ML20067D246
| ML20067D246 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/07/1982 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20067D249 | List: |
| References | |
| NUDOCS 8212130162 | |
| Download: ML20067D246 (5) | |
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SOUTHERN CALIFORNIA EDISON C0fiPANY SAN DIEGO GAS AND ELECTRIC C0riPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHElfi, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATIt!G STATION, UNIT 2 ArdENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 11 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendnent for the San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and F.lectric Conpany, The City of Riverside and The City of Anaheim, California (licensees) complies with the standards and requirements of the Atonic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in confornity with the application, as amended, the provisions of the Act, and the regulations of the 4
Comission;
)
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 Conn ssion's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the connon defense and security or to the health and safety of the public; 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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1 2.
Accordingly, the license is anended by changes to the Technical Specifi-cations as indicated in the attachnent to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby anended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 11, are hereby incorporated in the license.
SCE shall operate the facility in accordance with tne Technical Specifications and the Environnental Protection Plan.
3.
This license anendment is effective as of December 6, 1982.
FOR THE NUCLEAR REGULATORY C0fEISSION 5
George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing Date of Issuance: DEC 7 1992 C
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. 4 ATTACHMENT TO LICENSE AMENDMENT NO. 11 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by AmendMnt number and contain vertical lines indicating the area of change.
Amendment Page 3/4 3-75 3/4 3-76 I
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INSTRUMENTAT10N 3/4.3.4 TURBINE __OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MODES 1, 2* and 3*.
ACTION:
With one stop valve or one control valve per high pressure turbine a.
steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lead ** or l
isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS
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4.3.4 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
At least once per 7 days by cycling each of the following valves a.
through at least one complete cycle from the running position.
1.
Four high pressure turbine stop valves.
2.
Four high pressure turbine control valves.
3.
Six low pressure turbine reheat stop valves.
4.
Six low pressure turbine reheat intercept valves.
b.
At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running l
position.
l At least once per 18 months by performance of a CHANNEL CALIBRATION l'
on the turbine overspeed protection systems.
c.
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d.
At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or i
Corrosion.
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With any main steam line isolation valve and/or any main steam line isolation valve bypass valve not fully closed.
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SAN ONOFRE-UNIT 2 3/4 3-75 AMENINENT NO.11 I
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f INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued)
- For performance of surveillance testing of the valves in the unaffected low pressure turbine steam lead, the valve or valves closed in an affected low pressure turbine steam lead may be re-opened following successful completion of surveillance test-ing of that valve in accordance with 4.3.4.2a. for a period not to exceed one hour. The provisions of Specification 3.0.4 are not applicable to the low pressure turbine valves. This license amendment is in effect during the time interval of December 6, 1982 until the completion of-50% power startup testing or until January 31, 1983, whichever occurs first.
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l SAN ONOFRE-UNIT 2 3/4 3-76 AMENDMENT NO. 11 i
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