ML20141D642
| ML20141D642 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/26/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20141D645 | List: |
| References | |
| DPR-62-A-063, DPR-71-A-125 NUDOCS 8604080195 | |
| Download: ML20141D642 (8) | |
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedAugust 12, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Consnission'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 Comission'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 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:
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.- (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27, 1986
ATTACHMENT TO LICENSE AMENDMENT N0. 125 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 area is indicated by a marginal line.
Page 3/4 6-11
CONTAINMENT SYSTEMS SUPPRESSION POOL COOLING LIMITING CONDITION FOR OPERATION 3.6.2.2 The suppression pool cooling mode of the residual heat removal (RHR) system shall be OPERABLE with two independent cooling loops, etch loop consisting of two pumps and one heat exchanger.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one RHR suppre:sion pool cooling loop inoperable, operation may a.
continue and the provisions of Specification 3.0.4 are not applicable; restore the inoperable loop to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With both RHR suppression pool cooling loops inoperable, restore at least one loop to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The suppression pool cooling mode of the RHR system shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 92 days by verifying that each RHR pump can be started from the control room and develops a flow of at least 7,700 gpm on recirculation flow through the RHR heat exchanger and the suppression pool.
BRUNSWICK - UNIT 1 3/4 6-11 Amendment No.125
'o UNITED STATES 8'
~,'n NUCLEAR REGULATORY COMMISSION
- p WASHWGTON. D. C. 20555 t
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company l
(the licensee) dated August 12, 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; 1
l 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 (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 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-62 is hereby amended to read as follows:
.. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
&l W
rw Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET h0. 50-324 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised area is indicated by a marginal line.
Pag 3/4 6-11 i
l l
l I'
CONTAINMENT SYSTEMS SUPPRESSION POOL COOLINC LIMITINC CONDITION FOR OPERATION 3.6.2.2 The suppression pool cooling mode of the residual heat removal (RHR) system shall be OPERABLE with two independent cooling loops, each loop consisting of two pumps and one heat exchanger.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one RHR suppression pool cooling loop inoperable, operation may a.
continue and the provisions of Specification 3.0.4 are not applicable; restore the inoperable loop to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With both RHR suppression pool cooling loops inoperable, restore at least one loop to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The suppression pool cooling mode of the RHR system shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 92 days by verifying that each RHR pump can be started from the control room and develops a flow of at least 7,700 gpm on recirculation flow through the RHR heat exchanger and the suppression pool.
BRUNSWICK - UNIT 2 3/4 6-11 Amendment No. 63
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