ML20210H391
| ML20210H391 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/08/1997 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210H396 | List: |
| References | |
| NUDOCS 9708130466 | |
| Download: ML20210H391 (4) | |
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NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.o. 3066H001 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 136 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated March 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 wi.a 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.
NPF-12 is hereby amended to read as follows:
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. (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 136, are hereby incorporated into this license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
FOR THE NUCLEAR REGULATORY COMMISSION Gordon Edison, Acting Director Project Directorate 11-1 Division of Reactor Projects - 1/l!
Office of Nuclear Reactor Regulation Attachments:
1..
Changes to the Technical Specifications 2.
Safety Evaluation Date of Issuance:
August 8,1997 l
ATTACHMENT TO LICENSE 1.MENDMENT NO.136 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised area is indicated by a marginal _line.
Remove Paae Insert Pace 3/4 5-4 3/45-4 4
EMERGENCY CORE COOLING SYSTEMS SURVEtti ANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following vakes are in a.
the Indicated positions with power to the vake operators removed:
Valve Number Vane Function Vane Position 1
8884 HHSI Hot Log injection Closed 2.
8886 HHSI Hot Log injection Closed 3.
8888A LHSI Cold Log injection Open 4,
8888B LHSI Cold Leg injecti 1 Open 5.
8889 LHSI Hot Leg injection Closed 6.
8701A RHRInlet Closed 7.
8701B RHRinlet Closed 8.
8702A RHR Inlet Closed 9.
87028 RHRInlet-Closed 10.
8133A Charging /HHSI Cross Connect Open 11.
8133B Charging /HHSI Cross Connect Open 12.
8106 Charging Mini Flow Hender Isolation Open b.
At least once per 31 days by:
1.
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, and 2.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, c.
By a visualinspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the reactor building which could be transpor1ed to the RHR and Spray Recirculation sumps and cause restriction of the pump suctions during LOCA conditions. This visualinspection shall be performed:
1.
For all accessible areas of the reactor building prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within the reactor building at the completion of mch reactor building entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
Verifying automatic interlock action of the RHR system from the Reactor Coolant System by ensuring that, with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened.
SUMMER UNIT 1 3/4 5-4 Amendment No. 09,136 U