ML13316A624
| ML13316A624 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/04/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A623 | List: |
| References | |
| DPR-13-A-075 NUDOCS 8406070273 | |
| Download: ML13316A624 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION I-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. 75 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 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.
8406070273 840604.
PDR ADOCK 05000206 P
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- 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. 76, 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 THE NUCLEAR REGULATORY COMMISSION (vennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 4, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. 75 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 Pages Insert Pages 47 47 47a 50 50 51 51
4.3.1 CONtAIN1ZNT
=11I p icability:
Applies to containment leakage.
Objective:
To verify that leakage from the cont nrent spere is raintained within specified values.
S>ecification:
I.
Integrated Leakage Rate Tests, Type A A.
Test Pressure In order to verify leakage froAom the containment sphere, a Type A test shall be performed.
Type A tests shall consist of a peak pressure test or a reduced pressure test.
Peak pressure tests are conducted at a test pressure greater than or equal to 49.4 psig, and reduced pressure tests are condcted at a test pressure greater than or equal to-24.7 psig.
B.
Acceptance Criteria For the peak pressure test program the containment sphere leakage rate measured is less than.0.090 wt%/24 hours of the initial content of the containment air at the calculated peak pressure of 49.4 psig.
For the reduced pressure test program to be conducted at 24.7 psig, the measured leakage rate shall be less than 0.064 vt%/24 hours. of the initial content of the containment atsere at the c;lclated peak pressure of 49.4 psig.
The accuracy of each Type A test is verified by a supplemental test which (1) confirrs the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 25% of 0.12 vt%/24 hours for the peak pressure test or 0.085 vt%/24 hours for the redced pressure test, and (2) reuires the qgantity of air bled from or. injected into the cntainsent during the supplibental test to be equivalent to at least 75% of the total allowable leakage rate at 49.4 psig.
Amendment No.)2< 75,
47a C.
Freguency A set of 3 periodic ype A tests are perforzed at 40+ 10 mnth intervals during each 10-year service period
-Te 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 Tye A tests shall be submitted to the NRC for review and approval.
If two consec'tive periodic Zrype A tests fail to reet the above acceDtance criteria, a type A test is performed at each plant shutdown for refueling or appoximtely every 18 months, whichever occCurs first, until two consecutive Typ A tests meet the acceptance criteria, after which tire the noral test schele ray-. be resumed.
Amendment No. 75
B. Frequency The Safety Injection Recirculation System shall be tested at the same frequency as the integrated leakage rate tests.
In addition, whenever components of this system are used during normal operation, visual inspections for leakage shall be made.
Basis:
The Containment System is one of the major engineering safeguards and is a consequence limiting system. It represents the final physical barrier which, in the event of a loss of coolant accident, protects against the inadvertent release of fission products.
Leak Rate Testing Periodic conta.inent integrated leakage rate tests are performed at or above 49.4 psig or at or above 24.7 psig for the reduced pressare test progran.
The leak rate will be calculated using the formulas of Reference 2 (Total Tire) and Reference 3 (Mass Point).
Test schedules and the acceptance criteria specified herein are establis based on the requirements of 1DR50, Apendix JM.
A contairent leakage rate of 0.12 wt% of the initial content of containrent atmosphere at 49.4 psig/24 hours aintains public exposure well below QCFR100 values in the event of a hypothetical LOCA.
This leakage rate also limits public exposure to 10CR100 values even if -a complete core relt6ow is postulated.
Penetration Types A, B, and C are welded solid to the sphere and are tested as an integral part of the sphere. Types D, E, and F, the air lock, the equipment door, isolation valves, and the electrical penejrqtions are provided with test connections for periodic tests. 4)
Amendment No. 34 75
51 Recirculation System Testing The portion of the Recirculation System outside the containment 5
sphere is effectively an extension of the boundary of the containment. (
References:
References (1) 10 CTR 50, Appendix J.
(2) ANSI 195.4-1972 (3) xN51/AN5 56.8-1981
.(4) inal r
nieering ?epot ad Saffety A.
- nalsis, Parapa 5.3.
(5) Final Engineering Report and Safety Analysis, Parar;:nh 5.1 Amendment NO.
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