Letter Sequence Response to RAI |
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EPID:L-2022-LLE-0017, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In. (Open) |
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MONTHYEARCNL-22-054, Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours2022-04-15015 April 2022 Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours Project stage: Request CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.2022-04-25025 April 2022 Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In. Project stage: Request CNL-22-060, Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours2022-04-25025 April 2022 Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours Project stage: Response to RAI ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) Project stage: Other ML22117A1862022-04-29029 April 2022 Exemptions from the Requirements of 10 CFR Part 26, Section 26.205(d)(7) (EPID L-2022-LLE-0017) (Exemption) Project stage: Other ML22117A1852022-04-29029 April 2022 Exemptions from the Requirements of 10 CFR Part 26, Section 26.205(d)(7) (EPID L-2022-LLE-0017) (Letter) Project stage: Other ML22117A1952022-04-29029 April 2022 Exemptions from the Requirements of 10 CFR Part 26, Section 26.205(d)(7) Project stage: Request 2022-04-25
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Category:Letter type:CNL
MONTHYEARCNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-017, 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-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) CNL-23-005, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2023-12-26026 December 2023 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) CNL-23-069, 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-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) 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-23-059, 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-23-061, 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-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) 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-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) 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-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out 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-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) 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-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, 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 2024-09-24
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-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-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-22-064, 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-22-043, Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board.2022-05-0202 May 2022 Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board. CNL-22-060, Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours2022-04-25025 April 2022 Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours WBL-22-010, Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report2022-03-0202 March 2022 Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report CNL-21-098, Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4)2022-01-0505 January 2022 Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4) CNL-21-075, Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening2021-09-0808 September 2021 Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening CNL-21-070, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Unit 2 Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 22021-08-11011 August 2021 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Unit 2 Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C CNL-21-043, Response to Request for Additional Information Regarding Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the Watts Bar Nuclear Plant2021-05-14014 May 2021 Response to Request for Additional Information Regarding Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the Watts Bar Nuclear Plant CNL-21-041, Response to RAI Re Application to Modify the Watts Bar Nuclear Plant Technical Specifications 5.7.2.19, Containment Leakage Rate Testing Program (WBN-TS-19-01)2021-04-29029 April 2021 Response to RAI Re Application to Modify the Watts Bar Nuclear Plant Technical Specifications 5.7.2.19, Containment Leakage Rate Testing Program (WBN-TS-19-01) CNL-21-021, Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, .2021-03-30030 March 2021 Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, . CNL-21-005, Response to Request for Additional Info Re License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition & Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07)2021-01-22022 January 2021 Response to Request for Additional Info Re License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition & Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) CNL-21-014, Response to Request for Additional Information for Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for the Watts Bar Nuclear Plant, Unit 2 Steam Generators (WBN TS-391-20-024)2021-01-19019 January 2021 Response to Request for Additional Information for Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for the Watts Bar Nuclear Plant, Unit 2 Steam Generators (WBN TS-391-20-024) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-20-030, Response to Request for Additional Information to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-04-29029 April 2020 Response to Request for Additional Information to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-19-124, Response to Request for Additional Information to Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (W2020-01-13013 January 2020 Response to Request for Additional Information to Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN CNL-19-108, Response to NRC Second Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-10-28028 October 2019 Response to NRC Second Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors CNL-19-105, Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)2019-10-10010 October 2019 Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-19-062, Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)2019-09-0404 September 2019 Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-19-069, Final Response to NRC Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69,Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Pow2019-07-29029 July 2019 Final Response to NRC Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69,Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power 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-19-065, Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-07-15015 July 2019 Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors CNL-19-056, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602019-06-0707 June 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2019-03-21021 March 2019 Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2018-11-0909 November 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-128, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30)2018-11-0808 November 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30) CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-10-11011 October 2018 Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .2018-10-0404 October 2018 Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) ... CNL-18-104, Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals2018-07-30030 July 2018 Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals CNL-18-102, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ...2018-07-24024 July 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ... ML18155A4872018-06-0404 June 2018 Response to Request for Additional Information Regarding Cycle 1 Steam Generator Tube Inspection Report CNL-18-061, Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-31031 May 2018 Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-18-058, Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-04-27027 April 2018 Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) 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. 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-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)2018-02-15015 February 2018 Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) CNL-18-012, Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)2018-01-17017 January 2018 Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01) CNL-17-108, Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation2017-08-31031 August 2017 Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation 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-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)2017-07-21021 July 2017 Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS) CNL-17-091, Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn..2017-07-14014 July 2017 Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn.. 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-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-06-30030 June 2017 Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNL-17-066, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17)2017-06-0909 June 2017 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17) CNL-17-062, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements2017-05-19019 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements 2024-08-19
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1101 Market Street, Chattanooga, Tennessee 37402 CNL-22-060 April 25, 2022 10 CFR 26.9 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), "Fitness for Duty Programs - Work Hours"
References:
- 1. TVA Letter to NRC, CNL-22-054, Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours, dated April 15, 2022 (ML22105A579)
- 2. NRC Electronic Mail to TVA, Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request re 10 CFR Part 26 (L-2022-LLE-0017), dated April 25, 2022 (ML22115A140)
In Reference 1, Tennessee Valley Authority (TVA) submitted an exemption request for the Watts Bar Nuclear Plant (WBN), Unit 2 from the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 26.205, Fitness for Duty Programs - Work Hours, Sections (d)(4) and (d)(7) for Category A personnel to support activities required for the current extended WBN Unit 2 steam generator replacement (SGR) outage, for a period not to exceed an additional 60 days beyond the end of the current 60-day allowance of 10 CFR 26.205(d)(4).
