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EPID:L-2017-LLA-0391, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. (Approved, Closed) |
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MONTHYEARCNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. Project stage: Request ML17347A0252017-12-12012 December 2017 NRR E-mail Capture - TVA Nuclear Plants - Acceptance for Review - Application to Modify the TSs for TVA Plants to Resolve Bl 2012-01 Issues Project stage: Acceptance Review ML18213A3192018-08-17017 August 2018 Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant - Summary of Regulatory Audit to Support Review of License Amendment Request to Incorporate New Technical Specification for Unbalanced Voltage Relays Project stage: Approval CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays Project stage: Request CNL-19-023, Plants - Supplement to Application to Modify the Technical Specifications for the Browns Ferry Nuclear Plant (TS-512), Sequoyah Nuclear Plant (TS-17-03)and Watts Bar Nuclear Plant (TS-17-20) to ...2019-01-25025 January 2019 Plants - Supplement to Application to Modify the Technical Specifications for the Browns Ferry Nuclear Plant (TS-512), Sequoyah Nuclear Plant (TS-17-03)and Watts Bar Nuclear Plant (TS-17-20) to ... Project stage: Request ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection Project stage: Approval CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)2019-10-23023 October 2019 Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22) Project stage: Request 2018-08-17
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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:Technical Specification
MONTHYEARCNL-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) WBL-23-052, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual2023-11-0808 November 2023 Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual 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-23-028, 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-23-020, 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) ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) 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-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) WBL-22-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual2022-05-11011 May 2022 Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual ML20273A0432020-09-29029 September 2020 Plants Unit 1 and 2 - Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual CNL-20-008, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28)2020-07-27027 July 2020 Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28) CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)2020-06-22022 June 2020 Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) CNL-20-004, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01)2020-01-17017 January 2020 Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology2020-01-17017 January 2020 Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)2019-10-23023 October 2019 Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22) 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) L-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual2019-03-19019 March 2019 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-006, Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)2018-01-10010 January 2018 Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01) CNL-17-149, Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-12-27027 December 2017 Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) ML17321A0332017-11-16016 November 2017 Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) ML17306A8022017-11-0202 November 2017 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual NL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-09-29029 September 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) 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-17-022, Application to Modify Technical Specification 5.7.2.19 Regarding One-Time Extension of 10 CFR 50, Appendix J Type C Local Leakage Rate Tests (391-WBN-TS-17-05)2017-02-16016 February 2017 Application to Modify Technical Specification 5.7.2.19 Regarding One-Time Extension of 10 CFR 50, Appendix J Type C Local Leakage Rate Tests (391-WBN-TS-17-05) ML16113A0772016-04-22022 April 2016 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F2015-12-15015 December 2015 Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F ML15267A1832015-09-23023 September 2015 Watts Bar, Unit 2 - Submittal of Final Revision 0 of the Technical Specifications & Technical Specification Bases, and Final Revision 0 of the Technical Requirements Manual & Technical Requirements Manual Bases NL-15-181, Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mod2015-09-0303 September 2015 Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode CNL-15-181, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode 42015-09-0303 September 2015 Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode 4 CNL-15-133, Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-07-15015 July 2015 Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)2015-06-17017 June 2015 Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13) CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-04-0606 April 2015 Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)2015-03-31031 March 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) CNL-14-217, Responses to Requests for Additional Information - Developmental Revision I Technical Specification Sections 3.8 and 5.72015-03-0505 March 2015 Responses to Requests for Additional Information - Developmental Revision I Technical Specification Sections 3.8 and 5.7 CNL-14-180, Technical Specification Sections 3.0 and 3.10.12015-01-22022 January 2015 Technical Specification Sections 