ML13316A794
| ML13316A794 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/08/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A793 | List: |
| References | |
| DPR-13-A-087 NUDOCS 8502120156 | |
| Download: ML13316A794 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 87 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated September 9, 1983, as modified by letter dated April 12, 1984 and supplemented on November 14, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
PpDR 0
206
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No. DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR T NUCAR REGUL Y
MMISSION John
. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 8, 1985
ATTACHMENT TO LICENSE AMENDMENT NO. 87 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases by removing the following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
REMOVE INSERT 47a 48 48 49 49 50 50 51 51
-48
'C. Frequency 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 the 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.
II. Containment Penetration Leakage Rate Tests (Type B)
A. Test Pressure Type B tests are conducted at a test pressure at or above 49.4 psig.
In addition, the personnel airlocks are tested every six months at or above 49.4 psig. A lower pressure test, approximately 10 psig, will be used to test the personnel airlocks within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following an opening, except when the airlock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B. Acceptance Criteria The combined leakage rate of all penetrations subject to Type B tests and all containment isolation valves subject to Type C tests is less than 0.072 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig.
C. Test Schedule Type B tests, except for airlocks, are performed during every reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years.
Airlock volumes between the doors are tested:
(1) at least every six months and (2) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each opening, except when the airlock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Amendment No. 24, 5W, 87
49 1II.
Containment Isolation Valve Leakage Rate Tests (Type C)
A. Test Pressure:
Type C tests are conducted in accordance with the criteria specified in Appendix J of 10 CFR 50.
These Type C tests are conducted at a test pressure at or above 49.4 psig.
B. Acceptance Criteria (Maximum acceptable value)
The combined leakage rate of all penetrations subject to Type B tests and all containment isolation valves subject to Type C tests is less than.072 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig.
C. Test Schedule Type C tests are performed during each reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years.
Seal tests conducted on active containment ventilation isolation valves shall be performed every three months.
Seal tests conducted on passive containment ventilation isolation valves shall be performed every six months.
IV. Recirculation System A. Test Pressure Leak tests shall be performed on portions of the Safety Injection System used for recirculation at a pressure equal to or greater than the operating pressure under accident conditions. The test fluid shall be water.
B. Acceptance Criteria Visual inspection for leakage shall be made and if leakage can be detected, measurements of such leakage shall be made. The maximum effective leakage shall be maintained in accordance with Section 3.3.1.A(4) of Appendix A Technical Specifications.
C. Test Schedule Visual inspections of the recirculation loop outside containment (including the Containment Spray System) shall be made at intervals not to exceed the normal plant refueling interval. In addition, pumps and valves of the recirculation loop outside containment which are used during normal operation, shall be visually inspected for leakage at intervals not to exceed once every six months.
Amendment No. 34, 87
50 V. 'Test Result Report The results of Type A, B, and C leakage rate tests are submitted to the NRC in a summary technical report approximately three months after the conduct of the Type A tests. This report contains an analysis and interpretation of the Type A test results and a summary of periodic Type B and C tests performed since the last Type A test. Leakage rate test results from Type A tests that fail to meet the acceptance criteria specified in Section I.B above are reported in a separate attached summary report that includes an analysis of the test data, an instrumen tation error analysis, and the structural conditions of the containment or components, if any, which contributed to failure in meeting the acceptance criteria. Results and analysis of the supplemental verification test used to demonstrate the validity of the Type A test measurements are included.
VI. Containment Modification Any major modification or replacement of a component that is part of the containment boundary is followed by Type A, B, or C tests as applicable.
The results of such tests are included in the test result report described above and meet the respective acceptance criteria. Minor modifications or replacements performed directly prior to the conduct of a scheduled Type A test do not require a separate test.
Bases: The containment system is one of the major engineered safety features and is a consequence-limiting system. It represents the final physical barrier that, in the event of a loss-of-coolant accident (LOCA), protects against the inadvertent release of fission products.
I. Leakage Rate Testing Periodic containment integrated leakage rate tests are performed at or above 49.4 psig or at or above 24.7 psig for the reduced pressure test program. The leak rate will be calculated using the formulas of Reference 2 (Total Time) and Reference 3 (Mass Point).
Test schedules and the acceptance criteria specified herein are established based on the requirements of 10 CFR 50, Appendix J.()
A containment leakage rate of 0.12 wt% of the initial content of containment atmosphere at 49.4 psig/24 hours maintains public expos well below 10 CFR 100 values in the event of a hypothetical LOCA.
This leakage rate also limits public exposure to 10 CFR 100 values even if a complete core meltdown is postulated.
The acceptance criteria for (1) Type A test is 75% of the containment leakage rate specified above (2) Type 8 and Type C tests combined is 60% of the containment leakage rate specified above to allow for possible deterioration of the containment boundary between tests.
Amendment No. 4 7, 87
- 51 II.. Recirculation System Testing The portion of the Recirculation system outside the containment sphere is effectively an extension of the boundary of the containment.
Leakage from this system shall be maintained at as low as practical levels. The effective leakage of this system shall be maintained in accordance with the maximum leakage limitations established in Section 3.3.1.A(4) of Appendix A Technical Specifications.
The piping configurations of the recirculation and containment spray lines assure that leakage within Technical Specification limits will not deplete the isolation valve seal water system fluid inventory for at least 30 days at a pressure of 1.10 Pa.
Therefore, leakage from the isolation valves and containment penetrations for these systems is not added to the combined leakage rate for all penetrations and valves subject to Type B and C tests.
The containment penetrations encompassed by the recirculation and containment spray systems include penetrations for one containment spray line, three reactor coolant pump seal water injection lines, and the recirculation pump discharge line to the recirculation heat exchanger.
References (1) 10 CFR 50, Appendix J.
(2) ANSI N45.4-1972 (3) ANSI/ANS 56.8-1981 (4) Final Engineering Report and Safety Analysis, Paragraph 5.3.
Amendment No. 24. 7. 87