The letter also requested an exemption from 10 CFR 26.205(d)(6) for Category B personnel to support normal outage shutdown, startup, maintenance, fuel handling, and modification activities that are not related to the SGR project.
In Reference 2, the Nuclear Regulatory Commission (NRC) issued a Request for Confirmation of Information (RCI) and Request for Additional Information (RAI) and requested that TVA respond by April 25, 2022. The enclosure to this letter provides the TVA response to the RCI and RAI.
U. S. Nuclear Regulatory Commission CNL-22-060 Page 2 April 25, 2022 As noted in the enclosure, regarding the TVA response to RCI 1, the proposed exemption from 10 CFR 26.205(d)(7) also applies to Category B personnel.
There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Stuart L. Rymer, Senior Manager, Fleet Licensing, at slrymer@tva.gov.
Respectfully, Digitally signed by Rymer, Stuart Loveridge for Date: 2022.04.25 16:23:46 -04'00' James T. Polickoski Director, Nuclear Regulatory Affairs
Enclosure:
Response to NRC Request for Additional Information and Clarification cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant
Enclosure Response to NRC Request for Additional Information and Clarification NRC Introduction By letter dated April 15, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22105A579), the Tennessee Valley Authority (TVA) requested exemptions (1) from Title 10 of the Code of Federal Regulations (10 CFR) Section 26.205(d)(7) to use the less restrictive work hour limitations described in 10 CFR 26.205(d)(4) for no more than 60 days beyond the end of the current 60-day allowance for Category A personnel, and (2) from 10 CFR 26.205(d)(6) for Category B personnel to allow them to perform normal outage shutdown, startup, maintenance, fuel handling, and modification activities that are not related to the steam generator replacement (SGR) project.
The U.S. Nuclear Regulatory Commission (Commission, NRC) staff is reviewing your submittal and has identified areas where additional information or confirmation of information is needed to complete its review.
Request for Confirmation of Information:
- 1. Regarding Category B personnel, the NRC staff's understanding of TVAs request is as follows:
o TVA is requesting that Category B personnel be allowed to work extended hours for a 60-day period of time that would commence upon completion of the SGR project schedule milestone for polar crane turnover to the plant. This requested 60-day time period would be treated as administratively separate from the first 60 days of the unit outage that initially began on March 1, 2022.
o During this administratively established 60-day period, Category B personnel would be permitted to resume work schedules that include more hours per week than the number of hours per week permitted during normal unit operations in accordance with 10 CFR 26.205(d)(7). However, during this 60-day period, Category B personnel would be provided the minimum number of days off that would be required during the first 60 days of a unit outage, in accordance with 10 CFR 26.205(d)(4).
o TVA would potentially have the opportunity to extend the administratively established 60-day period for Category B personnel, in accordance with the limitations discussed in 10 CFR 26.205(d)(6). If TVA were to administer such an extension, then when calculating the allowed duration of the extension for these individuals, TVA would consider the hours worked by those individuals during the administratively established 60-day period (as opposed to considering the hours worked during the first 60 days of the unit outage that began on March 1, 2022).
o The exemption for Category B personnel would end when the Watts Bar, Unit 2 generator is synced to the electrical grid, and TVA would resume control of work hours in accordance with 10 CFR 26.205(d)(7).
Based on the NRC staff's understanding, as described above, an exemption would be needed from 10 CFR 26.205(d)(7) to allow for normal work hour controls to be relaxed during the administratively established 60-day time period.
CNL-22-060 E1 of 8
Enclosure Confirm that the NRC staff's understanding, as described above, is correct regarding the exemption request, as it applies to Category B personnel.
