ML19317G557
| ML19317G557 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, Crystal River, Rancho Seco  |
| Issue date: | 07/03/1972 |
| From: | Knuth D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003191129 | |
| Download: ML19317G557 (3) | |
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Richard C. DeYoung, Assista.t Director for P'.."l'c TECiCIICAL ASSIST.t:02 R2QUZOT 2CCS EVALUATION, D.iTD MAY 8,1972 In your =emorandum dated May 8, 1972 you requested our review of the ECCS acetions for the Operating Licensa Safety Evaluation for the Crystal River Unit' 3, Arkansas liuclear i Unit 1, and the 3ancho Seco Urtit 1 facilities. The reactors for all thraa of these fneilities have internal vent valves.
Consequently, the performnce of these systeus will be sinilar to Oconee Unit 1 which complied with the requirenents of the Interi PcJicy Statemnt.
Durin:; the courac of the ECCS Rulo !frding Hearing a proolen with the iM*d ECC arran;;cnent was idantified. In smrery, tha problem relates to
- m accident which is assumed to be caused by a break in the accur,hter lin ". : penetratu th2 reen:.ar v:as: 1.
h;.e of :.he fluid f rcn.-
ather acc::::12:ar m -c 11 m ba -assr.ed to be lost fer such aa neciden:
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Ch rrlas hrta, durina cron s erx in: tion, indicated that.m ir. currently analyzing this specific break.
'R recern:md that thia information be requestad frao Er.'J for di threa clants. Ic in nrocable wt this analysis need be dare for one plaat W ierably -
c Mile bland) rd suite!c arruvat provicied en relate t7e results at that analysia ta the re :nning tuo planCJ.
Je are also currently evaluating the conseqn.mes of smil breb for all PMn hsi;:ns.
'n'e have initiated a review of the ewt11 brua's. snalyaes on tirs E G designa in conjunction with our ravin of the Thr; = liile Island 1 applic.tica.
It is spected thct a rodel agracable to us vill be daveloped na a result of that review and eculd be applicable to. these thraa plants. Hovaver, va do not recoastend that the review of. these ~
i plants bo = ado contine;cuc upon completion of our Cencric review which at prasant is also related to the Three Mile Island application.
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4 If tha Technical Specifiestion for the facility allar tho' plant to be operated with:one or more primry coolant pumos:in ~sa idio condition appropriate analysna should be recucated.- The intant-of the analyses
.::ald bc to chev that the plant operating"in this =cd vould not result in consequances of a pestuisted -LOCA~which exceed the criteria set forth in the Interia Policy Statemaat.
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Richard c. DaYoung-
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jut 3 1972 An obvious solution to this aspect of the proble:m would be to precluda operation with ona or r. ore pungs eit of service until such analyses is provided. This approach would allev licensin;; of the plants to preceed without delay.
In sum: nary, the only additional analyses required to permit us to rococumend 1.icensing action. on all three of theco plents is resolution of the problem identified in the 2nd paragraph.
4 CHrinal s!g.ad by canaid F. Knee Nnald i'. rnuth, J.csistaat Piractor for Reactor Saf aty Directorate of Licensing
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