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Category:Letter type:CNL
MONTHYEARCNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology2024-01-22022 January 2024 Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology 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 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 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 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 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 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 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 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio 2024-09-24
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-251 January 5, 2016 10 CFR 50.4 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296
Subject:
NRC Confirmatory Order EA-14-005 - Completion of Actions Reference : Confirmatory Order (NRC Inspection Report 05000259/2013005, 05000260/2013005, and 05000296/2013005), dated May 1, 2014 The above referenced Confirmatory Order from the Nuclear Regulatory Commission (NRC) to Tennessee Valley Authority (TVA) details 20 TVA fleet and Browns Ferry Nuclear Plant (BFN)-specific actions related to the violation of Title 10 of the Code of Federal Regulations (CFR) 50.9, Completeness and Accuracy of Information , and related to the violation of 10 CFR 50.90, Application for Amendment of License , Construction Permit, or Early Site Permit.
The purpose of this letter is to provide TVA's basis for concluding that the Order has been satisfied. TVA entered the Confirmatory Order actions into the corrective action program as condition reports (CRs) and completed the associated CR cause analyses, corrective and preventative actions, enhancements, and effectiveness reviews. Based on the completion of these activities, TVA has determined that the Confirmatory Order has been satisfied. A summary of the actions taken is provided below.
The actions related to the violation of 10 CFR 50.9 required by the Confirmatory Order have been completed and included:
- 1) Fleet actions to develop and implement a fleet-wide procedure governing the preparation of information intended to support licensing submittals to the NRC; and,
- 2) BFN-specific actions to:
- a. Implement an Integrated Completeness and Accuracy Review Evaluation Board to provide pre-submittal reviews of correspond ence and supporting documentation for BFN submittals to the NRC; and,
- b. Benchmark industry best practices in the area of 10 CFR 50.9 compliance in the preparation and validation of NRC submittals.
U.S. Nuclear Regulatory Commission CNL-15-251 Page 3 January 5, 2016 The actions related to the violation of 10 CFR 50.90 required by the Confirmatory Order have been completed and included :
- 1) Fleet actions to :
- a. Benchmark industry methodologies used to maintain Licensing Bases Documents for incorporation consideration ;
- b. Develop and implement a fleet-wide Licensing Compliance Review procedure ,
including incorporation of the new procedure into existing procedures governing procedure adm inistration;
- c. Revise the TVA Nuclear Power Group administrative and techn ical procedures to incorporate the new Licensing Compliance Review procedure; and ,
- d. Convert the Final Safety Analysis Report Management procedure from a department-level procedure to a nuclear fleet-level procedure.
- 2) BFN-specific actions to :
- a. Perform a snapshot self-assessment to verify if commitments are being implemented accurately;
- b. Close the Corrective Action Program Fundamental Problem identified as part of TVA's response to the 2013 NRC Inspection Procedure 95003 inspection ;
- c. Implement interim actions until the Licensing Compliance Review procedure became active;
- d. Perform detailed reviews of Procedure Upgrade Project procedure revisions to ensure licensing basis information is identified ;
- e. Train Engineering , Licensing , and Licensed Operators regarding scope and hierarchy of licensing basis documents and lessons learned from EA-14-005;
- f. Implement the utilization of a second reviewer for commitments ;
- g. Review a sample of facility changes within the last ten years , based on risk and complexity , to determine whether the changes were appropriately incorporated into the licensing basis documents;
- h. Review a sample of facility changes within the last three years and outside the 10 CFR 50.59 process, based on risk and complexity, to determine whether the changes were appropriately incorporated into the licensing basis documents; and ,
- i. Make a presentation to the Regulatory Issue Working Group and the Regulatory Utility Group regarding the circumstances of these violations and the importance of effective management of the current licensing basis and complete and accurate communications with the NRC .
The Order also required several independent reviews , which have been completed :
- 1) An independent entity assessment of the completeness and adequacy of the 10 CFR 50.9 and 10 CFR 50.90 Root Cause Analysis reports to assess the completeness and adequacy of the root/contributing causes , extent of cause , extent of condition , and corrective actions to prevent recu rrence/corrective actions with consideration of assessment recommendations for implementation;
- 2) An independent effectiveness review of the 10 CFR 50.9 and 10 CFR 50.90 Root Cause Analyses corrective actions; and,
- 3) An independent reevaluation of Operations minimum shift staffing .
