Letter Sequence Other |
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Results
Other: CNL-14-032, Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), CNL-14-132, Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Bro, CNL-15-035, Fourth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), CNL-15-159, Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), CNL-16-036, Sixth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), CNL-16-132, Seventh Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, CNL-17-016, Eighth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), CNL-17-107, Ninth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events(Order No. EA-12-049), CNL-18-017, Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, CNL-18-056, Completion of Required Action for NRC Order Number EA-12-049, Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, ML12307A104, ML13064A465, ML13247A284, ML13338A634, ML14323A295, ML15069A358
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MONTHYEARML12307A1042012-10-29029 October 2012 Tennessee Valley Authority - Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML13064A4652013-02-28028 February 2013 Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) Project stage: Other ML13247A2842013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049) Project stage: Other ML13338A6342013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3, TAC Nos.: MF0902, MF0903, and MF0904 Project stage: Other ML13225A5412013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) Project stage: Acceptance Review CNL-14-032, Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-02-28028 February 2014 Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other CNL-14-138, Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.2014-08-28028 August 2014 Request for Relaxation from NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. Project stage: Request CNL-14-132, Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Bro2014-08-28028 August 2014 Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Brown Project stage: Other ML14323A2952014-11-26026 November 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML14281A1982014-12-23023 December 2014 Relaxation of the Schedule Requirements for Order EA-12-049 Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events. Project stage: Approval CNL-15-035, Fourth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML15069A3582015-04-0606 April 2015 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other CNL-15-159, Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other CNL-16-036, Sixth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other CNL-16-132, Seventh Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-08-26026 August 2016 Seventh Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other CNL-17-016, Eighth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2017-02-28028 February 2017 Eighth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other CNL-17-107, Ninth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events(Order No. EA-12-049)2017-08-31031 August 2017 Ninth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events(Order No. EA-12-049) Project stage: Other CNL-18-017, Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-02-23023 February 2018 Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other CNL-18-056, Completion of Required Action for NRC Order Number EA-12-049, Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-05-31031 May 2018 Completion of Required Action for NRC Order Number EA-12-049, Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other 2014-08-28
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Category:Letter type:CNL
MONTHYEARCNL-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-23-030, 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-23-032, 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-23-034, 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-23-018, 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-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance 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-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report 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-23-019, 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 CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-096, 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)2022-09-29029 September 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-22-083, 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).2022-09-13013 September 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-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322022-08-22022 August 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-076, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-01-17
[Table view] Category:Status Report
MONTHYEARCNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-052, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status2022-04-27027 April 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status CNL-21-048, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Miilstone Status Update2021-04-29029 April 2021 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Miilstone Status Update CNL-21-030, Decommissioning Funding Status Report2021-03-25025 March 2021 Decommissioning Funding Status Report CNL-21-032, Watt Bar Nuclear Plant, Units 1 and 2 - Annual Insurance Status Report2021-03-25025 March 2021 Watt Bar Nuclear Plant, Units 1 and 2 - Annual Insurance Status Report CNL-20-088, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2020-10-29029 October 2020 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update CNL-20-020, Annual Insurance Status Report2020-03-20020 March 2020 Annual Insurance Status Report CNL-19-015, Final Update on Progress of Facility Modifications for MSIV Leak Rate2019-05-28028 May 2019 Final Update on Progress of Facility Modifications for MSIV Leak Rate CNL-19-046, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update and Commitment Changes2019-04-29029 April 2019 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update and Commitment Changes CNL-19-135, Tennessee Valley Authority Browns Ferry Nuclear Plant - Ninth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe2018-12-27027 December 2018 Tennessee Valley Authority Browns Ferry Nuclear Plant - Ninth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe . CNL-18-136, Plants: Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2018-12-27027 December 2018 Plants: Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update CNL-18-084, Eighth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-06-27027 June 2018 Eighth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-18-093, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2018-06-22022 June 2018 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update CNL-18-025, Annual Insurance Status Report2018-03-28028 March 2018 Annual Insurance Status Report CNL-18-017, Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-02-23023 February 2018 Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events CNL-17-138, Plant'S Seventh Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2017-12-20020 December 2017 Plant'S Seventh Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-17-107, Ninth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events(Order