ML20093M291

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Advises That Response to NRC Request for Addl Info Re Question 3 Concerning Steam Generator Tube Rupture Requires Extensive Computer Analysis & Should Be Available in May 1985
ML20093M291
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 10/12/1984
From: Tramm T
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
9301N, NUDOCS 8410220046
Download: ML20093M291 (1)


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Commonwealth Edison

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/ Chicago Illinois 60690 October 12, 1984 V. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject:

Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Steam Generator Tube Rupture NRC Docket Nos. 50-454/455 and 50-456/457 Reference (a):

April 19, 1984 letter to B. J. Youngblood to D. L. Farrar

Dear Mr. Denton:

This is in response to your request for additional information regarding steam generator tube rupture in reference (a).

Commonwealth Edison will work with Westinghouse and the NRC Staff to develop responses for our Byron and Braidwood Stations consistent with the utility owners group work.

Our present schedule calls for a response to all questions by December 31, 1984, except for question 3.

The response to question 3, requires extensive computer analysis and should be available in May, 1985.

In the interim, we believe Byron Unit 1 can be operated r

safely because 1) Byron Station has approved emergency operating procedures in place to deal with this accident and 2) all equipment that is'necessary to mitigate a steam generator tube rupture is L

qualified to perform its safety function for this accident.

Please address further questions regarding this matter to this. office, i

Very truly yours, ft$

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T. R. Tramm Nuclear Licensing Administrator 1m 8410220046 841012 PDR ADOCK 05000454 P

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