ML20237F621
| ML20237F621 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/10/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237F623 | List: |
| References | |
| NUDOCS 8708130100 | |
| Download: ML20237F621 (8) | |
Text
UNITED STATES y
NUCLEAR REGULATORY COMMISSION y
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- j WASHINGTON, O. C 20555
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l CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMCNDMENT TO FACILITY OPERATIhG LICENSE b
Amendment No. 110 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee),datedAugust 29, 1986, as supphtmented July 16, i987, 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 confomity 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 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 licanse 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:
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J (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.110, 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 shall be implemented within 60,iays of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Elinor G. Adensam, Director Project Directorate I1-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: August 10, 1987 t
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ATTACHMENT TO LICENSE AMENDMENT N0.110 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 l
Replace the following page of the Appendix A Technical Specifications with j
the enclosed page. The revised areas are indicated by marginal lines.
Remove Page Insert Page 3/4 6-13 3/4 6-13 0
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(BSE?-1-88)
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.3.1 Each primary containment isolation valve specified in Table 3.6.3-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair, or replacement work is performed on the valv'e or its i
associated actuator, control, or power circuit by performance of the cycling test and verification of isolation time.
4.6.3.2 Each isolation valve specified in Table 3.6.3-1 shall be demonstrated OPERABLE at least once per 18 months by verifying that on a containment isolation test signal each isolation valve actuates to its isolation position.
4.6.3.3 The isolation time of each power-operated or automatic valve specified in Table 3.6.3-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.4 Each reactor instrumentation system isolation valve shall be
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demonstrated OPERABLE at least once per 18 months by cycling each valve through at least one complete cycle of full travel.*
.b
- The end of the current surveillance period for the surveillance requirements below may be extended beyond the time limit specified by Technical Specification 4.0.2a.
After November 2, 1984, the plant shall not be operated in Operational Conditions 1, 2, or 3 until the surveillance requirements listed below'have been completed. Upon accomplishment of the surveillance, the provisions of Technical Specification 4.0.2a shall apply.
Technical Specification 4.6.3.4; as applicable to excess flow check valves B21-F047C, B21-F04?D, B21-F049C, and B21-F0490.
BRUNSWICK - UNIT 1 3/4 6-13 Amendment No. 72 110
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee),datedAugust 29, 1986, as supplemented July 16,1987, complies with the standards and requirements of the Atomic Energy i
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 Comission's regulations; j
D.
The issuance of this amendment will not be inimical to the
)
comon defense and security or to the health and safety of the i
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.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications. as indicated in the attachment to this license amendment; l
and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is i
hereby amended to read as follows:
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/ -(2) Technical Specifications The T chnical Specifications contained in Appendices A and B, as revised through Amendment No. 137, 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 shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-Elinor G. Adensam Director Project Directorate II-1 Division of Reactor _ Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: August 10, 1987 l
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PR PM:PD21:DRPR 0
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ATTACHMENT TO LICENSE AMENDMENT NO.137
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l QCILITYOPERATINGLICENSENO.DPR-62 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.
Remove Page Insert Page 3/4 6-13 3/4 6-13
BSEP-2-91 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS b 4.6.3.1 Each primary containment isolation valve specified in Table 3.6.3-1 j
shall be demonstrated OPERABLE prior to returning the valve to service after l
maintenance, repair, or replacement work is performed on the valve or its I
associated actuator, control, or power circuit by performance of the cycling test and verification of isolation time.
4.6.3.2 Each isolation valve specified in Table 3.6.3-1 shall be demonstrated OPERABLE at least once per 18 months by verifying that on a' containment isolation test signal each isolation valve actuates to its isolation position.
4.6.3.3 The isolation time of each power-operated or automatic valve specified in Table 3.6.3-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.4 Each reactor instrumentation system isolation valve shall be demonstrated OPERABLE at least once per 18 months by cycling each valve through at least one complete cycle of full travel.
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BRUN! WICK - UNIT 2 3/4 6-13 Amendment No.
97 137
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