ML12306A498

Acceptance Review of Requested Licensing Action Concerning 25 Percent Surveillance Extension (TAC Nos. ME9485, ME9486, ME9489)(TS-475)

ML12306A498
Person / Time
Site:	Browns Ferry
Issue date:	11/02/2012
From:	Ellen Brown Plant Licensing Branch II
To:	James Shea Tennessee Valley Authority
Brown, Eva A.
References
TAC ME9485, TAC ME9486, TAC ME9489
Download: ML12306A498 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2,2012 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 2 AND 3 - ACCEPTANCE OF REQUESTED LICENSING ACTION CONCERNING 25 PERCENT SURVEILLANCE EXTENSION (TAC NOS. ME9485, ME9486, AND ME9489)(TS-475)

Dear Mr. Shea:

By letter dated August 28,2012, the Tennessee Valley Authority (the licensee) submitted a proposed amendment for Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment, if approved, would allow the licensee to delete the references to Section XI of the American Society of Mechanical Engineers Code (ASME Code) and add references to the ASME Code Operation and Maintenance of Nuclear Power Plants Section 5.5.6 to the Technical Specifications (TSs). The revision will allow the application of a 25-percent extension of surveillance interval to the accelerated frequencies used in the Inservice Test program. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this proposed amendment. 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.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) 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 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate

J.Shea - 2 acceptance review. TVA will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

Should there be any questions, please feel free to contact me at (301) 415-2315.

Sincerely, IRA!

Eva A. Brown. 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

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