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MONTHYEARML1013401882010-06-0808 June 2010 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, Areva Fuel Mechanical Design Report Project stage: Withholding Request Acceptance ML1013802442010-06-0808 June 2010 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, Thermal-Hydraulic Design Report Project stage: Withholding Request Acceptance ML1025202302010-09-24024 September 2010 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, GE14 Fuel Thermal Mechanical Information Project stage: Withholding Request Acceptance ML1025203012010-11-0404 November 2010 Letter Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant, Unit 1, Areva Fuel Transition, Unit 1 Cycle 9 Reload Safety Analysis for 105% Original Licensed Thermal Power Project stage: Withholding Request Acceptance ML1101805852011-01-24024 January 2011 Request for Additonal Information Regarding Amendment Request to Transition to Areva Fuel Project stage: Other ML1105900542011-02-23023 February 2011 Response to NRC Request for Additional Information Regarding Amendment Request to Transition to Areva Fuel Project stage: Response to RAI ML11095A0732011-03-28028 March 2011 Request for Additional Information Regarding a Request to Transition to Areva Fuel Project stage: RAI ML11136A1872011-04-26026 April 2011 NRR E-mail Capture - Audit Results Summary Report Supporting TAC ME3775 - BF1 Areva Fuel Transition and Related BF2/3 Request Project stage: Other ML11137A1992011-05-12012 May 2011 Response to NRC Request for Additional Information Regarding to Transition to Areva Fuel Project stage: Response to RAI ML11159A0412011-06-0707 June 2011 NRR E-mail Capture - Audit Results Summary Report Supporting TAC ME3775 - BF1 Areva Fuel Transition and Related BF2/3 Request Project stage: Other ML11234A0042011-08-23023 August 2011 Request for Additional Information Regarding Technical Specification TS-473, Areva Fuel Transition Project stage: RAI ML11286A1072011-10-0707 October 2011 Response to NRC Request for Additional Information Regarding Amendment Request to Transition to Areva Fuel Project stage: Response to RAI ML12018A3762012-01-23023 January 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML12083A0012012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML1208300592012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775) (TS-473) Project stage: Withholding Request Acceptance ML12083A0032012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML12083A0142012-04-0404 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (GEH-Harrison) (TAC No. ME3775) (TS-473) Project stage: Withholding Request Acceptance ML12100A1032012-04-11011 April 2012 Audit Report Regarding Tennessee Valley Authority Browns Ferry, Unit 1 Areva Fuel Transition Emergency Core Cooling System Evaluation Model Application (TAC No. ME3775) (Np) Project stage: Other ML12108A2482012-04-17017 April 2012 Request for Withholding Information from Public Disclosure for Areva Fuel Transition Documents (TAC No. ME3775)(TS-473) Project stage: Withholding Request Acceptance ML12114A0042012-04-18018 April 2012 Supplement to License Amendment Request to Transition to Areva Fuel Project stage: Supplement ML12129A1492012-07-0303 July 2012 Issuance of Amendment Regarding the Transition to Areva Fuel (TAC No. ME3775) (TS-473) Project stage: Approval ML13010A0162013-01-0404 January 2013 CFR 50.46 30-Day Report Project stage: Other 2011-05-12
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 24, 2010 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE FOR BROWNS FERRY NUCLEAR PLANT, UNIT 1, AREVA FUEL TRANSITION, GE14 FUEL THERMAL METHCNICAL INFORMATION (TAC NO. ME3775)
Dear Mr. R. Krich:
By letter dated April 16, 2010, you submitted an affidavit dated January 7, 2010, executed by Andrew A. Lingenfelter of Global Nuclear Fuel-Americas, LLC (GNF). You requested that the information contained in the following document be withheld from public disclosure pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 2, Section 2.390:
Report GNF 0000-0111-8036-RO-P, "GE14 Fuel Thermal-Mechanical," dated January 2010.
A nonproprietary copy of this document has been placed in the Nuclear Regulatory Commission's (NRC's) Public Document Room and added to the Agencywide Documents Access and Management System Public Electronic Reading Room.
The affidavit stated that the submitted information should be considered exempt from mandatory public disclosure because it fits into the following categories:
Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its us by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies, Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
We have reviewed your application and the material in accordance with the requirements of 10 CFR 2.390 and, on the basis of the statements in the affidavit, have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure.
R. Krich -2 Therefore, the version(s) of the submitted information marked as proprietary will be withheld from public disclosure pursuant to 10 CFR 2.390(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will; of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
If you have any questions regarding this maUer, I can be reached at 301-415-1321.
Sincerely,
~.- ~
~)b Stewart N. Bailey, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259 cc: Andrew A. Lingenfelter, Vice President Fuel Engineering Global Nuclear Fuel-Americas, LLC Additional distribution via Listserv
ML102520230 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME SBailey BClayton DBroaddus DATE 09/10/10 09/10/10 09/24/10