- 2. Regarding Category A personnel, the NRC staff's understanding of TVAs request is that the following condition would apply:
o When the Watts Bar, Unit 2 generator is synced to the electrical grid, the exemption for Category A personnel would end at that time, and TVA would resume control of work hours for these personnel in accordance with 10 CFR 26.205(d)(7).
Confirm that the NRC staff's understanding, as described above, is correct regarding the exemption request, as it applies to Category A personnel.
TVA Response
- 1. TVA confirms that the NRCs understanding, as described above, is correct regarding the exemption request, as it applies to Category B personnel.
- 2. TVA confirms that the NRCs understanding, as described above, is correct regarding the exemption request, as it applies to Category A personnel.
Request for Additional Information:
- 1. Section 26.9 of 10 CFR states, in part, that the Commission may grant exemption from the requirements in 10 CFR Part 26 as it determines are authorized by law and will not endanger life or property or the common defense and security, and are otherwise in the public interest.
To support the NRCs determination as to whether the requested exemption would be otherwise in the public interest, NRC staff are seeking clarification regarding the extent to which TVA took reasonable measures to recognize and mitigate the challenges that necessitated this requested exemption from regulatory requirements. To address this consideration, provide the following information:
- a. Explain what margin, if any, was incorporated into the scheduling of work for the SGR project to account for potential weather-related delays. Specifically, explain how seasonally expected weather conditions were considered when establishing margin within the schedule, and explain why the weather delays that occurred could not have been reasonably anticipated and planned for in the outage schedule.
- b. Explain why the issues that led to the emergent discovery delays listed in Table 4 could not reasonably have been identified and resolved prior to the commencement of the refueling outage.
- c. Describe any other factors, beyond those discussed in the responses to items a and b above, that reasonably affected TVAs ability to conduct planning in a rigorous/thorough manner to allow for identification of potential issues ahead of time.
CNL-22-060 E2 of 8
Enclosure
- 2. Section 26.9 of 10 CFR states, in part, that the Commission may grant exemption from the requirements in 10 CFR Part 26 as it determines are authorized by law and will not endanger life or property or the common defense and security, and are otherwise in the public interest.
Section VI of the submittal states the following:
The added flexibility will provide additional safety margin. There is no negative impact to the public interest as a result of this exemption request while the benefit to the affected employees will result in a positive impact to the public interest.
Provide additional details to support this statement, addressing the following:
- a. Given that the normal outage-related limits on work hours are intended to provide scheduling flexibility that is reasonable to support outage activities while still preventing the unsafe accumulation of fatigue, explain how the added flexibility under the requested exemption would provide additional safety margin.
- b. Discuss how the requested exemption is expected to result in benefit to the affected employees, considering that they will be working under extended work-hour conditions.
- c. Discuss any other factors that may have been considered that justify why the requested exemption would be in the public interest.
TVA Response to RAI 1
- a. TVA developed a project risk register as shown below in Table 1 to this enclosure. This risk register was developed using industry and TVA fleet operating experiences with a focus on the Sequoyah Nuclear Plant (SQN) Units 1 and 2, and Watts Bar Nuclear Plant (WBN)
Unit 1 steam generator (SG) replacements. The SQN Unit 2 SGs were replaced during the fall 2012 outage (U2R18), and the WBN Unit 1 SGs were replaced during the fall 2006 outage (U1R7). The SQN Unit 1 SGs were replaced in the spring 2003 outage (U1R12).
TVA did not have similar experiences with significant wind or snow events during the previous SG replacement outages.
The WBN Unit 2 SGR project was originally scheduled for the fall 2023 outage (U2R5), but it was accelerated to the spring 2022 outage (U2R4) due to inservice inspection results on the original SG-3 (OSG3). Additionally, the outage start date was moved to March 1, 2022, from the planned start date of April 14, 2022, which is typical for a WBN Unit 2 18-month cycle, due to the operational assessment on OSG3, limiting its run time based on the SG inspection results during the fall 2020 outage (U2R3) and the subsequent Cycle 4 fall 2021 mid-cycle outage. Rescheduling the start date of the U2R4 SGR outage was a significant impact for a project of this magnitude in terms of preparation and schedule, while also planning the fall 2021 mid-cycle outage that included inspection of all four SGs. The focus on the risk register was around potential emergent discovery issues based on previous experience. TVA was not able to predict when wind events will occur related to the actual lifts, and it is not typical outage scheduling practice to include external weather impacts directly in the outage schedule. If the weather events are placed in the schedule and do not CNL-22-060 E3 of 8
Enclosure occur as scheduled, then this significantly impacts the outage schedule, job preparation, and coordination, and adversely impacts the overall outage schedule and personnel safety.
