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MONTHYEARCNL-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 Project stage: Response to RAI ML19235A2862019-09-0303 September 2019 Summary of Meeting with Tennessee Valley Authority Regarding Request to Adopt Technical Specifications Task Force Traveler TSTF-500 at Watts Bar, Units 1 and 2 Project stage: Meeting ML19241A2962019-09-0606 September 2019 Transmittal of Individual Federal Register Renotice for License Amendment Request TSTF-50 Project stage: Other ML19241A2952019-09-0606 September 2019 Individual Federal Register Renotice for License Amendment Request TSTF-500 Project stage: Other ML19249C6672019-10-0808 October 2019 Revision of Schedule and Level-of-Effort Estimates for Review of License Amendment Requests Project stage: Approval 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) Project stage: Supplement ML19276E5572019-12-0909 December 2019 Issuance of Amendment Nos. 130 and 33 Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-500, DC Electrical Rewrite - Update to TSTF-360 Project stage: Approval 2019-12-09
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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-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-23-069, 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-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu 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-23-015, Expedited 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-22-08)2023-02-27027 February 2023 Expedited 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-22-08) 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-23-009, 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-22-109, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2022-12-22022 December 2022 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements CNL-22-101, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-012022-11-28028 November 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 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-22-098, 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-22-085, 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-22-077, 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-22-039, 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-22-071, 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-22-070, Status Regarding the Improved Flood Mitigation System Project2022-06-30030 June 2022 Status Regarding the Improved Flood Mitigation System Project 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-22-043, 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-22-046, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan.2022-04-28028 April 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan. 2024-01-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-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) 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-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 CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 22017-05-0505 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 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-17-029, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources2017-03-0606 March 2017 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources CNL-17-020, Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 112017-02-16016 February 2017 Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 11 2023-01-04
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Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-1 9-056 June 7, 201 9 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF
-90 Docket No. 50
-390 Watts Bar Nuclear Plant
, Unit 2 Facility Operating License No. NPF
-96 Docket No. 50
-391
Subject:
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 (WBN-TS-1 8-0 9) (EPID L-2018-LLA-0494)
References:
- 1. TVA letter to NRC, CNL 11 8 , "Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF
-500, Revision 2, 'DC Electrical Rewrite
- Update to TSTF -360' (WBN-TS-18-09)," dated November 2 9, 2018 (ML18334A389) 2. NRC Electronic Mail to TVA, "Watts Bar Nuclear Plant
- Final Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF
-500, Revision 2 (EPID L-2018-LLA-0494)" dated May 3, 2019 (ML19011A34
- 9) In Reference 1, TVA submitted a request for an amendment to the technical specifications (TS) for Watts Bar Nuclear Plant (WBN), Units 1 and 2. The proposed amendment revises TS requirements related to direct current (DC) electrical systems in accordance with Technical Specification Task Force (TSTF) Traveler TSTF-500, Revision 2, "DC Electrical Rewrite
- Update to TSTF
-360." In Reference 2, NRC issued a Request for Additional Information (RAI) and requested TVA respond by June 7, 2019. Enclosure 1 to this letter provides the response to the RAI.
As noted in Enclosure 1, the response to this RAI necessitates changes to the proposed TS 3.8.4 and 3.8.6 in Reference 1. Accordingly, Enclosure 2 provides markups of the existing TS and Bases pages to show the proposed changes. Enclosure 3 provides revised (clean) TS pages. The proposed TS changes in Enclosures 2 and 3 supersede the corresponding TS provided in Reference 1.
U.S. Nuclear Regulatory Commission CNL-19-056 Pag e 2 June , 201 9 The enclosure s to this l etter do not change t he no significant hazard considerations or t he environmental considerations contained in Reference 1.
Additionally, in accordance with 10 CFR 50.91(b)(1), TVA i s sending a co py o f this letter and the enclosure to t he Tennessee Department o f Environment and Conservation.
