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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-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) 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-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 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-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) 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-23-049, 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-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, 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-23-012, Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2023-04-11011 April 2023 Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance 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-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report 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-23-011, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-01-18018 January 2023 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 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-22-106, 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-22-099, 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-22-104, Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-10-31031 October 2022 Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 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-22-084, Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-09-16016 September 2022 Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ2022-08-22022 August 2022 Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Reques 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-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-080, Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating2022-07-22022 July 2022 Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating CNL-22-081, Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-21021 July 2022 Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 CNL-22-079, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-20020 July 2022 American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) 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-22-069, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-07-0101 July 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. CNL-22-070, Status Regarding the Improved Flood Mitigation System Project2022-06-30030 June 2022 Status Regarding the Improved Flood Mitigation System Project CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 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 CNL-22-047, Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2022-05-23023 May 2022 Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2022-05-13013 May 2022 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 402022-04-28028 April 2022 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40 CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf2022-04-28028 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf 2024-01-17
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation ML23117A1162023-04-27027 April 2023 Response to Follow-up Questions to TVAs Response to NRCs Request for Supplemental Information (Rsi) Related to August 4, 2022, Sequoyah ISFSI Exemption Request CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 ML22353A0662022-12-19019 December 2022 Response to Request for Supplemental Information (D-RSI) Request for Exemption from Non-Destruction-Examination Compliance CNL-22-084, Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-09-16016 September 2022 Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ2022-08-22022 August 2022 Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Reques CNL-22-069, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-07-0101 July 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 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-21-024, Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02)2021-06-15015 June 2021 Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02) CNL-21-039, Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2021-05-0505 May 2021 Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-20-082, Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)2020-11-10010 November 2020 Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02) CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020 Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-20-057, Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02)2020-08-12012 August 2020 Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02) ML20196L6892020-07-16016 July 2020 TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request CNL-20-032, Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis2020-05-14014 May 2020 Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis CNL-20-026, Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-02-18018 February 2020 Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-19-119, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-19019 November 2019 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-061, Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task2019-10-18018 October 2019 Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Fo ML19231A2082019-08-19019 August 2019 Response to Request for Information Regarding Unit 2 Cycle 22 - 180-Day Steam Generator Tube Inspection Report CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. CNL-19-057, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-12019-06-19019 June 2019 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-1 CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,.2019-03-21021 March 2019 Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,. CNL-19-016, Response to Request for Additional Information on License Amendment Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report2019-01-30030 January 2019 Response to Request for Additional Information on License Amendment Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. CNL-17-063, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2017-10-26026 October 2017 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-17-104, Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-08-0707 August 2017 Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-16-194, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2016-12-23023 December 2016 Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-16-178, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2016-12-23023 December 2016 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-123, Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-52016-07-28028 July 2016 Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 CNL-16-086, Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System2016-05-31031 