPOSITION -.i The.; Station Operations .. Review Committeej(SORC)lshall.ibel chaired'by the'; plantf manager "an.dishal.li;befcomposed ;;ofl regular members S f romithei Hopel; Creek Generatingl S tation(- s taf f [NUcl earI Engine sringif NuclearTMaintenahde'and 4;f rom Ithe
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Quality Assessment organization'havihg.experiencejin each of the"following akeasi l l 1. ' P1 anti;EOperations
? Engineering 4
- 2. j
- 3. Maintenance I i
- 4. Echemi:stry 5l ; Radiation; Protection i 6. > Quality Assessment
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l The? member having : experience ;'in[ the" areal lof "Radiationi. Protection E shall meetL the qualificationfrequirements'oflRegulatorp Guide'150Ll/ September 1975h $Allfother members Lshallimeet$thej requiremer.tsf of[ ANSI /ANS J3 {i;1981:[;fornthe{ appropriate discipline; : A11 membersTshall-be appointed;ih writing by the' plant an'ager;; TThe l Vice~Chairmenishall be'" drawn lfrom1the?SORC membersfandLahall"befappoint'd:/in e Writ.ing by the ' plant; manager? ALTERNATES 7?All i alternate i membe re] shall? be Tappointed 1:Linfwriting byLtheLSORC Chairman. H OnlyL;[the ;'. designated Vice" Chairmen or : thel plantf managerf mayfactfas Cha'irmani of:f a'/ SORCT meetin{.i S Nof morei than C twoI al ternat es ?i to};'membb es fahill participate l asf voting l members inf SORCf activities Latiadyfonelme~etthg. s Alternates
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for;X:membersf.will{not[makeTup} partf;of Ethelvoting).;quoruml;Lwheh} the ~ member;the alternate! represents isfalsofpresent; MEETING FREQUENCY [- The SORC *shsll . meet atileast'once1per salendar month 'and 'as convened by thel SORC.? Chairman [or':: his. design' ate'd.; alternate. 1 i 17;2 7c HCOs.vyggy
1 J 1 QUORUM iW2 The ![quoruniTlof ';;the7 80RCi neces saryf f 6r7theiperf ormande]jbfithe] SORC 4 responsibility}andl;authorityJprovisions3cff t:his3se6tiesyshallicensist;;iofJthe. Chsirmanforishis 7 design..a.tsdialtiernate7andf. styleast":[:f6uEyinsmbersEiscluding
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'lternat'es?
a RESP,0NSIBILITIES $ Thel:[ Station [OperationsfRevies} Committee?shall{be[Yesp6nsible fori
- 1) [ReviesTof 5 Q1)[ Upper;[tiefadministrative;[pfocedures;jithirf,the[" scope offRsgulatoryjGOidej:1!33]J2QB)y[ add"; changes][theretWand3f 2)] Nesly
- b. r. e.at_ed' procedures ~ orichanpeRto;Teiciating?proceddies ![thsbye%difs"A
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10fCFRl50 ? 59.(safety;;svaluation]:'as ?.desci1 bed ;inj Section117E2ifff 72111 l 21 1.Revies[6f [al l7 prop ~o se'd;[t s s tsland lexpsriment sj that ya f f e c t {ndeleiar satety} 3M ?Reviesh of:1 fall;f fpr6posedj Tbhanges) {toli Appendix] QA"i s; Technical Spe;cifications1 45 jRevie'w[offsllspropoesd[chahied[6rimo;dificati6ns;(to} plant?systenis]:;or equipment lT;tta ti;a f f ect{ndelea rZ sa fe tyy 53 2 Review [0fithef; safety {epalbatichs?thatChavelbeenfco@leted;;undsr.[ths; pkovisi'onsfofjl0jCFR}50159]
'0 6 EIn.itiation7or][revies:Loffinvestigationsi;of T alliviolatichs lefif the TechnisaHSpscifibsti6ns)-inclhding[thelrep6rtsicovering74valuatiod and!yecommeddationsitojprsventfreentren'es[ i 71:. 1Revies'of3al1$REPORTABLEiEVENTS! l l
i 1712-7d HCGSiUFSAR
82 ..Review : aff f acilityloperations J to .; detect ;ipotentiallnuclearjl safety hazards; 9; iPerformancelof 7 specia1Hrevieks;finvestigations f:offanalp.ses1((and reportsfthereonlasfreguestedLbyj;theiSORCi 10; FReviewloff the;1FifeIProtedtion[Programland;;-_1mplemsnting]procedu;res And[chingeshthsrstolthat"reju}iseial:10ilCFR 350i S 97. safety [svaluation ? I l I 11 0 ;L Reviewl of.j allf unplanned;;;ont site { releases f of f radioactivityf to7; the environsl: includingT ths;:jrepsra ti6a7affreports) cove sing fevdluat;ioni recommendations;[andfdisposition ';o f l the.fcorrectivejh et10nitoj presenti recurrencei l 1 1 12;'; j; Review L of s cha.nges]tbi thef PROCSSS$ CONTRORMANUAL;1] and s;: the70FFjSITE DOSE.CALCULATIONjMANUAL/ l AUTHORITY;M TheFStation;Loperations'Reviewl:Committeelsha11j ii ? Provide recommendationsi;in[ writing;tojthe;lplant(;managerfindicating approval 3;;;;or? :Ldisapproval.:[' o f;; yitems conpidered3 under?Ethe~ SORC responsibilities"above. 21 [ Prdvids[Nrittea$ndtification2WithinT24 T houEs[ to S[the [SsnioB Vibe Pres identMNuclsae(Opera.tions ,j[the LDirsetoFRQual~itpy NTf and] EP{ and ; Manag e ri - ;Qdalitgyf As s e s sment To f f- disag re ementJ betwe en K ths '; SORC snd t the 1 plantTmansgery houspee,;) ; ths@lant Shanageri7sha11[:[hsys
~responsibilityf forfresolution flofist.ich :J: disagreements [purssant5 to Technical? Specification;6(1];1!
2 RECORDS AND[REPORTSf?l: Thel l Station :Operationsi:Reviewf Committeefahally maintain tuinutes"of each'meetingTAnd copies shall::bejrovidedfE61ths:LSehibr:Vics Presidsht'
~
N Nuclear [ Operations ,(thsT Directorf Tj(Qualityd!. nth.] and EP$ thel Manager;Q Qsality Ascenamenty{andfthe Nuclear'ReviewTBoards 17j2@7s HCGS;UFSAR
17.2)l;ll. 2. 3 ; ;[6uclear?; Review Board : (NRB) The .NRBishall' perform the offsite independent' review function andlshall' . provide
~
oversightLforl audits of:: activities'~affecting plant' safety 4 .One ' NRB ' has i been established tolprovide"this1 oversight for;both. Salem and-: Hope l: Creek' Generating Stations; Its purpose "is s.to revieQaudit,; andH evaluate both . technicalj ? and
~
organizationalE~ matters pertaining.tofsafeTopesationlof the'stationsi TheLNRB shall R' be' ' established 1 ~in Ca'::writtenL charter .;thatT includosL Tmembershipi responsibilities , ;; reporting requir'e'mentsi.l potential' ; areas ? to l be~ reviewed, fand
~ ~
6ther aspectsine'ededlfor. operation'of ?the NRB. ?TheNRB shall function. to provide offaiteTindependent" review and"auditlactivities"in"the:follo' wing:areasi
- a. 1 Nuclear Power; Plant Operations b' . ' Engineering c . : Chemistry land. Radiochemistry '
- d. " Instrumentation and Control el .' Radiological: Safety f6 ? Quality [ Assurance g.' 1NondestructivelTesting hl ' Emergency Preparednes5 The NRB members shall collectively possess experience land competence in;the areas listed above. LConsultants orjother technical' experts lshallf6eLutilized-by the NRB.to thelextentinecessary. l NRB members'~shall-.meetior ekceed the qualifications [ described intSection 4;7?of ANS.713 1 1981h ; ExceptionsT to;} ;' the' ANS T 3.1-1981 L Sectionf4 4 7 (( qualification requirements can be" granted to a maximam*of two NRB members provided'stichlmembers
~
meet the followingfalternative qualificationsi L1) alminimum'of' twenty- (20}Tyears nuclear related' experience):12) ?shall' hold'or have' held 'alsenior reactor. operator license or " certification? and. 3)1 shall~ have'. served ~as*a ;minimumiin a: nuclear vice -presidentC or:Jequivalent:!; position! ;The Director;Qnality,; NT, 'Tand EP will approve 1and2;; document . the { alternativel:l qualifications foff NRB imembers Twhere 1 'exceptioni'to the;l; ANS -I ' 3.121981 l Section 64'.76 qualification ? requirements ( Tis necessary. The'NRBfshall report";tofandTadvise$theJChief Nuclear" Officer 'and-President 7 Nuclear BusinessiUniti;(CNO/PNBU)fon' those areas of responadbility pertaining to NRB; review and assessment. 17~2-7f HCGS-UFSAR
Th3 NRB satisfies the' requirements ;of 7 ANSI : N18.7-1976 - (ANS : 3.2) , - in ; that" the
~
E board fis composed of no less1than five' menNrs and no:more"than a minorit;y'of these members areifrom'either~the; Salem'oriHope Creek' operating organizations. A'quorumfshall consistiof not'less.than'a' majority..of.the rrembers, of' whish no more " than f a minority Joff thosai present-:Eshalli have E'linel responsibility ~for operating . the i plant . The Chairperson 7 of f the L NRB will) be} appointed ' by": the CNO/PNBUi The PSE&G members. shall' be selected f rom PSE&G management . personnel. In addition,la-minimum of three external consultants shall be ' members of the NRBi Meetings 7are scheduled by the' NRB' Chairperson'. .( A minimum 'o.f ~ two ' meetings a' year are conducted. : Minutes!of)the meetings'shall be prepared and? distributed to the CN0/PNBU.' The NRB,l and those. performing reviews or audits /assessmentsiunder.the cognizance 'ofl the 'NRB,'shall have access' to records and~ personnel:asEnecessaryjto properly
~
perform"theirifunctions. : The' NRB'shall;'be '. kept currention. cvents within L its responsibility by reviewing some or'all of7 the' followingT SORC minutes,; Licensee Event Reports,iviolations,..and/or audit reports, and.hylthe.'activitiesfof the board members;
~
The'NRB shall meet"twicela. year as'a' minimum,J3r more often as' determined by the Chairman ~. The NRB may appoint l . in~ writing '(such as in'. Board meeting' minutes) ,' subcommittees for'the purposes;of; performing revi~ews'~or studies in' areas'requiringLparticular expertisef.or for/ performing'specialiinveJtigations'. JNRB subcommittee' members shall-meet. or exceed the qualifications described in Section 4'.7'of ANS '3.1-1981; Thel chairperson'of an NRB subcommittee shall"be an NRB' member; The NRB'.or subcommittees /organizationsfappointed bylthe.NRB.shall: review:
~~
a; L The? safety evaluations i for-(changes + to L procedures, . equipment,:. or systemsiand tests or.[ experiments completedLunder thefprovision of 10CFR50.59E to' verify)>thaelsuch 1 actioris did1: noti constituteEan unreviewed' safety'questioni EThe results. of the Nuclear Review Board j reviews willlbe provided to:80RC. l
- b. Proposed changes to procedures, equipment,- or: systems, and ' tests ' or experiments that. involve an unreviewed safety question as defined'in 10CFRSO.59.
1 I l l 17.2-79 I HCGS-UFSAR 4
l
- c. JProposed changes (tolTechnical SpecificationsLor[ Facility [ Operating l Licenses; dy iviolations Y of .' app 11 cable ~' statutes;; Jcodes,; Tregulations{ Lorders;)
Technicall Specif1 cations;: ' license J- requirements [;llorfoffinternal - procedures or instructientF.havingjnuclearj aafety[ significance.
- e. i Significant (opera ting.;.;.abnormalitiesj or ?deviationsT f rom ! normal and expected performance Lof(plant" equipment;that; affect .nuclsar? safety;
- f. 1 Reportable eventsjrequired byj10CFR50.73.
gi Allf recognized l indication ? offan ?unantibipated ? de ficiencylinf some aspect 1of designior operation:of) structures /l systemshor.:; components thatic6uld?affectfnuclearfssfety]
- h. l Reports?and]heeting minutes of2the~SORC.
Thel NRB1 will E utilize f asl 'necessary,7: the foperating ; experience? feedbackfl(CEF) program tb revies current plant andfindustrp concerns 'and perform 'spect'a l' studies
~ '
and' investigations. Assessments /addits shall:be' performed.by;QA7 or:(byf speciallyjelectedl~groupsfoE
;indi?iddals, . ?includingi ; independent:C l[ consultants;; 1 who;i 1havej 2no? simmediate responsibility l fori the activit'y; they"l assess?'land' do Enot; f while] performing [the I assessmentj [r'eport: ; toi L a ' (inanagement ' f representativej l who i ' has} ~ immediate responsibility]forf:the act!ivity being; assessed?
~
2 Final audit; reports!shal1}be' reviewed;by;the NRB. The auditolshallfinclude: 4 1 l a". ; Thefconformance of facility,. operation _ to provisions lcostained within Technical' Specifications ~and(applicableilicense' conditions; l by . The; performance; trainingJ;and qualifications ef; the; entire facility l staff. ; c; ; The ' results 'of L actions; taken to ' correct deficiencies ' occurringlin
~
i facility ' equipment,- structuresf systemsfor method;of operation' that
- affect nuclearfsafetyp l
- d. The. performance.offactivities..requiredfby"the; Operational 1 Quality Assurance; Program ' to ineetithe ; Criteria l of ; Appendix LB . tof10CFR50, 17 '. 2 -.7h j HCGSiUFSAR 1
I
1 1 Q lAny,other3rM;'of[facilitploperation" considered. appropriate:by;the Director R ouslity[fNT,[and';;EP[or:the"CNO/PNBU?: fj .; The : f acilityl Firs l PEotectionTProgram'andlimplementing} procedures . l g ',' i AnL assessment lof Tthel" Fire JProtect; ion";and : Lossf Prevention ~: Program l implementation] .;lusing) [an] [estside~; 71ndependent? { fire ifl protection consultant h*. :LTheiradi61;ogicalfenvironmenta1{'monitoringipEogram"and the?EesOlt's thereofi
- i. r; The [ OFFS ITE" DOSE ll CALCULATION 1MANUALTand ? implementing i procedufesi jp jThe'IPROCESSU SCONTROLT PROGRAMj1End MimplEsentingfiproceduresj[for !
processing;fand packaging;;off.radi'oactive Mastes! kJ i-The { perf ormancsfof i activi tiesi required [ bylthe (Quali ty;i As surance Program for;:::efflhent;;:;and';;envifonmental? monitoring; The auditischedules shall; belreviewed.anndallysbylthe NRB' toiensbre that':they}are' being[ performed inTaccordance with 'thisTsection'of ?the '.UFSARj Recordsto.f NRBireviews 'and; minutes 'of'NRBimeetings ;shal1[be maintained! [ Reports of . reviews { meeting mirutes and :' auditTreportat sha117be.. prepared andldi'stributed aslindicated:belowi. E. 1 Minutes"of}eSch2NRB{ meeting [andiElrepOrtLofjNRBfrevisws{perforsed shall':j be[ p~reparediand[ forwarded (to? th' 7CNO/PNBUfwithin? e 307 days follo. wing)the meetingj i b; " Audit] reports'; shal1[belforwarded'; tof the? CNO/PNBUf andj management positions 1 responsible [: f or ~ the'(areae ? audited T within T 30 ? days ;- af ter completion? of j thelaudi t exiti meeting] for L those lauditsi conddcted; by f the"OA1Departmest'land(within soldaysTafter; completion of:f.hefaudit i for2 those ~ auditis ' conducted. by';'an" independent consultant! i ! l 1 17k2S71 i HCGS-UFSAR I
1 l l 17;.2.1;1.2.4[ J.Ossite IndependentLReview j l I The' ManagerMQuality ; Assessment 'shall": bei responsibleT for.Lonsite Tindependent , review, 1The(;onsite? independent'reviewishallibe' performed byFa' minimum offfour ! h ) .: pe r sonnel ' whoi arefindependent i of; planti managementi fThese[ individuals':shall reportjtolthe ManagerT-;QualityfAssessment. ?TheTManager f Qualitp! Assessment shall' utilite'the!information obtained during 'onsite independent review asjinput
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to advise managemention.(:the~overallTquality and:. safety lofjoperationsjand(shall
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reportjto'andladvise~the CNO/PNBU,j through the Director ::-- Quality {NTfand EPkon' l l the results: of Lonsite independentIreview' si . For onsite" independent l review issues .. involvingi nod-QAf areas 1: underithe^ Director's j controlb the f.Manageri;ViQuality Assessment'has:the1 authority toldirectlyTreport thelresults tolths CNO/PN3UL The personnel performing onsite independentL review shair function'to provideF the
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review of ' plantfdesignTand' operatingj experience if 6rf potential?oppoi-tunities#to improve plant safety; Levaluation1of plant';~ operations and maintenance activities;
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and ' advice :to management 1on the; overalliqualityj and safetyf offplantioperations. Thesef- personnel? shall' make f recommendationsj for revised) procedures k equipment modifications, ~or;7other J.meansf Lof;;.improvingf plant;5 safetyC;.tofappropriate atation/ corporate' management. ' Onsite independent review shall.;encompassi i al fReviewlofiselectedfplant~ operating [characteristicsgNRC;fissua;ncesi industry advisories,?andLother appropriate'lcourcesEofiplantidesign and [ operating ' experience (information ' which - may ' indicate l areas.. for improving. plant safety. 4
- b. Review of;selectedLfacility: features [ equipmenty andfsystems.
l l
- Review M ofiselected j procedures ' 'andf plant (; Activitie5 j includincj e.
maintenance, .. modification, deperationallproblems, (and.] operational analysis; d.; - Surveillance of' selected plant. operations?and maintenance activities to.Jprovide): independent ~ verification: that"'theyl 'are:Dperformed correctly and that human; errors;arel reduced toias low as: reasonably achievab1'e. The personnel performing theLonsite independentjreviewlshalfLhavei '1)*at'least three < (3)-' years related experience lof which 'at leastl: twol.(2)j years' are nuclear related, f and'a' Bachelor Degre'e Tin Engineering or a related field; or 2) atjleast eight (8); years related: experience, of which~at least fivel {5) years are nuclear l related; 17.2-7j HCGS-UFSAR
1 At;leastififty percenti(50%)2. of .the' personnel;? performing;; the"onsite'. independent reviewishall;haveLa~'BachelorTDegree in! Engineering orfalrelated: field? JForLths di scipline~of,; 0pera t ions',ffal s enior ^ reactor.; operator;/ license ;';or;~; certif i cation . may be) used Tas lan?;alteinative lqualification Finstead?of 2' a';;f Bschelor ;) Degree l :in Engineering ~orf a irelated'. field / Personnel [ performing;thetensitelindependent? review functionishall;7be]qualifisd ini thefdi;scipline ' related to:;. the.. ' assigned Larea!of j review.: % single individual may be llqualifiedj to; performi reviewslinimorei than'; one~ discipline G ::The?requisits experience:may^havelbeen gainedfconcurrently.;linirelatedJdisciplines: The Directorf'-7 Quality,!:NT/fandIEP-will1-l approve"andddeument?the;[quslifications of ~ thosel; personnel:: performingj theTonsite "independentilreview";'who;f arei; qualified ba'aed: on Jat?least eight';1(8)? years ;;related.Texperience; 17.211}2.1lMaulewood'Testino" Services I Ths D Managerl: -f Maplewood iTesting';; Services ;; reports? tol; thel DirsctorM:~Servibe company);(Servco) fin (the] pSE&G L F6ssil.[. Generation , 1 Maplewood Testing l Services
- performs calibrntions, anslyses,'land evalustionslon spstems,;; equipment, land materials [as requested by.NBU departmentuT;'and. maintains compliance'withTit'sfquality[assuranceprogramasl approved'by}NBUQA7 1
17 5'1137 Deleted i i l I 17'2-7k HCGS-UFSAR
17.2.1.4 Distribution Systems DeDartment The Vice President - Electric Distribution Systems reports to the Senior Vice President Transmission and Distribution. The Distribution Systems Department is i responsible for providing support to Hope Creek operations for setting and l testing protective relays for the external vital power supplies at the station. 17.2.2 Quality Assurance Program [ The QA program is designed to comply with the requirements of 10CFR50, Appendix B, and with fire protection program requirements of Branch Technical Position CMEB 9.5-1. This program is applied to items and activities that can affect the health and safety of the public, i.e., Q, F, and R-designated items and activities. During the operational phase, this includes:
- 1. Structures, systems, and components delineated in Table 3.2-1 and marked as Y in "QA Requirement" column.
- 2. Safety-related activities delineated in Regulatory Guide 1.33 and summarized in Table 17.2-1, Section A and additional NRC i requirements contained in Table 17.2-1, Section B. ;
i
- 3. Portions of structures, systems, and components whose continued function is not required, but whose failure, caused by a safe !
! shutdown earthquake (SSE) , could reduce the functioning of a Seismic ! Category I structure, system, or component to an unacceptable safety level; or could result in an incapacitating injury to occupants of f i l i i t i i 17.2-8 i HCGS-UFSAR Revision 8 September 25, 1996 ;
- .. . - . . . . --. . - . -. . - - -.- - -.. = . - . . . . - . . - - -
1 1 the control room as shown in Table 17.2-2 and further delineated in Table 3.2-1.
- 4. Fire protection systems, including emergency lighting and j communications, shown in Table 17.2-3, and further delineated in l Table 3.2-1 as well as administrative controls, such as fire brigade training, control of combustibles and ignition sources, and firefighting procedures. ,
I
- 5. Radwaste management systems described in Table 17.2-4 and further delineated in Table 3.2-1.
