Letter Sequence Other |
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Results
Other: 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., 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), 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 Conditions, CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, 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 Conditions, CNL-19-003, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions, 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 Severe, ML16244A762, ML18038B606
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MONTHYEARCNL-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. Project stage: Other ML16244A7622016-09-0606 September 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) Project stage: Other 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) Project stage: Other 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 Project stage: Other ML18038B6062018-02-21021 February 2018 Report for the Audit of Licensee Responses to Interim Staff Evaluations Open Items Related to NRC Order EA-13-109 Project stage: Other CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-31031 May 2018 Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Project stage: Other 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 Project stage: Other 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 . Project stage: Other CNL-19-003, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-01-22022 January 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Project stage: Other CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2019-06-0707 June 2019 Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Project stage: Other ML19329E3192020-01-0202 January 2020 SE Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4540, MF4541 and MF4542; EPID No. L-2014-JLD-0044) Project stage: Acceptance Review 2018-02-21
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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-17-077 June 30, 2017 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, and DPR
-68 NRC Docket Nos. 50
-259, 50-260, and 50
-296
Subject:
Tennessee Valley Authority Browns Ferry Nuclear Plant
's 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 Number EA-13-109)
References:
- 1. NRC Order Number EA 109, "Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013 (ML13143A321)
- 2. NRC Interim Staff Guidance JLD-ISG-2013-02, "Compliance with Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 0, dated November 14, 2013 (ML13304B836)
- 3. NEI 13-02, "Industry Guidance for Compliance with Order EA 109, BWR Mark I & II Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 1, dated April 23, 2015 (ML15113B318)
- 4. Letter from TVA to NRC, "Tennessee Valley Authority's Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident (Order Number EA 109)," dated June 30, 2014 (ML14181B169)
U.S. Nuclear Regulatory Commission CNL-17-077 Page 2 June 30, 2017 5. Letter from TVA to NRC, "Tennessee Valley Authority's Browns Ferry Nuclear Plant First 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 Number EA 109)," dated December 19, 2014 (ML14353A428)
- 6. 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 Phase 1 of Order EA 109 (Severe Accident Capable Hardened Vents) (TAC Nos. MF4540, MF4541 and MF4542)," dated February 11, 2015 (ML14356A362)
- 7. NRC Interim Staff Guidance JLD-ISG-2015-01, "Compliance with Phase 2 of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions," Revision 0, dated April 29, 2015 (ML15104A118)
- 8. Letter from TVA to NRC, "Tennessee Valley Authority's Browns Ferry Nuclear Plant Second 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 Number EA 109)," dated June 29, 2015 (ML15181A338)
- 9. Letter from TVA to NRC, "Tennessee Valley Authority's Browns Ferry Nuclear Plant 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 Under Severe Accident Conditions (Order Number EA-13-109)," dated December 29, 2015 (ML15365A554)
- 10. Letter from TVA to NRC "Tennessee Valley Authority's Browns Ferry Nuclear Plant 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 (Order Number EA 109)," dated June 30, 2016 (ML16182A517) 11. Letter from TVA to NRC "Tennessee Valley Authority Browns Ferry Nuclear Plant's 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 (Order Number EA 109),"dated December 22, 2016 (ML16357A577) On June 6, 2013, the Nuclear Regulatory Commission (NRC) issued an Order (Reference 1) to Tennessee Valley Authority (TVA). Reference 1 was immediately effective and directed TVA to install a reliable hardened venting capability for instances of pre-core damage and under severe accident conditions, including those involving a breach of the reactor vessel by molten core debris. Specific requirements are outlined in Attachment 2 of Reference
- 1.
