ML20151V628
| ML20151V628 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/27/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151V581 | List: |
| References | |
| NUDOCS 8602110360 | |
| Download: ML20151V628 (2) | |
Text
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UNITED ST ATES f ^ #c ~j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NifCLEAR REACTOR REGut.ATION SUPPORTING AMEN 0 MENT NO. 3 TO FACILITY OPERATING LICENSE NO. NPF-38 LOUIS!ANA POWER AND LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated June 6,1985 Louisiana Power and Light Company (licensee),
requested changes to the Technical Specifications (Appendix A to Facility Operating Licensee NPF-38) for the Waterford Steam Electric Station, Unit 3.
The proposed changes would revise (1) Technical Specification 3.3.3.8 by addino four smoke detectors in the RAB and (2) Technical Specification 3.6.3 by correcting the identifyino numbers of three containment isolation valves.
2.0 DISCUSSION Technical Specification 3.3.3.8 addresses the operability reouiraments for fire detection instrumentation orovided to ensure adequate warnino and ornmpt fire detection. Table 3.3-11 lists the instrumentation necessary to ensure this function. Of that list, Function B instruments provide actuation of fire suppression systems as well as early warning and notification. The proposed change will revise the number of Function B smoke detectors in the Reactor Auxiliary Buildino Zone 27C of Technical Specification Table 3.3-11.
The number of detectors will be increased from 2 to 6 as the result of recent station modifications.
Table 3.6.-2 lists those containment isolation valves required operable by
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Technical Specification 3.6.3.
In listino the valves, two unfoue valve numbers are supplied for each.
The first number is the unique identifier assigned by the Architect-Engineer while the second number in parentheses is the unique identifier assigned by LP&L.
The proposed change involves correcting typographical errors in the three LP&L identifiers for manual / remote manual valves in Table 3.6-2.
These channes are:
96021103/20 O/20l!9 PDR ADocy oboon:gog I
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Penetration Existing Valve Proonsed Number Number Chance 53 2CA-V600 (CVR 3018) 2CA-V600 (CVR 301A) 63 2SA-V114 (LRT 101) 2SA-V114(LRT109) 63 2SA-V604 (LRT 102) 2SA-V604 (LRT 110) 3.0 EVALUATION In order to implement the results of the Fire Protection Program's fire hazards analysis for fire zone RAB 27C it is necessary to increase the Function B detection, which constitutes an additional control not presently included in the Technical Specifications. Because this chance provides for a more reliable Fire Protection System by includino additional smoke detectors, the staff finds it acceptable.
The purpose of the proposed change to Table 3.6.2 is to correct the identifying numbers for three containment isolation valves. Because this change is purely administrative and brings the Technical Specifications into conformance with other plant documents, the sta'f finds it acceptable.
4.0 CONTACT WITH STATE OFFICIAL The NRC staff has advised the Administrator, Nuclear Energy Division, Department of Environmental Quality, State of Louisiana of the proposed determination of no significant hazards consideration. No coments were received.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of facility components located within the restricted area. The staff has determined that the amendment involves no sianificant increase in the amounts of any effluents that may be released offsite and that there is no significant increase in individual ne cumulative occupation radiation exposure. The Comission has previously issued proposed findinos that the amendment involves no significant hazards consideration, and there has been no public coment on such findinos. Accordinoly, forth in 10 CFR 51.2?(c)(9)gibility criteria for cateoorical exclusion set the amendment meets the eli Pursuant to 10 CFR 51.22(h) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
Based upon our evaluation of the proposed changes to the Waterford 3 Technical Specifications, we have concluded that:
there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and such activities will be conducted in compliance with the Comission's regulations and the issuance of the amendments will not be inimical i
to the common defense and security or to the health and safety of the public.
We, therefore, conclude that the proposed changes are acceptable, and are hereby l
incorporated into the Waterford 3 Technical Specification.
Dated:
JAN 2 71986
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MN 2 7 1966 ISSUANCE OF AMENDMENT NO. 2 TO FACILITY OPERATING LICENSE NP. NPF-38 FOR WATERFORD 3 DISTRIRilTION
_ Docket File 50-382 NRC PDR Local PDR PBD7 Reading FNiraglia JLee (5)
JWilson Attorney, OELD LHannon EJordan RGrimes JPartlow TBarnhart(4)
WJones WRegan ACRS (10)
OPA RDiggs, LFNB I
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