The QA program is applied during the cperational phase using a graded approach to the extent consistent with the item's or activity's importance to safety. Where there is an inconsistency between tables (i.e., Tables 3.2-1, 17.2-1, 17.2-2, and 17.2-3) , the item will have QA provisions applied until the conflict is resolved and tables revised. These activities are performed in compliance with applicable regulatory requirements that include but are not limited to: 1
-1. Regulatory Guide 1.8, Qualification and Training of Personnel for )
Nuclear Power Plants
- 2. Regulatory Guide 1.17, Protection of Nuclear Plants Against Industrial Sabotage
- 3. Regulatory Guide 1.26, Quality Group Classifications and Standards for water, steam and radioactive waste containing components of Nuclear Power Plante
- 4. Regulatory Guide 1.29, Seismic Design Classification
- 5. Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment 4
4 [ 17.2-9 l HCGS-UFSAR Revision 4 l April 11, 1992 I
.-- - .. - - . - . . . . , . - . - - - =. -.-
P l
- 6. Regulatory Guide 1.33, Quality Assurance Program Requirements I (Operation)
- 7. Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants
- 8. Regulatory Guide 1.38, Quality Assurance Requirements for Packaging, i Shipping, Receiving, Storage, and Handling of Items for Water Cooled Nuclear Power Plants l
l
- 9. Regulatory Guide 1.39, Housekeeping Requirements for Water-Cooled Nuclear Power Plants ;
I l
- 10. Regulatory Guide 1.52, Design, Testing, and Maintenance Criteria for l Atmosphere Cleanup System Air Filtration and Absorption Units of l Light Water Cooled Nuclear Power Plants !
- 11. Regulatory Guide 1.54, QA Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants
- 12. Regulatory Guide 1.58, Qualification of Nuclear Power Plant ;
Inspection, Examination, and Testing Personnel
- 13. Regulatory Guide 1.64, Quality Assurance Requirements for the Design of Nuclear Power Plants l i
- 14. Regulatory Guide 1.74, Quality Assurance Terms and Definitions
- 15. Regulatory Guide 1.88, Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records
- 16. Regulatory Guide 1.94, Quality Assurance Requirements for Installation, Inspection, and Testing of Structural !
I l l i 1 l 17.2-10 HCGS-UFSAR Revision 0 April 11, 1988 l
. . -- - .-- - -- .. .= .__ . - - . . .. ~ - . _ - . - .-
1 Concrete and Structural Steel during the Construction Phase of Nuclear Power Plants )
- 17. Regulatory Guide 1.116, Quality Assurance Requirements for ]
Installation, Inspection, and Testing of Mechanical Equipment and j j System ; l
- 18. Regulatory Guide 1.123, Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants
- 19. Regulatory Guide 1.137, Fuel-Oil Systems for Standby Diesel Generators
- 20. Regulatory Guide 1.143, Design Guidance for Radioactive Waste l l
Management Systems, Structures, and Components Installed in Light i l Water Cooled Nuclear Power Plants. i l l
- 21. Regulatory Guide 1.144, AuditingofQualityAssuranceProgramsforl Nuclear Power Plants
- 22. Regulatory Guide 1.146, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants
- 23. BTP 9.5-1, Appendix A, Guidelines for Fire Protection for Nuclear l Plants Docketed Prior to July 1, 1976.
j l Commitments to Regulatory Guides, with respect to revision level, exceptions, ! etc, are contained in Section 1.8. l 1 The code QA requirements are used for the procurement of systems, components and structures covered by the ASME Boiler and Pressure Vessel Code Section III (classes 1, 2, and 3). The standard QA program controls apply to Q-Listed code items following receipt at the station. In addition, applicable requirements of Regulatory Guide 1.38 are applied to ASME Code procurements where necessary to l assure safe shipment. l i i ( I 17.2-11 ! HCGS-UFSAR Revision 8 September 25, 1996
)
Substantive changes to the QA program described herein will be submitted to the NRC within 30 days of implementation. Nonsubstantive changes will be identified in the annual UFSAR updates. The station General Manager has instituted and will maintain a station administrative procedures (SAP) manual. Regulatory Guide 1.33 requires that plant activities affecting quality-related items and services be conducted in accordance with written administrative controls prepared by management. The procedures and instructions by which plant 1 activities are performed are prepared by the responsible organization as required by Nuclear Administrative Procedures Manual, reviewed by the organization responsible for the activity, reviewed as required by QA and SORC, and j l l l i 1 i t i l l I r 4 j 17.2-12 4 HCGS-UFSAR Revision 8
- September 25, 1996
approved by the department manager. Nuclear Administrative Procedures (NAPS) and Station APs and all subsequent revisions thereto are reviewed by QA and SORC and are approved by the Station General Manager. Procedures cannot be implemented unless the review / approval process is accomplished. The Nuclear Administrative Procedures Manual provide a means to accommodate on-the-spot changes to subtier implementing procedures. The routine practice for revising a procedure is to repeat the original review and approval sequence. Implementation of the QA program is verified by means of independent inspections, I assessments, monitoring, and audits conducted by QA. ; QA reviews and analyzes problems affecting quality that occur during the operational phase. Items subject to review include:
- 1. Documented nonconformances occurring at the supplier's f acility and those identified during receiving, storage, installation, test, and operation, e.g., Deficiency Reports, Nonconformance Reports, Work Orders, Licensee Event Reports, etc.
- 2. Documented corrective actions taken on conditions adverse to quality I and actions to prevent recurrence on significant conditions adverse to quality.
- 3. NRC inspection findings, notifications, bulletins, etc.
~
The Director - Q'/"Sn Quality [ NT,llandlEPfand the' Manager M oualityJ. Assessment l j or hte--their designees, have has the authority to stop work through the issuance ! of a stop Work Order where continuance of an activity would seriously compromise quality or constitute a persistent and deliberate failure to correct a significant condition adverse to quality. Dee4snecc include the "anager Quality *.cccccr.cnt and the "cacgcr ccrrectiv 'ction and Quclity Services for aetifitics under their ccgnicance, b QA reports significant conditions adverse to quality affecting the quality assurance program to respective management along with: 17.2-13 HCGS-UFSAR Revision 8 September 25, 1996
1 l
- 1. Measures taken to improve QA program controls
- 2. Appropriate recommendations to achieve compliance with applicable j requirements.
Management pclicy r.d administrative procedures provide all personnel with awareness and direction for reporting of defects and noncompliance pursuant to 10CFR21. The QA program requires that safety-related activities and activities affecting l the fire protection of safety-related areas, be accomplished under suitably controlled conditions. The program takes into consideration the need for procedures, special controls, cleanliness, special processes, test equipment, tools, and skills to obtain the required quality and the verification of quality by inspection, test, examination, monitoring, assessments and independent review and audit. These activities include, but are not limited to, designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, reworking, repairing, ,
\
refueling, and modifying. j i Personnel who have the responsibility to implement the QA program also have the l responsibility and authority to escalate unresolved quality problems to the level l of management necessary to effect resolution. Escalation is applied by QA personnel to increasingly higher levels of management, up to the CNO/PNBU, as j l required. 1 Personnel performing Q,F, and R-designated activities are trained or indoctrinated as necessary to assure that suitable proficiency is achieved and maintained. Personnel outside the QA organization who perform inspections and tests are trained and qualified in QA concepts and practices. 17.2-14 HCGS-UFSAR Revision 8 September 25, 1996
. - -. - - - - . . . ~ - _ . . . . - _ . - - . . - . . - _ .
t I i Orientation is provided for new employees entering QA from other organizations , l within PSE&G and from outside the company. An outline of the course content and \ program objective is contained in the QA training and certification program. The training and certification program is designed to familiarize the employee with:
- 1. Codes, regulations, specifications, etc, applicable to nuclear and other power generation equipment i
- 2. QA procedures, instructions, specifications, documentation, records, etc
- 3. Auditing and assessment objectives and techniques t
- 4. Operational Quality Assurance Program
- 5. Quality Assurance Operational Philosophy l
- 6. Other organizations within PSE&G with which QA interfaces l
-QA administers formal QA training sessions for personnel outside the QA organization who perform safety related activities. The content of these training programs, dates of the sessions, and names of the attendees and their individual performance evaluations are documented and retained.
i 1 i i J l 1 I l 17.2-15 HCGS-UFSAR Revision 7 December 29, 1995
1 Personnal requiring cartification are evaluated to establish their qualifications for their respective level and discipline. Recertification is based upon demonstrated continued proficiency or requalification, if necessary. Personnel requiring certification in accordance with Regulatory Guide 1.58 are limited to personnel who perform inspection, test and non-destructive examination (NDE) activities, personnel who perform post design modification testing, and Inservice l Inspection Services personnel who perform NDE and tests required by the Inservice Inspection Program. Those above personnel who perform visual examination (VT1, 2,
- 3) and NDE in accordance with the Inservice Inspection Program are trained, l qualified and certified in accordance with a program which additionally meets the prescribed supplementary requirements of ASME Section XI. These personnel receive a periodic training needs assessment to identify additional supportive training needs, as well as, to evaluate individual post-training performance.
The assessment period is three years or less. Personnel who are qualified and requalified for their respective level and discipline in accordance with Regulatory Guide 1.8 and ANSI /ANS - 3.1 and direct or supervise the conduct of individual preoperational, startup, and operational inspections and tests, including Technical Specification Surveillances and periodic inspection and test of fire protection equipment, do not require certification per Regulatory Guide 1.58 and ANSI N45.2.6 1978. When a single inspection or test requires implementation by a team or group, personnel not meeting the requirements of Regulatory Guide 1.58 and ANSI N45.2.6 1978 may be used in data-taking assignments or in plant or equipment operation provided they are supervised or overseen by an individual participating in the inspection, examination, or test and the individual is qualified and requalified for their respective level and discipline in accordance with either Regulatory Guide 1.8 and ANSI /ANS - 3.1 or the individual is certified in accordance with Regulatory Guide 1.58 and ANSI N45.2.6 1978 as appropriate. Regulatory Guide 1.58 and ANSI l N45.2.6 1978 do not apply to NRC - Licensed Operators and Senior Operators for the performance of duties specified in 10CFR55 " Operator Licenses" . The Nuclear Training Center is responsible for the licensed operator training and retraining, in addition to other technical and supervisory training programs. 17.2-16 1 HCGS-UFSAR Revision 8 September 25, 1996
General Employee Training, which is required for all personnel having access to the station, is the responsibility of the Manager "ucicar Cccurity Directorc4 l Quality,)NT, land EP. Training programs of supporting organizations are described in their manuals, which are required to comply with the QA program. l i i 17.2.3 Design Control i 4 1 The scope of the design control program includes design activities associated with the preparation and review of design documents, including the correct j translation of applicable regulatory requirements into design modification, ) procurement, and procedural documents. The design control program includes activities such as field design. engineering, 4 associated computer programs, compatibility of materials, and accessibility for ! i inservice inspection, maintenance, and repair. l l Issuance of new drawings and revisions to existing drawings require the implementation of a design change. The term design change as used throughout this document, shall apply to both design and configuration changes. The Nuclear Engineering Manual (NEM) procedures, provide implementation guidance for the intent of Regulatory Guide 1.64, " Quality Assurance Requirements for the Design of Nuclear Power Plants." QA will conduct periodic engineering process assessments which include procedures contained in the 4NEM&. l The SeniorlVice~ Presidenti- Nuclear Engineering Depart =cnt has the 'overall 1 responsibility]:1for[ theldesignicontrol ! program? fcllcuing recpencibiliticc. Specific ~ responsibilities .Lare ' identified' Tin .Section .13J1'."l~,2 ;1.3 :
- 1. Prepare and update detailed engineering and decign dccumente, including drawingc and cpccifications, for all cyctc=c, componentc, j and ctructurec.
- 2. Epccify applicable ccdec, ctandardc, regulatcry and quality quic ^.nt :::pt;nc st;nd;;d;, nnd Oth: d::ign input in d::ign dccumente.
i 3. Identif y cyctc c, cc=pencntc, and ctructure: that are covered by the l
\
! quality accurance prograr l I ( 4. Pcrform desig; verification for cyctcms, components, and structurcc OcVered by the O? Prograr l ! 17.2-17 HCGS-UFSAR Revision 8 September 25, 1996
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- 5. Perferr ::fety evoluction; cf prop;;;d d ign changen, :: required.
- 52. J.pply Cencri 100"" 50.50 Cafety Evaluation, : requi-r d, to Ocnfiguraticn changer th:t impact the C72
- 5. Preparc dcrument fer prcour:=cnt of equip =cnt, . teri:1 , and 1
_ _ _ _ _ _ _ _. . , . I
-.c....._ ,
J
)
Recertend engineering ccncultents and 1 M r:teric; for procurement acrvic:: :nd accrdinate their ::tiviticc. I S. nevicu design dccument cubmitted by cupplicr ' including the
!!uelen: Sten: Capply Syster 'i!C C C ) cupplier) and contractcre.
O. Specify, er approv: : required, insp tion and/cr tect: M. D ignat whether they will ::ch th: scrvic: cf cthcr qualificd engineering crganizati:nc. The cognizant engineer is responsible for the identification and completion of design analyses. The purpose of design analysis is to assure that the technical design is accomplished in a planned, contrc,11ed, and correct manner. Types of design analyses include, but are not limited to, reactor physics, stress, seismic, thermal, hydraulic, radiation, and accident. Design verification is performed on design analyses, drawings, specifications, and other design documents, as applicable. It is the process of reviewing, confirming, or substantiating the adequacy of design by one or more methods. Design verification is performed on changes to previously verified designs, including evaluation of the effects of those changes on the overall design. In general, design verification is completed prior to installation and in all cases is completed prior to placing the modified system or component into service. l Design verification is performed by competent individuals or groups other than those who performed the original design with the following exception: a design 4 verifier may be the design originator's supervisor, provided that he did not l specify a singular design approach or ; 1 l I 1 t i i 17.2-18 HCGS-UFSAR Revision 8 September 25, 1996
rule out certain design considerations and did not establish the design inputs used in the design, or if the supervisor is the only individual competent to
- perform the verification. This design verification provision is individually documented and approved in advance by the supervisor's management. Procedural control is established for design documents that reflect the commitments of the I
UFSAR; this control differentiates between documents that receive formal design verification by interdisciplinary or multi-organizational teams and those which i can be reviewed by a single individual (a signature and date is acceptable l 1 ' 1 documentation for personnel certification). Design documents subject to I procedural control include, but are not limited to, specifications, calculations, computer programs, system descriptions, and drawings including flow diagrams, electrical single line diagrams, structural systems for major facilities, site 1 arrangements, and equipment locations. Specialized reviews should be used when l l l uniqueness or special design considerations warrant. ! The responsibilities of the verifier, the areas and features to be verified, the pertinent considerations to be verified, and the extent of documentation are ! t identified in procedures. Control of this function is assured through periodic QA/NSR audits and assessments. l Design verification methods comply with applicable requirements of ANSI N45.2.11 and may include, but are not limited to:
- 1. Design reviews
- 2. Alternate or independent calculations
- 3. Qualification testing.
In the event that the verification method for design modifications is only by test, procedures and instructions will be written which include measures to I ensure that: i I' l l 4 l 17.2-19 HCGS-UFSAR Revision 8 'l September 25, 1996
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l i l l l
- 1. Criteria are provided to specify when verification should be by test.
! 2. Where applicable, prototype, component or feature testing will be performed prior to installation of plant equipment. In those cases where this cannot be met, the testing will be deferred but not l beyond the point when the installation would be irreversible. 1 ! 3. Tests will be performed under conditions that simulate the most adverse design conditions, as determined by analysis. l Drawings are prepared by, or under the supervision of a designer from information received from the responsible engineer, manufacturer's drawings, etc. The drawings are reviewed and initialed as being checked by another designer or design supervisor. The drawings are approved by the functional supervisor or his designee. Specifications and changes thereto for items covered by the QA program are preparedbyNuclearEngineeringandarereviewedbySupplierAssessmentforQAl content. QA review assures that the documents are prepared, reviewed, and approved in accordance with company procedures and that the documents contain the necessary QA requirements such as inspection and test requirements, acceptance requirements, and the extent of documenting inspection and test results . The Station Operations Review Committee (SORC) reviews proposed changes affecting nuclear safety and makes recommendations concerning implementation of the change to the station general manager. The design change process provides for sign-off , of the design change by the appropriate department head for the purpcse of l identifying required procedure change. If the proposed modification involves a Technical Specification change, or is considered by the SORC to involve an unreviewed safety question (10CFR50.59), the ,i 17.2-20 HCGS-UFSAR Revision 8 September 25, 1996
matter is submitted to the Of fcit Ccfcty nc cicu Crcup (OCP) Nucle'ar[ Review Board ((NRB); for a determination of its safety implication before a license change request is submitted for NRC approval, rcr Nuclecr Engincering prepcred Duringjthefpreparation J of design changes, l Nuclear Engineering assigns a project team led by a project manager {as required. The project team consists of members of various organizations, both internal and l external to Nuclear Engineering. The project team members are responsible for providing technical and administrative input to the entire design change procees, which consists of design, installation, testing, and closecut phases. The j technical and administrative input is guided by the requirements of those organizations which comprise the project team. The project manager ensures that the specific requirements of each organization on the project team are considered to ensure the overall quality of the product. l For design changes important to safety, the QA representative on the project team provides input and assures that design changes include quality assurance requirements such as inspection and test requirements, acceptance requirements, test result documentation, and project team compliance with company procedures during preparation, review, and approval of design changes. l 1 Updating of records, including drawings, blueprints, instructions and technical manuals, and specifications resulting from design changes, is the responsibility of the Senior Vice President - Nuclear Engineering. Design change procedures l l provide for the timely update of affected drawings following design change implementation to reflect as-built configuration. 17.2.4 Procurement Document Control l i j Procurement documents and changes thereto for the purchase of Q, F, and R-l designated material, equipment, or services are reviewed and approved by QA prior to issuance by the Purchasing Department to the prospective supplier. QA review assures that spare and replacement parts are procured using controls which are commensurate with current QA program requirements. I I I 17.2-21 HCGS-UFSAR Revision 8 September 25, 1996 i l
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The review also assures that procurement documents adequately and correctly:
- 1. Identify applicable QA program requirements
- 2. Reference applicable regulatory requirements, codes, and standards l 3. Provide right of access for source surveillance and audit by QA or its agents
- 4. Provide for required supplier documentation to be submitted to PSE&G or ma.4ntained by the supplier, as appropriate l
l S. Provide for PSE&G review and approval of critical procedures prior l to fabrication, as appropriate. Procurement documents require suppliers and contractors of other than commercial l grade items to provide services or components in accordance with a QA program that complies with applicable parts of 10CFR50, Appendix B. The requirement for notifying PSE&G of procurement requirements that have not been met is conveyed to the supplier through the standard warranty provision contained in each purchase order. In addition, where 10CFR21 is imposed, suppliers are required to comply with applicable reporting requirements. 17.2.5 Instructions, Procedures, and Drawings organizations engaged in Q, F, and R-designated activities are required to perform these activities in accordance with written and approved procedures, instructions, or drawings, as appropriate. l Simple routine activities that can be performed by qualified personnel with no* >n , llls do not require a detailed written procedure. Complex activities regt. detailed procedures. The designation of those activities requiring l detailed procedures is r
- i 17.2-22 HCGS-UFSAR Revision 8 September 25, 1996 i
made by cognizant department heads and as a minimum, complies with applicable , requirements of Regulatory Guide 1.33. Procedures include, as appropriate, scope, statement of applicability, references, prerequisites, precautions, limitations, and checkoff lists of . inspection requirements, in addition to the detailed steps required to accomplish the activity. Instructions, procedures, and drawings also contain acceptance criteria where appropriate. The ctation appropriate General Manager or> Director is responsible for assuring that station procedures are prepared, approved, and implemented in compliance with the Nuclear Administrative Procedures Manual. Documentsaffectingnuclearl safety are reviewed by the SORC for technical content, by QA for QA requirements, and are approved by the responsible station department manager or his designee. 4 The Scnier Vice Precident "uclear Engineering Director $ iNuclear-tBusiness i Support is responsible for issuing specifications, drawings, blueprints, procedures, administrative and technical manuals associated with Q, F, and R-designated structures, systems, and components. Approved and implemented modificationsanddesignchangesareincorporatedinthesereferencedocumentsl for the life of the station. Master lists of current editions or revisions of these documents are maintained by Nuclear Busines's Support Engineering to assure that only current and approved referenced documents are used, i QA reviews and approves selected etction procedures that implement the QA program, including testing, calibration, maintenance, modification, rework, and repair. Changes to these documents are also reviewed and approved. In addition, QA is reeponsible for review and approval of selected specifications, test procedures, and results of testing. 17.2-23 HCGS-UFSAR Revision 8 September 25, 1996
I 1 1 17.2.6 Document Control l l Instructions, procedures, drawings, and changes thereto are reviewed for the inclusion of appropriate QA requirements approved by appropriate levels of l management of the PSE&G organizations producing such documents, and distributed on a timely basis to using locations. Measures are provided for the timely removal of obsolete or superseded documents from the using location. Supplier documents are controlled according to contractual agreements with suppliers. i l The following is a generic listing of key documents for the operational phase, showiug minimum organization responsibility for review and/or approval, including changes thereto:
- 1. Design specification - Nuclear Engineering, QA. l
- 2. Design modification, manufacturing, construction, and installation drawings - Nuclear Engineering, Nuclear Maintena'ce n Operatienc Ccrviccc, station operations j 3. Procurement documents -
initiating Nuclear Business Unit j Organization, !'urchccing Depart =cnt, Nuclear Business ~:' 3 Support Operation: Ocrviccc, QA I
- 4. Nuclear Administrative Procedures Manual - Nuclear Business Unit organizations responsible for implementation, QA l
- 5. Nuclear Business Unit second tier manuals, including station i administrative procedures - cognizant department head, QA
- 6. Maintenance, modification, and calibration procedures for Q, F, and R designated station work activities - Nu' ele'a' r Maintenance Station pt::. d =
- 7. Operating procedures - station operations J
, 17.2-24 HCGS-UFSAR Revision 8 September 25, 1996
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i B. UFSAR - !!uclear Operation: C rne : LibensifiQhdiRegura.tlon and l other Nuclear Business Unit organizations responsible for implementing applicable sections. In addition, QA reviews subsequent changes to UFSAR sections to the extent necessary for assuring compliance with applicable QA program requirements ; r
- 9. Maintenance, inspection, and testing instruction - Nuclear Business Unit implementing organizations
- 10. Post modification test procedures - Nuclear Engineering l
-11. Design Change Requests - Nuclear Engineering, QA l
QA involvement in the work activity includes review of work procedures prior to approval for designation of inspection hold points (see Section 17.2.10), review
~
of completed safety-related Work Orders on a sampling basis, and periodic QA f surveillance and assessments. The establishment and maintenance of a document control system for all ! instructions, procedures, specifications, and drawings received from the Nuclear Business Unit, or prepared at the station for use in operating, maintaining, l refueling, or modifying items and services covered by the QA program, is the responsibility of the DifectoQNucleihBUsisiAAsISUppy Cenior '.'ic: " resident j
!! :lcar Engineering. The Nuclear Administrative Procedures Manual describes the controls for specific documents. Control of station practices is included in the administrative procedures and in departmept directives authorized by the responsible station department managers. Measures are established to assure that j the administrative procedures and department directives are up to date, properly authorized, changed only after the required review and approvals are obtained, and distributed to appropriate personnel. Design change procedures provide for the timely update of affected drawings, following design change implementation, to reflect as-built configuration. Computerized databases maintained by the NBU organization are used to control drawings and specifications.
l i i l i 17.2-25 i HCGS-UFSAR Revision 8 , September 25, 1996 i d
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__. - - .~ _. - - . - - -. -. .. - __ e 1 Revision control of procedures and instructions is accomplished through the control of computerized databases. Controls of sof tware affecting nuclear safety l are identified in the Nuclear Administrative Procedures Manual. These controls are based on applicable guidelines provided by the NRC and include software review and approval as well as access controls to prevent unauthorized software i changes. 17.2.7 Control of Purchased Material, Equipment, and Services
, QA maintains an up-to-date listing of approved suppliers of material, equipment, and services covered by the QA program. This list identifies suppliers and contractors who have demonstrated the ability to supply acceptable material, equipment, or services. The list includes manufacturers of commercial grade items. All QA program procurements are made from approved suppliers.