U.S. Nuclear Regulatory Commission CNL-17-077 Page 3 June 30, 2017 Reference 1 required submission of a Phase 1 and Phase 2 Overall Integrated Plan (OIP) pursuant to Section IV, Condition D for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. References 2 and 7 endorse industry guidance document Nuclear Energy Institute (NEI) 13-02 , Revision 1 (Reference
- 3) with clarifications and exceptions identified in References 2 and 7. Reference 3 provides direction regarding the content of the Phase 1 and Phase 2 OIPs and includes guidance for combining the OIPs. Reference 4 provided TVA's Phase 1 OIP. The NRC issued its Interim Staff Evaluation relating to the BFN Phase 1 OIP on February 11 , 2015 (Reference 6). Reference 1 also requires submission of status reports at six-month intervals following submittal of the OIP. Reference 3 provides direction regarding the content of the status reports. TVA submitted the first six-month status report on December 19, 2014 (Reference 5), the second six-month status report on June 29, 2015 (Reference 8), the third six-month status report on December 29, 2015 (Reference 9), the fourth six-month status report on June 30, 2016 (Reference 10), and the fifth six-month status report on December 22, 2016 (Reference 11). The purpose of this letter is to provide the combined Phase 1 and Phase 2 OIP six-month status report pursuant to Section IV, Condition D of Reference 1, which delineates progress made in implementing the requirements of Reference
- 1. The Enclosure provides an update of milestone accomplishments since submittal of the Phase 1 OIP (Reference
- 4) with previous updates (References 5, 8, 9, 10 and 11) and the initial Phase 2 OIP (Reference
- 9) with previous updates (References 1 O and 11 ), including any changes to the compliance method, schedule, need for relief, and the basis for these changes. There are no new regulatory commitments resulting from this submittal.
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 30th day of June 2017. Respectfully, J. W. Shea Vice President, Nuclear Regulatory Affairs & Support Services Enclosure cc: See Page 4 U.S. Nuclear Regulatory Commission CNL-17-077 Page 4 June 30, 2017
Enclosure:
Tennessee Valley Authority Browns Ferry Nuclear Plant's Sixth Six-Month Status Report for the Implementation of Order EA 109, "Issuance of Order to Modify Licenses With Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" cc (w/Enclosure):
NRR Director - NRC Headquarters NRO Director - NRC Headquarters NRR JLD Director - NRC Headquarters NRC Regional Administrator - Region II NRR Project Manager - Browns Ferry Nuclear Plant NRR JLD Project Manager - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
CNL-17-077 E-1 ENCLOSURE Tennessee Valley Authority Browns Ferry Nuclear Plant's Sixth Six-Month Status Report for the Implementation of Order EA 109, "Issuance of Order to Modify Licenses With Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions" 1 Introduction Browns Ferry Nuclear Plant (BFN) developed an Overall Integrated Plan (Reference 1 in Section 8) documenting the installation of a Hardened Containment Vent System (HCVS) that provides a reliable hardened venting capability for instances of pre-core damage and under severe accident conditions, including those involving a breach of the reactor vessel by molten core debris, in response to Reference 2.
Updates of milestone accomplishments will be based on the combined Phase 1 and 2 Overall Integrated Plan dated December 29, 2015. BFN developed an updated and combined Phase 1 and 2 Overall Integrated Plan (Reference 7 in Section 8) documenting: 1. The installation of a Hardened Containment Vent System (HCVS) that provides a reliable hardened venting capability for instances of pre-core damage and under severe accident conditions, including those involving a breach of the reactor vessel by molten core debris, in response to Reference 2.
- 2. An alternative venting strategy that makes it unlikely that a drywell vent is needed to protect the containment from overpressure related failure under severe accident conditions, including those that involve a breach of the reactor vessel by molten core debris, in response to Reference 2 This enclosure provides an update of milestone accomplishments since submittal of the combined Phase 1 and 2 Overall Integrated Plan and previous update (Reference
- 10) including any changes to the compliance method, schedule, or need for relief/relaxation
and the basis, if any.
2 Milestone Accomplishments The following milestone(s) have been completed since the previous update (Reference 10).
The status is current as of June 1, 2017.