Enclosure 4 contains t he revised regulatory commitment associated wit h this su bmittal that supersede s t he commitment provided in Reference 1. Please addr ess a ny questions regarding t his request t o Kim berly D. Hulvey at (423) 751-3 275. I dec lare under penal ty o f pe rjury t hat t he foregoing is t rue and c orrect. Executed on t his th day o f June 201 9. Respectfully, Erin K. Henderson Director, Nuclear Regulatory Affairs
Enclosures:
1.Response to NRC Request for Additional Information Regarding LicenseAmendment Request to Revise Technical Specifications to Adopt TechnicalSpecifications Task Force (TSTF)
-500, Revision 2, "
DC Electrical Rewrite
-Update to TSTF-360" Docket Nos. 50
-390 and 50
-391 2.Markups of Technical Specification s and Bases Changes 3.Clean Technical Specification s and Bases Changes 4.Revised Regulatory Commitment cc (Enclosures): NRC Regional Administrator
- Region II NRC Project Manager - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation CNL-19-056 E 1-1 of 11 Response to NRC Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) -500, Revision 2, "DC Electrical Rewrite
- Update to TSTF
-360" Docket Nos. 50-390 and 50-391 INTRODUCTION By letter dated November 29, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession number ML18334A389), Tennessee Valley Authority (TVA, the licensee), requested an amendment to Facility Operating Licenses NPF
-90 and NPF
-96 for Watts Bar Nuclear Plant (WBN), Units 1 and 2. The proposed license amendment request would revise the WBN Units 1 and 2 TS to adopt the Nuclear Regulatory Commission (NRC)
-approved Technical Specifications Task Force (TSTF)
-500, Revision 2, "DC [direct current] Electrical Rewrite
- Update to TSTF
-360." Specifically, the licensee proposed changes to the TS requirements related to DC electrical power systems in TS 3.8.4, "DC sources
- Operating," TS 3.8.5, "DC Sources - Shutdown," and TS 3.8.6, "Battery Cell Parameters." Additionally, the licensee proposed to add to the TS Section 5.7, "Procedures, Programs, and Manuals," a new program titled "Battery Monitoring and Maintenance Program."
The Electrical Engineering Operating Branch (EEOB) staff has determined that the following additional information is needed to complete the review of the WBN license amendment request (LAR). Regulatory Requirements Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), Section 36, "Technical Specifications," requires, in part, that the operating license of a nuclear production facility include TS. 10 CFR 50.36 (c)(2) requires that the TS include limiting conditions for operation (LCOs) which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
10 CFR 50, Appendix A, General Design Criterion (GDC) 17, "Electric power systems," states, in part, that "an onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety.- The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure."
Regulatory Guidance TSTF-500, Revision 2, "DC Electrical Rewrite
- Update to TSTF
-360," dated September 22, 2009 (ADAMS Accession No. ML092670242).
CNL-19-056 E 1-2 of 11 EEOB RAI -1 The licensee proposed a new TS 3.8.4 Condition A with associated Required Actions and Completion Time for the required vital battery charger(s).
Condition A would state: Condition A One or two required vital battery charger (s) on one subsystem inoperable Required Actions A.1, A.2, and A.3 would state:
Required Action A.1 Restore battery terminal voltage to greater than or equal to the minimum established float voltage. Completion Time 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND Required Action A.2 Completion Time Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> In Enclosure 4 of the LAR, the licensee provided a commitment to include in the WBN updated safety analysis report (UFSAR) "a requirement to maintain a 2 percent design margin for the vital batteries which corresponds to a 2 amp float current value being used as an indication that the battery is at least 98 percent charged."
In Enclosure 6 of the LAR, the licensee stated that the "normal recharging of the battery from the design discharged condition can be accomplished in approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (with accident loads being supplied) following a 30
-minute AC power outage and in approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (with normal loads being supplied) following a 4
-hour AC power outage."
The NRC has identified the following discrepancies:
The 2-amp float current value for the vital batteries provides an indication that the batteries are less than 100 percent charged. It does not appear that a discussion about how the 2 percent design margin would ensure that the vial batteries would be 100 percent charged at a 2
-amp float current was provided.
It appears that it could take longer than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to fully recharge a vital battery that would be discharged for a period longer than 30 minutes before connecting the spare charger.
The staff requests the following information to address these discrepancies:
a) Explain how maintaining a "2 percent design margin - as an indication that the battery is at least 98 percent charged" will ensure that the WBN vital batteries are fully charged (i.e., capable of performing their design function). b) Provide a discussion to demonstrate that the vital battery can be fully recharged in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from Condition A after a 2
-hour discharge (i.e., the time allowed by Required Action A.1 to place the spare charger on the battery).