The responsible engineer and QA personnel select and evaluate prospective bidders and suppliers. The responsible engineer determines the technical competence of the supplier, while QA evaluates the prospective supplier's QA program for the capability of meeting applicable requirements of 10CFR50, Appendix B, and for extending applicable program requirements to subtier suppliers. Qualified QA personnel evaluate the prospective supplier's QA capability using one or more techniques, including but not necessarily limited to:
- 1. Evaluation of supplier's or contractor's procedures or manuals and changes thereto
- 2. ASME code stamp approval
- 3. Nuclear Utility Procurement Issues Council (NUPIC) or Nuclear Fuel Users Forum (NFUF) Audits.
- 4. Satisfactory past history of providing similar items I
17.2-26 HCGS-UFSAR Revision 8 September 25, 1996
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- 5. Survey of supplier's facility The evaluations of the prospective suppliers are conducted using standard ,
! checklist form designed to include the 18 quality criteria of 10CFR50, l Appendix B, as appropriate. Surveys of suppliers' capabilities include evaluation of management systems, manufacturing processes and adherence to QA/QV procedures. The results of l supplier evaluations are documented by the appropriate checklist form and filed. Supplier control is maintained through a planned inspection, monitoring, and ! audit program by QA. i QA and the responsible engineer conduct a review of the manufacturing process for complex manuf actured items, such as pumps, valves, heat exchangers, vesselc, electrical panels, etc. This review establishes critical inspection points and establishes a notification point program for the identified inspection or surveillance activities. The established inspection or surveillance activities are implemented by qualified QA personnel or QA agents. Commercial Grade Items are dedicated in accordance with recognized industry standards, e.g. EPRI NP 5652. 1 Monitoring of suppliers / contractors during fabrication, installation, ! modification, rework, repair, inspection, testing, and shipment of Q, F, and R-designated materials, equipment, and services, is conducted by qualified QA personnel or QA agents at the supplier's/ contractor's facility or at the generating station. Surveillances are conducted in accordance with written procedures and are designed to assure conformance with procurement requirements, in accordance with the safety significance of the item or service. l l 17.2-27 HCGS-UFSAR Revision 8 September 25, 1996
l i l Periodic evaluations of the supplier / contractor quality program are conducted, consistent with the importance or complexity of the item or service. Dependent I upon the evaluation, additional audits or corrections by the supplier / contractor may be required. Supplier's certificates of conformance are periodically evaluated by audit, inspection, or test to assure that they are valid. Results , of these audits, inspections, or tests are documented. Where feasible, replacement parts adhere to the original design criteria (such as Nuclear Steam Supply System (NSSS) components in accordance with NSSS documentation and other code components in accordance with AWWA, AISC, SPCC, and ! ASME B&PV Code, Section III, 1971 and Summer 1972 Addenda or later). This provides the intended level of safety, and does not result in redesign of the system. The requirement for appropriate supplier documentation of conformance t0 applicable code, standard, specification, or other quality requirements is provided by the procurement document. The supplier-provided documentation is reviewed either at the supplier's facility during source surveillance or by l Material Compliance Group during material evaluation activities. A data review checkoff is used to document the acceptability of the supplier-provided data and to identify discrepancies. l Evaluation of supplier equipment, material, and services is conducted by qualified personnel te verify correct identification, appropriate documentation, ! and to verify that the item is acceptable and can be released for storage, installation, or use. l Nonconforming items identified by the Material Compliance Group are tagged or l segregated to prevent inadvertent use. Nonconforming items are controlled as I described in Section 17.2.15. 17.2.8 Identification and Control of Materials, Parts, and Components Procurement document controls provide assurance that materials, parts, and components received can be properly identified. The J w 17.2-28 HCGS-UFSAR Revision 8
- September 25, 1996
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l l l identification is directly marked on the item, or on records traceable to the item. The data review conducted at receiving assures that proper documentation of received items is available. Materials and items received without proper i identification are tagged or segregated until satisfactory documentation and identification is obtained. l Procedures require Q, F, and R-designated materials, parts, and components to be marked or otherwise identified, and require that such identity be maintained i either on the item or on records traceable to it throughout receipt, storage, i installation, and use. Protection against use of incorrect or defective items j is also provided. l Material identification and traceability is maintained for rework, repairs, and I modifications throughout operation. Organicatienc *.ich imple=cnt requirement fcr the identification rad contr:1 cf j
=cterials, partc, and compcncnt; include Nucicar Opcratienc Scrvicca, Muelcarl Enginccring, ctation cpcr:tienc and O? for procurc=cnt document contrcic, and I'recurc .cnt and "atcricic "anage=cnt , station opcratienc and 07. for rcccipt, l cter gc, inct:11ation, incpection and tect activiticc.
l i ( IdentificationM a.ndZeontrol g of [materialsR;.[partsk [and @ omponent p arejfthe fe sponsibilit{6f 1Nusle AkMaintenanFeE Nuclsak Engineeringand.hacle Ari Bus inys s Support) { Procurement 7 document 2controlsfareythe7resporisibilitylof {Qualiti l Assurince! 1 Receipt { storage /finstallation(linspectiorifand(testjactivit'ie's; are i i the?re'sponsibilitp[offNuclesr[Businessj Supportp. OA.2. andlNuclear!MaintenaricsK. 17.2.9 Control of Special Processes Special process controls provide for the use of qualified procedures, equipment, personnel, and documentation of satisf actory completion of an activity. Special J processes are generally those processes where direct inspection is impossible or l disadvantageous. Procedures have been established for special processes such as welding, brazing,
- j. soldering, concreting, protective coating, cleaning, heat treating, and nondestructive examinaticn (NDE) to assure compliance with codes and design l specifications. The Senior Vice President - Nuclear Engineering is
( f 4 d 17,2-29 HCGS-UFSAR Revision 8 September 25, 1996
l responsible for preparing special process procedures such as concreting, protective coating and cleaning, while the General! Manager MNuclearlMaintienance Director Nuclear Opcratienc Servicca is responsible for preparing specifications for processes such as welding, brazing, soldering, and heat treating and . Nuclear Engineering is responsible for preparing specifications for non-destructive examination (NDE). These specifications are reviewed and approved by OA for necessary quality content. QA monitoring assessments and j audits assure that qualification of special processes, equipment and personnel have been satisfactorily performed. Proceduresforimplementingtherequirementsofthespecificationsarepreparedl either by the Nuclear Business Unit or by supplier personnel, and are reviewed by QA and the appropriate general manager or their designees, with the eveeption of special process procedures prepared by code suppliers holding a valid certificate of authorization.
- Qualification records of procedures, equipment, and personnel associated with special processes are retained as stated in Section 17.2.17.
l 17.2.10 Inspection A planned inspection program is conducted and documented by personnel appropriately qualified in accordance with Section 17.2.2. The inspection l program verifies conformance to the established procedure, code, or standard, consistent with the item's or activity's importance to safety. l The inspection program for maintenance and modification activities is based upon t the following three important levels of inspection: '
- 1. Worker Checks - Quality cannot be achieved unless the worker l
performs the activity in a quality manner. The worker is thel individual best able to control the quality of work performed. Work steps that contain 1 l i 17.2-3C HCGS-UFSAR Revision 8 i September 25, 1996
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i l l l elements impacting plant equipment or systems have provisions for l signoff by the worker. This worker sign-off establishes [ accountability for the activity and is acknowledgement that the activity has been performed as specified in the work step.
- 2. Supervisory Inspection - Although the work supervisor may have l overall responsibility for the conduct and performance of the work activity, certain conditions at the work location require i supervisory inspection to increase confidence that work activities are completed as specified through familiarity of the work activity, l work group, or past experience. Supervisory inspections are I
established in the appropriate work procedure and accomplished l through direct observation of the work activity. l
- 3. Independent Inspection - Independent inspections are not intended to dilute or replace the responsibility of the worker check or
- supervisory inspection for quality of work. Independent inspections i
provide the maximum confidence attainable that the work activity has ; been performed in accordance with the overall objective. Typical guidelines for establishing independent inspections include conditions similar to the following: ; Work activity affecting redundant equipment or potentially 3 causing cascading failure. ! Retest will not verify the applicable attribute. Establishing a baseline in a new process or procedure. It is deemed necessary to maintain confidence in the work process. . 1 l i l 17.2-30a HCGS-UFSAR Revision 4 April 11, 1992
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l This guidance is considered by the responsible QA organization in the establishment of inspection activities. I Independent inspections are identified as Inspection Hold Points (IHPs) in the applicable work instructions and are performcd by individuals independent of the work activity. IHPs cannot be passed without authorization from the applicable management representative responsible for the inspection activity. General guidelines for the inspection criteria are established by QA and incorporated into various administrative and work instructions. Independent inspections are performed by QA or other individuals who are independent of the work activities. If the individuals performing inspections are not part of the QA organization, the inspection procedures, personnel qualification criteria, and independence from undue pressure, such as cost and schedule, are reviewed for acceptability by the QA organization prior to initiation of the activity. l Work procedures and inspection instructions include, as required, characteristics to be inspected, method of inspection, acceptance / rejection criteria, required measuring and test equipment, and required reference documents. Documentation I includes inspection identification and results of inspection performance. ' As a result of its review, the Station Operations Review Committee (SORC) may recommend additional or different hold points to the organization performing the l work activity. Periodic inspection, other than IHPs, is performed by qualified individuals other than these who pertermed or directly supervised the activity being inspected. These typically include periodic inspections of the following: l l l i 17.2-30b HCGS-UFSAR Revision 4 April 11, 1992
. . - , . . . - . _ . - - - - ~ . _. _.. ._ . - . . - . - - . . . _ .
- 1. Storage areas l
- 2. Housekeeping (gentsral)
- 3. Fire protection equipment
!. 4. Special handling tools and equipment
- 5. NDE visual inspection required by the inservice inspection program.
An independent organization shall perform NDE as required, using qualified 1 individuals other than those who performed or directly supervised the activity. l i , l l When inspections are performed by individuals other than those who performed or directly supervised the work, but who belong to the same work group, and the activity involves breaching a pressure-retaining boundary, the quality of the l j work is demonstrated through appropriate testing, unless restrictions such as ! ALARA considerations prevent such testing. The applicable inspection and retest requirements necessary to assure that ; modifica. ions, rework, or repairs have been accomplished correctly are included 4 I in the dasign change package, work order, or procedure. The inspection and , retest requirements for modification, rework, and repair are based on the origit.41 inspection and test program, as well as the nature and scope of the i modification or repair activity. l l Evaluation and review of inspection results are conducted by personnel certified l Level II in ANSI /ASME N45.2.6 and SNT-TC-1A, as applicable. l , A planned and documented QA monitoring program is conducted by QA for Quality l Program activities, including the inspection program and personnel qualifications. Monitoring of the l l l i 1 17.2-31 HCGS-UFSAR Revision 8 4 September 25, 1996
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implementation of the QA program by station and site contractor personnel is conducted by QA, in addition to offsite supplier activities as appropriate. j conditions adverse to quality found during the conduct of monitoring are brought l l to the attention of the mr.nagement responsible for the activity. The Manager - Quality Assessment, or designee, routinely attends and participates l in plant work schedule and status meetings to assure that they are kept abreast of day-to-day work assignments throughout the plant and that there is adequate QA coverage relative to procedural and inspection controls, acceptance criteria, and QA staffing and qualification of personnel to carry out QA assignments. l I i i l i 1 I l i l 3 17.2-32 HCGS-UFSAR Revision 8 September 25, 1996
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l l 17.2.11 Test Control Q, F, and R-designated equipment and components that must be tested periodically to assure satisf actory performance, or have been replaced, modified, or repaired, } are tested by qualified personnel in accordance with written procedures that ! provide acceptance criteria based on requirements contained in applicable design and procurement documents. Provisions are implemented that assure that nonconformances are corrected or t resolved prior to the initiation of the preoperational test program on the item. Retest requirements are provided by engineering specifications or the responsible engineer, or both as were the original test requirements. The Nuclear Engineering l[. Nuclear' Maintenance and operations departments are responsible for preparation of test procedures incorporating the engineering parameters. Test procedures prescribe, as applicable:
- 1. Prerequisites, including completeness of test item (s)
- 2. Instructions for performing the test
- 3. Instrumentation and equipment for conduct of the test adequate to the test objective
- 4. Suitable environmental conditions and adequate test methods
- 5. Critical test sequence
- 6. Acceptance criteria.
I l 4 17.2-35 HCGS-UFSAR Revision 8 September 25, 1996
l 1 Test results, including verification of above items, are documented and reviewed < for acceptability by the qualified department representative. Cycter tect: l performed icllcuing modificctienc tc O, "
, cnd " desigacted cyctem: require Ii recic;. cf tect precedurec cnd tect recultc by the SO".C. ;
i TheNuclearAdministrativeProceduresManualprovidesfortheuseoftemporaryl l changes which are controlled in accordance with Technical Specifications. ! Detailed instructions for implementation of temporary changes are provided. - l i QA performs assessments of selected post modification tests to assure compliance l with the test procedure. Test results are reviewed for the following:
- 1. Presentation of proper documentation 1
- 2. Assurance that tests meet objectives
- 3. Identification and reporting of unacceptable results and initiation I of corrective measures.
17.2.12 Control of Measuring and Test Equipment 1 Test equipment, instrumentation, and controls used to monitor and measure l activities af fecting quality and personnel safety are identified, controlled, and calibrated at specific intervals by cognizant Nuclear Business Unit personnel. l Written procedures for meeting these requirements include provisions for:
- 1. Specifying calibration frequency
- 2. Recording and maintaining calibration records I
l I i 1 i i 17.2-36 l HCGS-UFSAR Revision 8 September 25, 1996
I
- 3. Controlling and calibrating primary and secondary standards ,
- 4. Determining methods of calibration l i
l S. Tracing use on safety-related items. Measuring and test equipment (M&TE) calibration procedures are prepared in accordance with the applicable supplier's manual requirements, ur.less specific f exemption is approved by the cognizant station department head. M&TE, which is ! so exempted, is identified by use of a label or tag on the item' . : Prior use of measuring and test equipment found to be out of calibration is-
. evaluated for possible effect on safety-related items. Measurements are repeated where necessary.
Sccendary Calibration standards arc libr:ted by certified ::libr:tien 1 hcratcric: and are traceable to the National Institute of Standards and , r Technology (NIST), physidalyconstants or best industry standards where no NIST , standards exist. !=pic=cnting prcccdurc uill prc cide for documenting the h: ic l cf calibratienc uhich are net traceabic t NMT,- To the extent permitted by the } t state-of-the-art, the accuracy of the primary standards used to perform this calibration are at least four times greater than the accuracy of the device being calibrated. Thc bi cf acccptance in dccu=cnted and authcri;ca, with i recpencibility :: igned tc the ecgni= nt depart =cnt he d. Procedures are inl place which describe the method and assign the responsibility for acceptance of lesser uncertainty ratios. Test equipment is marked or otherwise identified to indicate a unique identification number, the latest calibration date and the l I 17.2-37 HCGS-UFSAR Revision 8 September 25, 1996 l
next required calibration date. Measuringandtestequipmentisidentifiedbyl affixing a calibration label unless the size of the item makes this impractical. Out of calibration identification is used for instruments and controls to indicate this status pending calibration, repair, or replacement. Calibration f requency is based on the manufacturers recommendations. This frequency is adjusted when operating experience supports this action. 1 Organizations responsible for implementing measuring and test equipment calibration controls include station, Nuclear Maintenance Operatienc Ccrciccc, and Maplewood Testing Services. 17.2.13 Handling, Storage, and Shipping The control of handling, storage, cleaning, and preservation of material and equipment covered by the QA program is specified, implemented and accomplished by suitably trained personnel in accordance with predetermined work and inspection instructions. Implementing procedures provide for the storage of chemicals, reagents (including control of shelf life) , lubricants, and other consumable materials as required. The nuclear materials management group is l responsible for control of material in storage, including preservation and shipping controls. The station departments andjNucl' ear!7 Maintenance are responsible for system cleanliness and handling of equipment during operational maintenance or modification. Nuclear Engineering is responsible for specifying l equipment requirements. Manuf acturer's instructions and recommendations, design requirements, and applicable codes and standards are implemented, as appropriate. Compliance with specific handling, storage, or shipping requirements is required. Requirements for new components and spares, where applicable, are included in the procurement documents. l l l 17.2-38 HCGS-UFSAR Revision 8 September 25, 1996
17.2.14 Inspection, Test, and Operating Status Nuclear Business Unit procedures are required to specify the periodic tests and l inspections required for equipment covered by the QA program, and to include the necessary management controls to assure that such required tests and/or inspections are completed in accordance with specified requirements. Equipment awaiting repairs, under repair, or repaired, and received materials are marked to indicate the status of inspection and test requirements and/or acceptability for use. Procedures provide for tagging valves and switches to prevent inadvertent operation. These procedures control the application and removal of tags and are designed to prevent operation of valves and/or switches that could result in personnel hazard or equipment damage. Valve and equipment status boards or logs are maintained to indicate status. 17.2.15 Nonconforming Materials, Parts, or Components organizations involved in material receipt, installation, test, design modification and other operating activities are responsible for identifying, and documenting nonconformances. Nonconforming materials, where practical, are segregated to prevent installation or use until proper approvals are obtained. Materials, parts, or components that have failed in service are identified and, where practical, segregated. Procedures control the application and removal of tags. Documentation of the nonconformance includes a description of the nonconformance, review by GNGG ShiftiSuperintendent/NSS for Limiting Condition for Operation (LCO) applicability when appropriate and the disposition and inspection or retest requirements, as appropriate. The responsible Engineer dispositions each nonconformance report. Dispositions for repair or "use-as-is" are required to be reviewed and approved by QA prior to implementation. Rework or repair of nonconforming material, parts, i 17.2-39 HCGS-UFSAR Revision 8 September 25, 1996 l
or components is inspected or retested or both in accordance with specified test and inspection requirements established by the responsible engineering ; representative, based on applicable requirements. QA shall verify the satisfactory completion of the disposition of nonconformances. QA and other organizations in the Nuclear Business Unit reviewnonconformancel l reports for quality problems, including adverse quality trends, and initiate reports to higher management, identifying significant quality problems with recommendations for appropriate action. 17.2.16 Corrective Action Organizations involved in activities covered by the QA program are required to implement corrective action for significant conditions adverse to quality (SCAQ) and conditions adverse to quality identified within their scope of activity. Such conditions are documented and controlled by issuance of an action request. The QA Corrective Action Group reviews responses to action requests for adequacy and monitors these action requests through periodic summary and status reports to management. Responses to action requests are based on the four elements of , corrective action, which are:
- 1. Identification of cause of deficiency
- 2. Action to correct deficiency and results achieved to date
- 3. Action taken or to be taken to prevent recurrence
- 4. Date when full compliance was or will be achieved.
For significant conditions adverse to quality, such as LERs and NRC/INPO/CMAP findings, the CA Corrective Action Group is involved in the review of such conditions and provides oversight to assure timely 17.2-40 HCGS-UFSAR Revision 8 September 25, 1996
-. ~ - ~ _ _ _ . . -- -- .- . -.- - --
follow-up and close out. Items 3 and 4 are optional for conditions adverse to quality. Proper implementation of corrective action is verified through surveillance, inspection, assessment or audit, as appropriate. l The statien appropriate' general manager or[ dire'ctor is responsible for assuring that conditions adverse to quality are promptly identified and corrected for all activities involving station operation, maintenance, testing, refueling, and modification. Administrative procedures that govern station activities covered by the QA program provide for the timely discovery and correction of nonconformances.. This includes receipt of defective material, failure or malfunction of equipment, deficiencies or deviations of equipment from design performance, and deviations from procedures. In cases of significant conditions adverse to quality, the
]
cause of the condition is determined, and measures are established to preclude recurrence. Such events, together with corrective action taken, are documented and reported as described in Section 17.2.15. Corrective action is initiated by l the responsible department head, s QA closely monitors station conditions requiring corrective action. , i i Repetitive deficiencies, procedure or process violations at the station that are not classified as operational incidents or reportable occurrences, or l nonconformances under the QA program, are documented by-GA via the issuance of an action request. This request provides a formal administrative vehicle to
]
alert management of conditions adverse to quality that require corrective action. j i l I l 17.2-41 HCGS-UFSAR Revision 8 September 25, 1996
~ ~ _- .- . . _ - - - - _ -- . - -. . - _ - - - - - ~ _ . _ _ _ .