Phase 1 Unit 2 Design Engineering on
-site/Complete Phase 1 Unit 2 Implementation Outage Phase 1 Unit 2 Walk Through Demonstration/Functional Test Phase 1 Unit 3 Design Engineering On
-site/Complete Phase 2 Modifications Evaluation 3 Milestone Schedule Status The following provides an update to Part 5 of the combined Phase 1 and 2 Overall Integrated Plan. It provides the activity status of each item and whether the expected completion date has changed. These 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-17-077 E-2 Milestone Target Completion Date Activity Status Comments {Include date changes in this column} Phase 1 and 2 HCVS Milestone Table Submit Overall Integrated Plan Jun e 2014 Complete Submit 6 Month Updates:
Update 1 December 2014 Complete Update 2 Jun e 2015 Complete Update 3 [Simultaneous with Phase 2 OIP] December 2015 Complete Update 4 Jun e 2016 Complete Update 5 December 2016 Complete Update 6 Jun e 2017 Complete with this submittal Update 7 December 2017 Not Started Update 8 June 2018 Not Started Update 9 December 2018 Not Started
CNL-17-077 E-3 Phase 1 Specific Milestones Phase 1 Modifications:
Hold preliminary/conceptual design meeting November 2014 Complete Modifications Evaluation November 2015 Complete Unit 1 Design Engineering On
-site/Complete April 2016 Complete June 2016 Unit 1 Implementation Outage November 2016 Complete Unit 1 Walk Through Demonstration/Functional Test November 2016 Complete Unit 2 Design Engineering On
-site/Complete June 2016 Complete December 2016 Unit 2 Implementation Outage March 2017 Complete Unit 2 Walk Through Demonstration/Functional Test April 2017 Complete Unit 3 Design Engineering On
-site/Complete July 2017 Complete Unit 3 Implementation Outage March 2018 Not Started Unit 3 Walk Through Demonstration/Functional Test April 2018 Not Started Phase 1 Procedure Changes Active Operations Procedure Changes Developed July 2016 Complete Site Specific Maintenance Procedure Developed July 2016 Complete Procedure Changes Active November 2016 Complete Phase 1 Training:
Training Complete September 2016 Complete CNL-17-077 E-4 Phase 1 Completion Unit 1 HCVS Implementation December 2016 Complete Unit 2 HCVS Implementation April 2017 Complete Unit 3 HCVS Implementation March 2018 Not Started Full Site HCVS Implementation March 2018 Not Started Submit Completion Report [60 days after full site compliance]
June 2018 Not Started Phase 2 Specific Milestones Phase 2 Modifications:
Hold preliminary/conceptual design meeting January 2017 Complete Modifications Evaluation April 2017 Complete Unit 3 Design Engineering On
-site/Complete May 2017 In Progress September 2017 Unit 3 Implementation Outage March 2018 Not Started Unit 3 Walk Through Demonstration/Functional Test March 2018 Not Started Unit 1 Design Engineering On
-site/Complete December 2017 Not Started Unit 1 Implementation Outage October 2018 Not Started Unit 1 Walk Through Demonstration/Functional Test October 2018 Not Started Unit 2 Design Engineering On
-site/Complete May 2018 Not Started Unit 2 Implementation Outage March 2019 Not Started Unit 2 Walk Through Demonstration/Functional Test March 2019 Not Started Phase 2 Procedure Changes Active Operations Procedure Changes Developed September 2017 In Progress Site Specific Maintenance Procedure s Developed December 2017 Not Started Procedure Changes Active March 2018 Not Started
CNL-17-077 E-5 Phase 2 Training:
Training Complete December 2017 Not Started Phase 2 Completion Unit 3 HCVS Implementation March 2018 Not Started Unit 1 HCVS Implementation October 2018 Not Started Unit 2 HCVS Implementation March 2019 Not Started Full Site HCVS Implementation March 2019 Not Started Submit Completion Report [60 days after full site compliance]
May 2019 Not Started 4 Changes to Compliance Method The following is a list of changes made to the information provided in the Combined Phase 1 and 2 Overall Integrated Plan (Reference 7). These changes were made to clarify the OIP and provide more specific information because the design process is further along than previously anticipated.
These changes meet the NEI 13
-02 compliance method.
Attachment 7. Added Phase 2 ISE Open Items. Attachment 7. Updated OIP Open Item 1 and 3 to include closure documentation for Units 2 and 3. Attachment 7. Updated OIP Open Item 4 to include closure documentation for Unit 2.