No. EA-12-049)2017-08-31031 August 2017 Ninth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events(Order No. EA-12-049) CNL-17-077, Sixth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order EA-13-109)2017-06-30030 June 2017 Sixth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order EA-13-109) CNL-17-072, Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update2017-06-27027 June 2017 Hydrologic Engineering Center River Analysis System (HEC-RAS) Project Milestone Status Update CNL-17-031, Annual Insurance Status Report2017-03-30030 March 2017 Annual Insurance Status Report CNL-17-021, Decommissioning Funding Status Report2017-03-30030 March 2017 Decommissioning Funding Status Report CNL-17-016, Eighth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2017-02-28028 February 2017 Eighth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) CNL-16-182, Fifth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2016-12-22022 December 2016 Fifth Six-Month Status Report in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-16-132, Seventh Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-08-26026 August 2016 Seventh Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events CNL-16-098, Fourth Six-Month Status Report in Response to the June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2016-06-30030 June 2016 Fourth Six-Month Status Report in Response to the June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-16-036, Sixth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) CNL-15-254, Third Six-Month Status Report and Phase 1 and Phase 2 Overall Integrated Plan in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation.2015-12-29029 December 2015 Third Six-Month Status Report and Phase 1 and Phase 2 Overall Integrated Plan in Response to the June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation. CNL-15-159, Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) CNL-15-160, Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) CNL-15-082, Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - April 2015 Status Report2015-04-30030 April 2015 Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - April 2015 Status Report CNL-15-036, Fourth Six-Month Status Report in Response to the March 1, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to the March 1, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) CNL-15-035, Fourth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) CNL-15-018, Nuclear Power Group Commercial Grade Dedication Recovery Project - January 2015 Status Report2015-01-30030 January 2015 Nuclear Power Group Commercial Grade Dedication Recovery Project - January 2015 Status Report CNL-14-222, First Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident.2014-12-19019 December 2014 First Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident. CNL-14-195, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - October 2014 Status Report2014-10-31031 October 2014 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - October 2014 Status Report CNL-14-132, Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Bro2014-08-28028 August 2014 Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Brown CNL-14-063, the Tennessee Valley Authority Nuclear Power Group Commercial Grade Dedication Recovery Project - April 2014 Status Report2014-04-30030 April 2014 the Tennessee Valley Authority Nuclear Power Group Commercial Grade Dedication Recovery Project - April 2014 Status Report CNL-14-028, Second Six Month Status Report in Response to Order No. EA-12-051, Spent Fuel Pool Instrumentation2014-02-28028 February 2014 Second Six Month Status Report in Response to Order No. EA-12-051, Spent Fuel Pool Instrumentation CNL-14-032, Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-02-28028 February 2014 Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) CNL-14-008, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - January 2014 Status Report2014-01-31031 January 2014 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - January 2014 Status Report ML13093A3702013-04-0101 April 2013 Annual Insurance Status Report ML12354A1112012-12-14014 December 2012 Generic Letter 96-05 Class D Joint Owners' Group Motor Operated Valves ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1009500642010-04-0101 April 2010 Annual Insurance Status Report ML0909302852009-04-0101 April 2009 Watts Barr (WBN) Nuclear Plants - Insurance Status ML0713400902007-05-12012 May 2007 (BFN) - Completion of Unit 1 Restart Issues ML0712106242007-05-0101 May 2007 (BFN) - Status of Unit 1 Restart Issues, Revision 14 ML0709306892007-04-0202 April 2007 (Bfn), Sequoyah (Sqn), and Watts Bar (WBN) Nuclear Plants - Insurance Status ML0711705732007-03-28028 March 2007 TVA - Decommissioning Funding Status Report 2023-03-29
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-017 February 23, 2018 10 CFR 2.202 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904)
References:
- 1. NRC Order Number EA-12-049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12, 2012 (ML12054A735)
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, Revision 0, dated August 29, 2012 (ML12229A174)
- 3. NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 0, dated August 2012 (ML12242A378)
- 4. Letter from TVA to NRC, Tennessee Valley Authority - Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 29, 2012 (ML12307A104)
- 5. Letter from TVA to NRC, Tennessee Valley Authority (TVA) - Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant, dated February 28, 2013 (ML13064A465)
U.S. Nuclear Regulatory Commission CNL-18-017 Page 2 February 23, 2018
- 6. Letter from TVA to NRC, First Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant, dated August 28, 2013 (ML13247A284)
- 7. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC Nos. MF0902, MF0903, and MF0904), dated December 19, 2013 (ML13225A541)
- 8. Letter from TVA to NRC, Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 28, 2014 (ML14064A240)
- 9. Letter from TVA to NRC, "Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 28, 2014 (ML14248A496)
- 10. Letter from TVA to NRC, Fourth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 27, 2015 (ML15064A162)
- 11. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 (TAC Nos. MF0902, MF0903, MF0904, MF0881, MF0882, and MF0883), dated April 6, 2015 (ML15069A358)
- 12. Letter from TVA to NRC, Fifth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 28, 2015 (ML15240A228)
U.S. Nuclear Regulatory Commission CNL-18-017 Page 3 February 23, 2018
- 13. Letter from TVA to NRC, Sixth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 26, 2016 (ML16063A470)
- 14. Letter from TVA to NRC, Seventh Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 26, 2016 (ML16242A030)
- 15. Letter from TVA to NRC, Eighth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 28, 2017 (ML17060A187)
- 16. Letter from TVA to NRC, Ninth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 31, 2017 (ML17243A299)
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued an order (Reference 1) to Tennessee Valley Authority (TVA). Reference 1 was immediately effective and directed TVA to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Specific requirements are outlined in Attachment 2 of Reference 1.
Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan (OIP) pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document Nuclear Energy Institute (NEI) 12-06 Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the TVA initial status report regarding mitigation strategies. Reference 5 provided the TVA Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3 OIP. Reference 9 provided Revision 1 of the OIP.
U.S. Nuclear Regulatory Commission CNL-18-017 Page4 February 23, 2018 Reference 1 requires submission of a status report at six-month intervals following submittal of the OIP. Reference 3 provides direction regarding the content of the status reports. TVA provided the first six-month status report on August 28, 2013 (Reference 6) . The NRC issued its Interim Staff Evaluation regarding TVA's OIP on December 19, 2013 (Reference 7). TVA has provided the subsequent six-month status reports in References 8 through 10, and 12 through 16. The NRC issued its onsite Audit Report on April 6, 2015 (Reference 11 ).
The purpose of this letter is to provide the tenth six-month status report pursuant to Section IV, Condition C.2, of Reference 1. The enclosed report provides an update of milestone accomplishments since submittal of the ninth six-month status report, including any changes to the compliance method or schedule .
There are no new regulatory commitments contained in this letter. If you have any question regarding this submittal , please contact Mike Oliver at (256) 729-7874.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 23rd day of February 2018.
Respectfully,
~a:X~N-J . W . Shea Vice President, Nuclear Regulatory Affairs & Support Services
Enclosure:
Tennessee Valley Authority Browns Ferry Nuclear Plant's Tenth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) cc (Enclosure) :
NRR Director - NRC Headquarters NRO Director - NRC Headquarters NRC Regional Adm inistrator - Reg ion II NRC Project Manager - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT TENTH SIX-MONTH STATUS REPORT IN RESPONSE TO THE MARCH 12, 2012, COMMISSION ORDER MODIFYING LICENSES WITH REGARD TO REQUIREMENTS FOR MITIGATION STRATEGIES FOR BEYOND-DESIGN-BASIS EXTERNAL EVENTS (ORDER NUMBER EA-12-049) 1 Introduction In response to Order EA-12-049 (Reference 2 in Section 8), Browns Ferry Nuclear Plant (BFN) developed an Overall Integrated Plan (OIP) (Reference 1 in Section 8) documenting the diverse and flexible strategies (FLEX). OIP Revision 1 was submitted with the third six-month status report (Reference 7 in Section 8). This enclosure provides an update of milestone accomplishments since the submittal of the ninth six-month status report (Reference 15 in Section 8) regarding the OIP, including any changes to the compliance method or schedule.
2 Milestone Accomplishments No milestones have been completed since the submittal of the ninth six-month status report regarding the OIP, and milestone accomplishments are current as of February 23, 2018.
3 Milestone Schedule The following provides an update to Attachment 2, Milestones, of OIP Revision 1. The update provides the activity status of each item and whether the target date has changed.
The target completion dates are planning dates subject to change as design and implementation details are developed.
The revised milestone target completion dates do not impact the order implementation date.
CNL-18-017 Enclosure - Page 1 of 15
Revised Target Original Target Activity Activity Completion Date Status Date Submit Overall Integrated Plan February 2013 Complete Submit 6 Month Updates:
Update 1 August 2013 Complete Update 2 February 2014 Complete Update 3 August 2014 Complete Update 4 February 2015 Complete Update 5 August 2015 Complete Update 6 February 2016 Complete Update 7 August 2016 Complete Update 8 February 2017 Complete Update 9 August 2017 Complete Update 10 February 2018 Complete FLEX Strategy Evaluation March 2014 Complete Unit 1 - Validation of connection points for FLEX Phase 2 & 3 via November 2016 Complete walkthrough or demonstration.
(Graded approach)
Unit 2 - Validation of connection points for FLEX Phase 2 & 3 via April 2015 Complete walkthrough or demonstration.
(Graded approach)
Unit 3 - Validation of connection points for FLEX Phase 2 & 3 via April 2016 Complete walkthrough or demonstration.
