ML091900753

RAI, Request for Supplemental Information Regarding Extension of Technical Specification Completion Time for Emergency Diesel Generators

ML091900753
Person / Time
Site:	Browns Ferry
Issue date:	07/10/2009
From:	Ellen Brown Plant Licensing Branch II
To:	Swafford P Tennessee Valley Authority
Brown E, NRR/DORL, 415-2315
References
TAC ME1515, TAC ME1516, TAC ME1517, TS-466-T
Download: ML091900753 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR SUPPLEMENTAL INFORMATION REGARDING EXTENSION OF TECHNICAL SPECIFICATION COMPLETION TIME FOR EMERGENCY DIESEL GENERATORS (TAC NOS. ME1515, ME1516, AND ME1517) (TS-466-T)

Dear Mr. Swafford:

By letter dated June 19,2009, the Tennessee Valley Authority (TVA) submitted a license amendment request for Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment would allow a one-time extension of the emergency diesel generator out of service Technical Specification (TS) completion time from 7 to 14 days. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs 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 bases 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 the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.

In order to make the application complete, the NRC staff requests that TVA supplement the application to address the information requested in the enclosure by July 24, 2009. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate

P. Swafford -2 correspondence. The information requested and associated timeframe in this letter were discussed with Mr. F. Russ Godwin of your staff on July 9, 2009.

If you have any questions, please feel free to contact me at (301) 415-2315.

Sincerely, IRA!

Eva A. Brown, 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

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION ONE-TIME EXTENSION OF EMERGENCY DIESEL GENERATOR COMPLETION TIME TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2. AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296

1. In the submittal dated June 19, 2009, on page E1-4, it is stated that based on the work planned, the outage critical path duration for each emergency diesel generater (EDG) has been determined to be approximately 7 days, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Provide a safety basis that justifies for the requested extension to 14 days. Also, provide a complete schedule of the planned outages for all EDGs during the maintenance activities, including how much time will be provided between outage of one EDG to another.

2. Describe, in detail, the impact of removing an EDG from service for an extended period (Le., the capability to mitigate design-basis accidents and transients such as loss-of offsite power). Also describe whether the OPERABLE EDGs will be used to replace the power lost due to removing an EDG from service. If applicable, describe the time required to interconnect an EDG to another Shutdown Board. Also note any differences between the Browns Ferry units, provide a discussion concerning the ac power configurations [see Regulatory Guide 1.81], and the capacity of each EDG. If the OPERABLE EDGs cannot be credited, then describe the means intended to supplement the EDG under maintenance with a temporary power source during the period of extended allowed outage.

ML091900753 OFFICE LPL2-2/PM LP-WB/LA EEEB\BC LPL2-2/BC NAME EBrown BClayton GWilson by memo TBoyce DATE 7/09/09 7/09/09 7/02/2009 7/10/09