ML13326A697
| ML13326A697 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/25/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A696 | List: |
| References | |
| DPR-13-A-062 NUDOCS 8208310254 | |
| Download: ML13326A697 (4) | |
Text
I, pkREGUZ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY DOCKET NO. 50-206 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 62 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 June 25, 1982, complies with the standards and requirements of the.AtQmic 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 (1) 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.
19208310254 8282 8 AA c K o20o E 325 PPD 05000206 P.
-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. 62, are hereby incorporated in the license. Southern California Efison Company shall operate the facility in accordance with the Technical Specifi cations.
- 3. This license amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Denn sIM. 'Cr ute
- eld, ief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 25, 1982
ATTACHMENT TO LICENSE 'AMENDMENT NO.
62 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases by removing page 46d and by inserting the enclosed page 46d. This revised page contains the captioned amendment number and marginal line indicating the area of change.
46d 4.2.3 SAFETY INJECTION SYSTEM HYDRAULIC VALVE TESTING (SURVEILLANCE REQUIREMENT)
An interim surveillance testing program shall be conducted during the remainder of the current fuel cycle which began in June 1981.
At the next refueling outage, the interim program shall be supplanted by a long term surveillance testing program.
It is intended that this long term program will be developed and submitted to the NRC for review and approval at least 60 days prior to the next refueling outage.
The interim surveillance program shall be as follows:
- 1. At least once every 92 days, (except when the interval lapses while in mode 5 or 6, in which case the test may be delayed until a mode 3 or 4 operation prior to the next entry into mode 2) the unit shall be placed in mode 3 or 4 and a Hot SIS functional test (with the MOV-850 A, B & C valves locked closed) shall be performed. This test shall include a determination of the force required to open valves HV-851 A &B and the margin to available actuation force. This test shall be evaluated on the bases of the following criteria:
- a. If the measured actuator force for both the HV-851 A & B valves is less than 10,000 lbf*, the unit may be returned to power.
- b. If the measured actuator force of either HV-851 A or B is between 10,000 and 22,000 lbf*, the Hot SIS test for both valves shall be repeated to again determine required opening force and available margin. The prediction will assume a straight line extrapolation from the.following equation:
- Upon receipt of satisfactory data from continuing testing and analysis, the NRC staff will consider a request from Southern California Edison Company to change this-number to more accurately reflect existing conditions.
Amendment No. 57' 62