I 17.2.17 Quality Assurance Records Records necessary to demonstrate that activities important to quality have been performed in accordance with applicable requirements are identified and i maintained in accordance with Regulatory Guide 1.88, as noted in Section 17.2.2. l 1 Records shall be considered valid only when authenticated by authorized j personnel. Record types as a minimum, comply with applicable technical ! I specification requ:.rements and include operating logs, maintenance and modification procedures and related inspection results and reportable i occurrences. I The Nuclear Business Unit isresponsibleforthepermanentstorageofstationl ) records. The retention period for records; permanent storage location; and l methods of control, identification, and retrieval are specified by administrative l procedure. Individual station department heads are responsible for submitting ! applicable department records to the designated location for retention. 17.2.18 Audits Audits of PSE&G and supplier organizations that implement the QA program are performed by QA to verify compliance with the applicable portions of the program, ' l through personnel interview, observation of activities in process, and review of ' applicable documents and records as required. performance based assessment should be an integral part of the auditing program and should evaluate activities on the basis of their effect on the safe and reliable operation of the facility. An annual audit schedule is developed to identify the audits to be performed and their f requency. A dominant f actor in audit schedule development is performance in the subject area. Audit schedules are revised so that weak or declining areas receive increased audit coverage and strong areas receive less, consistent with the audit schedule frequency requirements of the Code of Federal Regulations and the UFSAR. Audits of the celected aspects of operational phase activities are performed with a frequency commensurate with safety significance and in a manner to assure that at least biennial (2 years) audits of safety related activities
-are performed. A list of operational phase activities subject to the audit program is provided in the Techniccl Spccificction; secti. ore 17;2WM2.3 and in Table 17.2-1.
Audits are conducted by audit teams comprised of a certified lead auditor and certified auditors, and technical specialists (when deemed necessary) . 1 17.2-42 HCGS-UFSAR Revision 8 September 25, 1996
Audits are conducted using preestablished written procedures and checklists. Areas of deficiency revealed by audits are reviewed with management and are corrected in a timely manner. Required corrective action is documented and . verified. Followup action, including reaudit of deficient areas, is performed. I The audit program conducted by QA includes, but is not limited to, the following j activities covered by the QA program: I
- 1. Operation, maintenance, and modification
- 2. Preparation, review, approval, and control of design, specifications, procurement and requisition documents, instructions, procedures, and drawings
- 3. Inspection programs 1
- 4. Indoctrination and training
- 3. Implementation of operating and test procedures l i
- 6. Calibration of measuring and test equipment i
l
- 7. Fire protection l
- 8. Other applicable activities delineated in Table 17.2-1.
l The audit data is analyzed and a written report of the results of each audit is distributed to appropriate management representatives of the organization (s) audited, as well as other af fected management personnel. Included in the report is a statement of QA program effectiveness. QA is audited by independent auditors at least every two years to verify implementation of the corporate QA program. Reports of these audits are directed ! to appropriate PSE&G management personnel. i l 17.2-43 HCGS-UFSAR Revision 8 September 25, 1996
TABLE 17.2-1 I HOPE CREEK Q ACTIVITIES / SERVICES The listing below identifies th)se activities and services, to which the Operational QA program applies during operations: A. Safety-related activities delineated in Regulatory Guide 1.33, Appendix A (S er. Regulatory Guide for further guidance on these ,
\
activities) i
- 1. "Le procedures that define safety-related processes and programs, and that provide for the control of nuclear operations, and that incorporate regulatory requirements and commitments, will be called administrative procedures. Refer to Section 13. 5.1. The following is a partial list of safety-related administrative procedures:
(a) Security Program, (Regulatory Guide 1.77) (b) Equipment Control, e.g., locking and tagging l I (c) Shift and Relief Turnover i (d) Bypass of Safety Functions and Jumper Control (e) Maintenance of Minimum Shift Complement and Call-In of Personnel (f) Fire Protection Program (FPP) including Inspection by Fire Consultants (g) Communication System. (h)[ (Statfion]OperationsIREOiew Committde[(SORC[
- 2. The general plant operating Procedures at Hope Creek will be called Integrated Operating Procedures (IOPs). Refer to Section 13.5.2.1.2.
- 3. The procedures for startup, operation and shutdown of safety related BWR systems at Hope Creek will be called System Operating Procedures (SOPS). Safety related BWR systems for Hope Creek are designated as QA required in Table 3.2-1.
Refer to Section 13.5.2.1.1.
- 4. The procedures for offnormal or alarm conditions of safety related BWR systems at Hope Cr+ek will be called alarm response procedures. Safety related BWR systems for Hope Creek are designated as QA required in Table 3.2-1. Refer to Section 13.5.2.1.4.
1 of 3 l HCGS-UFSAR Revision 8 l September 25, 1996 I I l
TABLE 17.2-1 (Cont)
- 5. The procedures for combating emergencies and other significant events, at HCGS will be broken down into two categories:
Emergency Operating Procedures (EOPs) and Abnormal Operating Procedures (AOPs). Refer to Section 13.5.2.1.3.
- 6. The procedures for the control of radioactivity will be broken down into several types to facilitate their use by the appropriate personnel. Structures, systems, and components that control the discharge of solid, liquid, or gaseous radioactive waste to the environment are designated as Quality Group R in Table 3.2-1. Refer to Section 13.5.2.2. The following is a '
representative list of procedures and systems related to the control of radioactivity: l j (a) Liquid Radioactive Waste System (b) Solid Waste System (c) BWR Gaseous Effluent System (d) Radiation Protection, including Occupational Radiation Exposure per Regulatory Guide 8.8 (e) Area Radiation Monitoring System Operation (f) Process Radiation Monitoring System Operation l 1 (g) Meteorological Monitoring and Data Collection Program (h) Packaging and Transport of Radioactive Material per 10CFR71 (i) Decontamination.
- 7. The procedures for performing Technical Specification required ,
surveillances will be broken down into several types to I facilitate their use by the appropriate personnel. Refer to Section 13.5.2.
- 8. The procedures for performing maintenance on safety related BWR systems at Hope Creek will be called maintenance procedures.
Safety related BWR systems for Hope Creek are designated as QA required in Table 3.2-1. Refer to Section 13.5.2.2.5. [ 9. The procedures for chemical and radiochemical analysis, sample l collection, maintenance of coolant quality, and maintaining concentrations or narmful agents within prescribed limits will be I called chemistry procedures. Refer to Section 13.5.2.2.1. 2 of 3 HCGS-UFSAR Revision 8 September 25, 1996
TABLE 17.2-1 (Cont) B. Additional NRC requirements
- 1. Technical Specification Administrative Controls (c) Otetica Operctienc nceicu Ccrmittcc (00nc)
(b) Muclecr Ocf et-f nc zic.. (c) Reportable occurrences.
- 2. Inservice Inspection Plan
- 3. Reporting of Defects and Noncompliance.
- 4. Modifications to Site Grading.
1 i l 1 l l i I 1 3 of 3 HCGS-UFSAR Revision 8 September 25, 1996
TABLE 17.2-2 SEISMIC II/I -DESIGNATED STRUCTURES, SYSTEMS, AND COMPONENTS A seismic II/I designation is incorporated on the following design document types:
- a. Drawings
- 1. System isometrics
- 2. Area drawings I
- 3. Concrete unit masonry details 4 Heating & ventilation duct layout
- 5. Control room ceiling layouts
- 6. Floor plans
- 7. Miscellaneous steel drawings
- 8. Piping and Instrumentation Diagrams (P&ID's)
- b. Indices
- 1. Pipe line index
- 2. Equipment index
- c. Specifications
- 1. Acoustical unit ceilings ;
- 2. Insulation for reactor pressure vessel (RPV) and drywell piping equipment The Seismic II/I identification on drawings and indices is provided in the detail of the document, as necessary, to define "Q" items / boundaries. A "Q" suffix is added to the drawing number of those drawings that identify application of the Seismic II/I QA program.
i The seismic II/I identification on specifications consists of adding a "O" suffix to the specification number. 1 i 1 of 2 HCGS-UFSAR Revision 4 April 11, 1992 l i l l
-- - . . - . . _ - . . _ . . . _ - . ~. -. .-. .... - . _ .. - . . . . .. _ . - . . . . .
l TABLE 17.2-2 (Cont) Seismic II/I structures, systems, and components are further delineated in Table 3.2-1. i i 4 I l E I l I i - I f l 1
; i s
l 2 of 2 HCGS-UFSAR Revision 0 i
I 1 TABLE 17.2-3 ; F-DESIGNATED SYSTEMS l An "F"-designation system is incorporated on the following design document types l as a minimum: I
- a. Drawings
- 1. P& ids for Fire Protection System (FPS)
- 2. FPS safety-related area drawings
- 3. Fire wall location drawings
- 4. Structural steel fireproofing drawings
- 5. Concrete unit masonry details
- 6. Penetration seal details
- 7. Door hardware schedules
- 8. Lighting notes, symbols, and details
- 9. Lighting and telephone plans
- 10. FPS isometrics.
l
- b. Indices !
1
- 1. Pipe line index ,
1
- 2. Equipment index l
- 3. Instrument index
]
- 4. Valve index. !
FPS-QA identification system incorporation on drawings and indices is provided l in the detail of the document, as necessary, to define "F" items / boundaries. An "F" suffix is added to the drawing number of those drawings that identify application of the FPS-QA program. Specifications are as follows: Deluge water spray and sprinkler system Fire and smoke detection system I I 1 of 2 HCGS-UFSAR Revision 0 April 11, 1988
. . . ._ _ _ . . ._ __ _ . _ _ . _ . _ . . = . . _ . ._ m ._ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . . _ .
1
, TABLE 17.2-3 (Cont)
Carbon dioxide systems Installation of carbon dioxide system Portable extinguishers Hose racks for wet standpipe system Horizontal fire pumps Fireproofing of structural steel 1 FPS-QA identification system incorporation onto specifications consists of adding an "F" suffix to the specification number. Fire Protection Systems, including emergency lighting and communications, are further delineated in Table 3.2-1. t 1 .i 11 i 1 4 2 of 2 HCGS-UFSAR Revision 4 April 11, 1992
TABLE 17.2-4 R - DESIGNATED SYSTEMS The letter "R" shall be used to identify items of the Radioactive Waste Management System which protect the health and safety of the public, and plant operating personnel from uncontrolled discharge of solid, liquid, or gaseous radioactive waste to the environment. The radwaste management systems classified as quality group R shall be designated by the use of R-flags on piping and instrumentation diagrams. Quality group R standards shall be those provided in Regulatory Guide 1.143. Radwaste Management Systems are further delineated in Table 3.2-1. ! l l l l 1 of 1 HCGS-UFSAR Revision 4 April 11, 1992 April 11, 1988
QUALITY ASSURANCEINUCLEAR SAFETY REVIEW DIRECTOR - UALITY ASSUR
' (UCLEAR SA E EVIEW
/
/ / /
MANAGE MANAGER MANAGER MANA MAN R NUCLEAR FETY CORRECTIVE ACTION & QUAllTY ASSESSMENT GUALITY SSESSMENT EW QUALITY SERVICES -il.lDff4ftEE8g EMPLOYEE Cof CERNS ALEM) ULATION
/ / /
$6scacc rgm;gge p g ;
UM ATTHc4s6 PUDLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK NUCLEAR GENERATING STATION OUAtlTY ASSURANCE 1 NUCLEAR SAFETY REVIEV/ Updated FSAR Revision 8. September 25.199G Figure 17.21 __________m_ --_. - - - - - - - - - - - ' ' - ' - ""
1 QUALITY, NUCLEAR TRAINING & , EMERGENCY PREPAREDNESS CHIEF NUCLEAR OFFICER & PRESIDENT - NBU DIRECTOR - QUALITY, NUCLEAR TRAINING AND EMERGENCY PREPAREDNESS
- i
- MANAGER QUALITY PROGRAM MANAGER MANAGER ASSESSMENT MANAGER-NRB CORRECTIVE ACTION EMPLOYEE ,
CONCERNS l t I TECHNICAL OPERATIONS EMERGENCY TRAINING / SERVICES TRAINING PREPAREDNESS MANAGER MANAGER MANAGER , PUBLIC SERVICE ELECTRIC AND GAS COMPANY , SALEM NUCLEAR GENERATING STATION QUALITY, NUCLEAR TRAINING
& EMERGENCY PREPAREDNESS t
Updated FSAR Figure 17.2-1 . Revision 8 Sheet 1 of 1 September 25,1996 I i
Document Control Dick LR-N970303 Att"2chment 3 f PROPOSED SALEM CHANGES
17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE Public Service Electric and Gas Company (PSE&G) is responsible for assuring that the operation, maintenance, refueling, and modification of the nuclear generating stations are accomplished in a manner that protects public health and safety and that is in compliance with applicable regulatory requirements. To carry out this responsibility, PSE&G developed and implemented a comprehensive Quality Assurance (QA) Program that was applicable to the design, construction, and testing phases and is now applied to the operatien phase. The Operational Quality Assurance Program is described in the fcllcuing dccumente:
- 1. !?C.VP PO.22 0010'O), Operational Ouclity ?.ccurance Prograr establ-ichcc the Ouclity *.ccurance Program Gr Nuclear Administrative Procedures Manualj [Thi's m'a nualTestablishes andE documents the programs and processes that implement the QA Program.
The QA Program provides measures to assure the control of activities affecting the quality function of structures, systems, and components, to an extent consistent with their importance to safety. The Quality Assurance Program encompasses fire protection of safety-related areas and other activities enumerated in Regulatory Guide 1.33. A planned monitclig assessment and audit program assures effective implementation of the Gperational Quality Assurance Program. An assessment is a direct observation of activities and review of documentation to verify compliance /conformance to specified requirements and effectiveness of processes. The program provides coordinated and centralized quality assurance direction, control, and documentation as required by Nuclear Regulatory Commission (NRC) criteria set forth in 10CFR50, Appendix B. The program provides for monitoring, assessing and auditing elements of the Fitness-For-Duty (FFD) Program as set forth in 10CFR26 and is applied to, and includes non 0-list (i .e. balance of plant) activities and services necessary to achieve safety, reliability, availability, and economy in the operation of the Salem Generating Station. Applicable NRC Regulatory Guides, codes, and standards, as well as the policy statements contained in the Nuclear Administrative Procedures Manual, are used by PSE&G organizations performing activities affecting safety to prepare appropriate implementing procedures. To assess the effectiveness of the PSE&G Quality 17.2-1 SGS-UFSAR Revision 15 June 12, 1996
l i Assurance Program, independent auditors from outside the company r:dit the l l program every 2 years for compliance with 10CFR50, Appendix B, and other i regulatory commitments. Reports of such audits are made directly to upper management. < l l Quality Assurance l (QA) policy statements are issued by key management l representatives, including the Chairman and Chief Executive Officer and the Chief I Nuclear Officer and President - Nuclear Business Unit (CNO/PNBU). These policy ' i
- statements are mandatory throughout the Company for nuclear facilities. i 1
,- Key policy elements, as they apply to nuclear safety, include the following:
- 1. Nuclear safety is of the highest priority and shall take precedence over matters concerning power production.
s
- 2. The public's health and safety is the prime consideration in the conduct and support of PSE&G's nuclear operations and shall not be compromised. All decisions which could affect the health and safety of the public shall be made conservatively. i
- 3. The Operational Quality Assurance Program is an essential part of the PSE&G commitment to safe and reliable nuclear power operation. l Applicable program requirements shall be strictly adhered to in the performance of activities covered by the Operational Quality Assurance Program.
PSE&G requires its suppliers and contractors to assume responsibility for establishing and implementing Quality Assurance / Quality Verification (QA/QV) programs, as applicable, to meet 10CFR50, Appendix B. However, responsibility for the overall QA program is retained and exercised by PSE&G. QA reviews those
~
programs and conducts appropriate monitoring and auditing as required to assure that the suppliers are properly implementing i l 1 17.2-2 SGS-UFSAR Revision 15 June 12, 1996
- . . . . - . - . - - . - - - ~ . - . . . - - . - - - . - - - . - - - . . - . - _ _ _ . . - . . . - .- - ,-. _ ..
1 i 1 l their QA/QV programs. The Operational QA Program verifies that requirements necessary to assure quality are properly included or referenced in procurement { documents. In addition, these suppliers' procurement documents include ! applicable PSE&G quality assurance requirements for items and services provided -; j by their suppliers. 1 J i i l l 17.2.1 Organization l " l The Operational QA Program, referred to hereaf ter as the QA Program, assures that ' ' . i-adequate administrative and management controls are established for safe i
- operation of the station.
I I ;
- Implementation is assured by ongoing review, monitoring, assessment and audit !
under the direction of the Director - Quality .". :ur . :/Mu:10:r C:fety review, NubleadjrainihQyd;Emaijehby}PrejiAEAdnsas3DjsebtorpiQuslip$ NTQahd! EPQ who reports to the CNO/PNBU. , i 1mplimentation[f or{thE ;[noh00A[larsssj[U$ds EitheQbont rol$o ff th5?Dirs ct'OyQual;itf[
' TfsndlEMis[asesrediby]the!Managefj%Qulal'itpfAssessuichtQ" N
Company organization is shown on Sigares 13.1-1 through 13.1-9 and 17.2-1. Responsibilities for activities affecting quality are described in the following , sections. I 17.2.1.1 Nuclear Business Unit j l The Chief Nuclear Officer and President - Nuclear Business Unit (CNO/PNBU) 'is j responsible for managing and directing the nuclear activities of the company. l Overall duties and responsibilities of the Nuclear Business Unit ' (NBU) are provided in Section 13.1. Vice Presidents, Directors and General managers reporting to the CNO/PNBU are responsible for implementation of QA requirements by their staff. These QA requirements are contained in the Nuclear Administrative Procedures Manual and individual department documents. The CNO/PNBU regularly assesses the scope, status, adequacy, and compliance of the QA program to 10CFR50, Appendix B, through:
- 1. Frequent contacts in staff meetings, QA audit reports, audits by I independent auditors, NRC inspection reports, department status reports.
17.2-3 j SGS-UPSAR Revision 15 ! June 12, I996 I
- 2. An annual assessment of the QA program that is preplanned and documented. This assessment addresses the scope, status, and adequacy of the QA program. Corrective action is identified and tracked.
17.2.1.1.1 Quality Assurance The DIP O?./NCP Director.M Quali.ty,]NT{;iand[ EP is responsible for defining, formulating, implementing, and coordinating the QA program. The O!" O?./NCn ne has been-delegated the authority and has the independence to interpret quality requirements, identify quality problems and trends, and provide recommendations or solutions to quality problems. The DID O?./"'" He is responsible for approval of the QA[ ewi NSR Department Manual ee-be used during the operations phase of the nuclear stationsj The DID O?./MCn He also is responsible for verifying compliance with established requirements for the QA program through document review, inspection, monitoring, assessments and audits forfallisreaslexceptithose non{QA' areasf undef his?;contro1T QA provides a centralized coordinating function for QA/QV activities applied to the operations phase. The BIP O? /NCD' I Director.? E-: ; Qualitiyf; l nth fand? EP has the authority and responsibility to stop work, through the issuance of a Stop work Order, when significant conditions adverse to quality require such action. The PSE&G policies and organization structure assure that the DIP O?./NCR , Director /6;;Qualityi L NT, l andiEP has sufficient organizational freedom and independence to carry out his responsibilities. Responsibilities of the Manager - Corrective Action and Ouality Cerviccc include the following:
- 1. Preparation c wl-ma-intenance of the O?./"En Department Manual, the 07. Prograr deceripticn :n the UFC?.", and the Operatiencl 07. Progr:r d ccription in the Nuclear ".dminictrative Prccedurec Manual.
- 2. Ecric.. Of the Unclear 7.dminictrative Precedurec Manual fcr compliance . tith the Operational OA Program
- 3. Performing acccccmcnts of PCCiC Progrer admin ctrative and impicm:nting precedurcc 'ac neccccary, thecc esseeemente may cice includ ctation adminictratirc and impicmcating p;cccdurec)
Conducting Of Prograr crientation for "EU perconnci adminictcring the braining and ccrtificaticn prograr for O?. perccnnel involved ir incpection, eeeeeements and auditing activiticc, maintaining th: 07. training plan, and maintaining O? training rcccrdc. 17.2-4 SGS-UFSAR Revision 15 June 12, 1996
- 5. n:::: cf neu regulatory requirement: for Q?. Pr:5::: impact,
- f. C;;; din: tion cf th :: ;it;;nt verification pr grc n ::1 :ted b :ier
?.dmini trati n of the Nucle:r ncpcir Pr:gra:
6 1. Review of engineering documents such as equipment specifications, unld pre :duren, etc. for inclusion of QA requirements. 4 2. Review and approve specifications for Q-listed materials, equipment, and services. M3. Review of procurement documents for insertion of applicable. QA requirements. M4. Conduct of supplier surveys, audits and surveillances. M S. Evaluation of prospective and existing Supplier QA Programs. M6j. Administration of the Corrective Action Program. M7 . Performing statistical analysis trend reports for management. 'M8. Monitoring / auditing of nuclear fuel fabrication and installation. M9,. Review of NBU fuel specifications for inclusion of QA requirements. M10. Perform material evaluation activities on items subject to the QA Program. Responsibilities 'a nd asthorities of the Manager - Quality Assessment include the following: -fi[(The'{abthoritylahd_3esponsib111tp}ts;fstopjdsk%throughithe[isssinceYefis
~
s toplWorkl0rde QlwhenTalgni ficantij condit ions (advers'el tolqualitp [ require s shch actionO 21 MiTheit.eedomlandj anthorityltoldirectlyf taccess;the;:'CNO/PNBU[ifjthf n'eed}for sdchla cce s alexis t s i f or;l;anyiis sue [ unde rihis ? ressionsibilli tygtiicludi ngl tho se
-relateditoi.nonjoMareasybnderfthe;controllofstheiDirectoriMoualityMNT[
and!EPh 17.2-5 SGS-UFSAR Revision 15 June 12, 1996
t I i 3> f The'responsibilityLAnd 'authositylforivesifying Ecomplianseiwithiestablished requirements sof 3 the[QATprograni;[through?documentZreviews;f inspecti;ons, sssessments/nndjauditslofinonhoAlaisasfsnder the?chntrol"off ths"Disectorp a ' [ Quality [NT{and EP) IThis[includesithe authositpitofinterpfet!QA program
~
requirementslddring [conddet?of f the Tabove' activities;
- 14. Development and implementation of the QA Audit and Assessment Program.
