ML20214G451
| ML20214G451 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-71-A-107) |
| Issue date: | 05/15/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214G455 | List: |
| References | |
| NUDOCS 8705270071 | |
| Download: ML20214G451 (4) | |
Text
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f UNITED STATES j k' % h t e
NUCLEAR REGULATORY COMMISSION 1
WASHINGTON, D C.20555 Q@4.1 CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No.107 N
License No. DPR-71 I,
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee), dated December 16, 1986, 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 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Cc mission'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 amesidment 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-71 is hereby amended to read as follows:
8705270071 870515 PDR ADOCK 05000325 P
i,
1 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.107, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
4 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II i
Attachment:
Changes to the Technical Specifications Date of Issuance: May 15, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT N0.,107 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET N0. 50-325 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised Greas are indicated by rarginal lines.
Remove Page Insert Page 3/4 6-16a 3/4 6-16a i
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g TABLE 3.6.3-1 (Continued) s O
PRIMARY CONTAlltfENT ISOLATION VALVE 8 I
Ey ISOLATION TIME II VALVE FUNCTIDW VALVE CROUP (Seconds)
Drywell CAD Inlet Valve 6
15 CAC-V161 Suppression Chamber CAD Inlet Valve 6
15 CAC-V162 '
Drywell CAD Inlet Valve 6
15 CAC-V163 R
Suppression Chamber Purge Exhaust Isolation Valve 6
15
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f CAC-V172 5
a I
1.
See Specification 3.3.2, Table 3.3.2-1 for isolation alsnal that operates each valve group.
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