ML19220A841
| ML19220A841 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/11/1968 |
| From: | Sears J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Racquel Powell US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904250023 | |
| Download: ML19220A841 (15) | |
Text
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Raynend Pcvell: Reacter Prcjects 2 ranch i2
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C22Y C::i:EAL PO4IR & LIOr CCMPATt IR:" rCUJ,Y f.A.Cf A"Gl'!L RZPCE" FL'R CL~2..~'. C22~K f2, DCCC: :10. S-320 In response to your request, the Prelf 91 nary Safety Analycis Report in support of the Jersey Central Power & Light C:=pany's applicatica for a construction pe: ait has been reviewed to:
(a) evaluate the applicant's subnittal regarding ccnduct of operaticas, (b) evaluate the pre-and pcst-critical testing progran and initial leading, and (c) evaluate the adegancy of the quality ccatrcl progran during ecnstractica.
De following eemts are subnitted for your use.
1.
Organization and Respcasib111 ties The applicatics states that the Plant Superint-daat is respcnsible for safe operation of the plant. He reports to the Manager of Generating Stations who in turn reports to the Vice President, Engineering, Genera-tica and Cperations.
The cornal operating shift vill censist of a shift fore =an, a centrol c rocxs operster, a control rocsa cperator (3), and two nuclear plant egaip-nant operators.
The shift fore =an reports to the cperations supervicer.
The operations superviser reports to the plant superintendent.
Accerling to the proposed organizatics chart, the abitt foma and the openticas superviser vill be licensed senier reactor operators.
"ne plant superintendent vill not be a licensed senicr reacter operator.
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He vill be responsible for the safe operatica of both Cyster Creek f1 and f2.
Ik?h the naintenance group and the technical suppo.~. group, vto vill functica ir. the areas of physics, chemistry, engineering _ end health
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physics, vill ser/c bcth rescters. Se 231stenance group vili con-sist of 33 men, and the technicc1 support group vill censist of 18 men. Se number of people of particular skills is act described.
The palificaticus of the people 20 vill fill the pcaiticas acted abov-are cet given. Se applicatica decs act state vtich, if any, of the Oyster Creek !1 cpersting :taff vill be transferred to f2 cr if atsff =e=bers vill be expected to svitch bac.c and forth betveen the two dissimilar resetors.
It is 1s-ossible to evaluate the alegacy of the operating organizatica c the basis of the informatica in the PS)2..
The PSAR presents c 17 general descriptive catorial en this tcpic cf orgsnization and respcasibilities. The same cc=ent can be made abcut all the other 1*e=s in Cecdlet of Cpersticas and Testing. We vil.1 =ake a =cre co:prehensive reviev and evaluatica cf these topic? at the PCI stage when the applicant vill have suh=10.ed the necessary detailed infor. atica. Se informatica on pality assurance in the PSAR ia scre cccrplete, as will be discussed later in this =encrandun, thcugh there are still sc=e gesticas that we believe should be answered nov.
2.
Training The spplicaticn states that the training prog ss starts with a 3-c sanths ecurse in basic theory for all perse :el withcut extenaive nuclear power station experience. No details cf the course, such as nunber of classroca bours for each subject, are Siven.
The appliestion states that all personnel withcut extensive and recent operating and maintenance experience in a nuclear pcver statica vill be sent to Sarten er so:e other reacter facility for approxi=ately six
- ncaths training.
'Io details of this trsining are giv-n.
The application states that the supervisory staff vill particirate in a two-ecath pressurised vater reacter techselecy ecurse, with special refersnee to the Oyster Crt.ek f2 nuclear plant dasign, at 3 & W.
The appliestica does not state vto is included en the supertiscry staff tu ing this ccurse.
The entire statico staff vill te essembled at the si e ene year before fael 1cating for en-ths-jeb treining &^r a 3 & W training superviser.
Jointly with the 3 & W stcrtup staff, the trainees vill prepare testing procedures End nor al n=d emergency CNrating preced:.:res. 'Ibe traineas vill perfors pre-criticcl tectiL6 under guidance cf 3 & W engineers.
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R Powl1 De applicatica dces net nentien en Instr;nentatica Engineer.
If Oyster Creek p2 is to have such an individual en staff, vill be have vencur ent naintenance respcasibilities on Cyste-Creek pl while ha is et smting to fellev *te checi-cut of the p2 pisnt? The two reac-tors are different types and have entirely different instmnent and cont.M systens.
3 Replacenent Persennel Se details of the training progras fer replacuent perscnnel are not given other than to state that the training vill cover the sano general naterial and follow the f W a-e"tal progran for the original staff.
4.
bergency Plan The application states that there vill be an e:aergency plan.
In the trans=ittal letter, dated October 30, 1968, acea:panying Anendment p+,
the applicant states that an e= ergs 2 cy plan for Oyster Creek f2 vill be included in a later anendment.
5 Procedures The application states that there vill be vritten precedures for nornal and emergency operating conditicas. There vill also be written e=er-gency procedures for copin6 with off-site releases of radicactivity.
6.
