ML20206E882
| ML20206E882 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/10/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20206E886 | List: |
| References | |
| DPR-71-A-106 NUDOCS 8704130774 | |
| Download: ML20206E882 (5) | |
Text
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UNITED STATES 4,
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CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated December 2, 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 (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 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.106, 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 C0tiMISSION e
.4f Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1987
i ATTACHMENT TO LICENSE AMENDMENT NO. 106
. FACILITY OPERATING LICENSE NO. DPR-71 i
DOCKET N0. 50-325 j
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
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3/4 1-19 i
3/4 1-20 1
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(BSEP-1-95)
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that:
j a.
1.
The volume and temperature of the sodium pentaborate solution are within the limits of Figures 3.1.5-1 and 3.1.5-2, and 2.
The heat tracing circuit is OPERABLE.
b.
At least once per 31 days by:
1.
Starting each pump and recirculating domineralized water to the test tank, 2.
Verifying the continuity of the explosive charge, and 4
3.
Determining the concentration of boron in solution by chemical analysis. This test shall also be performed anytime water or boron is added to the solution or when the sblution temperature drops below the limit established in Figure" 3.1.5-2.
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At least,once per 18 months during shutdown by:
c.
i 1.
Initiating one of the standby liquid control system loops',
including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping domineralized water into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch succe,ssfully fired. Both injection test loops shall be tested in 36 months.
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2.
Demonstrating that the minimum flow requirement of 41.2 spm per pump at a pressure of greater than or equal to 1190 psig is set.
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3.
Demonstrating that the pump relief valve setpoint is 1450 1 50 psig.
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BRUNSWICK - UNIT I 3/4 1-19 Amendment No. 106 i
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