ML20064N157
| ML20064N157 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/04/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064N155 | List: |
| References | |
| NUDOCS 8302160046 | |
| Download: ML20064N157 (3) | |
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Q Ch SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 10 TO OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO.50-39S INTRODUCTION By letter dated January 20, 1983, South Carolina Electric & Gas Company (the licensee) requested an amendment to the Appendix A Technical Specifications appended to License No. NPF-12 for the Virgil C. Sunmer Nuclear Station. The amendment wculd change the action statements for engineered safety feature actuation instrumentation to be consistent with the Westinghouse Standard Technical Specifications.
BACKGROUND AND DISCUSSIONS Table 3.3-3, " Engineered Safety Feature Actuation System Instrumentation",
identifies functional units of the protection system including action statements which riust be met when channels are inoperable.
In general the action statements require that inoperable sensing channels be placed in a tripped condition. For safety actions initiated on 2 out of 4 coincidence, placing a channel in trip results in safety action being initiated on a trip of one of the three remaining channels. Where inadvertent initiation of a safety function could be detrimental to plant safety, inoperable sensing channels are bypassed, rather than placed in a trip i
condition. This precludes inadvertent initiation of a safety function due to a single failure since two of the remaining sensing channels must trip to initiate safety actions. When one of two logic trains are inoperable, action statements require placing the plant in a hot shutdown condition if this type of channel cannot be returned to an operable status within a short period of time, generally 6 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
EVALUATION The licensee has proposed to change the Action Statement for the steam line isolation automatic actuation logic and actuation relays from Statement 19 to Statement 21. This changes the action from placing an inoperable logic train in trip to a shutdown action. We find the change to be acceptable since it is consistent with the recommendations of the Standard Technical Specifications for Westinghouse Pressurized Water Reactors, NUREG-0452, Revision 4.
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2-The licensee has proposed to change the Action Statement for emergency feedwater suction transfer on low pressure from Statement 19 to State-i ment 16. This :Sanges the action from placing an inoperable channel in trip to placing it in bypass. We find this change to be acceptable since it is consistent with the Westinghouse Standard Technical Speci-fications for channels which could produce an action detrimental to plant safety if inadvertently tripped.
The licensee has proposed to change the Action Statement for automatic switchover to containment sump on RWST level low-low from Statement 19 3
to Statement 16. This changes the action from placing an inoperable channel in trip to placing it in bypass. We find this change accept-able since it is consistent with the Westinghouse Standard Technical Specifications for channels which could produce an action detrimental to plant safety if inadvertently tripped.
Finally, the licensee has proposed to change the Action Statement for automatic switchover to containment sump automatic actuation logic and actuation relays from Statement 19 to Statement 14. This changes the action from placing an inoperable logic train in trip to a shutdown action.
We find this change acceptable since it is consistent with the Westinghouse Standard Technical Specifications.
The proposed changes in the Technical Specifications are consistent with the actions reconmended in the Standard Technical Specification' which have been reviewed and approved by the staff for Westinghouse plants and are, therefore, acceptable.
ENVIRONMENTAL CONSIDERATION We have determined that the amendment does not authorize a change in i
effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is i
insignificant frcm the standpoint of environmental impact and, pursuant to 10 CFP 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
CONCLUSION l'
We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant in' crease in the probability or consequences of accidents previously considered, does not create the possibility of an accident of a type different from any evaluated 6
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'd previously, and does not involve a significant decrease in a safety margin, the a'iendnent does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in conpliance with tha Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
February 4, 1983 Principal Contributors: Jon Hopkins, Licensing Branch No. 4, DL T. Dunning, Instrumentation and Control Systems Branch, DSI l
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