CNL-19-056 E 1-3 of 11 TVA Response to EEOB RAI -1 a) TVA has verified
, via the battery manufacturer
, that a charging current less than or equal to two amps (A) is an indication that the battery is at least 98 percent charged. Therefore, maintaining an additional two percent design margin in the WBN battery sizing calculation is needed to ensure that 100 percent battery capacity is available once charging current is 2 A or less. This is equivalent to the battery being 100 percent charged, because the sizing calculation ensures that the battery can perform its safety related function during a design bases event.
b) The time to return the battery to its fully charged condition is a function of the battery charger capacity, the amount of loads on the associated direct current (DC) system, the amount of the previous discharge, and the recharge characteristic of the battery. Total normal steady state loads on the battery chargers average less than 100 A based on walk down data. Each vital battery is rated for 2320 A
-hours. Each battery charger is rated for 200 A.
200 A available
- 100 A steady state load = 100 A excess capacity for battery charging.
Assuming the battery charger is offline for two hours (the time allowed by TSTF
-500 to place a charger on the battery) and assuming normal steady state DC system loads remain on battery during this time would equate to a two hour x 100 A (or 200 A
-hour) loss. Assuming 110 percent of 200 A
-hour (or 220 A-hour) would be required to restore the battery to a fully recharged state and given the 100 A excess battery charger capacity above, the battery can be restored to fully recharged within:
220 A-hour / 100 A = 2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
However, because the battery chargers are constant voltage chargers rather than constant current chargers, it is recognized that the battery charging current will taper off from the initial maximum current that the charger can supply to a final value of less than 2 A. TVA does not possess battery recharge current characteristic curves, but it is considered reasonable to expect that the battery would be fully recharged in less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to less than 2 A charging current, given the above charger capacity and relatively small amount of capacity removed from the batteries.
EEOB RAI-2 The licensee proposed a new TS 3.8.4 Condition D with associated Required Actions and Completion Time for the diesel generator (DG) battery charger(s).
Condition D would state:
Condition D One DG DC battery charger inoperable Required Actions D.1, D.2, and D.3 would state:
Required Action D.1 Restore DG battery terminal voltage to greater than or equal to the minimum established float voltage.
Completion Time 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> CNL-19-056 E 1-4 of 11 AND Required Action D.2 Verify Completion Time Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Required Action D.3 Restore DG battery charger to OPERABLE status Completion Time 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> In Enclosure 4 of the LAR, the licensee provided a commitment to include in the WBN UFSAR "a requirement to maintain a 2 percent design margin for the DG batteries which corresponds to a 1 amp float current value being used as an indication that the battery is at least 98 percent charged." The NRC has identified the following discrepancies:
The 1-amp float current value for the DG batteries provides an indication that the DG batteries are less than 100 percent charged. It does not appear that a discussion about how the 2 percent design margin would ensure that the vial batteries would be 100 percent charged at a 2
-amp float current was provided.
The 12-hour and 72
-hour completion times for verifying battery float current and for restoring the battery to operable status, respectively, are bracketed in the TSTF
-500. It does not appear that the bases for the proposed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for Required Actions D.2 and D.3, respectively, were provided.
The staff requests the following information to address these discrepancies:
a) Explain how maintaining a "2 percent design margin - as an indication that the battery is at least 98 percent charged" will ensure that the WBN DG batteries are fully charged (i.e., capable of performing their design function).
b) Provide the WBN basis for the 12
-hour and the 72
-hour completion times for Required Actions D.2 and D.3, respectively.
TVA response to EEOB RAI
-2 a) TVA has verified via the DG battery manufacturer that a charging current less than or equal to 1 A is an indication that the battery is at least 98 percent charged. Therefore, maintaining an additional 2 percent design margin in the WBN battery sizing calculation is needed to ensure that 100 percent battery capacity is available once charging current is 1 A or less. This is equivalent to the battery being 100 percent charged, because the sizing calculation ensures that the battery can perform its safety related function during a design bases event.
b) The 12-hour time to return the DG battery to its fully charged condition in this case is a function of the battery charger capacity, the amount of loads on the associated DG DC system, the amount of the previous discharge, and the recharge characteristic of the battery. Typical normal steady state loads on a DG battery charger is 10.41 A, based on pre-operational testing of DG battery charger 2B-B. Each DG battery is rated for 192 A-hours. Each battery charger is rated for 20 A. 20 A available
- 10.41 A steady state load = 9.59 A excess capacity for battery charging.
