ML103080101

E-mail Browns Ferry Nuclear Plant Units 1, 2, and 3-Acceptance of Requested Licensing Action-Modification of TS 3.7.3., Control Room Emergency Ventilation System

ML103080101
Person / Time
Site:	Browns Ferry
Issue date:	11/04/2010
From:	Gratton C Plant Licensing Branch II
To:	Matthews T Tennessee Valley Authority
Gratton C, NRR, DORL, 415-1055
References
TAC ME4668, TAC ME4669, TAC ME4670
Download: ML103080101 (1)

Text

From: Gratton, Christopher Sent: Thursday, November 04, 2010 9:28 AM To: 'Matthews, Thomas C IV'

Subject:

Acceptance review results

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: MODIFICATION OF TS 3.7.3, CONTROL ROOM EMERGENCY VENTILATION SYSTEM (TAC NOS.

ME4668, ME4669, AND ME4670)

Dear Mr. Matthews:

By letter dated August 27, 2010, the Tennessee Valley Authority (TVA) submitted a license amendment for Browns ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment request would add a new Action to TS 3.7.3, Control Room Emergency Ventilation (CREV)

System, to permit one or more CREV subsystems to be inoperable for up to 90 days when the inoperability is due to inoperable CREV System High Efficiency Particulate Air (HEPA) filter and/or charcoal adsorbers. An administrative change to correct errors in Unit 2 TS page header information that occurred during issuance of TS pages for a previous amendment was also included. 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