- 45. Performing assessments of contractor activities and evaluation of emergent contractor programs and procedures.
- 46. Planning and scheduling of surveillances conducted within the Nuclear Business Unit.
4*1. Performing station procedure review and concurrence, i 8: ;PreparationLandl maintenance o.f the.'QA/NSRlDephitmenti[Mahualgthe QALProgram description;inithe UFSAR[and theloperationd.l? QALProgramidescriptioniinithe Nucleas Admidistrative'Pr6cedures?Manuali )
- 9. Review of the Nuclear ~ Adminintrative Procedures!.ManualL for! compliance!with the]OperationallOA'; Program {
- 10. J PeEfortning "as'sessments[of) PSE&G[ Programi administrative f and71mpismentin$
pr6cedures(tias jnecessaryf 3 the sef assessments); may;Talso E-inc15de fstation administrativefandJimplementinglprocedures}}
- 11. l Conducting} QA Programiorientiation; forINBU,personneliand"; administering? the training [andTeertification pfogram for QA personnel?invbived in/ inspections assessments'~and" auditing ~ activities;1 maintaining [the OAitrainingjplanf[and maintainingjQAitraining} records {
- 12. . : Review'of .new regulatoryirequirements1 for{QA ?ProgramlimpactQ 131 [Coordinationlofithelcommitmentiverification'programionfa[ selected' basis]
514. Performing Code related inspections l and test performanceQandfreview;of weld proceduresfforj nclusioniof QA) requirements.
~
615. Performing design change package pre-implementation review and closure review for compliance with Inspection Hold Point (IHP) requirements. -716) Performing Performance Based Inspections; (IHPc)
- 17. ' Implementation ofE the"onsite ' independent: review.-
18; nRandom ascessments,are performed lon1.thefcable system toiensure;that;Jthey have"beenTinstalled"asLspecified-perfprocedure.
- 19. ' Quality' verificaticns (are ? performed;Lon i field:?installedicablesIto ensure thati-- the cab. lea 'are properly? installed 7 identified, and routed as specified
. -. . .- , _-. - - _. - -.- - ~ . . . . .- .. . . . - .- .-..-. - -
perfprocedurej nccpcacibilitic cf the "anag;r ':uclear Cafety ncvicu arc dcccribcd ic Ccction 12.1. Eccpencibilitic cf the ";ncgcr Licencing and Ecgulation crc deceribed ir C;; tion 12.1. Responsibiliti.es;T. 6ff. thel Pr_ogram ? ManaigeF%7 Nuclear' ire 91EN}Boardlinclu'dssIthe 1; f Providesfsupportitosthe;;~Nuclearf Review);iBoard[(NRB)fto}snslurejthatl;[the'NRB canl perf osm?it s) f enet'ibn[inshagemshtfoVersightlof;the ' NRB
- subebmittisesiand NRBilndepehdent3fevleusifind 2 ve rif iesithe Vadecplacyf 0f$10CFR50j 59fSafe ty Evaluatione"and] that.{the} proposedTactionsf d61not]:?lnvolpe';f an?Unreviewed Safety}Questionj f: ': M. a.nageis : and 'administerslthel tFainis. cF. re. .quirement s? for] Nuclear l Review Board psrsonnel; Responsibilities of the Manager -
Employee Concerns}7 5the][ Technical! Training 4eryicesl Manager $the[ Operation.slTraining;:ManagerMandtthe? Emergency Preparedness?.Madager are described in Section 13.1. 17.2.1.1.1.1 Quality Assurance Personnel Qualifications The DIP O*./NCP? Director [ Quality,jNTyandf:EP and the QA managers reporting s directly to him the OIn O?/NCn must each have a combination of 6 years of experience in the field of QA and operations. At least 1 of these 6 years of experience must be in the verall implementation of a nuclear power plant QA program. A minimum of 1 year and a maximum of 4 of the 6 years of experience may be fulfilled by related technical or academic training. , 1 Personnel performing inspections, examinations, and test activities (i.e., to verify conformance) are certified as Level I, Level II, Level III as appropriate to their responsibilities, also in accordance with Regulatory Guide 1.58. Personnel performing quality assurance audits are certified as auditors or lead auditors as appropriate to their reponsibilities in accordance with Regulatory l Guide 1.146. Thehualifica tionsl{ of;l the [ personnel] per f o rming ithel;{onsi t el:[ independent})eview function /drefdescribedfinisectionl17;2i1 % 2142 17.2-6 e SGS-UFSAR Revision 15 June 12, 1996 l t { i I
The D!P O'./ :cn;Djiector { Quality,fNTf and'.Ep fulfills the above qualifications i with the addition of the following:
- 1. Knowledge and experience in quality assurancefand? safety.
- 2. High level of leadership, with the ability to command the respect and cooperation of company personnel, suppliers, and construction forces. >
- 3. Initiative and judgment to establish related pc_leies to attain high achievements and economy of operations.
17.2.1 A.' Operational Review A11] programs and }pr6cedures .KeqUlred ' byiTechnical; Specificatioss;. and{ changes ;
.thereto,5will~ be reviewed in accordance with76ectiost17)2?f;1j2,l"below, iThree 0
advisory groups, the Station Operations Review Committee (SORC), theiNuclear Review Board.--(NRB) .,[and Quality Assessment [(QA)[(onsite1 independent" review)$.the Oncit: 0:fety ncricu Crcup (Cnc), and th: Offsit: Cafety n:.icu Crcup (Orn', are responsible for reviewing and evaluating items related to nuclear safety. The overall responsibilities of these groups are described bl'w eo ir Ocction 12.2. The "annscr Quality Assessment is expectedito;belrepresentedTatinvited t 211 SORC meetings and rcccivcc tht, minutcc cf thc m;;tingc, ettends the mcctings pericdic 12y. Asf.^part of sitefof fsite71ndependentj review]fune:iori,j the[NRBlis respOnsibleTfor selected l preplannedfindependent.l audits of.lpl:r.itToperations, iTheselaudits(are
~
generally conducted by QA[under NRBicognizance) 17.2.1.? "ac2^uced T^~ tin; "crvic^^ i I The ": nager "splewced Tccting Serviccc repc:tc tc the Director Sucinccc and
".cintenance 0 rvice: in fcccil g ncretion "spicuccd Tccting Cerviccc per4crac calibratienc, analyscc, and cvaluatienc cn cycter~, equip =cnt, and .aterialc, ac requected by PSEtC depart =cntc, and mainteirr cc=pliance with-4tc quality accurance progrc I
17.2-7 SGS-UFSAR Revision 15 June 12, 1996
I 17;2l1 g l.'2.1 Technical Review and Control l ACTIVITIES. . Procedures:and programs required by. Technical: Specification 6.8 j and other procedures which affect nuclear' safety as determined by the plant ' managerh;other.than;editorialilor typographical; changes shouldlbe: reviewed as ; followst 1; 'Each newly.. created procedure, programforfchangeLthereto shallibe independently ~ reviewed by anl individual knowledgeable;in the ! aubject; area:other'than'the individual;who, prepared the: procedure, program or procedure change. .ProceduresLother than the Station I Adminstrative proceduresLwill be approved bylthe' appropriate ; Department Manager orlby the plant manager . Each. Department l Manager lshall;be responsible for~'a predesignated class of , procedures, Security P1an' implementing procedures;'and' Emergency plan implementing procedures. On-thea spot; changes:tol procedures which clearly;;dd not change the
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- 2. I intent of.the approved.. procedures;shall beiapproved~by;twoimembers of- the plant, management fataff 3 at(least1 one of;' whom holds ;'a l Senior Reactor Operator; License! ' Revisions;to proceduresTwhich?may involve'a' change in' intent oftthe approved procedures'shalllbe reviewed'in"accordance~..with" Item 11'abovei
- 3. Individuals' responsible forjreviewsfperformed?inLaccordance'with Item 1"above shall!beiapprovedfby.the?$0RC chairmanfand' designated asl Station Qualified Reviewers? LALaystem of StationiQualified Reviewers;-.; each 'of f whom 'shall Lprossess qualifications"that meet'or
?
exceed thelrequirementslof?Section 414/of' ANSI.N18al;1971, shall be maintained'byftheTSORCjchairman, Leach review shallEinclude'a written determinatisnof whether or:not"additionalicross-disciplinary l review'is;necessary. ;If deemed:necessary,isuch review shall:lbe performed'by(the' appropriate designated 1 review-personnel.
"17 ,~ 217 a SGS-UFSAR' .. Revision'15
- June'12s;1996
/-
l l 4. ;If f the; Department Manager . determines that; the ' documents Linvolved require a 10 CPR 50'.59.safetyjevaluationgxthe documentslshallibe l forwarded for'SORC review and also:to the-Nuclear.! Review Board:for I an' independent; review to determine whether or not an unreviewed safetyfquestion"is.)involvedCDursuant' tot 10"CFR)$0.59;..'NRC approval?..ofEitems' involving unreviewed' safety questions,or I Technical? specification changes shall be.obtained priorTto l implementation 4 1 MON PECCEDURE.RELATED DOCUMENTS?-jTests or experimentsTand'chcnges.t'o l i equipmentLo.r5systemsjsha11Lbe; forwarded for'SORC^ review'and[alsolto the i Nuclear ReviewEBoard for an" independent' review to determine' whetherf orEnot'. an] ! unreviewedisafety! question;isjinvolved2:fThe.results;'of!theLNuclear Review L Board re' views"willfbefprovided to SORC. ; Recommendations lforl approval are made bylSORC'to the plant manager. Pursuant td 10[CFR"50~59[ NRC approval'of^ items involving;unreviewed ~ safety questions 'or requiring' Technicall Specification ! changes ~sh.all'be'obtained prior;to implementation.; I 4 1 RECORDS AND REPORTS # Written' records of' reviews performed inLaccordance withi item [1 above{lincluding recommendations'for approva1To f disapproval;[shall1be? l maintained. i 1 l 1
)
i i l I IL2-7b l SGS-UFSAR;1 : Revision'15 l . June.12,y1996 l
_ _ _ . ~ _ _ _ _ _ _ _ . - - . _ _ , . _ , - - _ . - _ . __ -__. . . _ . _ _ . _ _ _ . - - _ 4 j i i f 17.2%g,2 l 2l ' Statidn[ Operations] Review Committee [{SORC) i j FUNCTION 3 The[Stationioperations[ Review lCommitteelsha119 function? toiadvis'e j # theIplantLmanagerion[operationallmatters[ rela'teditolnucisarfsafety] 1 ) COMPOSITION i The} Stationloperations";. Review ' Committee [(SORC)/ shalll bef' chaired ) by[the]plantymanagerTandshallibeIcomposed"ofiregularj;membersfffomthesalem Generating (Station ;staf f jj; Nuclear $ngineeringp NuclearJ.Maintenancef andJ froni ] 'the ;Quali ty;; As ses'ement j organiz ation t having l[experi'ence ; in Teach}ofi thel following j areas } 1; Y Plant [ Operations 2 i; 1 Engineering I 3 '~ :;Maintenahce ] 4i , Chemistry Sj , , JRadiation* Protection
^^
] 6 , Equality 1 Assessment a ) The (member T having} experience linit& t arpajoff Radi'ationi Protection 'shall" meet { the~qu.alification7requirementsjfjRegulatoryjGuide1';0l;fSeptember[1975[jThe E ! member' having}experileheeTin; Quality' AssessmentTshallimeetiths]requirementsfofj a ANSI /ANS[3?l 1981[; lA11Lother, membersP s_ hall (meetlthe"requirementslof/ ANSI l N18 j l;1971C fori thaiappropriate[ discipline'h: : Allimembers[shall;(bs.[appointediih Writing l by.; thelplant{manageri iTheWice Chairmen [s halli be[ drawn [f rom?;thelSORC.! l membersland;Laha117befappointedTinVwriting;by,the) plant?manajeG f i 2 . j ALTERNATES;'} : All{ al t e rna te [; members ll shalllbslappointed (in %rit ing[bylt he] SORC ' l Chairman (fonlylthedesignsted'viceichairmenfor;2the' plant' manager;nay[ast'As ! Chaisman"'ofla } SORC meeting ( 1Noimoref thanftwolalternstes' tofmembers?shall j participate'as; voting membersiiniSORCJactivities.';'at7anyj.onelimeetings , ) Alternates /for membsrsfwill}notimakelup; part offtheWotiing}; T quorum whenlthe l j membe r : thelalternate L represents ils.l: also'; pr' e sent] MEETINGTFREQUENCY F The"SORC?shallimeetlatjleastfonce[pericalendarlmonth"and asfconvened by.}thelSORCi Chairman'for?his;fdesigna'ted? alternate j r i i
, il7:2;*7c SGS@UFSART LRevisionT15
< ~
-June:12h 1996
!' l l ) a t
i , i l l l i QUORUM MThe;.; minimum l quorum';of.; the[S_ ORC]necessaryj; forithe[perf ormance';;of.,;;the
~
SORC ?; responsibility [and ll authority]provi's,ional ofj this f sectiorifsha11]consis t.? of I l
.t.he ChairmanlorL his';;de'signated ' alternateLand ;four': membersiincluding l alternates 2 !
]
l RESPONSIBILITIESj y The (. Station L Operati;onsiRevi.ewiCommitteelsball- be responsiblellfori ! 1?f ' [ Review;;of f;[(1)] Upper,;ltierTadmin.istirative?procednres7within3he.1 , l- 8 coPelof) Rghlatorp[ Guide f li 33;;1(2[%[and[ changes? the'reto j ]and ! l(2 ) [ Newly [crea t odj proceduresy o richange si t ol exis ting lp rocedsreis] l thatTrequire y 10;[CFRl50;(59] safety]evuluationlas1ldesekibed[in f Section} 17?.271?l;;2 fli t
- 2) '1 Review'ofjall}; proposed 7testsTand[ experiments {thstfaffect' l nuclear; safety { '
3; l;. Reviewfof l all:f proposed ?' chang'es [tdlAppendiQA"fl Technical l Specifications 2: l 4b ? Review [of "alli pr6 posed f changes [orj;modificationsitd(planti sys temsl or(equipment : that"af f ect ' nucle;ar.):; safety { . SJ :LReview bf L;thelsafetylevaluations};thatihavQbeen]compl_et.edjundep the , provisi;ons lof;! 10] CFR (50 ! 59 Q 6.;;::: s lInvestigatiorilof[alliviolations]off the(Technica_l] Spec'ificatilons including} the } rlep6rts;" cove ringleValua tibn fandjedommsndat; ions
.tlo. prevent 7 recurrences i
7j.c_ ( Revie'wlbf fallTREPORTABLE'EVENTSp l
"" " ?17?2.7d' ' ' '
;fRevisionI15
' ~ '
SGS-UFSAR7 u _ _ , a' June 12..f..L1996
- , . , . .- , a , . - . . - - - m
SM ] iReviewl;;offfacilitp] operations]toidetect[potentlal[nucleaf safety [ hazards 7 9;(( Peiformancelof{special[ reviews {[ investigations [or* analyses [and] keports;!there6nTas]Eequestedibp[thefplant' managed 10Tl] Review Tof j theliFire]ProtestiOn [ progrsm [sndfimplementing . proceddreslandichangesjtheret'6}thatirequirefa210{CFR150;59 safetilevaluation? 112 2.R;eview(of[all;@nplsnnedlonksitW releases [of{radioactivit@;to LtheTensif6ds[includingithefpgeparattsdlof 3@rtsf(6vering ' e valuationsrecommenda tions;[';and Edispositilonl 6fiths[sofrectiVe action;to[preventWecurrencei
- 1. 2 h, awi i ReviewT..o.f. f c.hs. u. ges?.. tot.,
- . . . ~ t. h.e i PROCESS /C.O. NTROC. MANUAff_a.n.d I t.h.e,lO, FF4.,
SITE [ DOSE [CALCUIATION;MANUALI AUTHORITY flThe{S tationl lope rations 3evi'ew; Commit t e e{shall f ik _ /Pr6 fids?recommendati6nsitolthe]plsnt$ manager}iddicatin@ written approyalforfdIsapprova13 GitemsThons{dered[undey[thejSORC kesponalbilitiss7sboVej 2bfii'ovidej writteninotificati;on Esithiny2f! hosisit{ the;lseniorifics
~
Dresidentb fNuclear10perstionsG and}thelDirectbE M Qual'itV ENT add?EPfand[ Manager M Qdalit{ Assessmentlofidisagreemen;tQbetseen theSORC (and (the}l plant { maliayer ((h0we[Ue ry thejlsntfmsns5eh shall!haejesponsibilitpjfofTres61utiorfof{suchidisagrsements pursuant;tolyechnical!Spe;cification(6]igs 4 RECORDS *ANDjREPORTSf {The;l8.ti~atiosloperations);Regie$Committe.efshal1% maintain prittehl minutes [of Eeach);;'meetiinglandlcopies ishalll belprovided [tol theTsenlos . yice[ President];;MNOclear[Opefati6ns);fi;the.'/Dirsctor? )Qualitp8NT{and[EP]
~
Manager M Quality;[Assessmentk and;the;Ndelearll Review [Boardj F Mit2MW ~ ' ** *
'TReYisibs115 i
- $.-SGS;UFSARs E ,
" ".?i P t, , < am -> sn s [Juneg12 81996
I 17.2.1.112.3 iNuclear' Review BoardE(NRB) l The NRB'shall perform offsite Lindependent review function'and:shall'provi.de oversight;for audits of activities affectingLplant safety. L.One'NRB has been established to provide this: oversight for'bothrSalem and; Hope: Creek lGe'nerating Stations. ..Itsl purpose ll1s to; review lf audit;' and. evaluate both! technical: and
~~ '
organizational matters pertaining.to safe operation of'the' stations. The NRB: shall'be' established in a~ written charter ~that.Lincludes membership, responsibilities, reporting requirements, potential areas [to;be; reviewed, andl otherfaspects needed1for: operation;-of the: NRB. The NRB"shall~ function'to provide offsite independent: review and audit' activities in theffollowing areast
- a. . .NucleariPower: Plant Operations
- b. Engineering
- c. .Chemistryfand Radiochemistry
- d. ~ Instrumentation and' Control
- e. ' Radiological Safety
- f. : Quality. Assurance I
- g. . Nondestructive Testing
- h. ' Emergency. Preparedness The NRB members shall? collectively possess" experience andfcompetenselin;the a'reas'listedr above. ; consultants or otheritechnicaliexperts[shallytW utilizedi by~thelNRB'to thelextentfnecessary2
~
l NRB' members shall'meetfor'.exceedithe qualifications' described (AC Section 427
~
l of!ANS 3.1-1981. Exceptionsfto th'e~~ANS?311119815: Section~477 qualification l requirementsfcan be;. granted;tol.a maximum'of two NRB' members lprovidedLsuch members meet the;following;TalternativeLqualifications: -111alminimum of twenty l(20) f years ~ nuclear.:'related experiencef; 2);L shall'~ hold or. ha-ie~;' held a seni'or i
~
reactor operator license or certification [and 3)lshall'haveTserved as a minimum:in" a' nuclear vice-president'::"orfeguivalentipositions : The Director - Quality [ NT,;andlEPjwilllapproveland~ document the'l alternative l qualifications for.NRB members'where exception 7to the(ANST3~.141981'.Sectionl417 qualificatdon requi'rements is necessary.
~
The NRB.shall report to'and advise the Chief Nuclear Officer'and~Presidenti-Nuclear BusinessL Unit ' (CNO/PNBU) Ton those areas ~'ofl responsibility ' pertaining to NRB? review and' assessment. 17.2-7f SGS-UFSAR: -l Revision 15 June 12c-1996
Th3 NRB (Cticfin3.thi r;quirements of. ANSI N18.7-1976 (ANS 3;2),lin1that"the board is composedLof no less than'five members and ncimore than'a minority ofL
~
these members!are'from either thel $alem or Hope Creek l operating organizations. A. quorum'shallicensist of not less~than;a' majority of the members, of which no more than a minority ~of those present shall have line responsibility for . operating the" plant' 'ThejChairperson of the.NRB will be appointed by the
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l CNO/PNBUf The PSE&G' members'st.dll be' selected-from'PSE&G' management I personnel; .In? addition,la-minimum-ef:three external consultants shall'be members'of.the NRB; Meetings are scheduled by,the.NRB Chairperson. /A1: minimum ~ o f t'wo' meetings;a year lare: conducted. Minutes of.the meetings shall be prepared and' distributed to the CNO/PNBU. The. NRB,'and those performing reviews;or audits / assessments under the cognizance.of the NRB,'shall have access to' records and.' personnel as~necessary
~
to properly perform their' functions. The NRB shall be kept current on events within:its. responsibility by reviewing.some-or'all of'the/following': SORC mitiutes,2 Licensee Event - Reports, violations,' and/or audit' reports, andibp!. the - activities: of the board members. The NRB:'shall' meet"twice 'afyear as alminimum,'or more~often'asideterminedjby the Chairmani The NRB'msy'appointh in writingJ(such as'in Board' meeting minutes)',.
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l subcommittees for the purposes of performing reviews..or.l studies.in areas requiring;particular expertise orffor performing specialL-investigations! LNRBi subersmmittee members'shallimeet'or; exceed the' qualifications!describ'ed4in Section 4.7 of:ANS23.1-1981. 'The chairperson'oflan'NRBlsubcommitteeishall be
~
U an NRB member. The NRB or. subcommittees / organizations' appointed by the NRB sh'alll reviews
- a. LThe.safetyLevaluations"for'l changes to procedures,) equipment, or systems'and tests or experiments completed under;the'provisi~nL e of 10CFR50,59,!to verify that'such actions 1.did'not constitute an unreviewed safety question. The resultslof the Nuclear l Review ~ Board reviews will be provided td 50RC
- b. Proposed l changes to proceduresh equipment, Lor (systems,and; tents o experiment's'that' involve
'r ^an unreviewedisafety question.as defined'in'10CFR50;59.