CNL-19-056 E 1-5 of 11 Assuming the battery charger is offline for two hours (the time allowed by TSTF
-500 to place a charger on the battery) and assuming normal steady state DG DC system loads remain on battery during this time would equate to a two hour x 10.41 A (or 20.82 A-hour) loss. Assuming 110 percent of 20.82 A
-hour (or 22.90 A
-hour) would be required to restore the battery to a fully recharged state and given the 9.59 A excess battery charger capacity above, the battery can be restored to fully recharged within:
22.90 A-hour / 9.59 A = 2.39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />.
However, because the battery chargers are constant voltage chargers rather than constant current chargers, it is recognized that the battery charging current will taper off from the initial maximum current that the charger can supply to a final value of less than 1 A. TVA does not possess battery recharge current characteristic curves, but it is considered reasonable to expect that the battery would be fully recharged in less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to less than 1 A charging current, given the above charger capacity and relatively small amount of capacity removed from the batteries.
The 72-hour completion time for the DG batteries is consistent with the 72
-hour completion time for TS 3.8.4, Required Action A.3, and TS 3.8.5, Required Action A.3 in TSTF-500. As noted in TSTF
-500, the 72-hour completion time must be adopted unless a licensee wishes to adopt a longer completion time. Furthermore, the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> will allow, in many cases, a sufficient period of time to correct a charger problem. The 72-hour completion time is also commensurate with the importance of maintaining the DG DC system's capability to adequately respond to a design basis event.
EEOB RAI-3 The licensee proposed to revise SR 3.8.4.12 and renumber it as SR 3.8.4.6.
Renumbered SR 3.8.4.6 would state:
SR 3.8.4.6 --------------------------------------NOTE-----------------------------------------
Credit may be taken for unplanned events that satisfy this SR.
Verify ea OR Verify each DG battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
The NRC staff notes that a discussion about the basis for the proposed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> testing durations in the renumbered SR 3.8.4.6 was not provided.
CNL-19-056 E 1-6 of 11 Explain the basis for the proposed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> testing durations for the WBN DG battery chargers.
TVA Response to EEOB RAI
-3 Current TS SR 3.8.4.12 requires verification every 18 months that each DG battery charger is capable of recharging the associated battery from a service or capacity discharge test while supplying normal loads. TVA has decided to not adopt the TSTF
-500 SR option to verify that an or equal to the minimum recharging the associated battery from a service or capacity discharge test while supplying normal loads is sufficient to verify the operability of the battery charger. Enclosure s 2 and 3 provide the revised Technical Specifications (TS) and Bases to reflect this change.
Regarding the basis for the 24
-hour testing duration for the DG batter chargers, the WBN battery sizing calculations for the DG batteries indicate that the battery chargers are capable of fully charging the batteries within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, while simultaneously supporting the connected loads. Similar to the response to EEOB RAI
-2b, the time to return the DG battery to its fully charged condition is a function of the battery charger capacity, the amount of loads on the associated DG DC system, the amount of the previous discharge, and the recharge characteristic of the battery. Typical normal steady state loads on a DG battery charger is 10.41 A, based on pre-operational testing of DG battery charger 2B
-B. Each battery charger is rated for 20 A.
20 A available
- 10.41 A steady state load = 9.59 A excess capacity for battery charging.
The duty cycle for the DG batteries is based on the batteries supplying DG loads without benefit of chargers for four hours during a station blackout (SBO) event. The duty cycle of the DG batteries for a SBO event is approximately 66.5 A hours. Therefore, recharging the DG battery would equate to 66.5 A
-hours / 9.59 A = 6.93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br /> (assuming the battery is completely discharged and assuming normal steady state DG DC system loads remain on battery during this time).
