ML12221A015

Issuance of Amendments License Amendment Request Pursuant to 10 CFR 50.90: Adoption of NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants.

ML12221A015
Person / Time
Site:	Nine Mile Point
Issue date:	08/08/2012
From:	Bhalchandra Vaidya Plant Licensing Branch 1
To:	Langdon K Nine Mile Point
Vaidya B, NRR/DORL/LPL1-1, 415-3308
References
TAC ME8899
Download: ML12221A015 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 8,2012 Mr. Ken Langdon Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: ADOPTION OF NFPA 805, PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS (2001 EDITION) (TAC NO. ME8899)

Dear Mr. Langdon:

By letter dated June 11,2012, Nine Mile Point Nuclear Station, LLC (NMPNS, the Licensee),

submitted a license amendment request (LAR) for Nine Mile Point Unit 1. The proposed amendment would adopt a new risk-informed performance-based fire protection licensing basis which complies with the requirements in Title 10 of the Code of Federal Regulations (10 CFR),

50.48(a) and 10 CFR 50.48(c); the guidance in Regulatory Guide 1.205, "Risk-Informed Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants," Revision 1, and National Fire Protection Association (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition. This LAR also follows the guidance in Nuclear Energy Institute (NEI) 04-02, "Guidance for Implementing a Risk Informed, Performance-Based Fire Protection Program under 10 CFR 50.48(c)," Revision 2.

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 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 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 staffs ability to complete the detailed technical review are identified despite completion of an adequate

K. Langdon -2 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) 415-3308.

Sincerely, Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 cc: Distribution via Listserv

K. Langdon -2 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) 415-3308.

Sincerely, Ira!

Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 cc: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL 1-1 RtF RidsNRRPMNineMilePoint RidsNrrDorlDpr RidsNRRLAKGoldstein RidsRgn 1MailCenter RidsNrrDirsltsb RidsNrrDraAfpb RidsAcrsAcnw_MaiICTR GDentel, RI RidsNrrDraApla RidsNrrDssStsb RidsNrrDraAhpb LFields, NRRtAFPB JHyslop, NRRtAPLA CCandace, NRR/AHPB JRobinson, NRRtAFPB HKhadijah, NRRISTSB DPickett, NRRtDORLlLPL 1-1 RidsDorlLpl1-1 RidsOGCRp ADAMS Accession No.: Ml12221 A015 (*) - Per E-Mail dated 08/07/2012 (ML122200595)

NRRIDRNAFPB/BC OFFICE NRR/LPL 1-1\PM NRR/LPL 1-1\LA Lead Reviewer)(*) NRR/LPL 1-1\BC iNRR/LPL1-1\PM III NAME BVaid~a KGoldstein AKlein/JRobinson GWilson BVaidya DATE 08/08/12 08/08/12 08/07/12 08/08/12 08/08/12 II OFFICIAL RECORD COpy