ML13149A364

Acceptance Review Concerning LAR to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,

ML13149A364
Person / Time
Site:	Browns Ferry
Issue date:	05/31/2013
From:	Farideh Saba Plant Licensing Branch II
To:	James Shea Tennessee Valley Authority
Saba F NRR/DORL/LPL2-2
References
TAC MF1185, TAC MF1186, TAC MF1187
Download: ML13149A364 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 May 31, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place LP 3D-C 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - ACCEPTANCE REVIEW CONCERNING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD NFPA 805, "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS," (TAC NOS. MF1185, MF1186, AND MF1187)

Dear Mr. Shea:

By letter dated March 27,2013 (ML13092A393), as supplemented by letter dated May 16, 2013, Tennessee Valley Authority submitted a license amendment request (LAR) to transition the fire protection licensing basis at the Browns Ferry Nuclear Plant, Units 1, 2, and 3, from Title 10 of the Code of Federal Regulations (CFR), Section 50.48{b), to 10 CFR 50.48{c), National Fire Protection Association Standard NFPA 805.

Consistent with Section 50.90 of 10 CFR, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.

J.Shea

- 2 Consistent with Section 9.1 of the NRC Enforcement Policy, because the NRC found the submitted LAR acceptable for detailed review, enforcement discretion for previously identified non compliances and newly identified noncompliances discovered either by the licensee or the NRC while the LAR is under review will continue to be in place until the NRC disposition of the LAR.

Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there are instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-1447.

Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 cc: Distribution via Listserv

J. Shea

- 2 Consistent with Section 9.1 of the NRC Enforcement Policy, because the NRC found the submitted LAR acceptable for detailed review, enforcement discretion for previously identified noncompliances and newly identified noncompliances discovered either by the licensee or the NRC while the LAR is under review will continue to be in place until the NRC disposition of the LAR.

Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there are instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-1447.

Sincerely, IRA By ABilloch forI Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 cc: Distribution via Listserv DISTRIBUTION:

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LPLlI-2/BC LPLlI-2/PM NAME FSaba (ABilioch for)

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DATE 05/31/13 05/31/13 05/23/13 05/23/13 05/31/13 05/31/13 OFFICIAL RECORD COpy