ML16074A123

Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805

ML16074A123
Person / Time
Site:	Davis Besse
Issue date:	03/15/2016
From:	Blake Purnell Plant Licensing Branch III
To:	Boles B FirstEnergy Nuclear Operating Co
Purnell B, NRR-DORL 415-1380
References
CAC MF7190, EA-14-094
Download: ML16074A123 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Brian D. Boles Site Vice President M:u:d1 15, 2016 FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 N. State Route 2 Oak Harbor, OH 43449-9760 EA-14-094

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 -ACCEPTANCE OF LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATED STANDARD 805 (CAC NO. MF7190)

Dear Mr. Boles:

By application dated December 16, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15350A314), as supplemented by letters dated February 2 and March 7, 2016 (ADAMS Accession No. ML16033A085 and ML16067A195, respectively),

FirstEnergy Nuclear Operating Company (the licensee) submitted a license amendment request for the Davis-Besse Nuclear Power Station, Unit No. 1. The proposed amendment requests to adopt National Fire Protection Associated Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition (ADAMS Accession No. ML010800360), as an alternative to compliance with existing fire protection program requirements.

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 (1 O CFR), an amendment to the license must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 1 O 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, as supplemented, 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 staff's 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) 415-1380.

Docket No. 50-346 cc: Distribution via Listserv Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

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) 415-1380.

Docket No. 50-346 cc: Distribution via Listserv DISTRIBUTION:

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JPoo1e BPurnell DATE 3/14/16 3/14/16 3/10/16 3/10/16 3/14/16 3/15/16 OFFICIAL RECORD COPY