Records The application states that records vill be kept of desig:1, construc-tien, operation and maintenance, and that operations records will be reviewed daily. So section is nade of a health physics log, radicactive vaste release pernit systen, records of releases, perscnnel exposure records er che=istry 1c6s and records.
7 Ahinistrative Centrol The application states that all operations, =aintenance, testa and ew.rgencies are handled in accordance with writtan, approved procedures.
Audit of day-to-day operations vill be perforned by the Technical Sup-port Crcup and the Plant Operations Retiev C:nmittee.
A Plant Operations Reviev Cc=nittee vill ecasist of senior plant per-am al and two h*s fren the General Office Reviev 3 card. Neither emcri f I
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reqaire=ents for a quor.:1 cor freqaency of neetings for either cc= nit-tee are sectioned in the applicatica. Se Plant Cocnittee vill suhnit its recc nendatiens to the Generni Cffice Reviev 3 card and all sinutes of =cetings go to the chair =an of the General Office Reviev Scari.
Se Ceneral Office Beviev Board vill review ite.a refered to it by the Plent Cb==1ttee.
In ad.11 tion, it vill select, items for its own study.
It vill also periedically audit operaticas. Details of the Office Bcard's charter are not given - nunt:er of people, gaalificaticas of sane, fregaency of meetings, frequercv of audit, nethod of audit, to when does the Board report!
De application states that the Plant &perintendent repcrts to the Manager of Generating Stations who in turn reports to the Vice President of Engineering, but the application in to place describes the nachaniss by which the Manager and Vice President are hept inforned of what is going on in the plant.
8.
Plant Testing De application stater, that the JCP&L Project Manager is responsible for coordinating all catters pertaining to design and construction. The JCPSL Superintendent of Product,on has responsibility for training and pre-operational testing. We applicatica does not nestica vbether or not the Superintendent of Production has had any previous nuclear experience.
Frcn previous review of Cyster Creek fl, we suspect thaA be does not.
Section 13 of the PPR cc Initial Tests and operatice states that a eccsprehensive field testing progran vill be carried cut, that the core vill be leaded and that testa vill be =ade after initial criticality.
The section includes a list of 28 syste=s, and a check nart to indicate which of thosrt systema vill be subject to hydro, fancti.;nal, electrical and operstient.1 tests. There is also a list of ten post-critical tests.
Section 13 is inadequate for an evaluatica of the ec=petence of the licensee's staff to load and oper +.e he plant safely.
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In suemry, we have reviewed Sections 12, Nnct of Operations, and 13, Initial Tests and Operation, of the PSAR and the infor=atica therein is in-adequate for evaluatica. An outline is presented in Attachment A of the minh, infor=atien which should be transsitted to OSB in a PSAR. Attach-ment B is a series of qaestions you may wish to consider aaking the applicant to ansver in writing.
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C;al; v In Sedien 1.6 cf the PS 3, the cpplicant has identified the crgani:cticn:
end their reapcasibilitics in this project.
Jersey Cent-al Pewr & Light (JC C) 1: the c.-.cr.
Eurns & 3ce (3 & R) is the architec -encincer.
Pichard & L:ve (P & L) is desig: reviev specialist.
Burns & Rce (3 & R) is the ccastruction nanager.
Sabecek & V11ccx (3 & V) vill furnich and deliver the nuclea-stees supply cysten.
ME Assceintes (M?R) vill perfern gslity assurence func*icn.
Appendix 13 descrites the Quality Assurance pregran in general. Appendix S describes the specific pelity assurance progra:s for ccatsinnent.
In Supple-42, the applicant addressed the fc11cvin6 topics in answr to specific ment gestians by ORL:
30 Materials of constractica - containnent 4.0 Ccnstruction codes 4.6 Splicing of rebar 4.8 4:m11ty of installed liner 4.11 Proc resent and installation of prestressing naterial 4.13 Testing of anchcrage 6.o General quality centrcl progran 9 12 Procure =ent and installation of reacter protectica system Appendix 13 is antitled " Quality Assurance Progran" and includes sectiona en scope and general approach and i=nle=entation by contracters and scenta.
Sin appeMM has the statenent, "The JCPE gality assurance prog en starts at the initial desi p phase...."
Sectica 1.o has identified Pickard, Lcvc
& Associates as W. clear C=nsultants to serve as desip reviev specialists, but nowhere in the application is it described exsetly hev nnch desip reviev vill be dons by P & L.
Since no other centrseter has been identified as design reviewer, if P & L does not do it, evidently no independent desip reviev vill be made.
De JCP&L ?roject Manager is respcusible for gality centrol. He vill be assistad by MPR Associates in monitcring the perfc :ance of all centzacters.
Specifications for furnishing and installing this facility vill be written by 3 h V and 3 & R.
As JCP&L's niin ecatreeters, they are respencible for
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seeing tb.t these necessa:y gaality ecutrol previsiens are included in all the specificaticus they prepare. The applicatien states that all specifica-tions vill be revieved by MPR and/or JC?SL.to assure that the necessary 1:e a;Q cr quall,y ccatrol provisicca are incorpcratec in :nese docunenta.
