ML20012D702
| ML20012D702 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/06/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012D703 | List: |
| References | |
| NUDOCS 9003280262 | |
| Download: ML20012D702 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION e
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUT110RITY DOCKET NO. 50 395 VIRCll C. SulHER NUCLEAR STATION UNIT to. 1 AMENDHENT TO FACILITY OPERATIls LICENSE Amendient ho. 89 License No. NPF-12 1.
The Nuclear Regulatory Cor.raission (the Commission) has found that:
A.
The application for aner4nent by South Carolina Electric & Gas l
Compary (the liunsees), dated July 21, 1989s as supplenented by letters dated December 11, and Decenber 18, 1989 complies with the standards and requirenants of the Atomic Energy Act of 1954, as anended (the Act), and the Consnission's rules and regulations set forth in 10 CFR Chapter I; l).
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 anendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D.
The issuance of this anenanent will not be inimical to the coreon defense and security ur to the health and safety of the public; and E.
The issuance of this amenoment is in accordance with 10 CFR Part 51 of the Consnission's regulations and all applic61e requirenents have been satisfied.
2.
Accordingly, the license is anended by changes to the Technical Specifications, as inoicateo in the attachment to this license anendment; and paragraph 2.C.(2) of facility Operating License No. NPF-12 is hereby anended to rwad as follows:
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2 (2) Technical Specifications and Envimninental Protection Plan The Technical Specifications contained in Appendix A, as revised through Anendrxnt No. 89
, and the Environnental Prctection Plan contained in Appendix B, are hereby incorporated in_ the license.
South Camlino Electric & Gas Conpary shall operate the facility in accordance with the Technical Specifications and the Environnental Protection Plan.
3.
This aren&ent is effective as of its date of issuance, and shall be-inplemented within 75 days of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10N Ronnie Lo/for Elinor G. Adensarr, Director Project Directorate 111 Division of Reactor Projects 1/11 Attachne nt:
Changes to tte Technical Spccifications Date of Issuance: March 6, 1990
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AlTACHMENT TO LICENSE AMENDMENT NO. 89 TO FACILITY OPERATING LICENSE NO. NPF-12 1
DOCKET NO. 50-395
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Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and i
contain vertical lines indicating the areas of ctange. Corresponding overleaf pages are also provided to maintain docunent cospleteness.
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Remove Pages Insert Pages 3/4 5-4 3/45-4 1
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EMERGENCY CORE COOLING SYSTEMS r
SURVEILLANCE 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 valves a.
are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position 1.
8884 HHSI Hot Leg Injection Closed 2.
8886 HHSI Hot Leg Injection Closed 3.
8888A LHSI Cold Leg Injection Open 4.
88888 LHSI Cold Leg Injection Open 5.
8889 LHSI Hot Leg Injection Closed 6,
8701A RHR Inlet Closed 7.
87018 RHR Inlet Closed 8.
8702A RHR Inlet Closed 9.
87028 RHR Inlet Closed 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 visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the reactor building which could be transported to the RHR and Spray Recirculation sumps and cause restriction of the pump suctions during LOCA conditions.
This visual inspection 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 each 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 ac-tual Reactor Coolant System pressure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened.
1 SUMMER - UNIT 1 3/4 5-4 Amendment No. 89