ML14133A526

Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (TAC MF1185-87)

ML14133A526
Person / Time
Site:	Browns Ferry
Issue date:	05/21/2014
From:	Farideh Saba Plant Licensing Branch II
To:	James Shea Tennessee Valley Authority
Saba F DORL/LPL2-2 301-415-1447
References
TAC MF1185, TAC MF1186, TAC MF1187
Download: ML14133A526 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street LP 3D-C Chattanooga, TN 37402-2801 May 21, 2014

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS

{TAC NOS. MF1185, MF1186, AND MF1187)

Dear Mr. Shea:

By letter dated March 27, 2013, as supplemented by letters dated May 16 and December 20, 2013, Tennessee Valley Authority (the licensee, TVA) submitted a license amendment request to transition the fire protection licensing basis at the Browns Ferry Nuclear Plant, Units 1, 2, and 3 (BFN), from Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.48(b), to 10 CFR 50.48(c),

National Fire Protection Association Standard NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants."

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information provided by TVA, participated in an audit at the BFN site from September 9 - 13, 2013, and determined that additional information is needed to complete the review. By letter dated November 19, 2013, the NRC staff requested additional information. By letters dated December 20, 2013, January 10 and 14, February 13, and March 10, 2014, the licensee responded to the NRC staff's request for additional information (RAI).

The NRC staff reviewed the licensee's responses and determined that additional information is needed. The enclosure to this letter contains the staff's followup RAI specific to fire modeling.

As previously discussed with Mr. Gordon Williams of your staff, the NRC is requesting responses to the RAI by June 30, 2014.

J.Shea Please contact me at 301-415-1447, or via email at farideh.saba@nrc.gov, if you have any questions.

Docket Nos. 50-259, 50-260, and 50-296

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely,

~*zt..r Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

REQUEST FOR ADDITIONAL INFORMATION (RAI)

LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1, 2. AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 Fire Modeling (FM) RAI 01.01 By letter dated December 20, 2013 (ADAMS Accession No. ML13361A093), the licensee responded to FM RAI 01 (b)(i) and stated that, "Only fire propagation to stacks immediately adjacent to the source have been modeled, in accordance with FAQ [Frequently Asked Question] 08-0049." Explain how "immediately adjacent" is defined in this context, and describe the sequence of ignition of the bottom tray and vertical fire propagation that was assumed for an adjacent stack.

FM RAI 02.01 By letter dated December 20, 2013 (ADAMS Accession No. ML13361A093), the licensee responded to FM RAI 02.c and referred to NUREG/CR-6850, "EPRI [Electric Power Research lnstitute]/NRC-RES [Office of Nuclear Regulatory Research] Fire PRA [Probabilistic Risk Assessment] Methodology for Nuclear Power Facilities," Appendix Q, Section Q.2.2 to substantiate the damage delay time that was assumed for covered trays. However, the delay time that is recommended in NUREG/CR-6850, Section Q.2.2 should only be used for qualified cable. Confirm that all cables for which the delay time in NUREG/CR-6850 was used are qualified cables. If any cables for which the delay time in NUREG/CR-6850 was used are not qualified cables, provide a technical justification for the delay time assumed.

Enclosure

J.Shea Please contact me at 301-415-1447, or via email at farideh.saba@nrc.gov, if you have any questions.

Sincerely, IRA by AHon for/

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

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:

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