Attachment 7. Updated ISE Open Items 1, 11, 12, 13, 14, 15, and 16 to include closure documentation for Units 2 and 3. Attachment 7. Updated ISE Open Items 2, 8, 9, and 10 to include closure documentation for Unit 2. Page 29 of 86. Revised Key Parameter chart to include Unit 2 Component Identifiers.
Page 52-54 of 86.
Updated Part 5 Milestone Schedule. There are no changes to the compliance method as documented in the combined Phase 1 and 2 Overall Integrated Plan (Reference 7). 5 Need for Relief/Relaxation and Basis for the Relief/Relaxation BFN expects to comply with the order implementation date and no relief/relaxation is required at this time.
6 Open Items from Combined Phase 1 and 2 Overall Integrated Plan and Interim Staff Evaluations The following tables provide a summary of the open items documented in the combined Phase 1 and 2 Overall Integrated Plan or the Interim Staff Evaluation (ISE) and the status of each item.
CNL-17-077 E-6 Combined Phase 1 and 2 OIP Open Item Status Phase 1 Open Items
- 1. Perform an assessment of temperature and radiological conditions to ensure that operating personnel can safely access and operate controls at the Remote Operating Station based on time constraints listed in Attachment 2.
Closed - An assessment was completed and documented in the Design Change Technical Evaluation of DCN 71389 for Unit 1, DCN 71390 for Unit 2, DCN 71391 for Unit 3 , calculation MDQ0000642015000351 "HCVS Operator (Mission) Dose Calculation
," and calculation MDQ0009992014000291
"Temperature Response of the Reactor Building Following an Extended Loss o f AC Power." (This calculation also evaluates the temperature response in the Unit 1/2 and Unit 3 Diesel Building during an ELAP event.) 2. Perform an evaluation for HCVS ability to operate from the MCR and has the ability to be supplied adequate amounts of pneumatic pressure for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> actions.
Closed - An evaluation was performed and documented in calculation MDQ0000322015000347 R0, HCVS Nitrogen System Sizing Analysis, and DCN 71389. 3. Perform an evaluation for FLEX portable generators and nitrogen cylinders use past 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> actions.
Closed - An evaluation was performed for FLEX portable generators and documented in a White Paper reviewed during FLEX audit and documented in "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" (ML15069 A358). A nitrogen cylinder use evaluation was performed and documented in DCN 71389 for Unit 1, DCN 71390 for Unit 2, DCN 71391 for Unit 3 and calculation MDQ0000322015000347 "HCVS Nitrogen System Sizing Analysis
." A combination of installed and dedicated nitrogen cylinder carts will be used to provide a seven
-day supply of nitrogen. 4. Revise 1/2/3
-EOI Appendix
-13 to include venting for loss of DC power.
Closed for Unit 1 EOI Appendix-13 , Revision 3 was revised to include venting for loss of DC power.
Closed for Unit 2 EOI Appendix-13 , Revision 9 was revised to include venting for loss of DC power.
Unit 3 - In Progress
CNL-17-077 E-7 5. Perform an evaluation for FLEX portable generators use for post 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> actions in Severe Accident conditions.
Closed - An evaluation for FLEX portable generator use for post 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> actions was performed and documented in Engineering Information Record from AREVA (R06161114360), Projected Dose Rate Contour Map of Shine from the HCVS Vent Line Extending Above Refueling Floor (BFN). 6. Electrical load shedding will be performed in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the event.
Closed (Reference 6)
- Calculation EDQ0009992013000202 R3, 250V DC Unit Batteries, 1, 2, & 3 Evaluation for the Beyond Design Basis External Event (BDBEE) ELAP, has been issued to determine load shedding impact on the unit batteries.
- 7. The implementation of the HCVS DCN's will be staged so that there is no effect on the operating units.
Closed (Reference 6)
- A conceptual meeting was held in November 2014, and a staging plan was used to separate the existing HWWV from the HCVS.
- 8. The wetwell vent will be designed to remove 1% of rated thermal power at EPU conditions.