Assuming 110 percent of DG battery capacity of 66.50 A
-hour (or 73.15 A
-hour) would be required to restore the battery to a fully recharged state and given the 9.59 A excess battery charger capacity above, the battery can be restored to fully recharged within:
73.15 A-hours / 9.59 A = 7.63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br />.
However, because the battery chargers are constant voltage chargers rather than constant current chargers, it is recognized that the battery charging current will taper off from the initial maximum current that the charger can supply to a final value of less than 1 A. TVA does not possess battery recharge current characteristic curves, but it is considered reasonable to expect that the battery would be fully recharged in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to less than 1 A charging current, given the above charger capacity and relatively small amount of capacity removed from the batteries.
CNL-19-056 E 1-7 of 11 EEOB RAI-4 In Enclosure, Section 1.0 of the LAR, the licensee proposed relocating the Technical Specification (TS) Table 3.8.6
-1, "Battery Surveillance Requirements," to the proposed Battery Monitoring and Maintenance Program in TS 5.7. The Table 3.8.6
-1 includes Category A, B, and C limits for the battery cell parameters (i.e., electrolyte level, float voltage, specific gravity).
Confirm that the battery cell parameters (electrolyte level, float voltage, specific gravity) will continue to be controlled at their current Categories A, B, and C levels in the TS Battery Monitoring and Maintenance Program, and that actions to restore deficient values will be implemented in accordance with the licensee's corrective action program.
TVA Response to EEOB RAI
-4 TVA confirms that the battery cell parameters (electrolyte level, float voltage, specific gravity) will be relocated to the Battery Monitoring and Maintenance Program at their current Categories A, B, and C levels. The battery cell parameters within the program will be controlled consistent with IEEE 450
-2002, as specified in proposed TS 5.7.2.22, "Battery Monitoring and Maintenance Program." Actions to restore deficient values of any of the battery cell parameters specified in the program will be tracked and implemented in accordance with the TVA corrective action program.
EEOB RAI-5 The proposed new TS 3.8.6 Condition A would apply when one DG battery is found with one or more battery cell(s) with a float voltage of less than 2.07 volts (V).
The NRC staff notes that the 2.07
-V for the battery cell float voltage is bracketed in TSTF
-500. It does not appear that the basis for the proposed 2.07
-V limit for the WBN DG battery cell float voltage was provid ed. Explains the WBN basis for the 2.07
-V limit for the WBN DG battery cell float voltage.
TVA Response to EEOB RAI
-5 The 2.07 volt limit is consistent with the most limiting float voltage limit in WBN TS Table 3.8.6-1, "Battery Cell Parameters Requirements." The WBN battery cells are of the vented lead
-acid type with a nominal electrolyte specific gravity of 1.215. Open circuit voltage of the lead-acid battery cell is related to the specific gravity by a constant as shown in the following:
Open Circuit Voltage = Specific Gravity + 0.845 Therefore, for the WBN battery cells, the nominal cell open circuit voltage is 1.215 + 0.845 = 2.06 volts DC. A cell voltage of less than or equal to cell open circuit voltage indicates the cell is no longer being floated at a voltage sufficient to prevent discharge.
CNL-19-056 E 1-8 of 11 EEOB RAI-6 The licensee proposed adding a new TS 3.8.6 Condition F which would apply to one or two required vital battery (ies) on one subsystem or one DG battery found with a pilot cell electrolyte temperature less than the minimum established design limits. The Required Action F.1 would restore the pilot cell electrolyte temperature to greater than or equal to minimum establis hed design limits within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In Enclosure 1 of the LAR, the licensee states: "TVA verifies that battery room temperature is routinely monitored such that a room temperature excursion could reasonably expect to be detected and corrected prior to the average battery electrolyte temperature dropping below the minimum electrolyte temperature."
Regarding the selection of pilot cells, the TSTF
-500 states:
Previously, average battery temperature was monitored instead of pilot cell temperature. As a result, temperature was not a criterion with selecting a pilot cell. In order to use pilot cell temperature instead of the average battery temperature, temperature must be used as a criterion when selecting the pilot cell. [-] For batteries where it could be shown that the maximum temperature deviation across the battery did not exceed the IEEE 450 recommended maximum of 5°F [degrees Fahrenheit], the NRC has accepted that the cell temperature was not a critical parameter. Therefore, for these batteries, cell temperature did not have to be taken into account when selecting pilot cells.
The NRC has identified the following discrepancies:
It appears that a discussion about the frequency of monitoring the battery room and how the battery room temperature would be restored if it was outside the temperature design limits was not provided.