(Graded approach)
Perform Staffing Analysis January 2015 Complete Modifications:
Modifications Evaluation March 2014 Complete Unit 1 N-1 Walkdown October 2014 Complete Unit 1 Design Engineering November 2014 Complete Unit 1 Implementation Outage November 2016 Complete Unit 2 N-1 Walkdown March 2013 Complete Unit 2 Design Engineering December 2014 Complete Unit 2 Implementation Outage April 2015 Complete Unit 3 N-1 Walkdown March 2014 Complete Unit 3 Design Engineering November 2014 Complete Unit 3 Implementation Outage April 2016 Complete Storage:
Storage Design Engineering August 2014 Complete Storage Implementation April 2015 Complete FLEX Equipment:
Procure On-Site Equipment January 2015 Complete Develop Strategies with RRC February 2015 Complete Identify Off-Site Delivery Station April 2015 Complete Procedures:
CNL-18-017 Enclosure - Page 2 of 15
Revised Target Original Target Activity Activity Completion Date Status Date BWROG issues FSG guidelines April 2014 Complete Create Browns Ferry FSIs April 2015 Complete Create Maintenance Procedures April 2015 Complete Training:
Develop Training Plan December 2014 Complete Implement Training February 2015 Complete Unit 1 FLEX Implementation November 2016 Complete Unit 2 FLEX Implementation April 2015 Complete April 2017 Unit 3 FLEX Implementation April 2016 In-Progress April 2018 Full Site FLEX Implementation November 2016 In-Progress April 2018 Submit Completion Report December 2016 In-Progress May 2018 4 Changes to Compliance Method There has been no changes to the NEI 12-06 compliance method in OIP Revision 1 (Reference 7 in Section 8) that has not provided in previous 6 month updates.
5 Need for Relief/Relaxation and Basis for the Relief/Relaxation TVA requested and received relaxation from full implementation until the completion of the Spring 2017 refueling outage for BFN Unit 2 and the spring 2018 refueling outage for BFN Unit 3 to allow sufficient time to implement a severe accident capable hardened containment wetwell vent (References 8 and 9 in Section 8). The Milestone Schedule (Section 3 and OIP Attachment 2) has been revised to reflect this relaxation.
CNL-18-017 Enclosure - Page 3 of 15
6 Open Items from Overall Integrated Plan and NRC Evaluation The following tables provide a summary of the open items documented in the OIP or the NRC Evaluation and the status of each item.
Overall Integrated Plan Open Status Item OI-1: Flood and seismic re- Open pending NRC review. No further TVA action evaluations pursuant to required.
the 10 CFR 50.54(f) letter The flood and seismic reevaluations pursuant to the of March 12, 2012 are not 10 CFR 50.54(f) letter of March 12, 2012 are complete.
completed and therefore Reference TVA to NRC letter, Flood Hazard Reevaluation not assumed in this Report for Browns Ferry Nuclear Plant, Response to NRC submittal. As the re-Request for Information Pursuant to Title 10 of the Code of evaluations are Federal Regulations 50.54(f) Regarding Recommendations completed, appropriate 2.1, 2.3 and 9.3 of the NearTerm Task Force Review of issues will be entered into Insights from the Fukushima Daiichi Accident, dated the corrective action March 12, 2015; and calculation BFN Expedited Seismic system and addressed.
Evaluation Process (ESEP) HCLPF [High-Confidence-of-Low-Probability-of-Failure] Capacity Evaluations, CDQ0009992014000268 R2, respectively.
OI-2: Liquefaction of haul routes Closed - A liquefaction study for path from Staging Area B for FLEX will be analyzed to the West Access Portal was performed by Amec from Staging Area B to Environment and Infrastructure Inc. and documented in Staging Area A. Also, an their report dated August 19, 2014. The report concluded evaluation will be that liquefaction induced settlement will not exceed 2.5 and conducted of haul routes cracking due to lateral spreading will be insignificant. The from Staging Area D and Staging Areas inside the Protected Area (PA) were Staging Area C to Staging evaluated during construction of ISFSI Pad, and it was Area B. determined that there would be no significant displacement
(< 1.0) due to SSE seismic event (Ref Calc No.
CDQ007920030261, Soil Structure Interaction Analysis for BFN ISFSI Pad ). Therefore, it can be concluded that paths to the staging areas inside the protected area will not be susceptible to any significant deformations that would impact deployment of FLEX Equipment after any severe seismic event.
