ML20062N476
| ML20062N476 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000470 |
| Issue date: | 09/17/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC COMMISSION (OCM) |
| Shared Package | |
| ML093450149 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8203010150 | |
| Download: ML20062N476 (5) | |
Text
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l ADVISORY COMMI 3 6 c.c ON REACTOR SAFEGUdRCS
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NUCLEAR REGULATORY CoMM!r3 ION.
WASHINcTcN, D. c. 23555 September 17, 1975 4
H'onorable Wilihun A. Anders cairran U. S.10 clear Pagulat=ry C~--d' eion W== W ton, D. C. 20555
Dear Mr. Anders:
I subject: Clam.M E:ImmrII Sr2TARD SAFETZ IlmLEIS REPCRr - N-80..__
At its 185th Meeting, Septeder 11-13, 1975, the Advisory Cctr.ittee en
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Beactor Safeguards % eted its review of the Implicatica of Cmtion r.
1 Engineering, Inc. for a. Preliminary Dasign Approval (FDA) for its Standard M
Beference Syste-80, safety Analysis Report CIS92-80. 9
-1 ittee meetings were held with representatives of the Applicant, and che Euclear Pagulatory
- Meeica- (NRC) Staff in Windsor, Ccnnecticut, on february 28 and l' arch 1, 1975, and in Washingten, D. C., on May 23 and July 25, 15-75. te full
. Comittee met with representatives of the NEC Staff and the Applicant at its IS4th Meeting August 14-16, 1975. te Ccmittee also had the benefit of the rh - nts listad belo w
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Be Reference' System-80 design censists of' the nuclear staan supyly system (NSSS) with a rated core power of.3800 E(t), the NSSS control system, reactor prottation' system; engineered safety features actuation system, ch:rlical-ard - --
volume centrol syste, shutdoun cooling system, safety injectica system and fuel handling syste. Cci ustion Engineering will provide, at the optien of the user, certain other safety.-related systems wnich are.outside the secpe
-of tha Reference System-80 design. Dese non-stardard systems vill.be dealt...
with in the user,'s Safety Analysis Reports.
Se Ihference System-80 has been designed for applicatien to an envelope of plant sites which encocpasses all sites approved to date for C Lasticin Engineering MSSS. CZ E E-80 provides seismic resp:nse socctra for all 1:najor compencats, cnd equipment and piping systes, and other informatica required to ensure that the balance of plant is designed to protect the
, Reference System-80 from all site-related hazards. Applicaticn of the Reference System-80 design will require an evaluatien of each site to confirm its ac=ept& ility within the N.-80 envelope. Ebr c:ultiple reactor units at a single st:tien, CESS.E-80 requires that each i=;crtant safety-related item of the Reference Syst:=n-80 design be provided for each reactor unit.
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e 8203010150 810804 PDR FOIA MADDEN 80-555 PDR
1 Benorable Winiam A. Anders September 17, 1975
-CNSSAR-80-* li provide safety-related interface require nents-infor: nation -
essential to: the.dasign of the balance of plant censistent with the assu:::ptions:-
.2 used by Ccatustion E:.gineering in its: accident dtalyses. Since the utMity--ci.
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applicant-is resu:nsible for instituting the quality assurance pregrars-
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n=e===ry-to assure that au safety-related design. requirements have been- - -. r
. met, the Cc::=ittee-win review these matters in more detail with the uM1 by,.:.
applicants en a case-by-case basis. te Cc::=ittee re_mrds that, during.
the design, procurement, constructien, and startup,. ti:nely aad appropriate interdisciplinary system analyses te carried out te assure cc plate functiere -
compatibility across each intarface for an entire spectru:n of anticipated operations and postulated design basis accident corditiens.
2e URC Staff 4.'as identified several outstanding-issues which will require-resolutien before the issuance of the FL\\. te Cen:nittee recc=:n.-ds that
- these matters be resolvea in a :anner satisfactory to t5 e Staff. te Cem - - - - -
mittee wishes to-be kept infocned en the resolution of:the fonowing issuest
- 1. Se emergency cor.e cooling systati evaluation.
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Se analysis of the effects of anticipated transients
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without scram.
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Generic review of the effects of failures.of reactor. pt=p
--lubrication oil and ccmper-ant cooling water supply systecs.-
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2e ::est recent ACES reports en nucIear scuar statiens utilizing Cc::dustion Engineering NSSS are the Cecember 12, 1974 report on the application to constru--
the 2570 g(t). St. Txcie Plant, Crit No. 2 and the June 10, 1975 report on the applicatierrto cperate the-2570 Ctt)1 St.-Lucie Plant Unit "or 1.
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Conmittee report on the 3390.W(t). San Cnofre Nuclear Pcwer Generating Static:L thits Nos. 2 and 3, selected by the Staff for reactor system design w rarisen j
with the Reference System-80 desien, wes is.ued July 21, 1972. Ganeric matters which include pessible m overscoed during a loss of coolant accident, transit-
.._ associated.with. inadvertent operatica. of the. e:nergency core. cooling. systcm.. _.
or ch<=N1 and volt:::n centrol system. charging pu:nps, and analyscs of pestulatet rupturcs of the steam generater feed line, should be dealt with appropriately by the Staff. With regard to the rupture accident, the Cen=ittee rv ~.u.T.s that the Staff perform an independent check en the calculation of steam generste-blowdown force effects. It is expec*.cd that these items will be resolved in a manner satisfactory to the NRC Staff foHowing the FM and price to the Final D: sign Approval (FCA). During the interim period, the Cc=nittee will i
continue to review these itc=n on a case-by-case basis as wil as thrcugn other appecpriate SsWittee and full Cc:anit::ce nuetings.