It appears that a discussion about the selection of the WBN battery pilot cell based on temperature was not provided.
The staff requests the following information to address these discrepancies:
a) Provide a discussion about how the vital and DG battery rooms temperatures are monitored at WBN and provide the minimum frequencies at which the temperatures are monitored. Also explain how the licensee would restore the vital and DG battery rooms' temperatures if they were outside the temperature design limits.
b) Provide a discussion about the selection of the battery pilot cell based on temperature. If the temperature will not be used as a criterion for selecting battery pilot cells, provide an analysis of temperature deviations for the WBN batteries based on operation experience to show that the maximum temperature deviation across the batteries does not exceed the IEEE 450 recommended maximum of 5°F.
CNL-19-056 E 1-9 of 11 TVA Response to EEOB RAI
-6 a) The temperatures of the vital battery rooms and DG battery rooms are monitored once per shift (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) by Operations personnel. This satisfies Technical Requirement Manual (TRM) Surveillance Requirement (TSR) 3.7.5.1 to verify each area temperature is within limits every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The room temperatures are documented in the applicable Shift and Daily Surveillance Log and verified to be in compliance with TSR 3.7.5. For the vital battery rooms, the Auxiliary Building heating, ventilation, and air conditioning (HVAC) is designed to maintain the room temperature and relative humidity within the environmental design limits. The Auxiliary Building HVAC operating procedures include compensatory actions for coping with and recovery from loss of train cooling so that design temperatures for the area are not exceeded. For the DG batteries, the DG building ventilation system is design to maintain temperatures within the limits of the environmental design criteria. Should the battery room temperatures approach temperature limits specified in TR 3.7.5 , operations would employ existing HVAC features to improve room temperatures. DG room dampers may be closed to isolate outside air or fans can be energized to circulate air. Should design features fail to provide the needed heating or cooling, the site could proceed with temporary equipment installation or DG operation, if increasing room temperature is warranted.
b) WBN's current vital and DG battery surveillance performance practices and a review of actual electrolyte temperature deviations for these batteries demonstrates compliance with the IEEE 450 recommended maximum temperature deviation of 5°F.
Current WBN weekly surveillance instructions identify the basis for pilot cell section is based on voltage and specific gravity parameters, because cell temperatures are typically maintained within +/-3° F. The review of actual quarterly battery surveillance data since 2014 for the five vital batteries included 12 cells per battery for approximately 20 tests with a total of 100 tests reviewed. All recorded vital battery electrolyte temperatures were within the IEEE 450 recommended maximum of 5°F. The review of actual quarterly battery surveillance data since 2014 for the four DG batteries included 12 cells per battery for approximately 21 tests with a total of 84 tests reviewed. The tests were conducted at various times of the year, which is representative of the full range of ambient temperatures the DG rooms are subjected to. The recorded DG battery electrolyte temperatures were within the IEEE 450 recommended maximum of 5° F. This data supports that the maximum temperature deviation across the vital and DG batteries does not exceed the IEEE 450 recommended maximum of 5° F. This is consistent with the IEEE 450 recommendations for determining that cell temperature is not a critical parameter for selection of pilot cells. Therefore, the vital and DG battery pilot cells will not be chosen based on temperature.
EEOB RAI-7 The licensee proposed a new TS 3.8.6 Condition G out
-of-limit parameters for batteries in redundant subsystems based on the TSTF
-500 TS 3.8.6 Condition E for NUREG
-1431, "Standard Technical Specifications Westinghouse Plants," Revision 1.
WBN TS 3.8.6 Condition G and associated Required Action G.1 would state:
Condition G One or more batteries in redundant subsystems with battery parameters not within limits.
OR More than one DG battery with battery parameters not within limits.
CNL-19-056 E 1-10 of 11 Required Action G.1 Restore battery parameters to within limits.
Completion Time 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> The NRC has identified the following discrepancies:
The first option of the proposed Condition G did not specify the type of batteries which the condition pertains to.
The Required Action E.1 in TSTF
-500 restores the parameters for the batteries in one subsystem whereas the proposed Required Action G.1 would restore the parameters for all batteries [in the redundant (both) subsystems].
a) Clarify the type of batteries that would be addressed in in the first option condition of the proposed TS 3.8.6 Condition G.
b) Explain the basis for deviating from the TSTF
-500 Required Action for restoring th e parameters for the batteries in one subsystem.
