ML13326A668
| ML13326A668 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/05/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A667 | List: |
| References | |
| DPR-13-A-057 NUDOCS 8112030205 | |
| Download: ML13326A668 (5) | |
Text
0 UNITEDSTATES NUCLEAR REGULATORY COMMISSION n
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 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 57 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 October 21, 1981, as supported by information transmitted by letters dated October 16, 1981 and October.29, 1981,.comply 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.
,8112030205 811105 PDR ADOCK 05000206 P
PDR;
-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. 57, are hereby incorporated in the license. Southern California Edison Company shal.l 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
-Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division-of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 5, 1981
ATTACHMENT TO LICENSE AMENDMENT NO.57 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases by inserting the enclosed pages.
PAGES 46d 46e
A-2.%3 SAFETY INJECTION SYST &HYDRAULIC VALVE TESTING (SU VjLANCEREQUJREMENT)
An interim surveillance testing program shall be conducted during the remainder of the curre'nt 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, the unit shall be placed in mode 3 or 4 and a Hot S-IS functional test (with the MOV-850 AB&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 basis of the following criteria:
a-.
If the measured actuator force for both the HV-851 A&B valves is less than 10,000 1b4 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 oth valves shall be repeated to again determne 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
46e (22,000 F2)
T=
(F1 -
F)/TL where F, = measured actuator force from the first Hot SIS test during the current surveillance test (lbf)
F2 measured actuator force from the second Hot SIS test during the current surveillance, test (lbf)
TL time (In days) since the last surveillance testing F =,the actuater force from the previous surveillance test (1bf)*
If the calculated value of T does not exceed 92 days, the next surveillance test must be performed before T days had elapsed.
6:
If the measured actuator force of either HV-851 A or B' is greater.
than 22,000 lb,, the valve(s) shall be declared inoperable.
Test results shall be reported to the NRC along with proposed corrective actions and NRC approval obtained prior to returning the unit to service.
The first test shall be performed not.less than 14 days nor more than 21 days following return to power. from the current outage which began September 3, 1981.
For the first surveillance test, th-evalue of F shall be the aVerage actuator force of HV-851 A&B-val-ves from pre-operation testing (3135 lbf). All subseouent surveillance testing shall assume the F2 value from the previous surveillance test for each valve. If an F2 was not required during the previous surveillance test, the Fl value for each valve shall be assumed.
Amendment-No.
57