Table 1 - Summary of SGR Risk Register
- Risk Item Potential Impact 1 Safety - Behavior reinforcement standdowns 1-day 2 Weather Delays - Severe weather was estimated to 1-day include multiple events, three events for a total of one day.
This was related to potential tornado watches based on the SQN Unit 1 SGR in the spring.
3 Property Damage - Liquidated damages values assigned 1/2-day for standdowns 4 Radiological Conditions - Additional shielding or system 1-day flushing 5 Radiological Release - Free release of vendors equipment 8-hours 6 Polar Crane - Delays due to polar crane being returned to 2-day plant 7 Pipe Weld Rejects - Critical path push for reactor coolant 1-day system (RCS) welds 8 Steel Containment Vessel Weld Reject - Push for critical 1-day path for weld rejects 9 Loss of Containment Power - Inside containment 1-day 10 Rigging Incident - Crane related 1-day 11 Rigging incident non-crane 1-day 12 Contract Liquidated Damages - Added to ensure time for 1/2-day standdowns 13 Dropped Objects - For standdowns 1-day 14 Crane Failures - Based on pre-outage inspections and 1-day crane vendor (Simmers) 15 Concrete Form Failure or Blowout 1-day 16 Radiography Violation - For boundary violation and NRC 1-day review Total Potential Schedule Impact 15 days, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> A cross-discipline team reviewed this risk register and based on the potential aggregate impact, determined that nine days of schedule margin would be added to the schedule, as not all items would likely be a concurrent impact. The aggregate impact on actual weather and emergent discovery items, as of April 24, 2022, is 21 days 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. The heavy lifts related to SGR and the use of the large crane have been completed. However, there is still additional potential for CNL-22-060 E4 of 8
Enclosure emergent issues related to pipe fit-up, welding, support system/component reinstallation, duct-work replacement, and insulation work.
- b. Below is a revised Table 4 from TVA Letter CNL-22-054 (Reference) with the TVA response to RAI 1.b.
Revised CNL-22-054 Table 4 - U2R4 Emergent Discovery Delays Outage Date Description delays (hours)
Main steam rigging frame did not function as designed which required a modification to the frame.
RAI 1.b response: This issue was a result of an 3/27/2022 11 inadequate engineered frame design. When the frame was attached to the pipe and it was rigged up to the horizontal position, the frame bowed. This was a latent design error that was not foreseeable.
Supports PD-15 and PD-21 on SG-1 and SG-2 required significantly more cutting than planned.
RAI 1.b response: The SG cubicles were mapped and modeled, and the cuts were designed based on this 3/29/2022 72 model. The tolerances inside ice condenser plant cubicles are restrictive, and there was not enough margin provided in the models output resulting in additional cuts being required. This was a mapping and modeling limitation.
The SG-1 main steam line pipe has ovality issues, which prevented the cutting machine from effectively cutting the pipe and caused the machine to break.
4/4/2022 8 RAI 1.b response: The ovality issues were not obvious. Previous project operating experiences did not indicate that this was an issue that TVA should have pre-measured or considered.
Identified a fit-up issue between the RSGs and the support columns that required multiple columns to be relocated, template plates to be manufactured and foot bolts holes to be elongated.
4/4/2022 100 RAI 1.b response: The cold spring movement of the columns did not occur until after the SGs were cut out and removed. Previous project operating experience did not identify this significant column support movement.
The setup of the equipment to machine the SG-3 cold leg reactor coolant system was delayed due to the 4/10/2022 136 manufactured condition of the interior of the cast pipe.
CNL-22-060 E5 of 8
Enclosure Revised CNL-22-054 Table 4 - U2R4 Emergent Discovery Delays Outage Date Description delays (hours)
RAI 1.b response: This was an internal condition in the piping that was not identifiable until the pipe was cut and inspected.
Center of gravity of the original steam generator is preventing the straight vertical lift required to remove the construction shims and install permanent shims.
RAI 1.b response: This was an apparent manufacturing 4/12/2022 issue that changed the center of gravity from the design 60 by a small amount, requiring a one-inch shim. The SG was shipped and maintained horizontal until the project used the upender to perform the final vertical lift into the plant. Previous trunnion design used at SQN Unit 2 did not identify similar issue.
The lower compartment cooler ductwork around the SGs was planned to be removed in sections; however, due to interferences, the ductwork was cut into sections for removal and will require additional time and resources to weld the pipe back together.
