ML20138F854
| ML20138F854 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/29/1997 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-01, GL-97-1, NUDOCS 9705060071 | |
| Download: ML20138F854 (2) | |
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e Days Mirry SIuthern Nucl:ar Vicc. President Op ftting Company farley Poject RO. Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 d
April 29, 1997 SOUTHERN COMPANY Energyro Serve YourWorld" Docket Nos.:
50-348 50-364 10 CFR 50.54(f)
U. S. Nuclear Regulatory Conunission ATfN: Document Control Desk Washington, DC 20555-0001 Joseph M. Farley Nuclear Plant Response to Generic Letter 97 Degradation of Control Rod Drive Mechanism Nozzle and other Vessel Closure Head Penetrations Ladies and Gentlemen:
i The NRC issued Generic Letter (GL) 97-01, Degradation of Control Rod Drive Mechanism Nozzle and other Vessel Closure Head Penetrations, dated April 1,1997. In the generic letter, the NRC requested licensees to provide information necessary to verify compliance with 10 CFR 50.55a and 10 CFR Part 50, Appendix A, GDC 14, and to determine whether an augmented j
inspection program, pursuant to 10 CFR 50.55a(g)(6)(ii), is required for vessel head penetrations (VHPs). Specifically, the NRC requested licensees to provide a written report that includes the information listed in GL 97-01 for its facility within 120 days of the date of the GL. Additionally, GL 97-01, required that licensees provide a response within 30 days stating: (1) whether or not the requested information will be submitted and (2) whether or not the requested information will be submitted within the requested time period. This letter provides the Southern Nuclear Operating Company (SNC) 30-day response, required by GL 97-01.
SNC is currently pursuing a solution to the VHP issue in conjunction with the Westinghouse Owners Group (WOG). Several key meetings are scheduled prior to the duc date for the 120-day response, during which, it is expected that a program to address VHP cracking will be developed.
Due to the time and effort necessary to develop such a program, the information necessary to provide a complete response to GL 97-01, item I, may not be available within the allotted 120 days. SNC will provide a 120-day response that addresses Item 1.1 regarding the inspection activities performed to date and provide a plan for addressing the VHP issue, t
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U. S. Nuclear Regulatory Commission Page 2 SNC will provide a response within 120 days to GL 97-01, Item 2. Any plans to perform inspections will be included in the response to GL 97-01, Jtem 1.
Should you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY WI $f Dave Morey Sworn to andsubscribed before me thiskkay of f 1997
?0l0 Afb hh NkaryPublic My Commission Expires: f
/. /99Q TWS/maf F970lV4. doc Mr. L. A. Reyes, Region II Administrator cc:
Mr. J. I. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector I
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