May 2016 Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System CNL-15-218, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information2015-10-23023 October 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information CNL-15-171, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) - Response to Request for Additional Information2015-09-11011 September 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) - Response to Request for Additional Information CNL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. CNL-15-146, Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 (TAC Nos. MF0481 and MF0482)2015-08-0303 August 2015 Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 (TAC Nos. MF0481 and MF0482) NL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. CNL-15-136, Response to NRC Request for Additional Information Regarding ASME Request for Relief RP-072015-07-22022 July 2015 Response to NRC Request for Additional Information Regarding ASME Request for Relief RP-07 ML15176A6822015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8 ML15176A6812015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8 ML15176A7482015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 8 of 8 ML15176A7402015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 ML15176A6792015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 ML15176A6642015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8 2024-01-03
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SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 TENNESSEE 1\14 VALLEY AUTHORITY 1101 Market Street, Chattanooga, Tennessee 37402 CNL-22-053 August 22, 2022 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328
Subject:
Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis
- Second Partial Response to Additional Request for Additional Information (TS-19-02) (EPID L-2020-LLA-0004)
References:
- 1. TVA Letter to NRC, CNL-19-066, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)," dated January 14, 2020 (ML20016A396 and ML20016A397)
- 2. TVA Letter to NRC, CNL-20-026, "Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)
(EPID L-2020-LLA-0004)," dated February 18, 2020 (ML20049H184)
- 3. TVA Letter to NRC, CNL-20-032, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Response to Request for Additional Information (TS-19-02) (EPID L-2020-LLA-0004)," datec;l May 14, 2020 (ML20135H067)
- 4. TVA Letter to NRC, CNL-20-057, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02) (EPID L-2020-LLA-0004)," dated August 12, 2020 (ML20225A170)
- 5. NRC Electronic Mail to TVA, "SequoyahJ~uclear Plant, Units 1 and 2 -
Request fo'r Additional Information Regarding Hydrologic UFSAR Update (EPID L-2020-LLA~0004),"dated September 14, 2020 (ML20261H417)
]) o3D SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 kD53
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 U.S. Nuclear Regulatory Commission CNL-22-053 Page2 August 22, 2022
- 6. NRC Letter to TVA, "Summary of October 13, 2020, Closed Meeting With Tennessee Valley Authority to Discuss Responses to Requests for Additional Information Regarding Updated Final Safety Analysis Report Hydrologic Analysis License Amendment Request (EPID L-2020-LLA-0004)," dated October 27, 2020 (ML20293A080)
- 7. TVA Letter to NRC, CNL-20-082, "Partial Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plants Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02) (EPID L-2020-LLA-0004)," dated November 10, 2020 (ML20328A093)
- 8. TVA Letter to NRC, CNL-21-095, "Application to Revise Sequoyah Nuclear Plant, Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Software Dedication Report 16 Update to Revision 4 (TS-19-02) (EPID L-2020-LLA-0004)," dated December 21, 2021 (ML22013A278)
In Reference 1, Tennessee Valley Authority (TVA) submitted a request for an amendment to Renewed Facility Operating License Nos. DPR-77 and DPR-79 for Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively. This license amendment request (LAR) revises the, SQN Units 1 and ,2, Updated Final Safety Analysis Report (UFSAR) to reflect the results from the new hydrologic analysis. TVA determined that the proposed changes to the SQN UFSAR require prior Nuclear Regulatory Commission (NRC) approval.
In References 2, 3, and 4, TVA provided supplements to Reference 1. In Reference 5, the NRC provided a request for additional information (RAI) and requested that TVA respond by October 14, 2020.
Following receipt of Reference 5, TVA determined that there was a potentially unconservative unverified assumption in the calculations supporting the Apalachia Dam failure analysis and entered this issue into the TVA corrective action program. TVA communicated this information to the NRC during a closed public meeting on October 13, 2020 (Reference 6). This unverified assumption impacted some of the Reference 5 requested calculation files. As a result of this impact, TVA provided in Reference 7, a partial response to the Reference 5 request.
Reference 7 included the calculation files which were considered to not be impacted by the unverified assumption issue related to the Apalachia Dam failure analysis. Reference 8 provided an update to the Software Dedication Report 16-01 transmitted in Reference 7. to this letter provides responses to the RAls in Reference 5 not previously answered in Reference 7. In addition, Enclosure 1 provides an updated response for RAI 2.4-5 (1) because of impacts associated with resolution of the unverified assumption. The responses provided in this letter are consistent with the content of the revision of Reference 1 which will be provided later.
SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2
f SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 U.S. Nuclear Regulatory Commission CNL-22-053 Page 3 August 22, 2022 As indicated in Enclosure 1, some of the information requested by the NRC is provided in , which contains a digital versatile disc (DVD). Enclosure 2 contains security related information that TVA is requesting be withheld from public disclosure in accordance with Title 10 of the Code of Federal Regulations (1 0 CFR) 2.390, "Public inspections, exemptions, requests for withholding." '
This letter does not change the no significant hazard considerations nor the environmental considerations contained in Reference 1. Additionally, in accordance with 10 CFR 50.91 (b)(1 ),
TVA is sending a copy of this letter and the enclosure to the Tennessee Department of Environment and Conservation.
There are no new regulatory commitments associated with this submittal. Please address any questions regarding this submittal to Stuart L. Rymer, Senior Manager, Fleet Licensing at slrymer@tva.gov.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 22nd day of August 2022.
