ML19225A824

Forwards Proposed Changes to Tech Specs Re Safety Relief Valve Tail Pipe Monitoring Sys

ML19225A824
Person / Time
Site:	Hatch
Issue date:	07/13/1979
From:	Ehrensperger W GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19225A825	List: ML19225A824 ML19225A827
References
NUDOCS 7907200337
Download: ML19225A824 (2)

Text

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July 13, 1979 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 SAFETY / RELIEF VALVE TAIL PIPi; MONITORING SYSTEM Centlemen:

Georgia Fever Company hereby proposes an amendment to the Plant Hatch Unit 1 Technical Specific-tions (Appendix A to the Operatic.g License) pursuant to 10 CFR 50.90, as required by 10 CFR 50.59(c)(1). The proposed changes reflect the necessary information to ' included in the Technical Specifications in order to conform to the analyses bc ,a discussed in our letter dated April 3, 1978, concerning suppression pool temperature limits.

The proposed changes to the Technical Specifications consist specifically of additional Limiting Conditions for Operation and Surveillance hequirements that apply to the relief / safety valve tail pipe monitoring system which has been ins talled on Unit 1. These conditions and requirements are identical to those contained in the Plant Hatch Un - 2 E*andard Technical Specifications (STS). Functional details pertaining to the tail pipe monitoring system have already been presented to you and are contained in the enclosure of our April 3, 1978, letter. We do not propose any additional changes to the Unit 1 Technical Specifications at this time. Current requirements which address al.lowable torus water level and temperature are similar to those contained in the Unit 2 STS and include the information needed to support the analyses bases.

The Plant Review Board and Safety Review Board have reviewed and approved the proposed change to the Plant Hatch Unit 1 Technical Specifications and have determined that it does not constitute an unreviewed safety question. The probability of an accident is not increased nor is the possibility for failures of a different type not previously introduced, since the proposed charges conform to the suppression pool temperature limit analyses bases. Mergins of safety are not reduced because the relief / safety valve tail pipe moritoring 445 293 4 4

7907200/37 ,

Georgia Power zb Ditector of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission July 13, 1979 Page Two system will indicate and identify a stuck open relief / safety valve and thus assist in providing the reactor operator information needed in order to perform the appropriate actions.

Yours very trul;,

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W. E. Ehrensperder MRD/TBD.', ob At tacimen t Sworn to and subscribed before me this 13th day of July, 1979.

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t. < - , Pc . c m,:a swo at on. Nptary Public vi u.. . , u, v e:m u. .w. u, ma xc: Mr. Ruble A. Thomas George F. Trowbridge, Esquire a q 0gr.0 l