ML20133E528
| ML20133E528 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/05/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133E530 | List: |
| References | |
| NUDOCS 8507220532 | |
| Download: ML20133E528 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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- j WASHING TON,0. C. 20555 i
- l DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated March 21, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o)erate in confonnity with the application, the provisions of t1e Act, and the rules and regulations of the 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 j
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
1 0507220532 850705 PDR ADOCK 05000334 P
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-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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.arga, C Operating Reactors'B anch #1 Division of Licensi g
Attachment:
Changes to the Technical Specifications Date of Issuance: July 5, 1985
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ATTACHMENT TO LICENSE AMENDMENT 1.
'3cs i AMNNDMENT.NO. 94 TO FACILITY OPERATING LICENSE NO. DPR-66 j
s DOCKET NO. 50-334 l
Revise Appendix A as follows:
I Remove Pages Insert Pages 3/4 7-12 3/4 7-12 3/4 7-13 3/4 7-13 l
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PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two component cooling water subsystems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With less than two component cooling water subsystems OPERABLE, restore at least two subsystems 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water subsystems shall be demonstrated OPERABLE.
At least once per 31 days on a STAGGERED TEST BASIS by:
a.
1.
Verifying that each pump develops the required differential pressure and flow rate when tested in accordance with the requirements of Section 4.0.5.
2.
Cycling each testable power operated or automatic valve I
servicing safety related equipment through at least one complete cycle of full travel.
3.
Verifying that each valve (manual, power operated or automatic)
I servicing safety related equipment that is n6t locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by cycling each power operated valve servicing safety related equipment that is not testable during plant operation, through at least one complete cycle of full travel.
1 BEAVER VALLEY - UNIT 1 3/4 7-12 Amendment No. 94
PLANT SYSTEMS 3/4.7.4 REACTOR PLANT RIVER WATER SYSTEM (RPRWS)
LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two reactor plant river water subsystems supplying safety-related equipment shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4 ACTION:
With less than two RPRWS subsystems OPERABLE, restore at least two subsystems 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 be in at least HOT STANDBY within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two RPRW subsystems shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by:
a.
1.
Verifying that each pump develops the required differential pressure and flow rate when tested in accordance with the requirements of Section 4.0.5.
2.
Cycling each testable power operated or automatic valve l
servicing safety related equipment through at least one complete cycle of full travel.
3.
Verifying that each valve (manual, power operated or automatic) l servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by cycling each power operated valve servicing safet related equipment that is not testable during plant operation, ythrough at least one complete cycle j
of full travel.
BEAVER VALLEY - UNIT 1 3/4 7 13 Amendment No. 94
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