ML20117G790

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Responds to Request Re Steam Generator Tube Support Plate voltage-based Repair Criteria & Provides Comments and Clarification Re Commitments
ML20117G790
Person / Time
Site: Farley 
Issue date: 08/29/1996
From: Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9609050330
Download: ML20117G790 (2)


Text

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Southern Nucitar Operating Company Post Offica Box 1295 4

Birmingham. Alabama 35201

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  • Telephone (205) 868 5131 I

Southem Nudear Operating Company o.ve mo,ey Vice President Farley Project the Southern electnc System j

August 29, 1996 l

Docket No.: 50-364 10 CFR 50.90 l

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l

Washington, D. C. 20555 l

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Joseph M. Farley Nuclear Plant - Unit 2 Steam Generator Tube Support Plate Voltage-Based Repair Criteria i

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Ladies and Gentlemen:

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By letter dated August 22,1996, the NRC Staff requested Southern Nuclear commit to the following for the Farley Unit 2 alternate repair criteria:

l "1.

Pending the implementation of an NRC-approved process for updating a l

generic industry database for steam generator tube degradation, provide the l

l NRC with the database intended to be used prior to each refueling outage; and 2.

Use the database that has been used in the prior cycle of Farley Unit 2 as supplemented by all the data obtained from domestic Westinghouse steam

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generators having 7/8-inch diameter tubes that have been pulled and tested since the prior operating cycle."

Southern Nuclear will follow the above requests with the following comments / clarifications:

1.

Southern Nuclear will use the database forwarded to the NRC Staff by Duquesne Light Company letter dated March 27,1996, for the upcoming Farley Unit 2 inspection / evaluation. This database meets the requirements of 1 and 2 above.

2.

Southern Nuclea. will follow the guidance in 2 above; however, the database willinclude the data from tubes that have been pulled and tested up to 2 months prior to the outage. If a new, NRC-approved database is approved after that-time, its use is optional unless use of the old database is a safety concern, e.g.,

the burst or leakage correlations shift significantly in the non-conservative direction. Additionally, this commitment will be superseded when an NRC-approved process for updating the industry database is available.

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U. S. Nuclear Regulatory Commission Page 2 If there are any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY l

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Dave Morey Sworn to and subscribed before me this N9 dayaf h r m d 1996 0 nst Ydw w $ 6 Notary Public 8

My Commission Expireb4Y /79 7 0

REM / cit: database. doc cc: Mr. S. D. Ebneter, Region II Administrator Mr. J.1. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector

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Mr. T. A. Reed, NRR - Materials and Chemical Engineering Branch Dr. D. E. Williamson, State Department of Public Health s