ML13316A625
| ML13316A625 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/04/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A623 | List: |
| References | |
| NUDOCS 8406070280 | |
| Download: ML13316A625 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 75 TO.PROVISIONAL OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION
By letter dated September 9, 1983, Southern California Edison Company (SCE) (the licensee) requested an amendment to Provisional Operating License No. DPR-13 for the San Onofre Nuclear Generating Station, Unit No. 1.
This amendment would authorize changes to the Technical Specifications on containment leakage testing. This safety evaluation addresses only the changes relating to Type A testing (Integrated Leak Rate Testing). The remaining aspects of the above proposed change will be handled as a separate licensing action.
A Notice of Consideration of Issuance of Amendment and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on November 22, 1983 (48 FR 52827). A request for hearing and public comments were not received.
2.0 DISCUSSION AND EVALUATION Technical Specification 4.3.1 and its basis establish the requirements for containment leakage testing. The proposed changes relate to the Integrated Leakage Rate Tests, Type A tests and are discussed below.
A. Test Pressure A paragraph has been inserted under TS section 4.3.1.I.A to explicitly note that Type A tests may be conducted at peak pressure (49.4 psig) or at reduced pressure (24.7 psig).
This flexibility was already implied by the existing specifications on Type A testing and is in accordance with Paragraph III.A.2 of 10 CFR Part 50, Appendix J. This proposed
.change thus clarifies the test pressure requirements and is acceptable.
B. Acceptance Criteria Specification 4.3.1.I.B relating to the supplemental test performed to confirm the accuracy of the Type A test has been modified to allow the
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-2 test to be performed either by measuring the air bled from or injected into the containment during the test. Presently the specification refers only to air injected into the containment.
The licensee has referenced ANSI/ANS-56.8-1981 as the source of the methods for calculating the leak rate for the supplemental test. Appendix C to ANSI/ANS-56.8-1981 provides methods for verification of Leakage-test Accuracy (supplemental methods). These methods allow for a mass step change to be measured-either into or out of the containment.
The staff has reviewed the licensee's basis for the proposed change and finds it acceptable.
C. Frequency The specification on frequency of performance of Type A tests including retests has been revised to conform to the stated requirements of Paragraphs III.A.6(a) and (b) and III.D.1(a) and (b) of 10 CFR Part 50, Appendix J.
A set of 3 periodic Type A tests are performed at 40+ 10 month intervals during each 10-year service period. The third test of each set is performed when the plant is shut down for the 10-year plant inservice inspection. The permissible period for Type A testing shall be limited to periods when the plant facility is nonoperational and secured in shutdown condition.
If any periodic Type A test fails to meet the acceptance criteria above, the test schedule applicable to subsequent Type A-tests shall be submitted to the NRC for review and approval.
If two consecutive periodic Type A tests fail to meet the above acceptance criteria, a Type A test is performed at each plant shutdown for refueling or approximately every 18 months, whichever occurs first, until two consecutive Type A tests meet the acceptance criteria, after which time the normal test schedule may be resumed.
Since these provisions are exactly as specified in Appendix J to 10 CFR Part 50 the proposed changes are acceptable.
Based on the above discussion, the staff concludes that the Technical Specifications on Type A, Integrated Leak Rate Testing of containment are in conformance with 10 CFR Part 50, Appendix J.
3.0 ENVIRONMENTAL CONSIDERATION
The staff has determined that.the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, the staff has further concluded that the amendment involves
-3 an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR §51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ACKNOWLEDGEMENT C. Li and E. McKenna contributed to this safety evaluation.
Dated: June 4, 1984
Kenneth June 4, 1984 A copy of our related Safety Evaluation.is also enclosed. This action will appear in the Commission's Monthly Notice publication in the Federal Register.
Sincerely, Original signed by Walter Paulson for Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosures:
- 1. Amendment No. 75 to License No. DPR-13
- 2. Safety Evaluation cc w/enclosures:
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