Respectfully, 1 -:ti---
J ~ V,.1A.f./1-4 James Barstow V Digitally signed by Rearden,
/\Pamela S t -nafe: 2022.os.22 16:1 s:2s -04*00*
Vice President, Nuclear Regulatory Affairs & Support Services
Enclosures:
- 1. Response to NRC Additional Request for Additional Information
- 2. DVD Containing the Information Requested in Enclosure 1 (Security Related Information) cc (w/o Enclosure 2):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant, Units 1 and 2 NR~ Project Manager - Sequoyah Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 Enclosure 1 Response to NRC Additional Request for Additional Information RA/ 2.4-2: PMP Input/Output Files Section 2.4.3, "PMP ' [Probable Maximum Precipitation] on Streams and Rivers" of the proposed
, Updated Final Saff#ty Analysis Report (UFSAR) revision present the revised flood hazard estimations at the plant site due to riverine flooding. NUREG-0800, "Standard Review Plan
[SRPJ for the Review of Safety Analysis Reports for Nuclear Power Plants: L WR [Light-water Reactor] Edition," Revision 4, Section 2.4.3, "Probable Maximum Flood (PMF) on Streams and Rivers" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070730405), and Regulatory Guide (RG) 1.59, "Design Basis Floods for Nuclear Power Plants" (ADAMS Accession No. ML003740388), provide guidelines for estimating this flood causing mechanism. After reviewing the license amendment request (LAR) and enclosed documents, the NRG staff has determined that it needs additional information related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all PMP input/output files be provided, as summarized in Figure No. 1 of "Response to NRG IQVB Request for Additional Information" (ADAMS Accession No. ML20135H067), including:
- 1. Input Information
- a. User input (including storm types, durations, basins of interest)
- b. ArcGIS base Python script
- c. Tennessee Valley Authority (TVA) Project sub-basins shapefile
- d. Sub-basin geographic information system (GIS) encapsulating shapefile of TVA subbasins, shapes, area, and positions
- 2. Gridded PMP Point Data Development-: Dedicated Software
- a. Sub-basin text file of user input b.' Event specific Python script
- c. Modified PMP Evaluation Tool scripts and associated documentation
- d. Gridded PMP Point Data used for local intense precipitation (LIP) and PMF
- 3. Non-QA GIS Software Tools - Alternate ArcGIS Calculations
- a. Python scripts for creating Triangular Irregular Network (TIN) and utilizing Polygon Volume Tool
- b. ArcGIS sub-basin weighted average PMP depths for controlling PMF scenario TVA Response to RA/ 2.4-2 The requested information in items 1, 2, and 3a were provided in previous response letters (References 1 and 2.) The requested information in item 3b is provided in the following files on the digital versatile disc (DVD) in Enclosure 2 to this submittal.
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 CNL-22-053 E1-1 of 6
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 Enclosure 1 3.b. PMP Basin Depth following nesting volume adjustments for the Controlling PMF is in calculation CDQ0000002017000059 Revision 001. This calculation has been revised to address the dam safety issue at Apalachia Dam. Within this effort, it was determined that the controlling event nesting scenario changed from that which was previously provided in Reference 3. The precipitation timeseries file for the controlling simulation is located in Appendix_B.zip, Appendix_B-A_PCAT.zip, in folder "CHH_105," in folder "00_Precip," and in the file "CHH_105_HourlyDistributions.csv." The total applied rainfall depth files are in the same "CHH_105" folder in folder "09_OutputGraphics" in the files "Total_Applied_Rainfall_Depths_Antecedent.csv" and "Total_Applied_Rainfall_Depths_Main.csv." of Reference 1 provided a flowchart aid to facilitate the understanding of the interactions of the various TVA calculations that make up the SQN Hydrology analyses.
RAJ 2.4-3: LIP Modeling Input/Output Files Section 2.4.2, "Floods" of the proposed UFSAR revision presents the revised flood hazard estimations at the plant site due to LIP flooding. SRP Section 2.4.2, "Floods" (ADAMS Accession No. ML070100647), provides guidelines for estimating this flood causing mechanism.