; 17.2a?g SGS-UFSAR Revision'15 June 12,.1996
c4 iProposedl; changes to; Technical l Specifi' cations' or Facility Operjtting; Licenses; d;y :: Violations; of " applicable f statutes , i codes ,J regulati'onsi:Jordera n Technical l Specifications,311 cense'requirementsCorLof? internal < l proceduresTor;' instructions;having(nuclear safety? significance 7 I e, isignificantioperating abnormalities or~ deviations.from: normal ! and? expected performance;1offplantfequipment;that; affect: nuclear ; saf etyJ.. l f4 5 Reportableeventsfrequiredibyl10CFR50'.731 gp .'Allirecognized
; indications offan7unanticipatedideficiency[in somelaspectfoffdesignor'operationi.of.~ structures,[ systems,?or components thaticould.;affectinuclear': safety {
h .' : Reports.and;meetinglminutes of.the:'SORC4 1 i I The' NRB will utilize :as necessasp, L.the~operat.ing] experienced fee'dbacF;(OEF); program;to review current' plantLand;-industry:concernsfand perform;special . j studies"and investigations; l l Assessments / audits 1shalllbelperformedlbyTOA or;byl specially;fseleeted;; groups;or
~
; individuals pincludingjindependent consultants;Jwhofhave?noTimmediats kespohsibilitp{for"thef;activitp thep[ assess ~and.ldalnot!.whilefperforming3the j
Assessmenti"reportitoialmanagementirepresentative;who:.has'.immediate -
~
'responsib'ilityffor.ithe activity- being]assessedy Final-[ audit [ reports f ahallf be' reviewed by[ thel NRB, The audits shall 'includei at :The1conformance ofLfacility; operation 1to[provis' ions Montained within Technical; Specifications: Land [ applicable l license conditions:
;Thefperformancsb training :and qualifications (of the entire
~
b, . facility; staff; c, .The results"of' actions:taken to" correct ^deficienciesloccurring) in? facility;. eqnipmentTf structoresKaystemn, Eorimethod.-fof operationithatTaffect;nuclearfsafety?
'17J2-7h SGS-UFSARE JRevision715 June 12,.'.1996
I d; The" performance lofTactivities(required byjthe:(operational Quality;; Assurance; Program _to meet:the Criteria [ofl Appendix.B.t'o: 10CFR50i e '.. "Any.'other area *ofLfacility operation; considered; appropriate;by the Director:f-QualitydNT,i;and'EP'orithefCNO/PNBUl flg ::ThelfacilityjFirelProtection Program landl implementing;proceduresR g'i /An"assessmentTof:the' Fire Protection and f LossLPreventioniProgram implementation 1usingfan:loutside1'independentfffiref;; protection consultant hy l Thel; radiological 1 environmentalimonitoring;.;prograni'and the7results there'of;
- i. The.Of f site Dose l Calcula tion. Manda1 L andfimplementing;fproceduresJ
- j. (The $ Processh Controlj) Program f andl;;] implementing]fprocedures ? for processingi::andl packaging;;of;; radioactive ^ aastes!
- k. i;The:; performance fof lactivities L required ;;bp[ theT Qualityj Assurance Program ll f or Te f f16ent T and ~ envirdnmentall mon'itorinf.'
Theadditischedules shall be'; reviewed:annuallyfbylthefNRB::tofensurelthat$they ake;;being';performedilin"accordancelwith this;LaectionTof ? the" UFSAR7 Records' of NRB reviews and mindtes of'NRB[ meetings 7shall be' maintainsd.' ? Reports off reviewsi.fmeetingiminhtes and; addit; report's '; shallibe;fprepared andTdistributed as"indicatedibelow al iMinutesToffeach.NRB' meeting;;andlafreportL;of NRB;reviewsiperformed shalli be{ prepared 'andE; forwarded ftof the7CN0/PNBU;swithin] 30Tdays following}the1 meeting (
- b. . L Audit' reports 'shall i be' forwarded T to$ theTCNO/PNBU7andEmanagement positions responsible?forithe ; areas'auditedLwithin?30fdays[after completion";of' the audit exit meetinglfor those~ audits l conducted bp the;QA Departnientf andlwithin160?daysTaf tefcompletion'of L thei'!' audit exiti:' meeting lLforjthosefaudits'lconddetedj:.by2;'angindependent consultant?
17;2'-71 SGS-UFSAR'l ! Revision 15
* ;; June 12 J 1996
i 17 ; 2 .1,1. 2 . 4.'
'Onsite.IndependentiReview j l
The' Manager . Quality Assessment shall"be responsible'for onsite independent:: l review. The'onsite; independent' review shall'~be performed by a~' minimum ofLfour (4) personnel ~ who' ~are , independent of plant management. 'These; individuals i shall : report' to the . Manager . - Qu'ality . Assessment. The Manager.H Ouality Assessment shall: utilize the information'..;obtainedlduringL;onsitel independent review as; input' to advise _ managementf on theloveral11 quality and safety; of i operations and'shall; report tofand' advise the CN0/PNBU,"through~thefDirector7 Quality, NT/"and EP on?the,results of, independent' reviews. [Forionsite independentEreview issues involving noniOA areas under the. Director's control, l the Manager f Quality Assessment has'the' authority toldirectlyjreport the
~
results to the CNO/PNBUi The personnel.; performing'onsite. independent.. review shall function to provides the review of; plant"designiandl operating. experience forP potential opportunities to~ improve plant safety;' evaluation of plantioperationsfand maintenance activities;; and ' advice. to management'on the overalll'qualityf and safety of plant operations. The'~personnelishall make: recommendations'for
~
revised procedures,fequipment. modifications,.or^other means'bfLimproving pisnt safetylto appropriate" station / corporate' management. OnsitelindependentTreview shall'encompassa I
- a. Review of' selected plantfoperatingicharacteristics, NRC j
issuances,findustryladvisories;land"other7appropriatelsources ! of plant design andT operatirig' experience -infortsationlwhich' map 3 1 I indicate:' areas'for' improving l plant safety 2
- b. Review of' selected' facility' features,TequipmentiTand[ systems 2
~
l
- c. Review of' selected procedures and plant'activ.ities' including maintenance;' modification [ operational; problems [and operational analysis,
- d. Surveillance-ofiselected plant operationsfand maintenance activities to provide independent verification!thatathey are performed 1 correctly;and;thatthuman~errorsfarelreduced toLas71ow as' reasonably / achievable) 17.~2-7j SGS-UFSAR 1 Revision 15
-. June.12f 1996
The-personnel performing the onsite' independent. review-shall:havei 1) at least three L (3)f years ; related experience ' of .which 'at least L two. !(2) ' years are
~
nucleart related,;and a2 Bachelor Degree;;in' Engineering-.or afrelated;fieldi or
- 2) ~ at' l' east' eight [(6)Cyears related experience,; of which"atileastf five '(5)-
years t are nuclear. related. At. 'leastifif ty percent; (50%)Jof the' personnel performingLthe'onsite independent review shall have a!D Bachelor Degree ~in-Engineering f or' a ' related ' field. For the ' ' di'a cipline Lofl' Operat ions , a ' senior reactor ioperator. ~ license .~or' certification E may ' be? . used =as ~ anL alternative , qualification linstead'of a. Bachelor Degree in Engineering or a;related. field. Personnel performing.the onsite. independent. review function:shall be qualified in the' discipline.related to;the;assignedfarea of. review; ..Aisingle individual may'be ' qualified to perform reviews in more than';one disciplinei (The requisite experience may have been gained concurrentlyLinirelated disciplines. The DirectoryQuality, NT, and EP will. approve.and document: thequalificationsjof those personnel. performing the' onsite independent review who ~are. qualified based on; at least eight ' (B)' years related ~ experience. 17.2.1.2 'Manlewood Testina Services The Manager Maplewood Testing Services reports to'the' Director- Service l Company 1Servco)~in.the PSE&G' Fossil' Generation Business Unit.
~
Maplewood Testing Serviceslperforms calibrationsi analyses [land evaluations on systemsi equipment, and materialsj "as requested by NBU 'departmentsf and maintains compliance.with its; quality assurance program as approved byLNBU QA. l l l t i 17.2-7k SGS-UFSAR' ? Revision'15 June'12, 1996
17.2.1.3 Distribution Systems Department The Vice President - Electric Distribution Systems reports to the Senior Vice
- President Transmission and Distribution. The Distribution Systems Department l is responsible for providing support to Salem operations for setting and testing
! protective relays for the external vital power supplies at the station. 17.2-8 SGS-UFSAR Revision 15 June 12, 1996
. _ . - . . ~ . . . ..
17.2.2 Quality Assurance Program The QA program is designed to comply with the requirements of 10CFR50, Appendix B, and with fire protection program requirements of Appendix A of Branch Technical Position No. 9.5-1. This program is applied to items and activities delineated in the Salem Q-List that can affect the health and safety of the public. During the l 17.2-8a SGS-UFSAR Revision 14 December 29, 1995
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l J 4
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1 s t i g THIS PAGE INTENTIONALLY BLANK l 1 J r i t 1
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i 17,2-8b SGS-UFSAR Revision 11 July 22, 1991 I i
l 1 l 1 operational phase, this includes: I
- 1. Structures, systems, and components delineated in Table 17.2-1, Section 2. .
- 2. Safety-related activities delineated in Regulatory Guide 1.33 and summarized in Table 17.2-1, Section 1.
- 3. -Portions of structures, systems, and components whose continued i function is not required, but whose failure, caused by a safe shutdown earthquake (SSE), could reduce the functioning of a seismic Category I structure, system, or component to an ,
unacceptable safety level; or could result in an incapacitating injury to occupants of the control room as shown in Table 17.2-1.
- 4. Fire protection systems, including emergency lighting and communications, as shown in Table 17.2-1.
- 5. Radwaste management systems as described in Table 17.2-1.
'The QA program is applied during the operational phase using a graded approach l to the extent consistent with the item's or activity's importance to safety. ll l These activities are performed in compliance with applicable regulatory requirements that include but are not limited to: 1 i
- 1. Regulatory Guide 1.8, Qualification and Training of personnel for i Nuclear Power Plants.
- 2. Regulatory Guide 1.17, Protection of Nuclear Plants Against Industrial Sabotage.
- 3. Regulatory Guide 1.29, Seismic Design Classification.
- 4. Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing of 17.2-9 SGS-UFSAR Revision 15 June 12, 1996
Instrumentation and Electric Equipment.
- 5. Regulatory Guide 1.33, Quall'.y Assurance Program Requirements (Operation).
- 6. Regulatory Guide 1.37, Quality Assurance Requirementa for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants.
- 7. Regulatory Guide 1.38, Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water Cooled Nuclear Power Plants.
- 8. Regulatory Guide 1.39, Housekeeping Requirements for Water-Cooled Nuclear Power Plants.
- 9. Regulatory Guide 1.54, QA Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants.
- 10. Regulatory Guide 1.58, Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel.
- 11. Regulatory Guide 1.64, Quality Assurance Requirements for the Design of Nuclear Power Plants.
- 12. Regulatory Guide 1.88, Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records.
- 13. Regulatory Guide 1.94, Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel during the Construction Phase of Nuclear Power Plants.
17.2-10 SGS-UFSAR Revision 10 July 22, 1990
I , 14. Regulatory Guide 1.137, Fuel-Oil Systems for Standby Diesel l Generators.
- 15. Regulatory Guide 1.144, Auditing of Quality Assurance Programs for I Nuclear Power Plants.
- 16. Regulatory Guide 1.146, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants.
17, BTP 9.5-1, Appendix A, Guidelines for Fire Protection for Nuclear Plants Docketed Prior to July 1, 1976. Commitments to Regulatory Guides, with respect to revision level, exceptions, j etc, are contained in Section 3, Appendix 3A. l' The code QA requirements are used for the procurement of systems, components, and structures covered by ASME Boiler and Pressure Vessel Code B31.1 and B31.7 l or evaluated to be an acceptable replacement. The standard QA program controls apply to Q-Listed code items following receipt at the station. In addition, applicable requirements of Regulatory Guide 1.38 are applied to ASME Code procurements where necessary to assure safe shipment. Substantive changes to the QA program described herein will be submitted to the l NRC within 30 days of implementation. Nonsubstantive changes will be identified in the annual UFSAR updates. I 17.2-11 SGS-UFSAR Revision 15 June 12, 1996
F The station General Manager has instituted and will maintain a station l administrative procedures (SAP) manual. Regulatory Guide 1.33 requires that plant activities affecting quality-related items and services be conducted in accordance with written administrative l controls prepared by management. The procedures and instructions by which plant activities are performed are prepared by the responsible organization as required by the Nuclear Administrative Procedures Manual, reviewed by the organization 1 l responsible for the activity, reviewed as required by QA and SORC, and approved by the department manager. Nuclear Administrative Procedures (NAPS) and station APs and all subsequent revisions thereto are reviewed by QA and SORC and are approved by the station General Manager. Procedures cannot be implemented unless the review / approval process is accomplished. The Nuclear Administrative Procedures Manual provides a means to accommodate on-the-spot changes to subtier implementing procedures. The routine practice for revising a procedure is to repeat the original review and approval sequence. Implementation of the QA program is verified by means of independent inspections, assessments, monitoring, and audits conducted by QA. QA reviews and analyzes problems affecting quality that occur during the operational phase. Items subject to review include:
- 1. Documented nonconformances occurring at the supplier's facility and those identified during receiving, storage, installation, test, and operation, e.g., Deficiency Reports, Nonconformance Reports, Work Orders, Licensee Event Reports, etc.
- 2. Documented corrective actions taken on conditions adverse to quality and actions to prevent recurrence on significant conditions adverse to quality.
- 3. NRC inspection findings, notifications, bulletins, etc.
l l 17.2-12 l SGS-UFSAR Revision 15 June 12, 1996
. . _ _ _ _ . _ _ . - _ . _ _ _ _ . .. . . _ _ _ .. _ . - . _ . ~ . _ _ . _ _ _ . _ _ _ _ _ . _ .
{ The DI" OA/NGR Director M Quali.ty, NThifandi EP [and? thef Manase.r}{ Quality y Asse'esmentior their designees, has have the authority to stop work through the issuance of a stop Work Order where continuance of an activity would seriously l compromise quality or constitute a persistent and deliberate failure to correct a significant condition adverse to quality. D ign :: includ; th; ".:n:ger
; Ouclity ?. ::::: nt fer :tifitie ::nducted at the at tion and the ": nager Corr et44: Action and Quality Service for supplier ::tivitics.
4
. QA reports significant conditions adverse to quality affecting the quality assurance program to respective management, along with:
l l 1. Measures taken to improve QA program controls.
- 2. Appropriate recommendations to achieve compliance with applicable requirements.
l Management policy and administrative procedures provide all personnel with
- l. awareness and direction for reporting of defects and noncompliance pursuant to 10CFR21.
The QA program requires that safety related activities and activities affecting i j the fire protection of safety-related areas, be accomplished under suitably controlled conditions. The program takes into consideration the need for procedures, special controls, cleanliness, special processes, test equipment, i tools, and skills to obtain the required quality and the verification of quality 4 by inspection, test, examination, monitoring, assessments and independent review and audit. These activities include, but are not limited to, designing, j purchasing, fabricating, handling, shipping, storing, cleaning, erecting, 4
) installing, inspecting, testing, operating, maintaining, reworking, repairing, ; refueling, and modifying.
I Personnel who have the responsibility to implement the QA program also have the j responsibility and authority to escalate unresolved quality problems to the level
; of management necessary to effect resolution. Escalation is applied by QA personnel to increasingly higher levels of management, up to the CNO/PNBU, as j
. required, a
4 l i i 4 4
)
17.2-13 SGS-UFSAR Revision 15 3 June 12, 1996 4
., = - . - . - . . . .
- Personnel performing Q-Listed activities are trained or indoctrinated as necessary to assure that suitable proficiency is achieved and maintained.
f Personnel outside the QA organization who perform inspections and tests are trained and qualified in QA concepts and practices, i l. I Orientation is provided for new employees entering QA from other organizations ; l within PSE&G and from outside the company. An outline of the content and program objective is contained in the QA training and certification program. The training and certification program is designed to f amiliarize the employee with: i
- 1. Codes, regulations, specifications, etc, applicable to nuclear and other power generation equipment, j
- 2. QA procedures, instructions, specifications, documentation, records, etc.
- 3. Auditing and assessment objectives and techniques.
- 4. Operational Quality Assurance Program.
- 5. Quality Assurance Operacional Philosophy.
- 6. Other organizations within PSE&G with which QA interfaces.
QA administers formal QA training sessions for personnel outside the QA organization who perform safety related activities. The content of these training programs, dates of the sessions, and names of the attendees and their individual performance evaluations are documented and retained. Personnel requiring certification are evaluated to establish their qualifications for their respective level and discipline. Recertification is based upon demonstrated continued proficiency or requalification, if necessary. Personnel requiring certification in accordance with Regulatory Guide 1.58 are limited to personnel who perform inspection, test, and nondestructive examination (NDE) > 17.2-14 SGS-UFSAR Revision 15 June 12, 1996
l l l 303 activities, personnel who perform post-design modification testing, and I Inservice Inspection personnel who perform NDE and tests required by the Inservice Inspection Program. Those above personnel who perform visual examination (VT1, 2, 3) and NDE in accordance with the Inservice Inspection ! program are trained, qualified, and certified in accordance with a program which ' t additionally meets the prescribed supplementary requirements of ASME Section XI. l These personnel receive a periodic training needs assessment to identify additional supportive training needs, as well as to evaluate individual post-training performance. The assessment period is 3 years or less. Personnel who are qualified and requalified for their respective level and j discipline in accordance with Regulatory Guide 1.8 and ANSI N18.1 and direct or supervise the conduct of individual preoperational, startup, and operational l inspections and tests, including Technical Specification Surveillances and l periodic inspection and test of fire protection equipment, do not require certification per Regulatory Guide 1.58 and ANSI N45.2.6 1978. When a single inspection or test requires implementation by'a team or group, personnel not meeting the requirements of Regulatory Guide 1.58 and ANSI N45.2.6 1978 may be used in data-taking assignments or in plant or equipment operation provided they l are supervised or overseen by an individual participating in the inspection, l examination, or test and the individual is qualified and requalified for their respective level and discipline in accordance with either Regulatory Guide 1.8 and ANSI N18.1 or the individual is certified in accordance with Regulatory Guide 1.58 and ANSI N45.2.6 1978 as appropriate. In addition, Regulatory Guide 1.58 and ANSI N45.2.6 1978 do not apply to NRC - Licensed Operators and Senior Operators for the performance of duties specified in 10 CFR 55 " Operator Licenses". The Nuclear Training Center is responsible for the licensed operator training and retraining, in addition to other technical and supervisory training programs. Training programs of supporting organizations are described in their manuals, which are required to comply with the QA program. 1 i i j i l 17.2-15 l SGS-UFSAR Revision 15 ' June 12, 19?6 l
General Employee Training, which is required for all personnel having access to the station, is the responsibility of the Director -JQuality/:.NT,.' and'EP "anage r "aclear Security. 17.2.3 Design Control The scope of the design control program includes design activities associated with the preparation and review of design documents, including the correct translation of applicable regulatory requirements into design modification, procurement, and procedural documents. The design control program includes activities such as field design engineering, associated computer programs, compatibility of l 1 i l l 17.2-15a SGS-UFSAR Revision 15 i June 12, 1996 i
1 l J l J l i i 4 l THIS PAGE INTENTIONALLY LEFT BLANK t A l j l 1 I i i 1 I l 1 I 17.2-15b SGS-UFSAR Revision 13 June 12, 1994
materials, and accessibility for inservice inspection, maintenance, and repair. Issuance of new drawings and revisions to existing drawings require the implementation of a design change. The term design change, as used throughout this document, shall apply to both design and configuration changes. l i a The Nuclear Engineering Manual (NEM) procedures provide implementation guidance ,
, for the intent of Regulatory Guide 1.64, " Quality Assurance Requirements for the !
Design of Nuclear Power Plants." QA will conduct periodic engineering process l assessments which include procedures contained in the 4NEMf, . The Senior J Vice[ Presiden(-L ; Nuclear Engineering Ocpartrcut has overall responsibility [for';the design]contro1}pragpami: FSpecificiresponsibilitiesfare identified?in Sect;ionJ1311.1.2;1{3lth fallering recpencibiliticc. - 1 i ( 1. Preparc and update detailed engineering and dccign dccurentc, { , including drawings and specificaticac, fcr all cyctcms, components, _. a. . . _. . . . ._. . . _ , , h
- 2. Epccify applicable ccdcc, ctandardc, regulatcry and qu
- 1-i4,af f cquircm:nts acccptancc standarde, and Othcr accign input ;n design !
j _m_.._.,.__ r d f i j 3. Identify cyctc=c, cc=penantc, 2nd structurcc that crc ccvered by
~
th quality accurance program f ll 0 Perferr dccige verification for cystc;c, cc=poncntc, and structurcs : q cercred by the O?. Prcgrar i e Pe r f er- caf ety evaluatiene of propoced decign changec, := required . 1 e i i s 1 I En T.pply Ccncric 10Cr" 50.50 Cafcty Evaluation, : 70guired, tc ccnfiguratien changcc that impact the C?." 5 P cparc accumente fer procu:cment of equipment, materialc, and componcnic, 17.2-16 ; SGS-UFSAR Revision 15 : June 12, 1996 ) i i l
R:::.. ..:ni :ngineering concult:nts and 1 hcrateries f or precurc= cat l- :: vies and : rdinct: their tivitic:
? RVier d ign d: ument: Cub =itted by cupplier (including the
";;1 r Cte: Cupply Oyster ("CCC) cupplier; and contracters.
^
(. . Op :ify, : approv: :: required, insp :ti::: rnd/ : t;:te, l
- 10. D::ignet uhether they uill ::ch th ::rvie: cf :ther qualified-( engin ring rgani :tiene, I
i The cognizant engineer is responsible for the identification and completion of ( design analyses. The purpose of design analysis is to assure that the technical l design is accomplished in a planned, controlled, and correct manner. Types of
' design analyses include, but are not limited to, reactor phys ics , stress, seismic, thermal, hydraulic, radiation, and accident.