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llenorable William A. Anders September 17, 1975 W r.cak linear heat generation rate is reduced to 12.1 kw/ft in order to
. Wt the ECCs final acceptance criteria of Appendix K,10 CFP. 50. S e Com-
- t. Lee recognizes that censervative restricticns used in the imC-acpreved. -
J-f-
um -odel and the use of a generalized centalment envelope yielding low. :n:
conreiire ent pressures cay be factors centributirg to the imposed reduction 9 --
in the rec =issible linear heat generatica rates. 2e reduced limit iqunen restrictions on ::cdes for plant coeratien and becomes decendent on inece conitoring systers for verifichtien that li=its are not exceeded..:-
. a to C~enittee recc: mends that for a standard reactor of this size, larger r.af ety :.:rgins, such as obtainable frem higher reflooding rates, shculd..
be d nnstrated. Progra=s underway by Cc=bustien Engineering, Inc.,
i inclu!n analytical and experirental studies aimed at.providing the u-.
tec!mical base for ECCS redel i=provements, as well' as stbdying possible cturn. c involving auganted ECC systec:s. Be C dttee believes that these......
previr.: h constitute a sufficient basis for proceedi. Tat this time and
-r that. ttw-de:enstration of larger safety margins should be part of the first maior revised versien of the Reference Syste=-80 design which, as stated by ochuction E.gineering, Inc., is likely to be submii ted for review in
, about..t-o years.
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to 0-nittee needs to ec=plete its review of the suitability of the new v
R x h Iucl.and nodified.ccre reactivitJ centrols.of the Reference.Systcm..:.
80 d. nion attich are now scheduled for initial proof. testing at Arkansas Nucle.ir che, t: hit No. 2 and at St. T.::cie Plant, Unit No. 2. 2e Con =ittee also nmla to ec=plete its review of the new cere protectica calculator -
synt.e and the computer-based core operating limit supervisory 1.fstem which will to inecrprated into the Reference Systa.-80 design in the event they are nucer nnfully decenstrated at Arkansas Nuclear Cne, Unit tio. 2.
Se Comit.t.m needs to tx! assured of the dependability of in-ccre neutren flux.
ccnnnrn..for. control of reactors cprating.at.lcw ccre p=.vc peaking, facters For t hi:: pirpore the Co.mittec recc=mands that the Staff and the Applicant cont.in:: to gathat pertinent infor=stion frc:. cperating CE re:cters.
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Mn n..it t*>c will continue its review of these matters as appropriate i
doen., nt.ition is submitted and the improvements sought can be evaluated.
. un newit tee recognizes the imecetance to safety and i= proved designs of d, v. lopin; cgtational mthcds to provide best esti= ate analyses of ih'A.avt other postulated accidents. Se C ::mittee encourages the Applin..nt. a:sl the NRC Staff to accelerate their efforts to this end.
yc O : mitt.ec wiches to be kept infc=ned.
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fionorable William A. Anders september 17, 1975
'She CES:Wi-80 design should include previsienn which anticipate the
- naintenance, incpectica, and operaticnal needs.of the plant throughcut:....... :.
its service life, including cleaning and decontaminatica of the pri=ary-coolant system, and eventual decc=is-icaing. Inrparticular, the C. ::.ittee believes that the 1:::C Staff and Cedustien Engineering, 'Inc.','should review methods and precedures for renoving - =:1ations of radioactive cent =inatica
. Aer%y mainte. nance and inspnctica progrs=s can be rcre effectively:and-safely carried out.
Se Cca::ittee celieves that Cceustien Enginaering and the ::RC Staff should continne to review the Reference. Syste=.-80 for design cnanges that will further i= prove protecticn against sabotage.
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'2e Cemittee believes that methcds that seek to develop reference syste s
> 4-through standardi:atica and through replicatica need to be ccupied with ongoing progrc=s that will pe=it design changes to. reference ~ syste=s which 1:: grove safety and which, v. ten justified, will ~be ir plemented in
-5' a timely =::n:mr. Use of reference systa=s should lead to rere efficient
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and effective licensing revie:s. Progra== such as CES2R40 will centrii::ute to this process. A transition period will be required in which the C-4 ttee will still give attentica to the ite=s ncted, on a case-cy-case basis.
2e'Ccmittee believes that, subject to the aboin ec:::. ants and successful completien of the EsD progrz=s, the Ccdustica Engineering Peference System-00 design can be 9 r ae fully engineer.uf to serve as a reference syste..
Sincerely yours, MM William Kerr chat.rsan--
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Honorable Willim A. Anders 5-September 17, IF REFERCCES TO E C5 3AR-80 I. M :.
I.'. C2 nstian E:.gi=eering st ndard Safety Analysis Report for System-80 (CESST."
with Ma~*-=nts 1 through 36 L Report to the Mviscrf C_..Jttee on Reacter Safe:;uards frem the Cffice of clear Paactor Ragulation, dated July, 1975 Supple::ent 1 to the Papert to the Mvisory Cc==ittee en Peactor m
Safeguards frem the Offica c.f 1A: clear Paactor Pagulatien, dated August 8, 1975 4.
Intter, dated Pr.rch 24, 1975, Cr ustion bgineering, Inc.; to CRL concerning infoc:ntien en the fuel transfer t: e
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Intter, dated March 10, 1975, C= tstien bgineering, Inc., to CPI
-ming radiciodine spiking effects en accident releases
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Intter, dated Januar/ 15,'1975, C
- tica Engineering Inc., to CRL eme* ming views on Anticipated Transients Without Scram s
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