ML13310B911

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Acceptance Review Concerning License Amendment Request to Adopt NFPA 805, Performance -Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants
ML13310B911
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 11/07/2013
From: Siva Lingam
Plant Licensing Branch II
To: William Gideon
Duke Energy Progress
Lingam S
References
TAC MF2746
Download: ML13310B911 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. William G. Gideon, Vice President H. B. Robinson Steam Electric Plant Duke Energy Progress, Inc.

3581 West Entrance Road Hartsville, SC 29550 November 7, 2013

SUBJECT:

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2-ACCEPTANCE REVIEW CONCERNING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD NFPA 805, "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS" (TAG NO. MF2746)

Dear Mr. Gideon:

By letter dated September 16, 2013, Duke Energy Progress, Inc. (the licensee) submitted a license amendment request (LAR) to transition the fire protection licensing basis at the H. B. Robinson Steam Electric, Unit No. 2, from Title 1 0 of the Code of Federal Regulations (CFR), Section 50.48(b), to 10 CFR 50.48(c), National Fire Protection Association Standard NFPA 805.

Consistent with Section 50.90 of 1 0 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 purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this 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.

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.

Consistent with Section 9.1 of the NRC Enforcement Policy, because the NRC found the submitted LAR acceptable for detailed review, enforcement discretion for previously identified noncompliances and newly identified noncompliances discovered either by the licensee or the NRC while the LAR is under review will continue to be in place until the NRC disposition of the LAR.

Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there are 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) 415-1564.

Docket No. 50-261 cc: Distribution via Listserv Sincerely,

~G'-~

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there are 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) 415-1564.

Docket No. 50-261 Sincerely, IRA/

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Distribution via Listserv DISTRIBUTION:

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