After reviewing the submitted LAR and enclosed documents, the NRG staff has determined that it needs additional information related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all LIP modeling input/output files be provided, including:
- LIP hydrodynamic mod(:3I input/output files for simulating local intense precipitation surface runoff, routing, and flooding.
TVA Response to RAJ 2.4-3 The requested information was provided in a previous response letter (Reference 1).
RAJ 2.4-4: PMF Modeling Input/Output Files Section 2.4.3, "PMF Flood in Rivers and Streams" of the proposed UFSAR revision presents the revised flood hazard estimations at the plant site due to LIP flooding. SRP Section 2.4.3, provides guidelines for estimating this flood causing mechanism. After reviewing the license amendment request (LAR) and enclosed documents, the NRG staff has determined that it needs additional information related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all modeling input/output files be provided for controlling PMF (with hydrologic dam failures) scenario, including:
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 CNL-22-053 E1-2 of 6
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 Enclosure 1
- 1. Tabular data associated with the controlling primary and secondary area nesting sequence and the controlling PMP rainfall depth spatial distribution over the watershed" (LAR Enclosure, Section 2.4.3.1) as well as executable version of the tools (if any) used to distribute the gridded PMP values into subbasin space and time.
- a. LAR Enclosure 3, Figure 2.4.3-1
- b. *LAR Enclosure 3, Figure 2.4.3-5a (as provided in LAR Enclosure 4, Table 2.4.3-1)
- 2. Executable version of sub-basin unit hydrograph calculations (as referenced in LAR Enclosure 4, Section 2.4.3.3), as well as electronic version of data shown in LAR Enclosure 3, Figure 2.4.3-6.
- 3. Executable version of calculation files (if applicable) for estimating precipitation excess (as referenced in LAR Enclosure 4, Section 2.4.3.2).
- 4. Shapefiles (or similar locational data) for HEC-RAS model limits river gage, Sequoyah plant site and dam locations, as shown in LAR Enclosure 3, Figure 2.4.3-4 and Figure 2.4.3-5 (as referenced in LAR Enclosure 4, Section 2.4.3.3)
- 5. Executable version of the runoff and HEC-RAS model files, including'HEC-RAS inputs such as calibrated geometry, unsteady flow rules and inflows (as reference in LAR Enclosure 4, Section 2.4.3.3).
TVA Response to RA/ 2.4-4 The requested information is provided in the following files on the DVD in Enclosure 2 to this submittal.
- 1. The process used to distribute the gridded PMP values is described in CDQ0000002017000080, Revision 001, Appendix B.
1.a. The tabular data associated with LAR Enclosure 3, Figure 2.4.3-1 is in calculation CDQ0000002017000059, Revision 001. The precipitation timeseries file for the controlling simulation is in "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," in folder "00_Precip," and in the file "CHH_105_HourlyDistributions.csv." The total applied rainfall *depth files are in the same "CHH_ 105" folder, in folder "09_OutputGraphics," and in the files
Total_Applied_Rainfall_Depths_Antecedent.csv" and "Total_Applied_Rainfall_Depths_Main.csv."
1.b. The tabular data associated with LAR Enclosure 4, Table 2.4.3-1, is in calculation CDQ0000002017000059, Revision, 001. The total applied rainfall depth files for the controlling simulation are in "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," in folder "09_OutputGraphics," and in the files "Total_Applied_Rainfall_Depths_Antecedent.csv" and SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 CNL-22-053 E1-3 of 6
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure ~
Enclosure 1 "Total_Applied_Rainfall_Depths_Main.csv." The runoff determined in the excess computation is in folder "CHH_105," in folder "01_APl_calculation," and in file "CHH_105_API_Outputs.dss." The subbasin areas used in the excess computation are in CDQ0000002016000044, Revision 000 in folder "Appendix_B" and in file "Appendix_B_Reservoir_Analysis.xlsx." CDQ0000002016000044, Revision 000 was previously provided in Reference 1.