( Design verification is performed on design analyses, drawings, specifications, and other design documents, as applicable. It is the process of reviewing, confirming, or substantiating the adequacy of design by one or more methods. Design verification is performed on changes to previously verified de-1gns, including evaluation of the effects of those changes on the overall design. In general, design verification is completed prior to installation and in all cases is completed prior to placing the modified system or component into service. Design verification is performed by competent individuals .or groups other than those who performed the original design, with the j following exceptions a design verifier may be the design originator's supervisor, provided that he did not specify a singular design approach or rule out certain design considerations and did not establish the design inputs used in the design, or if the supervisor is the only individual competent to perform the verification. This design verification provision is individually documented and approved in advance by the supervisor's management. Procedural control is i i i
)
17.2-17 l SGS-UFSAR Revision 9 July 22, 1989
~_ - -- -
4 established for design documents that reflect the commitments of the UFSAR; this control dif ferentiates between documents that receive formal design verification , by interdisciplinary or multiorganizational teams and those which can be reviewed by a single individual (a signature and date is acceptable documentation for personnel certification). Design documents subject to procedural control ! include, but are not limited to, specifications, calculations, computer progr .4, system descriptions, and drawings, including flow diagrams, electrical single-line diagrams, structural systems for major facilities, site arrangements, and , equipment locations. Specialized reviews should be used when uniqueness or special design considerations warrant. The responsibilities of the verifier, the areas and features to be verified, the pertinent considerations to be verified, and the extent of documentation are identified in procedures. Control of this function is assured through periodic l
- QA/NSR audits and assessments.
j , Design verification methods comply with applicable requirements of ANSI N45.2.11 and may include, but are not limited to:
- 1. Design reviews.
- 2. Alternate or independent calculations.
- 3. Qualification testing.
In the event that the verification method for design modifications is only by test, procedures and instructions will be written which include measures to ensure that:
- 1. Criteria are provided to specify when verification should be by :
test.
- 2. Where applicable, prototype, component or feature testing will be performed prior to installation of plant equipment. In those cases where this cannot be met, the 17.2-18 SGS-UFSAR Revision 15 June 12, 1996
I testing will be deferred, but not beyond the point when the installation would be irreversible. l
- 3. Tests will be performed under conditions that simulate the most i I
adverse design conditions, as determined by analysis. { I Drawings are prepared by, or under the supervision of, a designer from informn '.on received from the responsible engineer, manuf acturer's drawings, etc. The drawings are reviewed and initialed as being checked by another designer or design supervisor. The drawings are approved by the functional supervisor or his j designee. Specifications and changes thereto for items covered by the QA program are prepared by Nuclear Engineering, and are reviewed by Supplier Assessment for QA content. QA review assures that the documents are prepared, reviewed, and approved in accordance with company procedures and that the documents contain the necessary QA requirements, such as inspection and test requirements, acceptance requirements, and the extent of documenting inspection and test results The Station Operations Review Committee (SORC) reviews proposed changes af fecting nuclear safety and makes recommendations concerning implementation of the change to the station general manager. The design change process provides for signoff of the design change by the appropriate department head for the purpose of identifying required procedure change. If the proposed modification involves a Technical Specification change or is considered by the SORC to involve an unreviewed safety question (10CFR50.59), the matter is submitted to the Nucleas Review Board'(NRB)Offsite ccfety nccicu Orcup 'OSn) for a determination of its safety implication before a license change request is submitted for NRC approval. DuringLthe; preparation ;of.."cr "ucicer "ngineering prcpered design changes, Nuclear Engineering assigns a project team led by a project manager,fasfrequired. The project team consists of members of various i I l l I l
- 17.2-19 SGS-UFSAR Revision 15 l June 12, 1996
l organizations, both internal and external to Nuclear Engineering. The project l team members are responsible for providing technical and administrative input to the entire design change process, which consists of design, installation, testing, and closecut phases. The technical and administrative input is guided by the reg'tirements of those organizations which comprise the project team. The project manager ensures that the specific requirements of each organization on i 1 j the project team are considered to ensure the overall quality of the product. J l For design changes important to safety, the QA reprenantative on the project team I f provides input and assures that design changes include quality assurance l requirements such as inspection and test requirements, acceptance requirements, test result documentation, and project team compliance with company procedures during preparation, review, and approval of design changes. ~ Updating of records, including drawings, blueprints, instructions technical ) i manuals, and specifications resulting from design changes, is the responsibility j of the Senior Vice President - Nuclear Engineering. Design change procedures provide for the timely update of af fected drawings following design change l l l implementation to reflect as-built configuration. t 17.2.4 Procurement Document Control i Procurement documents and changes thereto for the purchase of Q-Listed material, I equipment, or services are reviewed and approved by QA prior to issuance by the Purchasing Department to the prospective supplier. QA review assures that spare and replacement parts are procured using controls which are commensurate with j' current QA program requirements. > l i 17.2-20 SGS-UFSAR Revision 15 June 12, 1996 i
l The review also assures that procurement documents adequately and correctly: 1
- 1. Identify applicable QA program requirements.
- 2. Reference applicable regulatory requirements, codes, and standards.
- 3. Provide right of access for source surveillance and audit by QA or its agents.
- 4. Provide for required supplier documentation to be submitted to PSE&G or maintained by the supplier, as appropriate.
- 5. Provide for PSE&G review and approval of critical procedures prior to fabrication, as appropriate.
Procurement documents require suppliers and contractors of other than commercial-grade items to provide services or components in accordance with a QA program that complies with applicable parts of 10CFR50, Appendix B. The requirement for notifying PSE&G of procurement requirements that have not been met is conveyed to the supplier through the standard warrant y provision contained in each purchase order. In addition, where 10CFR21 is imposed, suppliers are required to comply with applicable reporting requirements. 17.2.5 Instructions, Procedures, and Drawings organizations engaged in Q-Listed activities are required to perform these j activities in accordance with written and approved procedures, instructions, or drawings, as appropriate. Simple, routine activities that can be performed by qualified I 17.2-21 SGS-UFSAR Revision 10 July 22, 1990
l 4 personnel with normal skills do not require a detailed written procedure.
- Complex activities require detailed procedures. The designation of those activities requiring detailed procedures is made by cognizant department heads and, as a minimum, complies with applicable requirements of Regulatory Guide 1.33.
Procedures include, as appropriate, scope, statement of applicability, references, prerequisites, precautions, limitations, and checkoff lists of inspection requirements, in addition to the detailed steps required to accomplish l i the ectivity. Instructions, procedures, and drawings also contain acceptance j criteria where appropriate. ; l The appropriateUstation general managerWdirector is responsible for assuring that ctatier procedures are prepared, approved, and implemented in compliance with the Nuclear Administrative Procedures Manual. Documents affecting nuclear safety are reviewed by the SORC for technical content, by QA for QA requirements, and are approved by the responsible station department manager or his designee. The Director? -1[Nuclea@BusinessMSupportCenicr Vic: Precident "ucicar Engineering is responsible for issuing specifications, drawings, blueprints, procedures and administrative and technical manuals associated with structures, systems, and components covered by the QA Program. Approved and implemented modifications and design changes are incorporated in these reference documents for the life of the station. Master lists of current editions or revisions of these documents are maintained by Nuclear Business [SupportEnginccring and are available at the station to assure that only current and approved referenced i documents are used. QA reviews and approves selected ctation procedures that implement the QA program, including testing, calibration, maintenance, modification, rework, and repair. Changes to these documents are also reviewed and approved. In addition, QA is responsible for review and approval of selected specifications, test procedures, and results of testing. l l I l I l l 17.2-22 { SGS-UFSAR Revision 15 i June 12, 1996
I l 17.2.6 Docuraent Control i i Instructions, procedures, drawings, and changes thereto are reviewed for the i inclusion of appropriate CA requirements, approved by apppropriate levels of management of the PSE&G organizations producing such documents, and distributed on a timely basis to using locations. Measures are provided for the timely removal of obsolete or superseded documents from the using location. Supplier documents are controlled according to contractual agreements with suppliers. The following is a generic listing of key documents for the operational phase, showing minimum organization responsibility for review and/or approval, including changes thereto:
- 1. Design specification - Nuclear Engineering, QA.
- 2. Design modification, manufacturing, construction, and installation 1 1
drawings - Nuclear Engineering, Nuclear MaintenanceOperctions 1 1 Scrficcc, station operations. { 1
- 3. Procurement documents - Illitiating NBU organization, Purchecing 1 Ocpertment, Nuclear BusindssiSupportOperction: Ccrciccc, QA.
- 4. Nuclear Administrative Procedures Manual - NBU organizations j responsible for implementation, QA. I
- 5. NBU second-tier manuals, including station administrative ;
procedures - Cognizant department head, QA. I
- 6. Maintenance, modifica tion, and calibration procedures for 0-Listed designated station 'iork activities - Nuclear ]MaintenanceGt+ Men operctienc.
7 Operating procedures - Station operations. 1 17.2-23 SGS-UFSAR Revision 15 June 12, 1996
- 8. UFSAR - Licensingrand! Regulation"uclecr Cpcretienc Cerviccc and other NBU organizations responsible for implementing applicable sections. In addition, QA reviews subsequent changes to the UFSAR sections to the extent necessary for assuring compliance with applicable QA program requirements.
- 9. Maintenance, inspection, and testing instruction - NBU implementing organizations.
- 10. Post-modification test procedures - Nuclear Engineering.
- 11. Design Change Requests - Nuclear Engineering, QA.
QA involvement in the work activity includes review of work procedures prior to approval for designation of inspection hold points (see Section 17.2.10) , review of completed safety-related Work Orders on a sampling basis, and periodic QA surveillance and assessment. The establishment and maintenance of a document control system for all instructions, procedures, specifications, and drawings received from the NBU or prepared at the station for use in operating, maintaining, refueling, or modifying items and services covered by the QA program is the responsibility of the Director $ 4 : ? Nuclear 7 Business FSupportiC:nic: " ice President W eleae Engineering. The Nuclear Administrative Procedures Manual describes the coatrols for specific documents. Control of station practices is included in the administrative procedures authorized by the responsible atetien department managers. Measures are established to assure that administrative procedures are up to date, properly authorized, changed only after the required review and approvals are obtained, and distributed to appropriate personnel. Design change procedures provide for the timely update of af fected drawings, following design change implementation, to reflect as-built configuration. Computerized databases maintained by the NBU organization are used to control drawings, specifications, procedures and instructions. 317J2-24' SGS-UFSART :RevisionD15 June 12jl]1996
. _. . - .- .- . . - - _ . _ . _.~. _ . _. . . -
Controls of software affecting nuclear safety are identified in the Nuclear Administrative Procedures Manual. These controls are based on applicable guidelines provided by the NRC and include software review and approval as well as access controls to prevent unauthorized software changes. 17.2.7 Control of Purchased Material, Equipment, and Services ] QA maintains an up-to-date listing of approved suppliers of material, equipment, f and services covered by the QA program. This list identifies suppliers and contractors that have demonstrated the ability to supply acceptable material, equipment, or services. The list includes manufacturers of commercial-grade items. All QA program procurements are made from approved suppliers. The responsible engineer and QA personnel select and evaluate prospective bidders and suppliers. The responsible engineer determines the technical competence of the supplier, while QA evaluates the prospective supplier's QA program for the capability of meeting applicable requirements of 10CFR50, Appendix B, and for extending applicable program requirements to subtier suppliers. Qualified QA personnel evaluate the prospective supplier's OA capability using . one or more techniques, including but not necessarily limited to:
- 1. Evaluation of supplier's or contractor's procedures or manuals and e changes thereto. l
- 2. ASME code stamp approval.
- 3. Nuclear Utility Procurement Issues Council (NUPIC) or Nuclear Fuel Users Forum (NFUF) Audits.
- 4. Satisfactory past history of providing similar items.
i l 17.2-25 SGS-UFSAR Revision 15 3 June 12, 1996 l l
- 5. Survey of supplier's facility.
i l The evaluations of the prospective suppliers are conducted using standard ] checklist form designed to include the 18 quality criteria of 10CFR50, Appendix B, as appropriate. Surveys of suppliers' capabilities include evaluation of management systems, manuf acturing processes, and adherence to QA/QV procedures. The results of supplier evaluations are documented by the appropriate checklist form and filed. Supplier control is maintained through a planned inspection, monitoring, and audit program by QA. QA and the responsible engineer conduct a review of the manufacturing process for complex manufactured items, such as pumps, valves, heat exchangers, vessels, electrical panels, etc. This review establishes critical inspection points and establishes a notification point program for the identified inspection or surveillance activities. The established inspection or surveillance activities are implemented by qualified QA personnel or QA agents. Commercial grade items , are dedicated in accordance with recognized industry standards, e.g. EPRI NP-5652. t Monitoring of suppliers / contractors during fabrication, installation, modification, rework, repair, inspection, testing, and shipment of Q-Listed materials, equipment, and services is conducted by qualified QA personnel or QA agents at the supplier's/ contractor's facility or at the generating station. Surveillances are conducted in accordance with written procedures and are designed to assure conformance with procurement requirements, in accordance with the safety significance of the item or service. Periodic evaluations of the supplier / contractor quality program are also conducted, consistent with the importance or complexity of the 17.2-26 SGS-UFSAR Revision 15 June 12, 1996 i
item or service. Dependent upon the evaluation, additional audits or corrections by the supplier / contractor may be required. Supplier's certificates of conformance are periodically evaluated by audit, inspection, or test to assure that they are valid. Results of these audits, inspections, or tests are documented. Where feasible, replacement parts adhere to the original design criteria (such as Nuclear Steam Supply System (NSSS) components in accordance with NSSS l documentation and other code components in accordance with AWWA, AISC, SPCC, and ASME B&PV Code, editions and addenda as applicable to the component or system) . This provides the intended level of safety and does not result in redesign of the system. l The requirement for appropriate supplier documentation of conformance to , applicable code, standard, specification, or other quality requirements is provided by the procurement document. The supplier-provided documentation is reviewed either at the supplier's facility during source surveillance, or by Material Compliance Group during material evaluation activities. A data review checkoff is used to document the acceptability of the supplier-provided data and ! to identify discrepancies. l Evaluation of supplier equipment, material and services is conducted by qualified personnel to verify correct identification, appropriate documentation, and ' o verify that the item is acceptable and can be released for storage, installation, or use. l Nonconforming items identified by the Material Compliance Group are tagged or ( segregated to prevent inadvertent use. Nonconforming items are controlled as I described in Section 17.2.15. l l 17.2.8 Identification and Control of Materials, Parts, and Components l l Procurement document controls provide assurance that materials, j ! l l l l t i J , 17.2-27 l SGS-UFSAR Revision 13 l June 12, 1994
parts, and components received can be properly identified. The identification is directly marked on the item or on records traceable to the item. The data review conducted at receiving assures that proper documentation of received items is available. Materials and items received without proper identification are tagged or segregated until satisf actory documentation and identification is obtained. Procedures require that Q-Listed materials, parts, and components be marked or otherwise identified and that such identity be maintained either on the item or on records traceable to it throughout receipt, storage, installation, and use. Protection against use of incorrect or defective items also is provided. Material identification and traceability is maintained for rework, repairs, and modifications throughout operation. Identificationj fand ; 'contror;Mofy;inaterials b [ parts;.R;.andMcomponentsEurenthe iresponsibility [of 'NucleariMaistenanceJNuclear? EngineeringfandjNuclearl Business 'Supportp ;Prosurement[documentM;controlslareh;th6 responsibility [of.J[Quslitp
~
Assuiancef Rece.iptQstorage[ installation,Jinspectiori'and test acti;vities hreithe Tof; LNuclear) Business;j ' Supporth TQAf (and$ INuclear
~
responsibility" Maintenance.organi-eatienc -tich impicment requirements for th: identification and centr:1 cf materialc, partc, and ccmponente include Nuclear Operatienc serviccc, Nuciccr Engineering, station cperatienc and 07. for precurcm:nt docum:nt centrel and Precurement and " teri:1c "anagement, ctatic cperatienc and O?. for rcccipt, etcragc, inctallation, incpectica and tcct activiticc. 17.2.9 Control of Special Processes Special process controls provide for the use of qualified procedures, equipment, personnel, and documentation of satisfactory completion of an activity. Special processes are generally those processes where direct inspection is impossible or disadvantageous. Procedures have been established for special processes such as welding, brazing, soldering, concreting, protective coating, cleaning, heat treating, and nondestructive examination (NDE) to assure compliance with codes and design specifications. The Senior Vice PresidentVP - Nuclear Engineering is responsible for preparing special process procedures such as concreting, protective coating and cleaning, while the 17.2-28 SGS-UFSAR Revision 15 June 12, 1996
G2naral Manager - NuclearJMaintenanceWcicar Opcratienc Cerviccc is responsible for preparing specifications for processes such as welding, brazing, soldering, and heat treating. Nuclear Engineering is responsible for preparing specifications for nondestructive examination (NDE). These specifications are reviewed and approved by QA for necessary quality content. QA monitoring assessements and audits assure that qualification of special processes, equipment, and personnel have been satisfactorily performed.
]
Procedures for implementing the requirements of the specifications are prepared either by the NBU or by supplier personnel and are reviewed by QA and the appropriate general manager, or their designee, with the exception of special process procedures prepared by code suppliers holding a valid certificate of authorization. Qualification records of procedures, equipment, and personnel associated with special processes are retained as stated in Section 17.2.17, 17.2.10 Inspection A planned inspection program is conducted and documented by personnel appropriately qualified in accordance with Section 17.2.2. The inspection I program verifies conformance to the established procedure, code, or standard, l consistent with the item's or activity's importance to safety. The inspection program for maintenance and modification activities is based upon the following three important levels of inspection:
- 1. Worker Checks - Quality cannot be achieved unless the worker performs the activity in a quality manner. The worker is the individual best able to control the quality of work being performed. Work steps that contain elements impacting plant equipment or systems have provisions for signoff by the worker.
This worker slo 7tablishes accountability for the activity and is i t s 17.2-29 SGS-UFSAR Revision 15 June 12, 1996
I ? a acknowledgement that the activity has been performed as specified in l
- j. the work step.
i l
- 2. Supervisory Inspection - Although the work supervisor may have ;
overall responsibility for the conduct and performance of the work l l activitys .certain conditions at the work location require ; supervisory inspection to increase confidence that work activities j are completed as specified through familiarity of the work i activity,t work group, or past experience. Supervisory inspections l are established in the appropriate work procedure and accomplished i 1 through direct observation of the work activity. ' L . l 3.. Independent Inspection - Independent inspections are not intended I to dilute or replace the responsibility of the worker check or l supervisory inspection for quality. of work. Independent i inspections provide the maximum confidence attainable that the work l activity has been performed in accordance with the overall objective. Typical guidelines for establishing independent inspections include conditions similar to the following:
- Work activity affecting redundant equipment or potentially causing cascading failure.
- Retest will not verify the applicable. attribute.
- Establishing a baseline in a new process or procedure.
l
- It is deemed necessary to maintain confidence in the work I process.
I This guidance .is considered by the responsible QA organization in the j establishment of inspection activities. ! 1 i j I i 1 1 1 I i I 17.2-30 SGS-UFSAR. Revision 9 l July 22, 1989
- - ,,c -
, -v., y - . - , ~ - ,
i Independent inspections are identified as Inspection Hold Points (IHPs) in the applicable work instructions and are performed by individuals independent of the i work activity. IHPs cannot be passed without authorization from the applicable l management representative responsible for the inspection activity. i I General guidelines for the inspection criteria are established by QA and ! incorporated into various administrative and work instructions. Independent inspections are performed by QA or other individuals who are independent of the work activities. If the individuals performing inspections are not part of the QA organization, the inspection procedures, personnel qualification criteria, and independence from undue pressure, such as cost and schedule, are reviewed for acceptability by the QA organization prior to initiation of the activity. Work procedures and inspection instructions include, as required, characteristics to be inspected, method of inspection, acceptance criteria, required measuring and test equipment, and required reference documents. Documentation includes inspection identification and results of inspection performance. As a result of its review, the Station Operations Review Committee (SORC) may recommend additional or different hold points to the organization performing the work activity. Periodic inspection, other than IHPs, is performed by qualified individuals other than those who performed or directly supervised the activity being inspected. These typically include periodic inspections of the following:
- 1. Storage areas.
- 2. Housekeeping (general).
l l l i l 17.2-31 SGS-UFSAR Revision 11 July 22, 1991
- 3. Fire protection equipment.
- 4. Special handling tools and equipment.
- 5. NDE visual inspection required by the inservice inspection program.
An independent organization shall perform NDE as required, using qualified individuals other than those who performed or directly supervised the activity, i When inspections are performed by individuals other than those who performed or j directly supervised the work, but who belong to the same work group, and the l activity involves breaching a pressure-retaining boundary, the quality of the ) work is demonstrated through appropriate testing, unless restrictions such as ) ALARA considerations prevent such testing. l l The applicable inspection and retest requirements necessary to assure that modifications, rework, or repairs have been accomplished correctly are included in the design change package, work order, or procedure. The inspection and retest requirements for modificaricn, rework, and repair are based on the original inspection and test program, as well as the nature and scope of the j I modification or repair activity. Evaluation and review of inspection results are conducted by personnel certified l Level II in ANSI /ASME N45.2.6 and SNT-TC-IA, as applicable. A planned and documented QA monitoring program is conducted by QA for quality program activities, including the inspection program and personnel qualifications. Monitoring of the implementation of the QA program by station and site contracte personnel is conducted by QA, in addition to offsite supplier activities as appropriate. Conditions adverse to quality found during the conduct of monitoring are brought to the attention of the management responsible for the activity. I l l i 17.2-32 i SGS-UFSAR Revision 15 June 12, 1996
_. . - - u - - - - - .
.- a .u_ _ - _a._-- .s -a +__a s .
I
- The Manager - Statica Quality AssessmentAccurance, or his designee, routinely attends and participates in plant work schedule and status meetings to assure i that they are kept abreast of day-to-day work assignments throughout the 1 1 ant and that there is adequate QA coverage relative to procedural and inspection controls, acceptance criteria, and QA staffing and qualification of personnel to carry out QA assignments.
