ML13310B007
| ML13310B007 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/11/1983 |
| From: | Krieger R Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13310B008 | List: |
| References | |
| TASK-03-05.A, TASK-3-5.A, TASK-RR NUDOCS 8310130127 | |
| Download: ML13310B007 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 October 11, 1983 Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 SEP Topic III-5.A, Effects of Pipe Break on Structures, Systems and Components Inside Containment San Onofre Nuclear Generating Station Unit 1 SEP Topic III-5.A, Effects of Pipe Break Inside Containment, requires that participating utilities compare their facilities with current criteria for protection against pipe breaks inside containment.
The results of the analysis for inside containment pipe break effects are described in the enclosed report. This report, similar to that submitted for the outside containment analysis, uses a "screening" approach to eliminate many interactions using conservative techniques.
The result of this approach is the elimination of many interactions from more detailed analysis.
As with the outside containment work, this report includes the results of evaluations of mechanical interactions. An evaluation of electrical components for pipe whip and/or jet impingement has not been included in this report.
This evaluation will be conducted in conjunction with implementation of modifications required by 10 CFR, Appendix R.
Integration of these two projects will more efficiently utilize SCE's resources as both projects may require rerouting or protection of certain electrical components.
For those interactions identified as "unresolved" in the enclosed report, the next phase of analysis will further evaluate the interactions 83i(0130127 8331011 PDR ADOCK 05000206 P
Mr. D.
October 11, 1983 using more refined analytical techniques and/or plant specific criteria where necessary.
The need to conduct further analysis and the schedule will be determined during the Integrated Assessment.
If you have any questions on this report, please let me know.
Very truly yours, R. W. Krieger Supervising Engineer San Onofre Unit 1 Licensing GEH:8834 Enclosure bcc:
(See attached sheet)