CNL-18-017 Enclosure - Page 4 of 15
Overall Integrated Plan Open Status Item OI-3: TVA will confirm that they Closed - The duration of the ELAP is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and all have enough fuel onsite permanent plant sources of AC power are considered for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A unavailable. The T/Gs will burn No. 2 Diesel Fuel at a full diesel fuel storage and load consumption rate of 110 gallons/hour per T/G. The refueling plan also has to T/Gs are not provided with their own fuel oil storage tanks.
be developed. Two portable trailer mounted Transcube fuel oil storage tanks with 1200 gallon of No. 2 Diesel Fuel each will be stored in the FESB and available for deployment with the 480V and 4kV generator sets. Each Transcube will be equipped with adequate hose, valves, manual priming pump, and compatible connections necessary to support initial generator operation. One dedicated Transcube for the 480V generator will provide adequate fuel for the first 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of operation, and one shared Transcube between the two 4kV generators will provide adequate fuel for the first 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Three Gorman-Rupp portable diesel engine driven self-priming centrifugal diesel fuel pumps will be stored in the FESB. These pumps can be staged to transfer fuel oil from any of the eight Diesel 7 Day fuel oil storage tanks with a Technical Specifications minimum capacity of >35,280 gallons each or from one of two fuel oil storage tank located on the east side of the plant. The total combined Technical Specification minimum volume for the 8 installed EDGs is 282,240 gallons.
CNL-18-017 Enclosure - Page 5 of 15
Overall Integrated Plan Open Status Item OI-4: BFN will evaluate SRV Open pending NRC review. No further TVA action qualification against the required.
predicted containment Based on review of Environmental Qualification (EQ) response with FLEX BFNEQSOL009 D4 for the SRV solenoid, testing results implementation to ensure indicate that the SRV solenoid will actuate sufficiently with there will be sufficient the following DC bus voltage and pneumatic pressure DC bus voltage and supply:
pneumatic pressure to operate the SRVs Drywell Temperature < 340°F throughout Phase 1 and Pressure at least 45 psig > containment pressure Phase 2.
DC voltage > 105 VDC MAAP analysis calculation NDN0009992014000242 provides accident progression timelines for cases that predict peak Drywell temperatures to be less than 317°F, which is well within qualifications (340°F).
TVA calculation MDQ0009992014000239 provides sizing and requirements for the alternate nitrogen system to ensure adequate 100 psig pneumatic supply is available under Beyond Design Basis External Event (BDBEE) conditions. DCNs 71387, 70810, & 71386 (for Units 1, 2 &
3, respectively) have been completed that provides an alternate nitrogen supply to each of the two Drywell control air headers on each unit.
CNL-18-017 Enclosure - Page 6 of 15
Overall Integrated Plan Open Status Item OI-5: A reference source for the Closed - 1/2/3-FSI-6C, Key Instrument Readings During plant operators will be Loss of DC Power, are new FLEX procedures that have developed that provides been developed to provide guidance during a BDBEE with approaches to obtaining the loss of instrument power. A 3-Tiered approach to FLEX necessary instrument measurement strategies as follows (all three tiers may not readings to support the be applicable for every measurement to be obtained):
implementation of the TIER 1: Provide power to primary instruments (i.e.,
coping strategy (NE 12-transmitter or RTD) and measure at locations directly 06, Section 3.2.1.1 0).
accessible from the Control Bay. These locations are the This reference source Auxiliary Instrument Rooms or Electric Board Rooms.
should include control Primary instrument wiring would be lifted and handheld room and non-control devices connected which provide both power and room readouts and should measuring capabilities.
also provide guidance on how and where to TIER 2: Provide power to primary instruments and measure key instrument measure at Reactor Building locations. These locations are readings at containment within Secondary Containment. Primary instrument wiring penetrations, where would be lifted and handheld devices connected which applicable, using a provide both power and measuring capabilities.
portable instrument (e.g., TIER 3: Provide alternate instruments to measure the a Fluke meter). Such a desired parameters as close to the process as is practical.
resource could be provided as an attachment to the plant procedures/guidance.
Guidance will include critical actions to perform until alternate indications can be connected and on how to control critical equipment without associated control power.
CNL-18-017 Enclosure - Page 7 of 15
Overall Integrated Plan Open Status Item OI-6: Validate the preliminary Closed - Calculation EDQ0009992013000202, 250V DC Battery studies that were Unit Batteries 1, 2 & 3 Evaluation for BDBEE Extended performed to ensure Loss of AC Power (ELAP), documents the load calculation appropriate battery life will for the 250 volt unit batteries. This load study strips be available with regards nonessential loads to allow BFN Units 1, 2, & 3 to last 12 to the overall FLEX hours.
strategies. Ensure that DCN 71470 is the modification that procures fans for buildup of hydrogen is installation in the battery rooms during a beyond design considered and mitigated basis event to account for the hydrogen production during appropriately.
battery off gassing during battery charging.
