ML13330A316
| ML13330A316 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/29/1981 |
| From: | Moody W Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105050501 | |
| Download: ML13330A316 (2) | |
Text
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Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 W. C. MOODY TELEPHONES MANAGER, NUCLEAR LICENSING April 29, 1981 (213) 572-1817 (2 13) 5 72 -180 6 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 t
1 Gentlemen:
Subject:
Docket No. 50-206 Steam Generator Repair Program San Onofre Nuclear Generating Station Unit 1 By letter dated March 5, 1981, we submitted the report entitled, "Technical Evaluation Report for a Hybrid Joint, San Onofre Nuclear Generating Station, Unit 1, March, 1981."
The information contained in the report relates to the use of leak limiting sleeves, including the design criteria for this type of sleeve, the development and qualification tests to evaluate this type of sleeve and the field tests to confirm the characteristics of this type of sleeve in the steam generator environment.
This letter confirms telephone discussions with members of the Regulatory Staff on April 24 and 27, 1981 concerning the leakage limit from the primary to the secondary system contained in the aforementioned report.
Specifically,
- 1. the leakage limit was conservatively calculated as the maximum allowed to maintain the radiological consequences to less than the limits of 10 CFR 100 during main steam line failures outside containment,
- 2.
the Regulatory Staff considers a plant adequately designed against main steam line failures outside containment if the radiological consequences are a small fraction (i.e., approximately ten percent) of the 10 CFR 100 exposure guidelines, and
- 3. the development, qualification and field test information indicates that the leak limiting sleeves will limit the primary to secondary leakage during main steam line failures outside containment to less than the maximum allowed by the Technical Specifications (i.e.,
approximately one gallon per minute); therefore, this leakage should be used by the Regulatory Staff to determine whether the repaired steam generators are adequately designed against a main steam line failure outside containment.
0 Sat
D.
April 29, 1981 If you have any questions or desire further information concerning this matter, please contact me.
Very truly yours,