ML13333A379

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Summarizes Actions Taken Prior to NRC 790824 Meeting on Pipe Breaks.Work Undertaken to Identify High Energy Lines Inside Containment & Sys Required for Safe Shutdown.Effects of Postulated Breaks in High Energy Lines Examined
ML13333A379
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 07/09/1979
From: Haynes J
SOUTHERN CALIFORNIA EDISON CO.
To: Ziemann D
Office of Nuclear Reactor Regulation
References
TASK-03-05.A, TASK-07-03, TASK-3-5.A, TASK-7-3, TASK-RR NUDOCS 7907090261
Download: ML13333A379 (1)


Text

Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 Director of Nuclear Reactor Regulation Attention:

D. L. Ziemann, Chief Operating Reactors Branch #2 UN Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Subject:

Systematic Evaluation Program (SEP)

San Onofre Nuclear Generating Station Unit 1 Your letter dated December 7, 1978 indicated that a meeting would be scheduled with us to discuss SEP topic III-5.A, "Effects of Pipe Break on Structures, Systems and Components Inside Containment", and further noted that you expected that the program to resolve this topic might require substantial effort on our part. Our letter of January 24, 1979 confirmed our availability to meet with you at your convenience.

In subsequent discussions with members of your Staff, it was indicated that the Staff would prefer to meet with us after we have had the opportunity to take a preliminary look at this topic and identify potential problem areas.

As a result of these discussions we have under taken work to identify the high energy lines inside containment, identify7 the systems required for safe shutdown, and examine the effects of postulated breaks in the high energy lines. We anticipate this work to be complete to the point that we would be able to meet with members of your Staff any time after August 24, 1979.

Also, we would anticipate discussing at that meeting the additional analyses that will be required to complete the evaluation of this topic.

If we can provide any additional information at this time, please let me know.

Very truly yours, J. G. Hayn/s Chief of Nuclear Engineering 7907 09Q~