ML110950195

Acceptance of Requested Licensing Action Deletion of Low Pressure Coolant Injection Motor-Generator Sets

ML110950195
Person / Time
Site:	Browns Ferry
Issue date:	04/05/2011
From:	Gratton C Plant Licensing Branch II
To:	Matthews T Tennessee Valley Authority
Gratton C, NRR, DORL, 415-1055
References
TAC ME5796, TAC ME5797
Download: ML110950195 (2)

Text

From: Gratton, Christopher Sent: Tuesday, April 05, 2011 8:58 AM To: Matthews, Thomas C IV Cc: Boyle, Patrick; Gratton, Christopher; Lingam, Siva

Subject:

Acceptance review results

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: DELETION OF LOW PRESSURE COOLANT INJECTION MOTOR-GENERATOR SETS (TAC NO(S). ME5796 AND ME5797)

Dear Mr. Matthews:

By letter dated February 25, 2011, the Tennessee Valley Authority (TVA) submitted a license amendment for Browns Ferry Nuclear Plant (BFN), Units 2 and 3. The proposed amendment request would delete BFN, Units 2 and 3, Technical Specification Surveillance Requirement 3.5.1.12, which requires the verification of the capability to automatically transfer the power supply from the normal source to the alternate source for each Low Pressure Coolant Injection subsystem inboard injection valve and each recirculation pump discharge valve on a 24-month frequency. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff=s acceptance review of this amendment 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.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (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 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 staffs 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) 415-1055.

Christopher Gratton Senior Project Manager Division of Operating Reactor Licensing

Office of Nuclear Reactor Regulation