Closed (Reference 6)
- The existing wetwell vent (CLTP) and the HCVS (EPU) have been designed for 1 percent of rated thermal power at EPU conditions.
- 9. Implement the Harris Radio System for communication between the MCR and the ROS. Closed - A communication system has been implemented that uses hand held radios for communication between the main control room
and the remote operating station. (DCN 70852)
CNL-17-077 E-8 Phase 2 Open Items
- 1. Perform an evaluation for the locations of the SAWA equipment and controls, as well as ingress and egress paths for the expected Severe Accident conditions (temperature, humidity, radiation) for the Sustained Operating period.
In Progress
- 2. Perform an hydraulic evaluation to ensure flow adequacy can be met for all 3 units using 1 FLEX pump to support SAWA flow requirement In Progress Phase 1 Interim Staff Evaluation Open Item Status 1. Make available for NRC staff audit an evaluation of temperature and radiological conditions to ensure that operating personnel can safely access and operate controls and support equipment.
Closed - An assessment was completed and documented in the Design Change Technical Evaluation of DCN 71389 for Unit 1, DCN 71390 for Unit 2, and DCN 71391 for Unit 3, calculation MDQ0000642015000351 "HCVS Operator (Mission) Dose Calculation" , and calculation MDQ0009992014000291 "Temperature Response of t he Reactor Building Following an Extended Loss o f AC Power." (This calculation also evaluates the temperature response in the Unit 1/2 and Unit 3 Diesel Building during an ELAP event.) Documentation is available for audit.
- 2. Make available for NRC audit documentation that procedure 1/2/3
-EOI Appendix-13 has been revised to include venting for loss of dc power.
Closed for Unit 1 EOI Appendix-13 , Revision 3 was revised to include venting for loss of DC power.
Closed for Unit 2 EOI Appendix-13, Revision 9 was revised to include venting for loss of DC power.
Documentation is available for audit.
Unit 3 - In Progress
- 3. Make available for NRC staff audit documentation demonstrating that all load sheds will be accomplished within one hour of event initiation and will occur in an area not impacted by a possible radiological event.
Closed - Calculation EDQ0009992013000202 R3, 250V DC Unit Batteries, 1, 2, & 3 Evaluation for the Beyond Design Basis External Event (BDBEE)
Extended Loss of AC Power (ELAP), has been issued to determine load shedding impact on the unit batteries, and is available for audit.
CNL-17-077 E-9 Phase 1 Interim Staff Evaluation Open Item Status 4. Make available for NRC staff audit documentation that demonstrates that operating units that have not implemented the order will be able to vent through the existing vent system unaffected by the implementation of HCVS on other units.
Closed - A conceptual meeting was held in November 2014, and a staging plan was used to separate the existing HWWV from the HCVS. Documentation is available for audit.
- 5. Make available for NRC staff audit analyses demonstrating that HCVS has the capacity to vent the steam/energy equivalent of one percent of licensed/rated thermal power (unless a lower value is justified), and that the suppression pool and the HCVS together are able to absorb and reject decay heat, such that following a reactor shutdown from full power containment pressure is restored and then maintained below the primary containment design pressure and the primary containment pressure limit.
Closed - The existing wetwell vent (CLTP) and the HCVS (EPU) have been designed for 1 percent of rated thermal power at EPU conditions.
Analyses are available for audit.
- 6. Make available for NRC staff audit documentation that demonstrates adequate communication between the remote HCVS operation locations and HCVS decision makers during ELAP and severe accident conditions.
Closed - A communication system has been implemented that uses hand held radios for communication between the main control room and the remote operating station (DCN 70852). Documentation is available for audit.
- 7. Make available for NRC staff audit documentation of an evaluation verifying the existing containment isolation valves, relied upon for the HCVS, will open under the maximum expected differential pressure during BDBEE and severe accident wetwell venting.
Closed - An evaluation was performed and concluded that the containment isolation valves will open under the maximum expected differential pressure and is documented in FLOWSERVE Report RAL
-70181, Design Review Report of Size 14 Class 150 Wafer Butterfly Valve with Pneumatic Actuator R1. Documentation is available for audit.