Flex procedure 0-FSI-4A, Control Bay/Reactor Building Lighting And Ventilation During ELAP, installs the fans during a beyond design basis event in the battery rooms on elevation 1C (593) in the control bay.
OI-7: BFN will take actions as Open pending NRC review. No further TVA action necessary to assure RCIC required.
can operate at elevated In order to ensure continued operation with high RCIC room temperatures.
temperatures, 2 Emergency Operating Instruction (EOI) appendices are directed to be performed by the Station Blackout (SBO) flowchart. EOI Appendix-16K is performed to bypass the RCIC area high temperature isolations.
EOI Appendix-20M is performed, and it contains steps to disable the RCIC electronic governor and control flow with the RCIC trip/throttle valve, FCV-71-9. The electronic governor is susceptible to failure at room temperatures above 150°F, which occurs at approximately 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> into the event. These appendices are performed as soon as the SBO flowchart is entered. In order to ensure continued operation with high suppression pool temperatures, DCN 71329 included a connection point from the Emergency Equipment Cooling Water (EECW) header, which will supply cooling water to the RCIC oil cooler. This allows the normal cooling water supply (suppression pool) to be valved out and cooler water from the FLEX pumps via the EECW header to be valved in.
CNL-18-017 Enclosure - Page 8 of 15
Overall Integrated Plan Open Status Item OI-8: Perform modifications, as Closed - Reactor Core Isolation Cooling (RCIC) system has necessary, to ensure that been evaluated using the Expedited Seismic Evaluation RCIC is seismically Process (ESEP). Calculation CDQ0009992014000268, robust. BFN Expedited Seismic Evaluation Process (ESEP) HCLPF Capacity Evaluations, has determined that the RCIC system is seismically rugged and complies with the requirements of BFN FLEX Strategies. Based on the conservative evaluation documented in this calculation, BFN Units 1, 2, & 3 meet all seismic capacity requirements for ESEP. The ESEP review performed for BFN Units 1, 2,
& 3 was summarized in AREVA Inc. Document No. 51-9230498 Rev. 1, Expedited Seismic Evaluation Process (ESEP) Summary Report for Browns Ferry Nuclear Plant, dated December 10, 2014.
OI-9: Develop and perform the Closed - DCN 71329 installed connection points in the B design modifications EECW pump room, D Residual Heat Removal Service identified in the FLEX Water (RHRSW) pump room, and the B RHRSW pump Strategy document to room for connection of the portable FLEX pump systems.
permit the timely and safe This DCN also established a connection point and isolation connection of the FLEX for the RCIC oil coolers. FLEX Support Instructions (FSIs) and NSRC equipment direct the connections and operation of FLEX pump during the adverse systems.
conditions encountered DCN 71454 installed a pump deployment path from the during these beyond FESB to the new FLEX Pump Deployment pads at the design basis events.
Intake Pump Station forebay. 0-FSI-6A, Damage Assessment, (Ref. 13n) provides guidance during a BDBEE. Steps are directed to identify issues that will impede deployment of equipment and implementation of FLEX strategies.
OI-10: Design and construct a Closed - Flex Mitigation System Design Criteria Flexible Equipment BFN-50-7360 identifies the design attributes and storage Storage Building, located requirements for the FESB.
above the probable DCN 70745 implemented the design of the building which maximum flood level, complies with the Flex Design Criteria.
which is adequately protected from the hazards listed in Section 1 CNL-18-017 Enclosure - Page 9 of 15
Overall Integrated Plan Open Status Item OI-11: Modify currently installed Closed - Proposed modifications to the existing Hardened hardened wetwell vent to Wet Well Vent (HWWV) to comply with NRC Order install backup pneumatic EA-13-109 includes the design for a backup pneumatic supply or provided supply for operation of the Hardened Containment Vent procedural guidance for System (HCVS) valves (FCV-064-0221 & 0222) during an manual operation, to allow BDBEE. However, compliance with Order EA-13-109 does use within current design not support implementation schedule of the FLEX Order limits. EA-12-049. Based on the difference in implementation schedules between Orders EA-13-109 and EA-12-049, BFN has requested and received a relaxation for full compliance with Order EA-12-049.
