ML20206E004
| ML20206E004 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/10/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20206E007 | List: |
| References | |
| DPR-62-A-126 NUDOCS 8606230041 | |
| Download: ML20206E004 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION L
j WASHINGTON, D. C. 20655 g
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 126 License No. DPR-62 9
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated June 4, 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 Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be corducted without endangering the health and safety of the public, and (ii) that such activities will be 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 ic 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-62 is hereby amended to read as follows:
p$'$D 1 86061o P
K 05000324 PDR
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.126, 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 and will remain effective until December 6, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 10,1986 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACILITY OPERATING LICENSE NO. DPR-62 4
DOCKET NO. 50-324 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
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TABLE 3.6.3-1 (continued) f h
FRIMARY CONTAYMMENT ISOLATION VALVES N
4 IsotATION TIME Il (seconds) h VALVE FUNCTION VALVE CROUP s'
NPCI steem ilme Isolation valves 4
50 E
E41-F002 y
E41-F003 n
RPCI terms section isolation valves 4
80 E41-F042 E41-F041 l
RCIC steam 11ae isolation valves 5
20*
E51-F007
..E51-F008.
Drywell purge exhaust backup valve 6
15
.y CAC-V10 7
Containment air porge isolation valve 6
15 CAC-V15 Suppression chamber vent valve 6
15 l
CAC-V22 Drywell purge enhenst valve 6
15 CAC-V23
- The Isolatlom Tlme for valve E51-F007 Is extended to 30 seconde until Dew 6,1986 at which
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time the 20 second limit will be re-established.
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