U.S. Nuclear Regulatory Commission CNL-15-251 Page 3 January 5, 2016 With the submittal of this letter, all actions required by NRC Confirmatory Order EA-14-005 have been completed . There are no new regulatory commitments contained in this letter. If you have any questions regarding this response , please contact J. L. Pau l, BFN Nuclear Site Licensing Manager, at (256) 729-2636.
cc: NRC Regional Administrato r- Region II NRC Senior Resident Inspector- Browns Ferry Nuclear Plant
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-251 January 5, 2016 10 CFR 50.4 ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington , D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296
Subject:
NRC Confirmatory Order EA-14-005 - Completion of Actions Reference : Confirmatory Order (NRC Inspection Report 05000259/2013005, 05000260/2013005, and 05000296/2013005), dated May 1, 2014 The above referenced Confirmatory Order from the Nuclear Regulatory Commission (NRC) to Tennessee Valley Authority (TVA) details 20 TVA fleet and Browns Ferry Nuclear Plant (BFN)-specific actions related to the violation of Title 10 of the Code of Federal Regulations (CFR) 50.9, Completeness and Accuracy of Information , and related to the violation of 10 CFR 50.90, Application for Amendment of License , Construction Permit, or Early Site Permit.
The purpose of this letter is to provide TVA's basis for concluding that the Order has been satisfied. TVA entered the Confirmatory Order actions into the corrective action program as condition reports (CRs) and completed the associated CR cause analyses, corrective and preventative actions, enhancements, and effectiveness reviews. Based on the completion of these activities, TVA has determined that the Confirmatory Order has been satisfied. A summary of the actions taken is provided below.
The actions related to the violation of 10 CFR 50.9 required by the Confirmatory Order have been completed and included:
- 1) Fleet actions to develop and implement a fleet-wide procedure governing the preparation of information intended to support licensing submittals to the NRC; and,
- 2) BFN-specific actions to:
- a. Implement an Integrated Completeness and Accuracy Review Evaluation Board to provide pre-submittal reviews of correspond ence and supporting documentation for BFN submittals to the NRC; and,
- b. Benchmark industry best practices in the area of 10 CFR 50.9 compliance in the preparation and validation of NRC submittals.
U.S. Nuclear Regulatory Commission CNL-15-251 Page 3 January 5, 2016 The actions related to the violation of 10 CFR 50.90 required by the Confirmatory Order have been completed and included :
- 1) Fleet actions to :
- a. Benchmark industry methodologies used to maintain Licensing Bases Documents for incorporation consideration ;
- b. Develop and implement a fleet-wide Licensing Compliance Review procedure ,
including incorporation of the new procedure into existing procedures governing procedure adm inistration;
- c. Revise the TVA Nuclear Power Group administrative and techn ical procedures to incorporate the new Licensing Compliance Review procedure; and ,
- d. Convert the Final Safety Analysis Report Management procedure from a department-level procedure to a nuclear fleet-level procedure.
- 2) BFN-specific actions to :
- a. Perform a snapshot self-assessment to verify if commitments are being implemented accurately;
- b. Close the Corrective Action Program Fundamental Problem identified as part of TVA's response to the 2013 NRC Inspection Procedure 95003 inspection ;
- c. Implement interim actions until the Licensing Compliance Review procedure became active;
- d. Perform detailed reviews of Procedure Upgrade Project procedure revisions to ensure licensing basis information is identified ;
- e. Train Engineering , Licensing , and Licensed Operators regarding scope and hierarchy of licensing basis documents and lessons learned from EA-14-005;
- f. Implement the utilization of a second reviewer for commitments ;
- g. Review a sample of facility changes within the last ten years , based on risk and complexity , to determine whether the changes were appropriately incorporated into the licensing basis documents;
- h. Review a sample of facility changes within the last three years and outside the 10 CFR 50.59 process, based on risk and complexity, to determine whether the changes were appropriately incorporated into the licensing basis documents; and ,
- i. Make a presentation to the Regulatory Issue Working Group and the Regulatory Utility Group regarding the circumstances of these violations and the importance of effective management of the current licensing basis and complete and accurate communications with the NRC .
The Order also required several independent reviews , which have been completed :
- 1) An independent entity assessment of the completeness and adequacy of the 10 CFR 50.9 and 10 CFR 50.90 Root Cause Analysis reports to assess the completeness and adequacy of the root/contributing causes , extent of cause , extent of condition , and corrective actions to prevent recu rrence/corrective actions with consideration of assessment recommendations for implementation;
- 2) An independent effectiveness review of the 10 CFR 50.9 and 10 CFR 50.90 Root Cause Analyses corrective actions; and,
- 3) An independent reevaluation of Operations minimum shift staffing .
U.S. Nuclear Regulatory Commission CNL-15-251 Page 3 January 5, 2016 With the submittal of this letter, all actions required by NRC Confirmatory Order EA-14-005 have been completed . There are no new regulatory commitments contained in this letter. If you have any questions regarding this response , please contact J. L. Pau l, BFN Nuclear Site Licensing Manager, at (256) 729-2636.
cc: NRC Regional Administrato r- Region II NRC Senior Resident Inspector- Browns Ferry Nuclear Plant