ML20079G476
| ML20079G476 | |
| Person / Time | |
|---|---|
| Site: | Brunswick (DPR-062) |
| Issue date: | 12/31/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079G479 | List: |
| References | |
| DPR-62-A-090 NUDOCS 8401200131 | |
| Download: ML20079G476 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION yovy[s 3;
WASHING TON, 0. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated December 7,1983, as supplemented by letter dated December 16, and December 20, 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 reauirements 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-62 is hereby amended to read as follows:
9401290131 831231 PDR ADOCK 05000324 p
2-(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 90, are hereby incorporated in the license.
The licensee _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 NICLEAR REGULATORY C0f1!4ISSION Domenic B. Vassallo, Chief.
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 31, 1983 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 90 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as indicated on revised page 3/4 8-10.
The changed area is indicated by a vertical line.
Remove-Page Insert Page 3/4 8-10 3/4 8-10
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At least once per 18 months, during shutdown, by verifying that either:
1.
The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the battery is subjected to a battery service test, or 2.
The battery capacity is adequate to supply a dummy load of the following profile while maintaining the battery terminal voltage
>__ 105 volts.
a)
During the initial 60 seconds of the test; 1)
Battery 2A-1 > 1056.42 amperes, 2)
Battery 2A-211074.90 amperes, 3)
Battery 2B-1 > 1089.06 amperes, and 4)
Battery 23-211042.67 amperos.
b)
During the remainder of the first 30 minutes of the test; 1)
Battery 2A-1 > 243.19 amperes, 2)
Battery 2A-2 [ 159.10 amperes, 3)
Battery 2B-1 > 176.79 amperes, and 4)
Battery 2B-2 1 216.67 amperes.
c)
During the remainder of tihe 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test; 1)
Battery 2A-1 > 89.52 amperes, 2)
Battery 2A-2150.34 amperes, 3)
Battery 2B-1 > 53.39 amperes, and 4)
Battery 2B-2175.09 amperes.
3.
At the completion of either of the above tests, the battery charger shall be demonstrated capable of recharging its battery at a rate of at least 200 amperes while supplying normal D.C.
loads. The battery shall be charged to at least 95% capacity in i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
At least once per 60 months during shutdown by verifying that the e.
battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.
This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test and af ter normal equalizer charge.
BRUNSWICK ~ UNIT 2 3/4 8-10 Amendment No. 90
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