ML20136F814

Application for Amends to Licenses NPF-2 & NPF-8,revising TS 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements

ML20136F814
Person / Time
Site:	Farley
Issue date:	03/07/1997
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20136F818	List: ML20136F814 ML20136F823
References
RTR-NUREG-1431 NUDOCS 9703170064
Download: ML20136F814 (2)

Text

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D:ve Morey South:rn Nucl:tr Vice President Optrating C:mpany Farley Project P.O. Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 March 7, 1997 SOUTHERN COMPANY Energy to Serve YourWorld" Docket Nos.: 50-348 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk Washington, DC 20555 I Joseph M. Farley Nuclear Plant Request to Revise Technical Specifications ,

Containment Isolation Valves Surveillance Reauirements Ladies and Gentlemen: )

In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) j' proposes to amend the Joseph M. Farley Nuclear Plant Units I and 2 Technical Specifications.

The proposed changes will revise Surveillance Requirements associated with Specification 3/4.6.3, i

" Containment Isolation Valves." These changes will allow operability testing for the containment i isolation valves listed in Table 3.6-1 of the Tecimical Specifications during a defueled status.

These proposed changes are technically consistent with the requirements of NUREG-1431, Revision 1," Westinghouse Standard Technical Specifications," issued on April 7,1995.

The basis for the proposed technical specification changes is provided in Enclosure 1.

The supporting significant hazards evaluation pursuant to 10 CFR 50.91 is provided in Enclosure

2. Based upon the evaluation provided, SNC has determined the proposed changes to the technical specifications do not involve a significant hazards consideration as defined by 10 CFR 50.92.

SNC has also determined that the proposed license amendment will not significantly affect the quality of the human envirorunent.

The revised typed pages of the proposed technical specifications, including page change instructions, are included in Enclosure 3. The marked pages are provided in Enclosure 4. A copy of these proposed changes is being sent to Dr. Donald E. Williamson, the Alabama State Designee, in accordance with 10 CFR 50.91(b)(1).

g lEN.hIN 9703170064 970307 l PDR ADOCK 05000348 P PDR

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! . 1 U. S. Nuclear Regulatory Commission Page 2 NRC review and approval of these proposed changes is requested by the 1998 Spring and Fall i outages for Units 2 and I, respectively.

If there are any questions, please advise.

Respectfully submitted, ,

SOUTHERN NUCLEAR OPERATING COMPANY l l

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• 1 Dave Morey i

SWORN TO AND SUBSCRIBED BEFORE ME This '/ day of h 1997 MfLCfN Notary Public V h

JMG: contisol. doc My Commission Expires: (/kk7 1 Enclosures

1. Basis for Change Request 1

2. 10 CFR 50.92 Evaluation I

3. Page Change Instructions and Revised Pages l

4. Hand-Marked Pages  !

cc: U. S. Nuclear Regulatory Commission. Washington. D_C J. I. Zimmerman, Licensing Project Manager, NRR U. S. Nuclear Regulatorv Commission. Region II L. A. Reyes, Regional Administrator T. M. Ross, Senior Resident Inspector State of Alabama D. E. Williamson i

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