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lanrcare of this sentence is of eencern.
It is not clear exactly how nach reviev cf specifiestiens vill be d ce by M?R and hev nuch by JC?iL.
Ansv-r 8.1 cf Suppla aat <2 states that the Raclear ?cver Activities Orcup
(.T' AG) of Genersl Pablic IJt111 ties Corperntien has encloyed a quality ass =-
I ance and centrol specialis* vho is respccsible for nenitoring the quality assurance and centrcl progren established for Jersey Crntral. Section 3 4 of Appendix 13 states that JC?iL vill statica a fall-tine Resident Q ality Centrcl Representative at the constructica site.
It is not clear if these are ene and the sane persen, nor is it clear whether this is a new hire to the N?AG of JC?iL cr if it is sinply aucther engineer vesring two hats, nor is it clear d en the resident will arrive at the site. You say vish to ash for clarifiestica cf +2ese points.
S L V and 3 & R are respcasible for insuring that =anufseturers of ecnocnents purchased by 'len for this project adhere to the quality centrol provisions of the purchase specificaticns. yor items nanufactured by S & W divisicas other +2an the B & W Xaclear Power Generation D:partnent, the B & V &aclear bever Generation Department vill saintain a separate quality assurance grcup cich vill audit the quality centrol pro 5ran within 3 & W.
C e application statas that bc n B & W and B & R have hecte office Qaality Assurance Super-vircrs with C,uality Assurance Groups reporting to them. De application does not state helt large these groups are. Menbers of these groupo vill perfors surveillance on manufacturers' and constructor's prograns to ensure that quality requirenents are being net.
Both 3 & W and 3 & R vill maintain a etrplete quality control history file including results of audits. De ap-plication does not state vbere, during ccastraction, these files vill be located, nor when they vill be turned over +A JC?&L.
In yigare 8.2-1, the applicant has farnished an organization chart shoving respcnsibility channels for quality centrol. Accceding to the chart, 3 & W vill not farnish on-site quality centrol supervision. As construction sans-ger, that is the responsibility of 3 & R.
B & R vill establish a part of its Q ality Assurancs Group at the ccnstraction site to perforn surreillance on subcontractors. According to the chart, the quality ccatrol field inspec-tors are different people from those with responsibility for get+* ; '2-pro-jects ecnstructed. Q2esticus Wieh the chsn-t does not ansver are qualifica-tions of the people doing the quality centrol verk, hov =any quality centrol people are involved and when they vill arrive at the site. S e application states, "'fhe scheduling of the surveillance effert by the 3 & R QA Group is coordinated with their Resident Constructica Manager." S is is a sinple, inocucus statet which say be interpreted to acan that 3 & R vill statica cae QC nas ea-site voo vill call for belp free his nais office CA Grcup vhen and if he deens necessary. Du say wish to ask for clarificatics of these points.
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R. ? cecil The applicatica does not state hov =uch of constru: tion vill be done directly by 3 & R and vtat vil.1 be subccatracted. The applicatica does state tnat the 3 & B on-site Q ality Assurance Group vill include r= independent tcat labcratory with iisciplines in electrical, instramentation and contrcl, It is act clear, if 3 & P sacranical, nelling, structural, concrete, etc.
does its evn concrete vors, whether this 3 & R Icb vill do testing or vt:ther an independent agency vill be e= ployed. Since there is a vell-documented history of incespetence on the part of engineering testing laboratoriec in the New Yort area, you may vish to inquire vbat services vill be perferred by vhat laborstories and vnat are the Taalifications of these laborateries.
The application states that MPR vill perfern, ca a spct-check monitcring basis:
(a) specification docu ent reviev to see that adequate quality cen-trol requiresents are included, (b) periodic audit at site and unu*acturers' plants, (c) witness, on spot-check basis, various tests, (e) evaluate, on request, proposed vaivera to specifications.
Se phrases, " spot-check" and"on regaest,' are of ecacern. The applicatica does not uke clear just hev extensive vill be MPR's involve =ent in the pro-
"- is a We suggest that elsrification of this point is regaired.
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basic tenet of good project ranagement that every propcsed change go throu6h at least the same review procedure as the origins 1 specifications. You r.ay vish to inquire vbo determines, and on v'3at basia, whether a regaest should be made to MIR to evaluate a proposed change.
In Supplement f2, question 4.11 related to factory gaality control on pre-stressing ec=ponenta; and questien 912 related to quality ecstrol procedures for ec=penents of the reactor protective system (fabrication, shipment, stcrage, field instmM ation, system and ccmponent eneckcut, and records).
The prestressing syste= vill be furnished by 3 & R.
D e reactor protective
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The ansvers to the two questions are This lenda one to believe that either the applicant or one of identical.
his contractors has authored a quality ccatrol procedures =anual.
Ycu =ay wish to suggest to the applicant that, while he may hesitate to tranc=1t such a dorament through official channels, study of the d.ccu=ent by I:RI.-CC3 vould give us a better eppreciatica of the extent of bla gaality assursace pregram.
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