- 8. Make available for NRC staff audit documentation of a seismic qualification evaluation of HCVS components.
Closed for Unit 1 and Unit 2
- All electrical and I&C components were procured as seismically qualified or as Seismic Class I to ensure their functionality following a seismic event. Seismic qualification reports of HCVS components are available for audit.
Unit 3 - In Progress
CNL-17-077 E-10 Phase 1 Interim Staff Evaluation Open Item Status 9. Make available for NRC staff audit descriptions of all instrumentation and controls (existing and planned) necessary to implement this order including qualification methods.
Closed for Unit 1 and Unit 2
-Instrumentation and controls necessary to implement this order including equipment description, location, and qualifications are available for audit.
Unit 3 - In Progress
- 10. Make available for NRC staff audit the descriptions of local conditions (temperature, radiation and humidity) anticipated during ELAP and severe accident for the components (valves, instrumentation, sensors, transmitters, indicators, electronics, control devices, and etc.) required for HCVS venting including confirmation that the components are capable of performing their functions during ELAP and severe accident conditions.
Closed for Unit 1 and Unit 2
-Descriptions of local conditions (temperature, radiation and humidity) anticipated during ELAP and severe accident for the components (valves, instrumentation, sensors, transmitters, indicators, electronics, control devices, and etc.) required for HCVS venting including confirmation that the components are capable of performing their functions during ELAP and severe accident conditions are available for audit. Unit 3 - In Progress
- 11. Make available for NRC staff audit the final sizing evaluation for HCVS batteries/battery charger including incorporation into FLEX DG loading calculation.
Closed - HCVS batteries/battery charger final sizing evaluation was performed and documented in the Design Change Technical Evaluation of DCN 71389 for Unit 1, DCN 71390 for Unit 2 and DCN 71391 for Unit 3. There is no incorporation of the HCVS battery/battery charger required into the FLEX DG loading calculation due to no plans or requirements to recharge the HCVS battery after depletion. The HCVS electrical loads will be aligned back to their normal power supply which is the Unit Battery. The recharging of the Unit Battery is incorporated into the FLEX DG loading calculations. Calculation EDQ0003602014000281 R3 "Electrical Evaluation for Portable Power Supply for Unit Battery Chargers" and calculation EDQ0003602015000325 R1 "Electrical Evaluation for 4KV Spare FLEX Turbine Generators." Documentation is available for audit. 12. Make available for NRC staff audit documentation of the HCVS nitrogen pneumatic system design including sizing and location.
Closed - Evaluation has been completed and documented in calculation MDQ0000322015000347 R1, HCVS Nitrogen System Sizing Analysis, DCN 71389 for Unit 1, DCN 71390 for Unit 2 , and DCN 71391 for Unit 3. Documentation is available for audit.
CNL-17-077 E-11 Phase 1 Interim Staff Evaluation Open Item Status 13. Make available for NRC staff audit the seismic and tornado missile final design criteria for the HCVS stack.
Closed - Tornado and seismic missile criteria are located in System 64A Design Criteria Document (DCD). As part of DCN 71389 for Unit 1, DCN 71390 for Unit 2, and DCN 71391 for Unit 3 a markup reflecting these changes has been generated and will be incorporated in the next revision of the DCD per TVA process.
Documentation is available for audit.
- 14. Provide a description of the final design of the HCVS to address hydrogen detonation and deflagration.
Closed - The final design of HCVS at BFN to address hydrogen detonation and deflagration is the installation of a check valve near the vent discharge release point. A description of this design is contained in the Technical Evaluation for DCN 71389 for Unit 1, DCN 71390 for Unit 2, and DCN 71391 for Unit 3.
Documentation is available for audit.
- 15. Provide a description of the strategies for hydrogen control that minimizes the potential for hydrogen gas migration and ingress into the reactor building or other buildings.
