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MONTHYEARML0603806721996-06-14014 June 1996 Calculation CD-Q0000-940339, Rev. 1, Calculation of Basic Parameters for A46 and Individual Plant Examination of External Events (IPEEE) Seismic Program. Project stage: Other ML0603806772004-06-0909 June 2004 TVA Calculation CDQ1 074 2004 0160, Rev 0, HCLPF Calculations of RHR Heat Exchanger Anchorage for Seismic IPEEE Program. Project stage: Other ML0603806762004-06-0909 June 2004 TVA Calculation CDQ1 999 2004 0156, Rev. 0, HCLPF Calculations of MCC Anchorage for Seismic IPEEE Program. Project stage: Other ML0603806712006-02-0202 February 2006 Response to NRC Request for Additional Information Regarding Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - Submittal of Browns Ferry Unit 1 Seismic and Internal Fires IPEEE Reports Project stage: Response to RAI ML0717201862006-03-31031 March 2006 Enclosure 2 Technical Evaluation Report on the Seismic Portion of Browns Ferry Nuclear Plant Unit 1 Individual Plant Examination for External Events Project stage: Other ML0611700612006-05-0101 May 2006 Request for Additional Information IPEEE for Severe Accident Vulnerabilities - Submittal of Seismic and Internal Fires IPEEE Reports Project stage: RAI ML0717201972006-10-31031 October 2006 Enclosure 3 Technical Evaluation Report on the High Winds, Floods, Transportation and Other (Hfo) External Events Portion of Browns Ferry Nuclear Plant Unit 1 Individual Plant Examination for External Events Project stage: Other ML0717901962007-06-28028 June 2007 Closeout of Generic Letter 88-20, Supplement 4, Concerning Individual Plant Examinations of External Events for Severe Accident Vulnerabilities Project stage: Other ML0717805172007-07-16016 July 2007 Closeout of Generic Letter 88-20 Concerning Individual Plant Examination (MC5729) Project stage: Other 2006-02-02
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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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July 16, 2007 Mr. William R. Campbell Chief Nuclear Officer and Executive Vice President 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - CLOSEOUT OF GENERIC LETTER 88-20 CONCERNING INDIVIDUAL PLANT EXAMINATION (MC5729)
Dear Mr. Campbell:
This letter is to inform you that the Tennessee Valley Authority (TVA, the licensee) has addressed those actions necessary for the Nuclear Regulatory Commission (NRC) to complete the review of the Browns Ferry Nuclear Plant, Unit 1, response to Generic Letter (GL) 88-20, Individual Plant Examination [IPE] for Severe Accident Vulnerabilities. Over the last 3 years, the NRC staff has conducted reviews of the Unit 1 responses to GL 88-20.
GL 88-20 states that "each existing plant should perform a systematic examination to identify any plant-specific vulnerabilities to severe accidents." The NRC has reviewed TVA's response and concluded that the Unit 1 probabilistic risk assessment (PRA) is capable of identifying plant-specific vulnerabilities, and therefore, TVA has met the intent of GL 88-20 with respect to Unit 1. Given the existing information reviewed, the NRC staff finds that the information provided is adequate to support the closeout of GL 88-20. Closeout of GL 88-20 is not intended as approval or endorsement of any material for purposes other than those associated with meeting the intent of GL 88-20.
On a staff review, unrelated to the IPE submittal, the NRC performed an audit in late January 2006 of the PRA model in support of the extended power uprate (EPU) amendment request.
The NRC identified a number of weaknesses with the PRA model during the audit, primarily associated with the EPU application. These weaknesses were discussed with TVA staff and management at the conclusion of the audit. Until such time as the information needed to allow the NRC to reach a conclusion regarding the quality and technical adequacy of the PRA model is provided, the NRC staff does not believe that the existing Unit 1 PRA model should be used to support time-sensitive requests, such as a notice of enforcement discretion, or an emergency or exigent change to the Technical Specifications.
W. Campbell If you have any questions or concerns, feel free to contact Ms. Eva Brown at (301) 415-2315.
Sincerely,
/RA B. Mozafari for/
Thomas H. Boyce, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No: 50-259
ML071780517 NRC-001 OFFICE LPLII-2/PM RES DRA/APLA LPLII-2/LA LPLII-2/BC NAME EBrown DLew MRubin BClayton TBoyce by memo dated BMozafari for DATE 07/16/07 5/5/05 07/16/07 07/16/07 07/16/07 William R. Campbell, Jr. BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar Mr. Robert G. Jones, General Manager Senior Vice President Browns Ferry Site Operations Nuclear Generation Development Browns Ferry Nuclear Plant and Construction Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Decatur, AL 35609 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Mellen Browns Ferry Unit 1 Project Engineer Mr. Preston D. Swafford Division of Reactor Projects, Branch 6 Senior Vice President U.S. Nuclear Regulatory Commission Nuclear Support 61 Forsyth Street, SW.
Tennessee Valley Authority Suite 23T85 6A Lookout Place Atlanta, GA 30303-8931 1101 Market Street Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing Mr. Walter M. Justice II and Industry Affairs Interim Vice President Tennessee Valley Authority Nuclear Engineering & Technical Services 4X Blue Ridge Tennessee Valley Authority 1101 Market Street 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. William D. Crouch, Manager Licensing and Industry Affairs Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 P.O. Box 2000 Decatur, AL 35609 Decatur, AL 35609 Senior Resident Inspector General Counsel U.S. Nuclear Regulatory Commission Tennessee Valley Authority Browns Ferry Nuclear Plant ET 11A 10833 Shaw Road 400 West Summit Hill Drive Athens, AL 35611-6970 Knoxville, TN 37902 State Health Officer Mr. John C. Fornicola, General Manager Alabama Dept. of Public Health Nuclear Assurance RSA Tower - Administration Tennessee Valley Authority Suite 1552 6A Lookout Place P.O. Box 303017 1101 Market Street Montgomery, AL 36130-3017 Chattanooga, TN 37402-2801 Chairman Mr. Bruce Aukland, Plant Manager Limestone County Commission Browns Ferry Nuclear Plant 310 West Washington Street Tennessee Valley Authority Athens, AL 35611 P.O. Box 2000 Decatur, AL 35609 Mr. Robert H. Bryan, Jr., General Manager Licensing and Industry Affairs Mr. Masoud Bajestani, Vice President Tennessee Valley Authority Browns Ferry Unit 1 Restart 4X Blue Ridge Browns Ferry Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Decatur, AL 35609