ML20003F483

Application to Amend License DPR-57,revising Diesel Generator Operability Requirements When Reactor Is in Shutdown or Refuel Modes & Fuel Is Not in Reactor Pressure Vessel

ML20003F483
Person / Time
Site:	Hatch
Issue date:	04/02/1981
From:	Widner W GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20003F484	List: ML20003F483 ML20003F503
References
TAC-43627, NUDOCS 8104210369
Download: ML20003F483 (3)

Text

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April 2, 1981

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V g U. S. tOclear Regulatory Corrnission g of 1 Office of POclear Reactor Regulation (. g fg A Washington, D. C. 20555 '

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CoERATItG LICENSE DPR-57 \v b EDWIN I. HATCH NUCLEAR PLANT UNIT 1 Td / < -

PROPOSED CHAtCE TO TECHNICAL SPECIFICATI0f6- Y O"M

- Lh DIESEL GEtERATOR OPEPMILITY Gentlemen:

In accordance with the provisions of 10 CFR 50.59, as required by 10 CFR 50.90, Georgia Power Company proposes an amencinent to the Technical Specifications (Appendix A to the Operating License).

The proposed change would revise the diesel generator operability requirements when the reactor is in the SHUTDOWN or REFUEL modes and fuel is not in the reactor pressure vessel.

Existing Plant Hatch Unit 1 Technical Specifications (i.e. 3.9.C) require a minimum of two diesel generators to be operable whenever (1) work is being done which has the potential for draining the reactor pressure vessel, or (2) core or contalment cooling is recuired, or (3) secondary containment is required. Specification 3.9.C was issued when only Unit I was licensed to operate and the above mentioned three criteria at that time applied to requirements for protection of fuel when it was in the reactor pressure vessel. Subsequent to completion of Unit 2, a separate specification was incorporated into the Unit 1 Technical Specifications to require secondary containment whenever Unit 2 is not in CCLD SHJTD0wN.

Thus, the existing specification on Diesel Generator operability is impacted by the secondary containment requirement tied to thit 2 operation.

Accordingly, the proposed revision to the Unit 1 Diesel Generator operability specification has taken the secondary containment requirenent into consideration. The proposed change to the Technical Specifications would relax the number of Diesel Generators reouired to be operable from two to one when the reactor mode switch is in the SHUTDC#N or REFUEL positions and no fuel is in the reactor vessel. In addition, power must be capable of being supplied from the one operable Diesel Generator to the fuel pool cooling system and to one train of the Standby Gas Treatment System (SGTS) to meet secondary containment requirements on the refueling floor.

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Georgia Power d U. S. tbclear Regulatory Commission Page 2 April 2, 1981 The proposed change to the Technical Specifications has been reviewed by the Plant Review Board and the Safety Review Board and has been determined not to involve an unreviewed safety question. The probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously analyzed has not been increased due to the proposed change; the ability to provide for fuel pool cooling and secondary containment is not impaired by the proposed change which is only effective when no fuel is in the vessel. The possibility of an accident or malfunction not previously analyzed is not created; the change introduces no new modes of failure-- the power supply for fuel pool cooling, which would normally be shed in a loss-of-offsite-power (LOSP) event is now required to be aligned such that power will not be lost in event of a LOSP; also, the SGTS train selected will have both normal and emergency power l supply as usual. Furthermore, margins of safety are not reduced inasmuch as sources of power to SGTS and fuel pool cooling are supplied as they normally would, with an increase in reliability of the supply to fuel pool cooling due to the realignment of supply source.

Due to the potential impact on existing work in progress at the intake structure and a potential delay in the scheduled date for reloading fuel in the reactor pressure vessel, work which is scheduled for early April, we request your review and approval of the proposed changes to the Unit 1 Technical Specifications by April 8, 1981.

The proposed amendment has been evaluated as a single Class III amendment and a check for $4,000.00 is enclosed. The evaluation of amendment class is enclosed as Attachment 1.

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: 8 >

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W. A. Widner Sworn to and subscribed ,before spe this 2nd day of April,1981.

.* Notary Pubhc, Georgra. State at Large C

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f My Comm:sson Expres Sept. 20,1983 Notary Public RDB/mb 1% :hments xc: Max Manry R. F. Rogers, III

ATTACHMENT 1 NRC DOCKET 50-321 OPERATING LICENSE OPR-57 EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 PROPOSE 0 CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License DPR-57 and has determined that:

a) The proposed amendment does-not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b) The proposed amendment does not contain several complex issues, does not involve ACRS review, and does not require an environmental impact statement; c) The proposed amendment does not involve a complex issue, an environmental issue or more than one safety issue; d) The proposed amendment does involve a single safety issue, namely, a change in the number of diesel generators required to be operable when the unit is in the SHUTDOWN or REFUEL mode with no fuel in the vessel.

e) The proposed amendment is therefore a Class III amendment.

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ATTACHMENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57 would be incorporated as follows:

Remove Pace Insert Page 3.9-6 3.9-6 a

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