Closed -The HCVS provides a direct vent path from the wetwell to an exhaust point above the Reactor Building Roof in accordance with NEI 13-02 section 4.1.5. This is a leak tight system with no boundary valves outside the PCIV's that would allow hydrogen gas migration and ingress into the Reactor Building or other buildings. Per NEI 13
-02 FAQ-04 an effluent release velocity of 8000 fpm will assure that the effluent plume will not be entrained into the roof recirculation zone of a given building. A description of this design is contained in the Technical Evaluation for DCN 71389 for Unit 1, DCN 71390 for Unit 2, and DCN 71391 for Unit 3. Documentation is available for audit.
- 16. Provide design details that minimize unintended cross flow of vented fluids within a unit and between units on the site. Closed -The BFN design includes a separate HCVS stack for each unit as well as meeting the testing criteria and valve requirements for PCIVs, control and boundary valves. A description of this design is contained in the Technical Evaluation for DCN 71389 for Unit 1, DCN 71390 for Unit 2, and DCN 71391 for Unit 3. Documentation is available for audit.
CNL-17-077 E-12 Phase 2 Interim Staff Evaluation Open Item Status 1. Licensee to perform a hydraulic evaluation to ensure flow adequacy can be met for all 3 units using 1 FLEX pump to support SAWA flow requirement.
In Progress
- 2. Licensee to evaluate the SAWA equipment and controls, as well as the ingress and egress paths for the expected severe accident conditions (temperature, humidity, radiation) for the sustained operating period.
In Progress
- 3. Licensee to demonstrate how SAWA flow is capable to perform its intended function for the sustained operating period under the expected temperature and radiological conditions.
In Progress
- 4. Licensee to demonstrate that containment failure as a result of overpressure can be prevented without a drywell vent during severe accident conditions.
In Progress
- 5. Licensee to demonstrate how the plant is bounded by the reference plant analysis that shows the SAWM strategy is successful in making it unlikely that a drywell vent is needed.
In Progress
- 6. Licensee to demonstrate that there is adequate communication between the MCR and the operator at the FLEX pump during severe accident conditions.
In Progress 7 Interim Staff Evaluation Impacts There are no potential impacts to the Interim Staff Evaluation(s) identified at this time.
CNL-17-077 E-13 8 References The following references support the updates to the combined Phase 1 and 2 Overall Integrated Plan described in this enclosure.
- 1. Letter from TVA to NRC, "Tennessee Valley Authority's Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident (Order Number EA 109)," dated June 30, 2014 (ML14181B169)
- 2. NRC Order Number EA 109, "Order Modifying Licenses with Regard to Reliabl e Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
," dated June 6, 2013 (ML13143A321)
- 3. NEI 13-02, "Industry Guidance for Compliance with NRC Order EA 109, 'To Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 1, dated April 2015 (ML15113B318)
- 4. NRC Interim Staff Guidance JLD
-ISG-2013-02, "Compliance with Order EA 109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 0, dated November 2013 (ML13304B836).
- 5. NRC Endorsement of industry "Hardened Containment Venting System (HCVS) Phase 1 Overall Integrated Plan Template (EA 109) Rev 0
," dated May 14, 2014 (ML14128A219).
- 6. JLD-ISG-2012-01, "Compliance with Order EA 049, Mitigation Strategies for Beyond-Design-Basis External Events," dated August 29, 2012 (ML12229A174)
- 7. Letter from TVA to NRC, "Tennessee Valley Authority's Browns Ferry Nuclear Plant 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 Under Severe Accident Conditions (Order Number EA 109)," dated December 29, 2015 (ML15365A554)
- 8. NRC Interim Staff Guidance JLD
-ISG-2015-01, "Compliance with Phase 2 of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," Revision 0, dated April 2015 (ML15104A118).
- 9. Letter from TVA to NRC "Tennessee Valley Authority's Browns Ferry Nuclear Plant 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 (Order Number EA 109)," dated June 30, 2016 (ML16182A517)
- 10. Letter from TVA to NRC "Tennessee Valley Authority Browns Ferry Nuclear Plant's 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 (Order Number EA 109)," dated December 22, 2016 (ML16357A577)
- 11. 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 Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) (C AC Nos. MF4540, MF4541 and M F4542)," dated September 6, 2016 (ML16244A762)