RAI 1.b response: The area around this ductwork is 4/13/2022 inaccessible for pre-inspection and walkdowns, based 217 on the piping and insulation run over and around the area. WBN Unit 1 had room to move the ductwork aside without cutting it into pieces. Based on small differences in how piping and insulation was installed on WBN Unit 2, TVA did not have the same amount of room and had to make cuts, which requires complicated welding to be completed to repair.
604 Total Hours (25.2 days)
- c. The following are qualitative issues that, in aggregate, have impacted the SGR project schedule to complete the SGR related activities under the 10 CFR 26 regulations.
- 1. The revisions to the SGR project schedule as discussed in the TVA response to RAI 1.a resulted in pre-outage work starting later than normal and continued through the start of the outage.
- 2. The security uninterrupted power supply was out of service twice (February 8, 2022, and February 16, 2022) due to emergent issues, limiting access to the WBN north portal and requiring manual access controls. This impacted workhours during those days for pre-outage work.
- 3. The SGR project received less craft resources than originally requested and planned.
This limited the days off to maintain scheduled activities on-track and impacted the ability to bank hours for the post 60-day period. Additionally, the craft resources that CNL-22-060 E6 of 8
Enclosure were received contained an unusual number of new to nuclear workers that required additional time and effort which resulted in production losses for scheduled activities with durations originally planned based on recent fleet outage experience. Examples below.
x The background investigation data range (December 1, 2021, to April 12, 2022) for the staff-up for the SGR project showed that 52.7 percent of the population was either new to nuclear with initial background checks or updated background checks for personnel out of nuclear from one to three years.
x The SG Team (SGT) project received 30 less carpenters than originally requested, which created a delay in building scaffolding early in the outage, resulting in downstream delays to work for additional craft resources.
x Four people were needed to align and bolt up the RSG foot pad bolts. There were no more than four personnel on the crew resulting in a mixture of experienced and new to nuclear workers doing the bolting.
x Legacy issues required using people on aligning the columns and making templates for the foot pad bolting due to misalignment of the OSGs from original construction.
None of the workers were familiar with the process and had to learn on the job. The manpower for this work came from the same crews setting them.
Reference
- 1. TVA Letter to NRC, CNL-22-054, Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours, dated April 15, 2022 (ML22105A579)
TVA Response to RAI 2
- a. The proposed exemption will provide more flexibility for scheduling personnel because covered individuals will be able to work an additional day per week. This increased flexibility will provide additional opportunity to identify and address any issues that may arise.
Promptly identifying and correcting issues provides additional safety margin to plant personnel and outage craft resources. A similar response was provided by First Energy Corporation on June 9, 2010, in response to an RAI by the NRC (ML101600134) regarding a similar exemption request, which was approved by the NRC [see second bullet in Section VII, Precedent, of the proposed exemption request (TVA Letter CNL-22-054)].
- b. The main purpose behind the work hour rule was to improve safety by managing fatigue.
One of the underlying goals was to improve worker quality of life. Although not relevant to the main purpose of the rule to improve safety by managing fatigue, TVA believes that the flexibility contained in this exemption request will not only be helpful in promoting an effective and efficient startup, but the flexibility also will improve covered employee quality of life by providing additional resources while at work and potentially the opportunity to schedule the day off to a day more convenient to the employee. Furthermore, much of the SGT personnel are transient trade craft. A reduction in work hours would delay the project time and keep the employees away from home longer than expected. A similar response was provided by First Energy Corporation on June 9, 2010, in response to an RAI by the NRC (ML101600134) regarding a similar exemption request, which was approved by the NRC [see second bullet in Section VII, Precedent, of the proposed exemption request (TVA Letter CNL-22-054)].
CNL-22-060 E7 of 8
Enclosure
- c. Approval of this exemption request would ensure that TVA has the needed resources to complete the WBN SGR outage as currently scheduled, avoiding unnecessary impacts to TVAs ability to provide safe and reliable power to the Tennessee Valley during the summer reliability period beginning May 25, 2022. Without the exemption approval, TVA will be challenged from a reliability and environmental compliance perspective, especially as its service territory moves into warmer weather and resulting higher loads. This would result in TVA committing other generators and/or acquiring off-system energy replacements. If some or all of any market replacements can only be procured on a non-firm basis, there is a reliability risk if they are not available. TVA will also be challenged by, or potentially unable to comply with, new emissions regulations limiting generation at its fossil sites, if it needs to commit fossil units to cover the energy that WBN was planned to provide for the system based on its original outage schedule.
CNL-22-060 E8 of 8