ML20210E544
| ML20210E544 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/30/1982 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20209C222 | List: |
| References | |
| FOIA-86-151 CLI-81-30, NUDOCS 8609250040 | |
| Download: ML20210E544 (2) | |
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P!t CLEX1 REG JLATCRY COMMISSION d M' * / /
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wmput ents K. cAupcmNis sesse O L 3 t 1982 t!!M;1f!ANDLM l'CR:
D. G. Eiienhut, Director, Division of Licensing, FR'l TOM:
- a. M. Engelken, liegional Administratcr, Region v
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DIABLO CANYON DEf>IG.i VERIFICATION PROGRAM - SCOPE
)F PMASE I he have revie red.your metiurandu.1 of July 26, 1982, regarding possible inodificetinr.s t.o tie Ccnutission's Su. pension Order Nt,. CLI-81-30 i: defined as Pilase I of the v!rificatecn prog am).
Our convaents on the currect sta tu; of th: Diablo Can;<cn Design Verification activities and cua r3cen.iend.it t ins are provided talow.
1.ince ".be seiimic des 1gn cori: erns ware originall) identified in September '.981, techMcal assessmener of design idagt.acy hase been naic oy s.2veral organizacions inclutng the Independent Design ie-ificat.c n Program groups, the licensee's Technical Program ergnination, Erookhnen National Lotoritory, and the.1RC staff.
In'or ktion from thest asiessments has been received through tie var tout, technical reports is!,t.ed by each organization.
In troi.d te 17.s, t <o raurring areas of cancern have been identified by the awessrmnts mde to date.
These are:
(1) uncertainties in the de"elag,m?nt and 3pplicat'cn of scismic response spectr.i. and (2) unceratinf.ies in the consisten:y between t:ie designer't, assumptions and.weling techniques und the actual as-built condition of 'he plant.
Ir certain instance; the findings to date havs resulted in p'1ysir.al rodificatiJus to t*1e plant.
The magnitude of these changes is vary sr.'all (when comptred to the entire J.lant) ar.d it appaars (Sased on aveilable informa ion) thht t.o saf ety related system or car..panent would have failed (although strar.ses in excess of code al'ovatics may 5cve teen possibie) had a Hosgri earthqtake occur:ed.
The corrmissior's Crdtr required th.it mviews se perfor: red relating to the seismic Jesigr, ictivitics conducted prior ic June 7973, and sas d rected at those actions.iecessary to as sura safety during fuel Ira.dirg ard lod rower testing.
In refere1ce to the dute of June 1978, it does nct appear that the continued use of this lim: ting date is apf rapriitte 1,ince snrre of the pcor seit.mic design gractices existed beyo,d that date.
In ref 2rence to the identificnio.1 cf those actions nece;sary to assura sa fety durir.g fuel loading and law power testing 11 h clear that s reri sctions must be taken.
These include the following:
8609250040 860916 PDR FOIA HOLMESB6-151
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- 1. G. E 1 t.nhut 3 ktion nust t e tbke:1 to ver'.fy that saismic d.esign s)ectra have 3een properly developed and correctly applied for those structures, systerrs end components wFich assure safety of the plant dt. ring ft.el load o? low power test operations.
Tn acidition, the seisn'c ocequacy must also be assured for those s'.ruct ures, systems, and t.cm?onents which are in the proxiinity ofAcmmt.nica te with these r.afety iteins anti wnese failure would jEopurdi;,0 plant s1fety during fuel loac or low power operations.
b.
Fne th w o et ractunoc, sp tu..m. ai d wuponents described in a.,
aboie, !.pecif k actio1:, riust be tahn to atturo rodoling and c.'ez sn essunption ar e t.uns tstent witn the as-ballt condition of the plant.
Fo* those :.tr actu es, systems, and components described ia a.,
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above, fl1Fingr which have been generated from either tFe Independent Cesigi Ve n fictition &cgrom, the licensee's pe) gram, and the Brockhaven stur'y must be assessad.
Resolution rqusc be complete far those if ndings which.mpact on fuel load and low power 09erscional safety.
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L'pnn satlif actcry conpletion of the above activities, it is reco.. rended that the.icensee be per;iittec to ined fuel and conduct low power l
test ope ations.
I Pr'or to the initiatfen of reactor operation above St. power, it is l
racoulended that the li ensee complete those activities currently
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d ucrited in the Indi peWent Design Ve ification Program Phase II P. c.grarr.t nagement Plan.
In addition, we reiterate our position that consideration bi given to expsading tne s: ope of the Phase II prograni to include e 83Sessfilent of conf truction quality as discussed in my memorands:m cc Mr. Dat. ton of March 29, 1982.
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'de e)uld te pleased to discuss the ab2ve ricorrrendations with you further (c1. tac T. W. Bisnop US 463 3751).
N mg 0C.--
R. H. Engelken Regional Administr3 tor ec:
R. C. DeYoung H. R. Denton R. H. Volirrer E. Case R. Mattson L. Chandler R. Janes
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Crt ws T. Bishon
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