ML14135A262
| ML14135A262 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/23/1982 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-03-07.D, TASK-3-7.D, TASK-RR LSO5-82-04-069, LSO5-82-4-69, NUDOCS 8204280269 | |
| Download: ML14135A262 (4) | |
Text
April 23, 1982 Docket No. 50-206 LS05 04-069 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
DearmMr. Dietch:
SUBJECT:
SEP TOPIC III-7.D, CONTAINMENT STRUCTURAL INTEGRITY TEST SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 Enclosed is our final evaluation of SEP Topic 111-7.0. This evaluation compares your facility as described in the Safety Analysis Report you supplied on June 9, 1981 and other information on Docket No. 50-206 with criteria used by the staff for licensing new facilities. The eval uation concludes that the structural integrity test performed compares favorably with current criteria.
The evaluation will be a basic input to the integrated assessment of your facility and may be changed.iin the future if your facility design is changed or if NRC criteria relating to this topic is modified before the integrated assessment is completed.
Sincerely, Walter A. Paulson, Project Manager
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Operating Reactors Branch No. 5 Division of Licensing bs s(*c 1 )
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Mr. R. Dietch
.San Onofre Unit 1 Docket No. 50-206 Revised 3/30/82 cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire
.Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David.R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U. S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 U. S. Environmental Protection Agency Region IX Office ATTN:
Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596
ENCLOSURE SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 SAFETY EVALUATION REPORT SEP TOPIC III-
7.0 ASSESSMENT
OF CONTAINMENT STRUCTURAL INTEGRITY TEST
1.0 INTRODUCTION
The objective of this evaluation was to compare the containment structural integrity test procedure and results with current criteria and thus provide assurance that the containment will continue to perform its intended safety function.
2.0 REVIEW CRITERIA
References:
(A) Federal Regulation 10 CFR 50, Appendix A.
(B) NRC Standard Review Plan, Section 3.8.2.
(C) A.S.M.E. Boiler and Pressure Vessel Code Section III, Division 1,
. Article NE-6000.
(D) Letter from Southern California Edison to NRC dated June 9, 1981 which
- forwarded Draft Topic Assessment on SEP Topic III-7.D.
References A, B, and C outline current criteria for conducting and evaluating containment structural integrity tests. Reference D describes the containment structural integrity test conducted at the San Onofre plant.
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3.0 RELATED TOPICS AND INTERFACES SEP Topic VI-3, "Containment Pressure and Heat Removal Capability" wi.11 provide an assessment of the adequacy of the original design pressure for the containment. The evaluation.described herein is based on the design and test pressure loadings as presented in Reference D.
4.0 REVIEW GUIDELINES The test procedure and results were compared, as outlined in Reference D, with current criteria for such tests in order to determine if any significant deviations existed.
5.0 EVALUATION The San Onofre containment is a steel sphere approximately 140 feet in diameter and 1 inch thick.
The containment was subjected, directly after construction, to a pneumatic test pressure of 53.4 psig which is 1.15 times the orignal design pressure of 46.4 psig. This is more conservative in comparison to current criteria which requires, by Reference C, a test pressure of 1.1 times the design pressure. The licensee indicated in Reference D that the latest peak post-accident pressure postulated for this containment is 48.2 psig. Since 1.1 x 48.2 = 53.02 < 53.4, the original structural integrity test pressure would meet current requirements for.such tests.
6.0 CONCLUSION
Based on the review of the original structural integrity tests in comparison to current test criteria it is considered that the test was satisfactory and thus demonstrated that the structure is capable of performing its intended safety function.
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