ML20106E430

Revised Application to Amend License DPR-57,changing Tech Specs to Support Analog Transmitter Trip Sys Installation. Amend Request Originally Submitted on 840905

ML20106E430
Person / Time
Site:	Hatch
Issue date:	10/18/1984
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20106E433	List: ML20106E430
References
NED-84-539, TAC-55695, NUDOCS 8410290230
Download: ML20106E430 (2)

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Georgia Power Campany

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• 333 Pradmont Avenue Atlanta, Georgia 30308

. Telephone 404 526-6526 Marling Address:

Post Off;ce Box 4545 Atlanta, GEorg a 30302 h

Georgia Power

. L T. Gucwa tre southem entne sprem Manager Nuclear Engineenng and Chief Nuclear Engineer October 18, 1984

' Director of Nuclear-Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating acactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HMOI NUCLEAR PLANT UNIT 1 REVISION OF REQUEST EUR TECHNICAL SPECIFICATION CHANGES

'ID SUPPORT ANAIBG TRANSMITTER TRIP SYSPD1 INSTALLATIGI Gentlemen:

By letter dated September 5, 1984 (NED-84-436) Georgia Power Congany (GPC) proposed an amendment to the Edwin I. Hatcli Unit 1 Technical Specifications (Appendix A to the Operating License). Those proposed amendments were in support of plant design modifications associated with the installation of a General Electric Company (GE) Analog Transmitter Trip System (ATIS). Since that letter was submitted, certain changes in the ATrS design have occurred which require a revision of our previously proposed Technical Specification changes.

GPC recently identified that six additional ATrS instruments must be replaced during the outage now in progress due to their presence on an instrument rack which will be relocated. Two of these instruments (E41-N657A,B) are covered by Technical Specification requirements. The characteristics of the replacement devices require that changes be made to the trip setting and surveillance requirements for the trip function which they will perform (HPCI Steam Line High Differential Pressure).

Ehclosed with this submittal are changed pages and instructions for their use as replacements or additions in the document entitled "Edwin I.

Hatch Nuclear ' Plant Unit 1, Docket No. 50-321, Technical Specifications Revisions Associated With Installation of Analog Transmitter Trip System",

whidt was enclosed with our September 5, 1984 submittal. These changed pages include the revisions to GPCs proposed Technical Specifications. Also included are changes to the safety evaluation required by 10 CFR 50.59 and the significant hazards review required by 10 CFR 50.92.

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Geoigia Power d Director of Nuclear Peactor Regulation Attention: Mr. John F. Stolz, Chief Operating Beactors Brandt No. 4 October 18, 1984 Page Two These proposed changes to the Plant Hatch Unit 1 Technical Specifications have been evaluated by both the Plant Review Board and the Safety Review Board and both groups have determined that these changes do not 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 no increase in accident probabilities or consequences would be introduced by these changes. The probability of an accident or malfunction of a different type than previously evaluated in the ESAR does not result from these changes because the potential accident scenarios following implementation of these modifications are bounded by the present FSAR analyses. The margin of safety as defined in the Technical Specification is not reduced by these changes because the proposed new operability limits and surveillance requirements for plant systems are consistent with the present safety margins.

Very truly yours, W&

L. T. Gucwa cas/mb Enclosure xc J. T. Beckham, Jr.

H. C. Nix, Jr.

J. P. O'Beilly (NPC- Region II)

Senior Resident Inspector