ML20054F898

Application to Amend License DPR-57 Providing Limiting Condition for Operation W/O Secondary Containment Integrity

ML20054F898
Person / Time
Site:	Hatch
Issue date:	06/11/1982
From:	Widner W GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20054F899	List: ML20054F898 ML20054F900
References
NUDOCS 8206180178
Download: ML20054F898 (2)

Text

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June 11, 1982 Georgia Power f*e sour *w wW 9stp W. A W6dne, v.c e Peu.+ ni eed Ger. era' 8/amay f C59 8'X1 N<Of O ce .ereig Director of Nuclear Reactor Regulation U. S. tbclear Regulatory Comission Washington, D. C. 20555 PRC 000(ET 50-321 OPERATING LICENSE OPR-57 E0 WIN 1. HATCH NUCLEAR PLANT UNIT 1 SEC0tOARY CONTAIPNENT TECmICAL SPECIFICATION CHANGE PROPOSAL Gentlemen:

In accordance with the provisions of 10 CFR 50.90 as required by of 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes an amendment to the Edwin I. Hatch Nuclear Plant Unit 1 Technical Specifications (Appendix A to the Operating License). This proposal is in response to your request dated April 8, 1982, and would provide a clear Limiting Condition for Operation (LCO) for the situation where secondary containment integrity cannot be properly maintained, and will in addition provide more appropriate references to Technical Specification 3.7.C.l. In addition this proposal would provide clarification of the operability requirements for the Standby Gas Treatment System.

The present Unit 1 Technical Specifications do not provide an LCO for continued operation without secondary containment integrity. There is also a reference (in Technical Specification 3.7.C.2) to Technical Specification 3.7.C.I.d which does not presently exist in the Unit 1 Technical Specifications. The proposed change would correct these problems as requested by your April 8, 1982 letter.

The Plant Review Board and the Safety Review Board has reviewed and approved the proposed changes and have concluded that application of these proposed Technical Specification changes would in no way constitute an unreviewed safety question. The probability of occurrence or the consequences of an accident or malfunction of safety-related equipment would not be increased above those analyzed in the FSAR because this change would decrease the probability of occurrence of an accident concurrent with a loss of secondary containment integrity, while the change to the Standby Gas Treatment System Technical Specifications only involves a clarification of or potential]y misleading wording. The possibility of an accident malfurotion of a different type than analyzed in the FSAR would not result The from this change because no new modes of operation would be created.

margin of safety as defined in the Technical Specifications would not be reduced due to this change because the establistnent,,0f an LCO for secondary containment would increase tne margins of safety, while the change to the Standby Gas Treatment System Sections does not change the operability re @irements for this system.

8206180178 820611 g, DR ADOCK 03000323 PDR

GeorgiaPower A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission June 11, 1982 Page Two Instructions for incorporation of these changes along with copies of affected Technical Specification pages are enclosed.

Included with this proposal is a determination of amendnent class. We have determined this to be one Class III amendnent; however, we believe that it is exempt from a license fee in accordance with the provisions of 10 CFR 170.22, footnote 2.

W. A. Widner states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER COMPANY By: 78, //. WV[ O W. A. Widner Sworn to and subscribed before me this lith day of June,1982 i

Notary Public CBS/mb Erclosure xc: H. C. Nix, Jr.

R. F. Rogers, III J. P. O'Reilly (NRC-Region II) l I

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