TVA Response to EEOB RAI-7 a) TS 3.8.6, Condition G, is being revised to indicate that the first option applies to the vital batteries. See the revised TS and Bases in Enclosure s 2 and 3. b) TS 3.8.6, Condition G and associated Required Actions, for vital batteries are being revised to be consistent with TSF
-500. Because the DG batteries support DGs that are arranged in trains (i.e., DG 1A
-A and 2A-A are in Train A, and DG 1B
-B and 2B-B are in Train B), a new condition (Condition H) has been added to address multiple DG batteries in redundant trains with parameters not within limits. The required actions are consistent with TSTF
-500, in that they require the restoration of the DG batteries in one train to within limits in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This will ensure that the DG batteries either can support the operation of one train of DGs or are declared inoperable. Subsequent conditions have been re
-lettered accordingly.
Consistent with the above change, changes are being made to TS 3.8.4, Condition D, so that the condition applies to one or two inoperable DG battery chargers in one train. The wording of TS 3.8.4, Condition E, is being changed from referring to DG DC subsystem to referring to a DG DC train to be consistent with the terminology used for the arrangement of the DGs. See the revised TS and Bases in Enclosure s 2 and 3. Each DG DC electrical power system is independent and dedicated to its respective DG. The DGs that are supported by the DG DC electrical power systems are arranged in redundant trains (i.e., DG 1A
-A and DG 2A
-A are in Train A, and DG 1B
-B and DG 2B
-B are in Train B). When one or two DGs in a train are inoperable, that train of standby electrical power is incapable of performing the safety function and must rely on the redundant DG train to mitigate an event. Likewise, if one or two of the DG DC trains that support the DGs in that train are inoperable, that train of standby electrical power is incapable of performing the safety function and must rely on the redundant train to mitigate an event. Therefore, the LCO requires Train A and Train B DG DC electrical power subsystems to be OPERABLE to support the redundancy of the standby electrical power system.
CNL-19-056 E 1-11 of 11 EEOB RAI-8 In Enclosure 4 of the LAR, the licensee provided a commitment to verify that plant procedures will require verification of the selection of the pilot cell or cells when performing SR 3.8.6.5. The proposed new SR 3.8.6.5 would verify that each required vital battery and each DG battery pilot cell temperature is greater than or equal to minimum established design limits.
The NRC staff notes that the verification of the selection of the pilot cell or cells should be done when performing the SR that verifies the battery connected cell float voltage, as stated in the TSTF-500. Provide the justification for deviating from the TSTF
-500 with respect to the verification of the selection of the pilot cell during the SR for battery cell float voltage.
TVA Response to EEOB RAI-8 TVA is providing a corrected commitment to verify that plant procedures will require verification of the selected battery pilot cell during performance of SR 3.8.6.6 (verification of battery cell float voltage), consistent with TSTF
-500. This commitment supersedes the commitment provided in the referenced LAR to verify that plant procedures will require verification of the selected battery pilot cell during performance of SR 3.8.6.5. The revised commitment is provided in Enclosure 4.
The revised commitment also corrects the title of the reference to TS 5.7, "Procedures, Programs, and Manuals
." Reference TVA letter to NRC, CNL 118, "Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF
-500, Revision 2, 'DC Electrical Rewrite
- Update to TSTF
-360' (WBN-TS-18-09)," dated November 29, 2018 (ML18334A389)
Markups of Technical Specification and Bases Changes CNL-1-E2-1
Markups of Technical Specification and Bases CNL-1-E2-
Markups of Technical Specification and Bases CNL-1-E2-
Clean Technical Specification and Bases Changes CNL-1-E3-1
Technical Specification and Bases CNL-1-E-
Technical Specification and Bases CNL-1-E-
Revised Regulatory Commitment CNL-1 9-056 E4-1 Commitment Due Date/Event TVA commits that the licensee
-controlled program, required and described in TS Section 5.7, "Procedures, Programs, and Manuals," and titled, "Battery Monitoring and Maintenance Program," will require verification of the selection of the pilot cell or cells when performing SR 3.8.6.6
. Prior to implementation of the approved TSTF
-500 license amendment