ML20097B936

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Forwards Vogtle Electric Generating Plant GL 89-10 Close- Out Submittal Vol 1 Program Summary Rept & ...Vol 2 Design-Basis Capability Verification Rept
ML20097B936
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/31/1996
From: Mccoy C
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097B940 List:
References
GL-89-10, LCV-0136-K, LCV-136-K, NUDOCS 9602080023
Download: ML20097B936 (2)


Text

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/* Georgia Power Company 40 Inverness Center Parkway

. Pot Once Box 1295

'B rmingham Alabama 35201 I

  1. " Telephone 205 877-7122 L l C. K. McCoy Georcia u

Power .

l Vce President Nuclear Vogtle Project the southem electric sntem l January 31,1996 LCV-0136-K i J

Docket Nos.: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 l

Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT I GENERIC LETTER 89-10 l CLOSE-OUT SUBMITTAL l Georgia Power Company (GPC) requested approval to provide a submittal to facilitate the closure of the Vogtle Electric Generating Plant (VEGP) Generic Letter 89-10 program in licu of having a final inspection. The NRC subsequently approved this request in a letter dated August 25,1995. Pursuant to this approval, GPC is transmitting the VEGP l Generic Letter 89-10 Close-Out Submittal, Volumes 1 and 2, to the NRC foi review.

Volume 1, entitled " Program Summary Report" provides a detailed description of the program undertaken to implement the recommendations contained in the generic letter.

Included in this report is a discussion of the engineering design review methodology, the ]

differential pressure test program which was undertaken to validate this methodology and the subsequent reconciliation of the differential pressure test results with the engineering methodology.

Volume 2, entitled " Design-Basis Capability Verification Report" outlines the basis for justifying that each of the 256 valves included in the program is capable of perfonning its design-basis function. The valves included in the program are divided into 30 groups of identical valves with capability justifications developed for each group based on in-situ ,

differential pressure test data, EPRI Performance Prediction Program data or calculated margins.

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9602080023 960131 PDR ADOCK 05000424 i P PDR

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U. S. Nuclear Regulatory Commission Page 2 GPC believes that this submittal addresses all of the relevant issues associated with the VEGP GL 89-10 program in sufficient detail to facilitate the closure of the capability verification portion of the program. In addition, based on information provided at a Region II Workshop held in Atlanta on October 24,1995, GPC understands that the NRC has disassociated the issue of periodic differential pressure testing from the closure of GL 89-10. Therefore, this issue is not formally addressed in the VEGP close-out documentation.

Should you require any additional information regarding this response, please contact my office.

Sincerely, C. K. McCoy CKM et

Enclosures:

1. GL 89-10 Close-Out Submittal, Volume 1
2. GL 89-10 Close-Out Submittal, Volume 2 xc: Georgia Power Comoany Mr. J. B. Beasley, Jr.

Mr. M. Sheibani NORMS U. S. Nuclear .tegulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. L L. Wheeler, Licensing Project Manager, NRR Mr. C. R. Ogle, Senior Resident Inspector, Vogtle 4

LCV-0136-K 1