ML20141L933

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Responds to Re ATWS Status Rept on 751209. Schedule for Submitting Detailed Mod Design Cannot Be Provided Until 761117
ML20141L933
Person / Time
Site: Oyster Creek
Issue date: 10/04/1976
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To: Stello V
Office of Nuclear Reactor Regulation
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 EATJM-66, NUDOCS 9203270207
Download: ML20141L933 (1)


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Mr. Victor Stello, Jr., Director OCT8 19 Division of Operating Reactors

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Office of Nuclear Reactor Regulation f

United States Nuclear Regulatory Commission 4

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Dear Mr. Stcllo:

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Subject:

Oyster Creek Nuclear Cencrating Station tecket No. 50 219 Anticipated Transient Without Scram-Recirculation Pump Trip i

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Your 1ctter dated September 1,1976, stated that you have found that a rceirculation pump trip similar in design to the one described in your Anticipated Transient Without Scram (ATWS) status report dated December 9, 1975, and the General Electric Report NLDO-20626 will provide substantial additional protection for the mitigation of an AWS cvent.

You further requested that we inform you of our comnitment to modify our plant accord-ingly and our schedule for doing so.

g We do plan to modify the Oyster Creek Nuclear Generating Station to incorporate the recirculation pump trip, unless additional information is l

supplied by the industry during the finali:ation of your review that demonstrates l

that this modification will not significantly li* nit the consequences of an NNS event for the Oyster Creek Station.- At present we plan to implement the modi-fication during the spring refueling outage of 1978.

We cannot, at this time, provide our schedule for submittin't the detailed modification design to you for appruval, nor can we now provide our procurement schedule.

We will provide these hy November 17, 1976.

Very truly yours, O /4 71 n

'O Ivan R. Fluf dk.,'r.

Vice President pk 9203270207 910007 PDR FOIA DEKOK91-282 PDP

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NUCLEAR REGULATORY COMMISSION 3 0.y%

l ADVISORY COMMITTEE ON REACTOR SAFEGUARDS f

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..g, Dr. G. Paulson Assistant Comissioner for Science f

Department of Environmental Protection

-State of New Jersey i

Trenton, NJ 08625 1

Dear Dr. Paulson The Advisory Comittee on Reactor Safeguards has considered your request for conmnts on the prelimina y analysis by Mr. Peter Davis of the prob-ability of a catastrophic accident during the remaining lifetime of the Oyster Creek plant.

It is unfortunately not possible for the ACRS to provide a detailed review of this sttdy. We note, however, that Mr. Davis stggests that the incorporation of the automatic recirculation punp trip would lead to a substantial reduction in the probability of a core melt folicwing a failure to scram on an anticipated transient.

The ACRS has been following closely the continuing evaluation of the matter of anticipated transients without cerm (NNS) since the question was raised by this Comittee several years ago. The recirculation punp trip feature is included in most, if not all, of the newer boiling water reactors in operation or under construction, and in March 1976 the ACRS recommended that this-featurm ue implemented praptly on all operating BWR's unless analyses have shown that such a trip is not required to mitigate the consequences of NNS.

We urderstand that the Jersey Central Power and Light Conpany has made a comitment to install such a punp trip unless they are able-to provide a convincing demnstration Mt; r.Lgst a (see attachments).

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S cerely yours, N

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kM Dade W. Moeller

['f,g Chairman F

Y[g Attachments:

1) ACRSlettertoL.V.Gossk.N March 12, 1976

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2) Jersey Central Power & Light e<5 1, %h Canpany letter October 4,1976 9

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