- 2. The sub-basin unit hydrographs were developed in calculations CDQ000020080056 through CDQ0000020080073, and CDQ000020080091 and were also provided for NRC review in the External Hazards Branch (EXHB) Audit that began on September 14, 2020. The unit hydrographs calculations for the sub-basins above Chickamauga Dam also supported previous TVA submittals for WBN (Reference 4) that were reviewed and approved by the NRC in Safety Evaluation issued by letter dated January 28, 2015 (Reference 5). The unit hydrograph calculations for the sub-basins below Chickamauga Dam were also provided in the EXHB Audit because the Hydrologic Engineering Center- River Analysis System (HEC-RAS) model has been extended past Chickamauga Dam to Wheeler Dam below Browns Ferry Nuclear Plant. The unit hydrograph data were reformatted for use in the Hydrologic Engineering Center-Hydrologic Modeling System (HEC-HMS) in calculation CDQ0000002016000047 and were also provided for NRC review in the EXHB Audit.
The sub-basin unit hydrographs before reformatting are provided within Excel spreadsheets in calculation CDQ0000002016000047 in file "Appendix A.zip," "Appendix_A1_NUH_S-Graphs.xlsx." The sub-basin unit hydrographs which were reformatted are provided in Excel spreadsheets within calculation CDQ0000002016000047 in file "Appendix A.zip,"
"Appendix_A2_NUH_Adjusted_S-GreaphsR3.xlsm." These Excel files provide electronic versions of the data shown in LAR Enclosure 3, Figure 2.4.3-6. The application of the sub basin unit hydrographs for the controlling event are included in the PMP/PMF Calculation Automation Tool (PCAT) simulation located in calculation CDQ0000002017000059, Revision 001, "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "02_HEC-HMS_unit_hydrographs."
- 3. The process used to compute the precipitation excess is described in calculation CDQ0000002017000080, Revision 001, Appendix C. Precipitation Excess information for the controlling event is in CDQ0000002017000059, Revision 001 in "Appendix_B.zip,"
"Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "01_APl_calculation."
- 4. A shapefile for the subbasins is in CDQ0000002016000045, Revision 000 "Appendix A-A_Subbasins.zip." The HEC-RAS model was built utilizing river mile stations for each dam rather than coordinates. Table 6.4.6 in the HEC-RAS Model Set-up calculation, CDQ0000002014000021, Revision 005, lists each dam included in the model, the river on which it is located, its river mile, and the river miles for the headwater and tailwater cross-sections.
- 5. The automation for the hydrologic and hydraulic processes was performed by PCAT and is described in CDQ0000002017000080, Revision 001 as listed below.
SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 CNL-22-053 E1-4 of 6
SECURITY RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 Enclosure 1 The process for rain-on-reservoir calculation is described in CDQ0000002017000080, Revision 001, Appendix E. Rain-on-reservoir for the controlling event is in CDQ2000000017000059, Revision 001, "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "03_ROR_calculation."
The process for surface runoff and baseflow calculations is described in CDQ0000002017000080, Revision 001, Appendix F. Surface runoff and baseflow for the controlling event is in CDQ2000000017000059, Revision 001, "Appendix_B.zip,"
"Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "04_Surface_runnoff_scaling_and_baseflow. "
The process for tributary inflow routing is described in CDQ0000002017000080, Revision 001, Appendix G. Tributary inflow routing for the controlling event is in CDQ2000000017000059, Revision 001, "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "05_Routing."
The process for inflow hydrograph distribution is described in CDQ0000002017000080, Revision 001, Appendix I. Inflow hydrograph distribution for the controlling event is in CDQ2000000017000059, Revision 001, "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "07_lnflow_distribution."
The executable version of the HEC-RAS model for the controlling event is in CDQ2000000017000059, Revision 001, "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_105," and in folder "0B_HEC-RAS.!'
The Controlling PMF Results Data is in CDQ2000000017000059, Revision 001, "Appendix_B.zip," "Appendix_B-A_PCAT.zip," in folder "CHH_ 105," and in folder "09_OutputGraphics."