17.2.11 Test Control , Q-Listed equipment and components that must be tested periodically to assure satisfactory performance, or have been replaced, modified, or repaired, are tested by qualified personnel in accordance with written procedures that provide , acceptance criteria based on . requirements contained in applicable design and procurement documents. ' Provisions are implemented that assure that nonconformances are corrected or resolved prior to the initiation of the preoperational test program on the item. Retest requirements are provided by engineering specifications and/or the l responsible engineer, or both as were the original test requirements. The Nuclear Engineeringji[NdelearhlMaintenancs and operations departments are responsible for preparation of test procedures incorporating the engineering l 1 parameters. l Test procedures prescribe, as applicable:
- 1. Prerequisites, including completeness of test item (s).
I
- 2. Instructions for performing the test.
- 3. Instrumentation and equipment for conduct of the test adequate to j the test objective.
- 4. Suitable environmental conditions and adequate test methods, 17.2-33 SGS-UFSAR Revision 15 June 12, 1996
l
- 5. Critical test sequence. 1 I
1
- 6. Acceptance criteria.
j
)
l 1 Test results, including verification of above items, are documented and reviewed for acceptability by the qualified department representative. 1 4 In addition, the Nuclear Administrative Procedures Manual provides for the use 1 of temporary changes which are controlled in accordance with Technical 1 Specifications. Detailed instructions for implementation of temporary changes are provided. QA performs assessments of selected post-modification tests to assure compliance , i with the test procedure. Test results are reviewed for the following:
- 1. Presentation of proper documentation.
5 2. Assurance that tests meet objectives. t $ 3. Identification and reporting of unacceptable results and initiation of corrective measures. 17.2.12 Control of Measuring and Test Equipment 4 Test equipment, instrumentation, and controla used to monitor and measure activities affecting quality and personnel safety are identified, controlled, and calibrated at specific intervals by cognizant NBU personnel. Written 5 procedures for meeting these requirements include provisions for:
- 1. Specifying calibration frequency.
- 2. Recording and maintaining calibration records.
4
- 3. Controlling and calibrating primary and secondary a
d a i J 4 i i 17.2-34 SGS-UFSAR Revision 15 June 12, 1996 i
standards. t
- 4. Determining methods of calibration.
- 5. Tracing use on Q-Listed items.
Measuring and test equipment (M&TE) calibration procedures are prepared in accordance with the applicable supplier's manual requirements, unless specific exemption is approved by the cognizant station department head. M&TE, which is ' so exempted, is identified by use of a label or tag on the item. Prior use of measuring and test equipment found to be out of calibration is i evaluated for possible effect on safety-related items. Measurements are repeated where necessary. j l Ca. li. br. a.t.i. o.d,f..a..t..a. n. da.rd. . s.f.. a. k.ev eR.t...,ra..c.e.. a.. 'b.le.
.e -
. y . T.v't.-.M...c.t, he...v!.N..a.t. io. .r. ia.lTT..u. 4st.. i.6..
v;
- b. t.e. 7 o, f.. ? S.
,y f ts, ud, ak. .d. .s..g .a, h. d Technologp]NIST) Qhysicaly cons t arit s { or; be stfi.ndus t ry[s;t;andards ]where' no{othe r standa'rdstexistrLTo[thefsktentjpelrmitt'ed)pithe';etatej;ofith41arQthefibcUrasp O fithe;l s tnada rdsjused}tolpe rfo rmicalibratiions ;isla t]l esst2 f os(timei g reat e rithan t, he7;acesFaciM.of f.. t. h. eE.devics_[beid.gE. Ei1~ibratsdi'm ? Pro.. c...sdurssEs.r..if.i.. h_7, plicEwhich
~
. , _ m jieseribe? theYthethodsand Lassi' g n;[the]@esponsibilltpffoE3seceptance3[ofylsssii bncertainty] ratios!Screndary at:ndard cre : librated by certified ::libratzen 1:baratcric: and are traccable tc the National I.ctitute of Standard: and T:Pnclegy P?!ST), Or bent inductry tandard: 'hcrc nc NIST ctandard: Onist.
Implementing prc;;durcs .ill prccid; for documenting the basic cf : libration; which are net traceable te NIST. Tc th: cntent permitted by the ct:tc cf the art, th: : uracy cf the primary standard; used tc perfer thi: calibraticn is at 1 cant fcur ti=:2 greater th:2 th: ::uracy cf the defice being calibrated. The bi cf :::cptan:: i; dccumented and authori :d, with reopencibility
- igned t th: gni nt d:partment h: d.
Test equipment is marked or otherwise identified to indicate a unique identification number, the latest calibration date, and the next required calibration date. Measuring and test equipment is identified by affixing a calibration label, unless the size of the item makes this impractical. Out-of-calibration identification is used for instruments and controls to indicate this status pending calibration, repair, or replacement. Calibration frequency is based on the manufacturer's recommendations This frequency is adjusted when j operating experience supports this action. 17.2-35 SGS-UFSAR Revision 15 June 12, 1996
Organizations responsible for implementing measuring and test equipment calibration controls include station, Nuclear MaintenanccOperaticr.c Scr/iccc, l and the Maplewood Testing Services. 17.2.13 Handling, Storage, and Shipping The control of handling, storage, cleaning, and preservation of material and equipment covered by the QA program is specified, implemented, and accomplished f by suitably trained personnel in accordance with predetermined work and inspection instructions. Implementing procedures provide for the storage of chemicals, reagents (including control of shelf life), lubricants, and other ] consumable materials, as required. The nuclear materials management group is responsible for control of material in storage, including preservation and shipping controls. The station departments andE NaclsarR Maintlenancefare j respons'.ble for system cleanliness and handling of equipment during operational maintenance or modification. Nuclear Engineering is responsible for specifying equipment requirements. Manufacturer's instructions and recommendaticns, design requirements, and applicable codes and stan dards are implemented, as > ! appropriate. Compliance with specific handling, storage, or shipping
- requirements is required. Require ments for new components and spares, where l applicable, are included in the procurement documents.
17.2.14 Inspection, Test, and Operating Status NBU procedures are required to specify the periodic tests and inspections required for equipment covered by the QA program and to include the necessary management controls to assure that such required tests and/or inspections are completed in accordance with specified requirements. Equipment awaiting repairs, under repair, or repaired, and received materials are marked to indicate the status of inspection and test requirements and/or acceptability for use, procedures provide for tagging valves and switches to prevent inadvertent operation. These 17.2-36 SGS-UFSAR Revision 15 June 12, 1996
. _ _ _ _ . _ _ . _ . . _ _ _ . . . . . _ . _ _ _ _ _ _ _ _ , . . _ . _ _ _ . _ _ . _ ___ _ __ _ -.._ _.m. . _ . _ . _ _ _ _
l i procedures control the application and removal of tags and are designed to prevent operation of valves and/or switches that could result in personnel hazard or equipment damage. Valve and equipment status boards or logs are maintained to indicate status. 17.2.15 Nonconforming Materials, Parts, or Components ; Organizations involved in material receipt, installation, test, design j modification, and other operating activities are responsible for identifying and 1 documenting nonconformances. Nonconforming materials, where practical, are { i segregated to prevent installation or use until proper approvals are obtained. Materials, parts, or components that have failed in service are identified and, s where practical, segregated. Procedures control the application and removal of ! tags. ! Documentation of the nonconformance includes a description of the nonconformance, , review by shif t]SupspintiendentGNGG/NSS for Limiting Condition for Operation (LCO) ;
- j. ' applicability when appropriate and the disposition and inspection or retest l
requirements, as appropriate. The responsible Engineer dispositions each j nonconformance report. Dispositions for repair or "use-as-is" are required to l be reviewed and approved by QA prior to implementation. Rework or repair of j nonconforming material, parts, or components is inspected or retested, or both, i in accordance with specified test and inspection requirements established by the l l responsible engineering representative, based on applicable requirements. QA l l- shall verify the satisfactory completion of the disposition of nonconformances. : ! l QA and other organizations in the NBU review nonconformance reports for quality ) t problems, including adverse quality trends, and initiate reports to higher , l ' i management, l l } i ) i 17.2-37 i SGS-UFSAR Revision 15 l
- June 12, 1996 i
, _ , _ , _ ._ _ __ . . . . _ m.._-.
identifying significant quality problems with recommendations for appropriate action. 17.2.16 Corrective Action organizations involved in activities covered by the QA program are required to implement corrective action for significant conditions adverse to quality and . conditions adverse to quality identified within their scope of activity. Such conditions are documented and controlled by the issuance of an action request. j The QA Corrective Action Group reviews responses to action requests for adequacy and monitors these action requests through periodic summary and status reports to management. 1 Responses to action requests are based on the four elements of corrective action, which are: l 1. Identification of cause of deficiency.
- 2. Action to correct deficiency and results achieved to date.
- 3. Action taken or to be taken to prevent recurrence.
- 4. Date when full compliance was or will be achieved.
4 For significant conditions adverse to quality [ not identificd by 07., such as LERs and NRC/INPO/CMAP findings, the QA Corrective Action Group is involved in the 1 review of such conditions and provides oversight to assure timely followup and i 4 closecut. ' Items 3 and 4 are optional for conditions adverse to quality, i
- Proper implementation of corrective action is verified through surveillance i
inspection assessment or audit, as appropriate. The appropiristectction general manager orfdirsctor"is responsible for assuring that ! l l t 17.2-38 SGS-UFSAR Revision 15 June 12, 1996
_- - . .. - - - _ - . - _ _ _ . _ _ =. _ .. . ,. conditions adverse to quality are promptly identified and corrected for all activities involving station operation, maintenance, testing, refueling, and modification. Administrative procedures that govern station activities covered by the QA program provide for the timely discovery and correction of nonconformances. This i includes receipt of defective material, failure or malfunction of equipment, deficiencies or deviations of equipment from design performance, and deviations from procedures. In cases of significant conditions adverse to quality, the cause of the condition is determined, and measures are established to preclude f recurrence. Such events, together with corrective action taken, are documented and reported as described in Section 17.2.15. Corrective action is initiated by the responsible department head. QA closely monitors station conditions requiring corrective action. Repetitive deficiencies, procedure or process violations at the station that are not classified as operational incidents or reportable occurrences, or nonconformances under the QA program are documented by OA via the issuance of an action request. This request provides a formal administrative vehicle to alert management of conditions adverse to quality that require corrective action. 17.2.17 Quality Assurance Records Records necessary to demonstrate that activities important to quality have been performed in accordance with applicable requirements are identified and maintained in accordance with Regulatory Guide 1.88, as noted in Section 17.2.2. Records shall be considered valid only when authenticated by authorized personnel. Record types, as a minimum, comply with applicable technical specification requirements and include operating logs, maintenance and modification procedures and related inspection results and reportable occurrences. 17.2-39 SGS-UFSAR Revision 14 q December 29, 1995
The NBU is responsible for the permanent storage of station records. The retention period for records; permanent storage location; and methods of control, identification, and retrieval are specified by administrative procedure. Individual station department heads are responsible for submitting applicable department records to the designated location for retention. 17.2.18 Audits Audits of pSE&G and supplier organizations that implement the QA program are l performed by QA to verify compliance with the applicable portions of the program, through personnel interview, observation of activities in process, and review of applicable documents and records as required. Performance based assessment should be an integral part of the auditing program and should evaluate activities f - on the basis of their eff ect on the safe and reliable operation of the facility.
- An annual audit schedule is developed to identify the audits to be performed and their frequency. A dominant factor in audit schedule development is performance
; in the subject area. Audit schedules are revised so that weak or declining areas receive increased audit coverage and strong areas receive less consistent with the audit schedule frequency requirements of the Code of Federal Regulations and the UFSAR. Audits of the selected aspects of operational phase activities are performed with a frequency commensurate with safety significance and in a manner to assure that at least biennial (2 year) audits of safety related activities are performed. A list of operational phase activities subject to the audit program is provided in Sectionf17?2f1' lj2{3the Technicc1 Specificctienc and in Table ;
17.2-1. 4 Audits are conducted by audit teams comprised of a certified lead auditor, certified auditors, and technical specialists (when deemed necessary). Audits are conducted using preestablished written procedures and checklists. Areas of deficiency revealed by audits are reviewed with management and are corrected in a timely manner. Required corrective action is documented and verified. Followup action, including reaudit of deficient areas, is performed. The audit program conducted by QA includes, but is not limited to, the following activities covered by the QA program:
- 1. Operation, maintenance, and modification.
- 2. Preparation, review, approval, and control of design, specifications, procurement and requisition documents, instructions, procedures, and drawings.
17.2-40 SGS-UFSAR Revision 15 June 12, 1996
l !. 3. Inspection programs. I
- 4. Indoctrination and training.
l [ 5. Implementation of operating and test procedures.
- 6. Calibration of measuring and test equipment.
- 7. Fire protection.
- 8. Other applicable activities delineated in Table 17.2-1.
l The audit data is analyzed, and a written report of the results of each audit is distributed to appropriate management representatives of the organization (s) audited, as well as other af fected management personnel. Included in the report is a statement of QA program effectiveness. l l QA is audited by independent auditors at least every 2 years to verify implementation of the QA program. Reports of these audits are directed to appropriate PSE&G management personnel. l I i l l l I l 17.2-41 SGS-UFSAR Revision 15 Juna 12, 1996 l l l
l l l TABLE 17.2-1 l SALEM Q-LIST j The listing below identifies those activities, services, structures, components and systems to which the Operational Quality Assurance Program applies.
- 1. ACTIVITIES / SERVICES 1.1 Safety Related Activities Delineated in Regulatory Guide 1.33, App. A (See Regulatory Guide for further breakdown of activities) 1.1.1 Administrative Procedures
- a. Security Program (Regulatory Guide 1.17)
- b. Equipment Control (e.g., Locking and Tagging)
- c. Shift and Relief Turnover l l
- d. Bypass of Safety Functions and Jumper Control
- e. Maintenance of Minimum Shift Complement and Call-In of Personnel
- f. Fire Protection Program including Inspection by Fire Consultants
- g. Communication System h; fstati.on? Operations . Review CommitteeZ(SORC) 4 l
l 1.1.2 General Plant Operating Procedures l l l 1.1.3 Startup, Operation, and Shutdown of Safety-Related Systems 1.1.4 Abnormal, Offnormal, or Alarm Conditions 1.1.5 Combating Emergencies and Other Significant Events i 1.1.6 Control of Radioactivity I i l
- a. Liquid Radioactive Waste System (including the contaminated floor and equipment drain systems) 1
- b. Solid waste System I
- c. PWR Gaseous Effluent System
- d. Radiation Protection including Occupational Radiation Exposure per Regulatory Guide 8.8 l
- e. Area Radiation Monitoring System Operation I l
1 1 of 5 SGS-UFSAR Revision 13 June 12, 1994
l l i I Table 17.2-1 (Cont)
- f. Process Radiation Monitoring System Operation
- g. Meteorological Monitoring and Data Collection Program j I
h. Packaging and Transport of Radioactive Material per 10CFR71
- i. Decontamination
)
1.1.7 Technical Specification Surveillance 4 1.1.8 Performing Maintenance l 1.1.9 Chemical and Radiochemical Control 1 l 1.2 Additional NRC Requirements 1.2.1 Technical Specification Administrative Controls
- 2. Conc ab. Reportable Occurrences
)
- 2. EQUIPMENT, COMPONENTS, AND STRUCTURES 2.1 The following are items and systems contained in commitment letters to the NRC.
2.1.1 Accident Monitoring Instrumentation 2.1.2 AC Control Power Buses and Inverters , 2.1.3 All Systems Which Penetrate Containment, up to and including the Containment Isolation Valve (Identified in UFSAR Section 6.2.4) , a i
- 2.1.4 Anticipatory Reactor Trip on Turbine Trip i
4 2.1.5 Auxiliary Building (including Control Room and Diesel Generator Area) 2.1.6 Auxiliary Building Ventilation System (Supply and Exhaust Units) 4 2.1.7 Auxiliary Feedwater Storage Tank 2.1.8 Auxiliary Feedwater System 2.1.9 Component Cooling System l 2.1.10 Chill Water System i l l
, l i
2 of 5 SGS-UFSAR Revision 9 July 22, 1989
. - ~ -. . - _. . - . - - - . .-- . - - - - __
i Table 17.2-1 (Cont) l 2.1.11 Containment (including penetrations, concrete shielding, interior j structures, air locks, equipment hatch) ,
- a. Containment Polar Crane ;
2.1.12 Containment Pressure - Vacuum Relief System 2.1.13 Control Area Air Conditioning System 2.1.14 Control Panels - Class 1E circuits 2.1.15 Electrical Cable Tunnels 2.1.16 Emergency Power for Pressurizer Heaters 2.1.17 Emergency Power Supply System
- a. DC Power Supply System ,
- b. Diesel Generator Area Ventilation System
- c. Diesel Generators (including associated fuel oil, lube oil, starting auxiliary systems, fuel storage and day tanks, jacket cooling, governor, voltage regulation and excitation systems, piping and valves)
- d. Control Boards and Motor Contrnl Centers
- e. Control equipment, facilities and lines required for above items '
- f. Power distribution lines to equipment required for emergency transformers and switchgear supplying Engineered Safety Features (includes 4-kV, 460-V and 230-V vital buses) 2.1.18 Emergency Response Facilities (NUREG-0737, Supplement 1; document control and verification of functionality only) !
2.1.19 Engineered Safety Features
- a. Containment Spray System (including spray pumps, spray header, ,
spray additive tank, connecting piping and valves) ; 1
- b. Containment ventilation System (including fan coolers, distribution ducts, dampers, HEPA filters, and moisture separators) i
- c. ECCS (including Safety Injection and RHR pumps, RWST, Accumulators, <
RHR heat exchangers, containment sump, sump screen vortex suppression devices, and connecting pipes and valves) 3 of 5 SGS-UFSAR Revision 9 July 22, 1989 i
i Table 17.2-1 (Cont)
- d. Portions of the CVCS (including Centrifugal Charging Pumps, Boron Injection Tank, connecting piping) 2.1.20 Expendable and consumable items necessary for the functional j performance of critical structures, systems, and components l (i.e., weld rod, boric acid, fuel oil, etc) l 2.1.21 Feedwater System (to outermost isolation valve) 2.1.22 Fire Protection System for safety-related areas (hardware) 2.1.23 Fuel Handling Building 2.1.24 Fuel Handling Building Ventilation System (exhaust units) 2.1.25 Fuel Handling System 2.1.26 Fuel Transfer Tube 2.1.27 Hydrogen Recombiners, Hydrogen Analyzers, and Supports 1
2.1.28 Instrument Air System (including accumulators, interconnecting J piping and valves) for air-operated valves that perform a safety function 2.1.29 Instrumentation and Control Systems required for safe shutdown (including safety-related instrumentation) 2.1.30 Instrumentation for detection of inadequate core-cooling ; 2.1.31 Leakage Detection System (as discussed in UFSAR Section 5.2.7) 2.1.32 Main Steam System (to isolation valve) 2.1.33 Meteorological Data Collection Program (hardware) 2.1.34 Missile Barriers (protecting safety-related equipment) 2.1.35 Nuclear Instrumentation System 2.1.36 Plant Shielding 2.1.37 Process Instrumentation and Controls (those portions required for Class I equipment and systems) 2.1.38 Radiation Monitoring System (those portions required for Class I equipment and systems) 2.1.39 Radioactive Waste Disposal Systems l l 4 4 of 5 SGS-UFSAR Revision 6 February 15, 1987
. . . - ~ . - -- . -
Table 17.2-1 (Cont)
- a. Gas Decay Systems
- b. Compressor ,
l 2.. 40 Reactor Coolant System (including piping, valves, steam generators, pressurizer, safety and relief valves, block valves, piping to pressurizer relief tank, reactor coolant pumps, and supports) 2.1.41 Reactor (including vessel, supports, internals, fuel assemblies, RCC assemblies and drive mechanisms, supporting and positioning members, and in-core instrumentation) 2.1.42 Reactor Protection System I 2.1.43 Residual Heat Removal System 2.1.44 Safety Parameter Display Console (instrument calibration and verification only) 2.1.45 Sampling System (to outermost containment isolation valve) 2.1.46 Service Water Intake Structure 2.1.47 Service Water System (entire system serving the nuclear portion of the plant, as shown in UFSAR Figures 9.2-1A and B) 2.1.48 Shoreline Dike (for protection against excessive wave action) ! 2.1.49 Spent Fuel Pool Cooling System 2.1.50 Steam Generator Blowdown System (to outermost containment isolation valve) 2.1.51 Switchgear Room Ventilation System ' 2.1.52 Valve operators for all valves incorporated in this list 2.2 Items Required by Regulatory Guide 1.29, " Seismic Design , Classifications," Regulatory Position 3. t p l o 1 i I l i 5 of 5 l SGS-UFSAR Revision 9 July 22, 1989 l ; j
QUALITY ASSURANCE / NUCLEAR SAFETY REVIEW
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Director Qua3f Assuranc M1uclear fe Review
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Manager Quality Manage)r 2Gality
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Manager tJuclep afety Manger Corrective Action Assessment As etsment Manager Employee Manage censing & Re" w & Quality services Ccncerns egulation Joper, reek). (Salem)
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Rsporcs .rgy gycyjg 17.z-t h)iT11 ATTAts(GD.
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION OUAllTY ASSURANCE NUCLEAR SAFETY REVIEW UNITS 1 & 2 Opdated FSAR Figure 17.2-1 Revision 15 Sheet 1 of 1
QUALITY, NUCLEAR TRAINING & EMERGENCY F REPAREDNESS CHIEF NUCLEAR OFFICER & PRESIDEliT - NBU D: RECTOR - QUALITY, NUCLEAR TRAINING AND EMERGENCY PREPAREDNESS " i ~? MANAGER QUALITY PROGRAM MANAGER MANAGER ASSESSMENT MANAGER-NRB CORRECTIVE ACTION EMPLOYEE CONCERNS l t TECHNICAL OPERATIONS EMERGENCY TRAINING / SERVICES TRAINING PREPAREDNESS MANAGER MANAGER MANAGER , PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION i QUALITY, NUCLEAR TRAINING I
& EMERGENCY PREPAREDNESS UNITS 1 & 2 Updated FSAR Figure 17.2-1 Revision 15 Sheet 1 of 1 l i
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