Valves FCV-064-0221 and -0222 have the ability to be manually operated based on the design implemented under GL 89-16, Installation of a Hardened Wetwell Vent. The event in which operation of the HCVS valves would be needed is a BDBEE. Operations would be performing actions as needed to maintain the plant in a safe condition, and operation of components to vent containment would be performed in accordance with procedure 2-EOI Appendix 13, Emergency Venting Primary Containment. Since the plant is performing mitigation strategies and fuel damage has not occurred, environmental conditions in the area would allow access to the valves for operation.
OI-12: Design and install the Closed - The design and implementation of the Spent Fuel modifications required by Pool Level Instrumentation was completed in accordance Order EA-12-051 for with Engineering Change Packages DCN 71159, DCN enhancing the SFP. 71160, and DCN 71161 for BFN Units 1, 2, & 3, respectively. The applicable codes, standards, regulatory requirements, and procedures are spelled out within the stated DCNs.
CNL-18-017 Enclosure - Page 10 of 15
Overall Integrated Plan Open Status Item OI-13: Determine the design Closed - BFN has two Ford F550 trucks equipped with specifications for FLEX scraper blades and winches for debris removal and one equipment yet to be compact track loader CAT 299D for debris removal.
ordered, such as the six DCN 71470 provided a 480v supply and connection Portable Ventilation Fans, strategy to portable lighting and ventilation during a the Mobil Water BDBEE.
Purification Unit, debris 20 Smithlight Battery operated LED work lights were removal equipment for the provided in the DCN.
FLEX Equipment Haul path and piping for the A total of 12 fans were provided in the DCN and will be FLEX low pressure deployed and operated using 0-FSI-4A in the Control Bay.
pumps.
Fan Quantity TA16-5000 3 Coppus Vano 3 175CV Coppus Vano 2 250CV Pedestal Fan 3 30 inch Barrel Fan 1 OI-14: Deployment strategies Closed - DCN 70745 (Site Bunker Building), DCN 71454 and deployment routes will (Install Deployment Roads and Pump Landings),
be assessed for impact DCN 71405 (Stage 4kv Diesels for Fukushima Event and due to identified hazards Provide Connection Points), and DCN 71470 (Stage 480v and guidance power supply and support equipment to charge the Unit developed/provided to Battery Chargers) have ensured sufficient area is available ensure that 1) sufficient for deployment. Additionally, all deployment accessories area is available for such as pumps, ramps, winches, and other transfer deployment, 2) haul paths assemblies such as equipment trailers, as appropriate, remain accessible without have been assessed and are included to ensure OIP interference from outage timeframes are met.
equipment during refueling Haul paths and deployment pads will be observed daily outages and 3) during Nuclear Security rounds to ensure both paths and deployment locations for pads are accessible without interference.
the pumps including ramps, winches or other transfer assemblies as appropriate to deploy all pumps and hoses within the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Phase 1 coping interval.
CNL-18-017 Enclosure - Page 11 of 15
OI-15: Detailed staffing studies Closed - Browns Ferry Nuclear Plant has completed a based on the Phase 2 ELAP ERO Staffing Analysis Report in accordance procedures/guidance with NEI 12-01. The analysis concluded the on-shift ERO developed. staffing present for the no-site access 6-hour time period is sufficient to perform the FSI, EOI, and emergency response tasks.
OI-16. Validation of the time lines Closed - Validation of the time lines for the various for the various strategies. strategies was performed in accordance with 0-FSI-8B, FLEX Strategy Validation Process (Ref. 13s). This FSI utilized NEI 14-01 FLEX Validation Process as a reference.
OI-17: Browns Ferry Nuclear Closed - BFN has utilized the industry-developed guidance Plant (BFN) will utilize the from the BWROG, EPRI, and NEI Task team to develop industry developed site specific procedures that addressed the criteria in guidance from the Owners NEI 12-06 (Ref. 6). Procedure 0-AOI-57-1A, Loss Of Groups, EPRI and NEI Offsite Power (161 and 500 KV)/Station Blackout, the Task team to develop site EOI appendices, and the FSIs support the existing specific procedures or symptom-based command and control strategies in the guidelines to address the current EOIs.
criteria in NEI 12-06.
These procedures and/or guidelines will support the existing symptom based command and control strategies in the current EOIs.
OI-18: New training of general Closed - Procedure TRN-30, Radiological Emergency station staff and EP will be Preparedness Training, requires the Emergency performed prior to the first Preparedness responders to complete INPO Generic Basic BFN unit design Flex Training (NANTEL 00002382), and, for persons implementation outage. assigned key positions, the INPO Generic Advanced Flex These programs and Training (NANTEL 00002385). Training requirements by controls will be position are listed in TRN-30, Attachment 3. This TRN was implemented in developed in accordance with the Systematic Approach to accordance with the Training (SAT).