RAJ 2.4-5: Seismic Dam Failure Modeling Input/Output Files Section 2.4.4, "Potential Dam Failures, Seismically Induced" of the proposed UFSAR revision in the application presents the revised flood hazard estimations at the plant site due to seismic dam failure flooding. SRP Section 2.4.3 provides guidelines for estimating this flood causing mechanism. After reviewing the license amendment request (LAR) and enclosed documents, the NRG staff determined that it needs additional information related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all modeling input/output data files be provided for controlling seismic dam failure scenario, including:
- 1. Hydrologic Engineering Center River Analysis System simulation setup, input and output files for four potentially critical seismic-flood event combinations (as referenced in LAR Enclosure 4, Section 2.4.4.2).
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 CNL-22-053 E1-5 of 6
SECURITY RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 This letter is decontrolled when separated from Enclosure 2 Enclosure 1
- 2. Calculations for 25-year and 500-year flood inflows (as referenced in LAR Enclosure 4, Section 2.4.4. 1)
TVA Response to RA/ 2.4-5 The requested information for items 1 and 2 of this RAI 2.4.5 was provided in a previous response letter (Reference 1). However, the information for item 1 was impacted by the calculation revisions prompted by the Apalachia Dam issue and as such, the seismic analysis was reevaluated. The requested information for item 1 is provided in the following files on the DVD in Enclosure 2 and supersedes the information provided in Reference 1.
- 1. The revised Seismic HEC-RAS files for the input and output files for the four potentially critical seismic-flood event combinations (as referenced in the LAR Enclosure 4, Section 2.4.4.2) are located in CDQ0000002014000024, Revision 006, "Seismic Dam Failure Simulations Calculation," "Appendix_A.zip," "Appendix_B.zip," "Appendix_C.zip," and "Appendix_F .zip."
- 2. The 25-year and 500-year flood inflow calculations were provided in a previous response letter (Reference 1).
References:
- 1. TVA Letter to NRG, CNL-20-082, "Partial Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plants Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02) (EPID L-2020-LLA-0004)," dated November 10, 2020 (ML20328A093)
- 2. TVA Letter to NRG, CNL-21-095, "Application to Revise Sequoyah Nuclear Plant, Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis-Software Dedication Report 16 Update to Revision 4 (TS-19-02)
(EPID L-2020-LLA-0004)," dated December 21, 2021 (ML22013A278)
- 3. TVA Letter to NRG, CNL-19-066, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)," dated January 14, 2020 (ML20016A396 andrML20016A397)
- 4. TVA Letter to NRG, "Application to Revise Watts Bar Nuclear Plant, Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01)," dated July 19, 2012 (ML122360173)
- 5. Letter from NRG to TVA, "Watts Bar Nuclear 'Plant, Unit 1 - Issuance of Amendment To Revise Updated Final Safety Analysis Report Regarding Changes to Hydrology Analysis (TAC No. ME9130)," dated January 28, 2015 (ML15005A314)
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Enclosure 2 DVD Containing the Information Requested in Enclosure 1
- 1. Tennessee Valley Authority, Calculation CDQ0000002017000059, Chickamauga Dam (CHH) Probable Maximum Flood (PMF) Analysis, Revision 1, May 10, 2022 (Security-Related Information)
- 2. Tennessee Valley Authority, Calculation CDQ0000002014000021, HEC-RAS Model Setup, Revision 5, May 03, 2022 (Security-Related Information)
- 3. Tennessee Valley Authority, Calculation CDQ0000002016000045, Weekly API Determination, Revision 0, December 07, 2016
- 4. Tennessee Valley Authority, Calculation CDQ0000002014000024, Seismic Dam Failure Combined with Rainfall Event Simulations, Revision 6, May 10, 2022 (Security-Related Information)
- 5. Tennessee Valley Authority, Calculation CDQ0000002017000080, Revision 001, PMP/PMF Calculation Automation Tool (PCAT) Model Set-up, Revision 1, May 03, 2022 (Security-Related Information)
- 6. Tennessee Valley Authority, Calculation CDQ0000002016000047, Unit Hydrograph Data Translation for HEC-HMS, Revision 0, May 25, 2017 CNL-22-053 E2-1 of 1