ML20063P024

Application to Amend App a of License NPF-5,changing Tech Spec Figures 3.2.3-1 & 3.2.3-2 to Reflect Changes in Operating Limit Min Critical Power Ratios Resulting from Reanalysis of Pressurization Transients by GE

ML20063P024
Person / Time
Site:	Hatch
Issue date:	10/04/1982
From:	Beckham J GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20063P025	List: ML20063P024 ML20063P026
References
TAC-49054, NUDOCS 8210120047
Download: ML20063P024 (2)

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er o"ce na e A' m :a G. eg a 30302 GeorgiaPower SININom w a ay x, ea,y;, October 4, 1982 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission -

Washington, D. C. 20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 MCPR TECHNICAL SPECIFICATION CHANGE PROPOSAL Gentlemen:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) proposes an amendment to the Edwin I. Hatch Unit 2 Technical Specifications (Appendix A to the Operating License). The proposed changes to Figures 3.2.3-1 and 3.2.3-2 reflects changes in the Operating Limit Minimum Critical Power Ratios (0LMCPRs) resulting from reanalysis of pressurization transients performed by General Electric (GE) with the corrected ODYi1 Code.

Please note that the revised OLMCPRs have increased by 0.02 or less with respect to 0LMCPR valves incorporated in the Technical Specification change proposal made to the U. S. Nuclear Regulatory Commission (NRC) on March 11, 1982. By a letter dated May 5, 1982, GE informed GPC that "the original Hatch-2 Cycle-3 OLMCPRs are based on end-of-cycle conditions, and are at least 0.02 conservative until 2000 MWD /ST before E0C3". GPC received the Hatch-2 Cycle-3 ODYN analysis correction from GE in mid-Septerrber. By September 14, 1982, the more conservative OLMCPRs were implemented at Plant Hatch Unit 2 with the core average exposure at approximately 2900 MWD /ST before E0C3.

The Plant Review Board and the Safety Review Board have reviewed the

[, proposed changes and have concluded that application of these proposed Ec fi a 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 equipment important to safety are not increased

, t/ooO g above those analyzed in the FSAR due to this change because the changes do not involve any new modes of operation not previously analyzed. The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because the changes do not involve any new modes of operation not previously analyzed. The margin of safety, as defined in Technical Specifications, is not reduced due to this change because all margins have been verified by analyses, and the results have been published in Hatch 2 Licensing Supplement, Y1003J01A32, with Errata and addenda sheets showing the 0DYN analysis correction.

8210120047 821004 PDR ADOCK 05000366 P PDR

L GeorgiaPower d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission October 4, 1982 Page Two Instructions for incorporating these changes along with copies of affected Technical Specification pages are enclosed.

We have determined this proposal to be a class III amendment since this amendment involves a single safety issue and does not involve a significant safety hazard consideration .

Enclosed in a check for S4,000.

If you have any questions, please contact this office.

Sincerely yours,

. T. Beckham, Jr.

DLT/mb xc: H. C. Nix, Jr.

R. F. Rogers, III J. P. O'Reilly (NRC-Region II) 700775