Systematic Approach to Additional overview training was developed for Training.
Maintenance personnel that may be asked to deploy and connect equipment in various scenarios. This training was developed using the SAT process and approved by the respective Maintenance training oversight committees. The Technical training organizations also documented Training Needs Analysis for their groups with conclusions being that Nantel Basic FLEX overview is sufficient at this time.
CNL-18-017 Enclosure - Page 12 of 15
OI-19: TVA will establish a Closed - A contract has been established between TVA and contract with the Strategic the SAFER team, AREVA Inc. Document No. 51-9233061 Alliance for FLEX Rev. 0, Browns Ferry Nuclear Plant SAFER Response Emergency Response Plan. Two off-site local staging areas have been identified, (SAFER) team. A local and one onsite staging area has been identified. The assembly area must also onsite staging area (Staging Area B) is located in the be established by SAFER Northeast corner of the Owner Controlled Area at the and TVA for equipment Facility and Vehicles Maintenance Shop. The two off-site moved from the National staging areas are TVA Helicopter Operations at the SAFER Response Center Northwest Alabama Regional Airport (Staging Area C) in (NSRC) to BFN. Muscle Shoals, Alabama, and at the Pryor Field Regional Airport (Staging Area D) in Decatur, Alabama.
OI-20: Evaluate different Closed - New procedures 1/2/3-EOI Appendix-20K, strategies to allow removal Suppression Pool Pump Down Using RCIC (FLEX), utilize of water from the RCIC in test mode to pump the torus to the Condensate Suppression Pool. Storage Tanks. The required valves are dc-powered and Determine if any will be available to be operated from the Main Control modifications are required Room.
and what strategies are deemed feasible.
OI-21: Abnormal operating Closed FSI-6A, Damage Assessment, is a new FLEX procedure, AOI-100-9, procedure that has been developed to provide guidance Turbine Building Internal during a BDBEE. Steps are directed to identify issues that Flooding, provides the will impede deployment of equipment and implementation symptoms and operator of FLEX strategies. Building assessments are performed actions to be taken for this and information provided to the FLEX Response SRO, Shift condition. During Manager, or Site Emergency Director to make decisions development of based on results. Internal plant flooding will be identified, procedures to support and alternate routes are available for performance of these FLEX strategies, adequate strategies. Doors are verified unlocked and available to guidance will be given to allow access to the Control Bay and Reactor Buildings via operators to ensure their Electric Board Rooms on elevations 621 and 593.
travel paths avoid these areas.
7 Potential Draft Safety Evaluation Impacts There are no potential impacts to the Draft Safety Evaluation identified at this time.
CNL-18-017 Enclosure - Page 13 of 15
8 References The following references support the updates to the OIP described in this attachment.
- 1. Letter from TVA to NRC, Tennessee Valley Authority (TVA) - Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant, dated February 28, 2013 (ML13064A465)
- 2. NRC Order Number EA-12-049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, dated March 12, 2012 (ML12054A735)
- 3. NEI 12-06 Revision 0, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated August 21, 2012 (ML12242A378)
- 4. Letter from TVA to NRC, First Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant, dated August 28, 2013 (ML13247A284)
- 5. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC Nos. MF0902, MF0903, and MF0904), dated December 19, 2013 (ML13225A541)
- 6. Letter from TVA to NRC, Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 28, 2014 (ML14064A240)
- 7. Letter from TVA to NRC, "Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 28, 2014 (ML14248A496)
- 8. Letter from TVA to NRC, Request for Relaxation from NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated August 28, 2014 (ML14247A447)
- 9. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 2 and 3 - Relaxation of the Schedule Requirements for Order EA-12-049 Issuance of Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (TAC Nos. MF0903 and MF0904), dated December 23, 2014 (ML14281A198)
- 10. Letter from TVA to NRC, "Fourth Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 27, 2015 (ML15064A162)
CNL-18-017 Enclosure - Page 14 of 15
- 11. Letter from TVA to NRC, Fifth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 28, 2015 (ML15240A228)
- 12. Letter from TVA to NRC, Sixth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 26, 2016 (ML16063A470)
- 13. Letter from TVA to NRC, Seventh Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated August 26, 2016 (ML160242A030)
- 14. Letter from TVA to NRC, Eighth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), dated February 28, 2017 (ML17060A187)
- 15. Letter from TVA to NRC, Ninth Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904),
dated August 31, 2017 (ML17243A299)
CNL-18-017 Enclosure - Page 15 of 15