ML20081K642

Responds to Generic Ltr 83-28 Required Actions Based on Generic Implications of Salem ATWS Events. Requests Requirements Expressed in Generic Ltr 83-28 Be Resolved as Part of Normal Licensing Review Process

ML20081K642
Person / Time
Site:	Vogtle
Issue date:	11/08/1983
From:	Foster D GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GL-83-28, GN-276, NUDOCS 8311100219
Download: ML20081K642 (3)

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• Georg a Power Cornpany 333 P.e$nont Aveque Adanta, Georgta 30308 TeterAone 404 52G7726

. Maang AdJtess Post Office Box 4645

. Atianta, Georgia 30'302 h Georgia Power

' D. O. Foster the southern eiwtrc system Vice Presdert an<1 General Manager Vogtle Project November 8, 1983 Director of Nuclear Reactor Regulation Log: GN-276 Attention: Ms. E. G. Adensam File: X6BK10 Licensing Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 GENERIC LETTER 83-28

Reference:

Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)

Dear Sir:

The referenced letter was not received by the Vogtle Project however, due to the importance of the issue, a response is detailed below. Due to the length of time until the receipt of the Unit 1 OL, it is requested that the require-ments expressed in the referenced letter be resolved as part of our normal licensing review process. The writing of procedures, programs, policies and Technical Specifications necessary to implement the requirements of your generic letter are in the embryotic stage and necessary hardware modi-fications are under study. It is also intended that the Vogtle Project will avail itself of industry efforts through the Westinghouse Owners Group and INPO which will address the generic aspects of the referenced letter.

Below is a status of where the Vogtle Project stands on each of the sections of the enclosure to the referenced letter.

1.1 Post-Trip Review (Program Description and Procedure): The VEGP post-trip program and procedure will not be completed until July 1986.

The program and procedure will address the requirements expressed in the referenced letter and utilize the information and data as provided by 1.2 below.

1.2 Post-Trip Review - Data and Information capability: An evaluation will be made of the information and data necessary to support the requirements of a post-trip program and procedure as specified in the referenced letter. The required report will be su'omitted to the NRC in January 1986.

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r7 Director of Nuclear Reactor Regulation Log: GN-276 November File: X6BK10 Page 2 2.1 Equipment Classification and Vendor Interface -(Reactor Trip System Components): A review of the Reactor Trip System components will be performed to confirm their classification consistent with the referenced letter. An additional review will establish that all NSSS vendor information is available and reflects actual system configuration and its maintenance.- A program will be established to maintain NSSS vendor. interface consistent with the requirements of the referenced letter. The reviews and-program implementation will be completed by July 1986.

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2.2 Equipment Classification and Vendor Interface (Programs for All Safety-Related Components): The scope of this requirement involves commitments which require additional study. INFO has established a NUTAC to develop _an industry approach to meet these requirements.

Until INPO has completed its report, and we have time to study its recommendations, no specific commitments can be made.

3.1 Post-Maintenance Testing (Reactor Trip System Components): The VEGP maintenance procedures of the reactor trip system will not be completed until July 1986. The procedures will address the concerns of the referenced letter. Any changes which may be required of the Technical Specifications due to this review will be_ submitted for staff approval.

'3.2 Post-Maintenance Testing (All Other Safety-Related Components): This requirement is closely related to the completion of 2.2 discussed above. As such, no specific commitments can be made at this time.

'4.1 Reactor Trip System Reliability (Vendor-Related Modifications): All modifications recommended by the NSSS vendor will be reviewed-to verify

-that either: (1) the modification .has' been implemented; or (2) a written evaluation of the~ technical reasons for not implementing the modification will be prepared. This review will be completed by July 1986.

4.2 _ Reactor Trip System Reliability (Preventive Maintenance and Surveillance

-Program for Reactor--Trip Breakers): The VEGP maintenance and surveillance programs will be completed by July 1986. They will address the requirements expressed in the referenced letter.

4.3 Reactor Trip System. Reliability (Automatic Actuation of Shunt Trip Attachment for Westinghouse Plants): The Vogtle Project is presently

evaluating this modification. A commitment to install this modification i cannot be made until the evaluation is completed.

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! 4.4 Not' applicable to VEGP.

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~ LT Director of = Nuclear Reactor Regulation Log: GN-276 November File: X6BK10 Page'3 4.5 Reactor Trip System. Reliability.(System Functional Testing): The VEGP functional testing of the reactor trip system is dependent upon the action taken in 4.3 above. .The test program consistent with the final VEGP design configuration and the necessary Technical Specification changes will be completed by July 1986.

Should you have any' questions do not hesitate to contact us.

Yours truly,

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o o D. O. Foster DOF/sw xc: M. A. Miller R. A. Thomas D. E. Dutton J. A. Bailey O..Batum L'. T. Gucwa G.-Bockhold, Jr.

G. F. Trowbridge, Esquire 4