ML13354B879

Acceptance Review Results License Amendment Request to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants

ML13354B879
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/31/2013
From:	Jason Paige Plant Licensing Branch II
To:	Capps S Duke Energy Carolinas
Paige, Jason NRR/DORL 415-5888
References
TAC MF2934, TAC MF2935
Download: ML13354B879 (2)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 December 31, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 -ACCEPTANCE REVIEW RESULTS RE: LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT-WATER REACTOR GENERATING PLANTS (TAC NOS MF2934 AND MF2935)

Dear Mr. Capps:

By letter dated September 26, 2013, Duke Energy Carolinas, LLC submitted a license amendment request for McGuire Nuclear Station, Units 1 and 2. The proposed amendment would adopt a new fire protection licensing basis which complies with the requirements in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.48(a), 10 CFR 50.48(c), and the guidance in Regulatory Guide (RG) 1.205, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants," Revision 1, dated December 2009. 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 10 CFR 50.90, 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 NRC staff to make an independent assessment regarding the acceptability of the proposed amendment 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 Duke Energy supplement the application to address the information requested in the enclosure by January 8, 2014. This will enable the NRC staff to complete 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

s. Capps -2 for review pursuant to 10 CFR 2.101, and the NRC staff will cease its 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 NRC staff's detailed technical review by separate correspondence.

The information requested and associated time frame in this letter were discussed with your staff on Wednesday, December 18, 2013. If you have any questions, please contact me at (301) 415-5888.

Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosure:

As stated cc w/encl: Distribution via Listserv SUPPLEMENTAL INFORMATION LICENSE AMENDMENT ADOPT NATIONAL FIRE PROTECTION ASSOCIATION DUKE ENERGY CAROLINAS, MCGUIRE NUCLEAR STATION, UNITS 1 AND DOCKET NOS. 50-369 AND 1. Table W-1 states that the total fire CDF is 2.70E-5/yr for Unit 1 and 3.87E-5/yr for Unit 2. Please summarize the principle difference{s) between the Units that cause the different risk estimates.

Please also provide a Table of the Unit 2 risk-significant scenarios such as that provide in Table W-2 for Unit 1. Enclosure S. Capps for review pursuant to 10 CFR 2.101, and the NRC staff will cease its 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 NRC staff's detailed technical review by separate correspondence.

The information requested and associated time frame in this letter were discussed with your staff on Wednesday, December 18, 2013. If you have any questions, please contact me at (301) 415-5888.

Sincerely, IRA! Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

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