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MONTHYEARML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: Request NLS2012040, Enclosure 2, GNF S-0000-0140-2518-R0-NP, GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 282012-05-30030 May 2012 Enclosure 2, GNF S-0000-0140-2518-R0-NP, GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 28 Project stage: Other ML1219300742012-07-10010 July 2012 Acceptance Review Email, License Amendment Request, Revise Technical Specification 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation Project stage: Acceptance Review ML12235A2522012-09-0505 September 2012 Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: RAI ML12285A3562012-10-0303 October 2012 Response to Nuclear Regulatory Commission Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: Request NLS2012099, Response to Nuclear Regulatory Commission Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio2012-10-31031 October 2012 Response to Nuclear Regulatory Commission Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: Request ML12299A0922012-11-0909 November 2012 Issuance of Amendment No. 243, Revise Technical Specification 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation Project stage: Approval ML12291A8132012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 5/11/2007 Affidavit Executed by Thomas Smed, Studsvik Scandpower Gardel BWR-Cooper Nuclear Station Power Distribution Uncertainties Project stage: Withholding Request Acceptance ML12289A0712012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 9/13/12 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas LLC VSP-NPP-HP1-12-087 - Response to RAIs Project stage: Withholding Request Acceptance ML12285A1412012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 4/25/12 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas LLC GNF-A Report No. S-0000-0140-2518-R0-P Project stage: Withholding Request Acceptance ML12341A1112012-12-31031 December 2012 Correction to Safety Evaluation Pages Issued with Amendment No. 243 Dated 11/9/2012, Revise TS 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation Project stage: Approval 2012-11-09
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Text
From:
Wilkins, Lynnea Sent:
Tuesday, July 10, 2012 4:05 PM To:
McCutchen, Edward L.
Cc:
Burkhardt, Janet; Lent, Susan
Subject:
Acceptance of Cooper LAR To Revise Technical Specification Safety Limit Minimum Critical Power Ratio (ME8853)
Ed, By letter dated May 30, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121570406), Nebraska Public Power District (NPPD) requested an amendment to the Facility Operating License for the Cooper Nuclear Station (CNS). The proposed amendment would revise Technical Specification Section 2.0, Safety Limits.
Specifically, the amendment would revise two recirculation loop and single recirculation loop Safety Limit Minimum Critical Power Ratio (SLMCPR) values to reflect results of a cycle specific calculation.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (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 staff to proceed with 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. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-1377.
Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377