ML14108A408

Acceptance of Requested Licensing Action License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Generating Plants

ML14108A408
Person / Time
Site:	Beaver Valley
Issue date:	04/22/2014
From:	Jeffrey Whited Plant Licensing Branch 1
To:	Emily Larson FirstEnergy Nuclear Operating Co
Whited J, NRR/DORL/LPLI-2
References
TAC MF3301, TAC MF3302
Download: ML14108A408 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 22, 2014 Mr. Eric A Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2- ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION (NFPA) 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT-WATER REACTOR GENERATING PLANTS (TAC NOS. MF3301 AND MF3302)

Dear Mr. Larson:

By letter dated December 26, 2013, 1 as supplemented by letter dated February 14, 2014, 2 FirstEnergy Nuclear Operating Company submitted a license amendment request for Beaver Valley Power Station, Units 1 and 2 (BVPS). The proposed amendment requests review and approval to transition the fire protection licensing basis at BVPS, 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 (NFPA) 805. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this proposed license 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 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.

1 Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML14002A086.

2 ADAMS Accession No. ML14051A499.

E. Larson If you have any questions, please contact me at (301) 415-4090 or via e-mail at Jeffrey.Whited@nrc.gov.

Sincerely, o;-£utdd Jeff~,&,h.ited, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 cc: Distribution via Listserv

ML14108A408 *via email OFFICE DORL/LPL 1-2/PM DORLILPL 1-2/LA DORLILPL 1-2/BC DORLILPL 1-2/PM NAME JWhited ABaxter* MKhanna JWhited DATE 4/21/2014 4/21/2014 4/21/2014 4/22/2014