ML11341A006

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Acceptance Review of the Measurement Uncertainty Recapture Power Uprate License Amendment Request (TAC Nos. ME7164, ME7165, ME7166)
ML11341A006
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 12/08/2011
From: Stang J
Plant Licensing Branch II
To: Gillespie P
Duke Energy Carolinas
Tobin, Margaret, 415-8394
References
TAC ME7164, TAC ME7165, TAC ME7166
Download: ML11341A006 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 8, 2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (OCONEE 1,2, AND 3), ACCEPTANCE REVIEW OF THE MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NOS. ME7164, ME7165, AND ME7166)

Dear Mr. Gillespie:

By letter dated September 20,2011, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) for Oconee 1, 2, and 3. The proposed amendment requested approval of a measurement uncertainty recapture (MUR) power uprate. An acceptance review was performed by the Nuclear Regulatory Commission (NRC) to determine if there was sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. By letter dated November 7,2011, the NRC informed the licensee that additional information was 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.

By letter dated November 21, 2011, the licensee supplemented the September 20, 2011, application with the additional information requested by the NRC. The purpose of this letter is to provide the results of the NRC staffs acceptance review of this LAR. Consistent with Section 50.90 of Title 10 ofthe Code of Federal Regulations (10 CFR). Part 50, 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 now completed its review of your application and supplemental information, and concludes that it now provides 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.

P. Gillespie If you have any questions, please contact me at (301) 415-1345 or via email John. Stang@nrc.gov.

Sincerely, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: Distribution via Listserv P. Gillespie If you have any questions, please contact me at (301) 415-1345 or via email John. Stang@nrc.gov.

Sincerely.

IRA! John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 cc: Distribution via Listserv DISTRIBUTION:

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