3.0 and 3.10.1 ML14307A9812014-11-0303 November 2014 Periodic Submission for Changes Made to Technical Specification Bases and Technical Requirement Manual ML14170A0442014-06-16016 June 2014 Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D ML14170A0452014-06-16016 June 2014 Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0462014-06-16016 June 2014 Attachment 2 - TS Bases Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML13357A0512013-12-12012 December 2013 Synopsis of Revisions Included in Watts Bar Unit 2 Developmental Revision H of Technical Specifications and Technical Specification Bases. Part 2 of 2 ML13357A0542013-12-12012 December 2013 Technical Specifications Bases ML13353A4782013-12-12012 December 2013 Fuel Handling Accident Dose Analysis Final Safety Analysis Report and Technical Specification Revision ML12333A2422012-11-20020 November 2012 Application to Modify Technical Specification 4.3.1, Criticality, (WBN-TS-12-03) ML12333A2402012-11-19019 November 2012 Unit I, Application to Modify Technical Specification 3.7.10, Control Room Emergency Ventilation System (WBN-TS-12-01) ML12240A2242012-08-23023 August 2012 Update to Technical Requirements Manual (TRM) Bases Section 3.7.2, Developmental Revision B ML12065A0352012-02-28028 February 2012 Watts Bar, Unit 2 - Technical Specifications Table of Contents Through Page B 3.9-32 ML12065A0362012-02-28028 February 2012 Submittal of Developmental Revision G of the Unit 2 Technical Specification (TS) and Technical Specification Bases 2023-09-20
[Table view] Category:Amendment
MONTHYEARCNL-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-23-059, 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 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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-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-20-008, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28)2020-07-27027 July 2020 Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28) CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)2020-06-22022 June 2020 Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) CNL-20-004, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01)2020-01-17017 January 2020 Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)2019-10-23023 October 2019 Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22) 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-17-149, Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-12-27027 December 2017 Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) ML17321A0332017-11-16016 November 2017 Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) NL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-09-29029 September 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) 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-15-133, Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-07-15015 July 2015 Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)2015-06-17017 June 2015 Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13) CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-04-0606 April 2015 Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)2015-03-31031 March 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) ML14170A0462014-06-16016 June 2014 Attachment 2 - TS Bases Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0452014-06-16016 June 2014 Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0442014-06-16016 June 2014 Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D ML11228A0472011-08-10010 August 2011 Technical Specifications (Developmental Revision F), Enclosure 1 ML1022900752010-08-16016 August 2010 Unit 2 - Change to Developmental TS Section 4.2.2, Control Rod Assemblies ML1005504412010-02-0202 February 2010 Developmental Revision B - Technical Specifications 2.0 - Safety Limits ML1005503672010-02-0202 February 2010 Developmental Revision B - Technical Specifications Table of Contents ML1005504742010-02-0202 February 2010 Developmental Revision B - Technical Specifications 5.0 - Administrative Controls ML1005504712010-02-0202 February 2010 Developmental Revision B - Technical Specifications 4.0 - Design Features ML1005504012010-02-0202 February 2010 Developmental Revision B - Technical Specifications 1.0 - Use and Application ML1005504472010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.0 - Limiting Condition for Operation (LCO) Applicability ML1005504642010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.9 - Refueling Operations ML1005504492010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.1 - Reactivity Control Systems ML1005504622010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.8 - Electrical Power Systems ML1005504612010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.7 - Plant Systems ML1005504502010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.2 - Power Distribution Limits ML1005504512010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.3 - Instrumentation ML1005504532010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.4 - Reactor Coolant System ML1005504562010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.5 - Emergency Core Cooling Systems ML1005504582010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.6 - Containment Systems ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0913205622009-04-30030 April 2009 Application for Technical Specification Change to Correct Minor Error in Amendment 70 ML0900900442008-12-31031 December 2008 Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle ML0831708612008-11-12012 November 2008 License Amendment Request TS-08-11 to Revise Reactor Coolant System Leakage Detection Systems - Exigent Change Request ML0712106042007-04-25025 April 2007 (WBN) Unit 1 - Technical Specification Change 07-01, Revision of Number of Tritium Producing Burnable Absorber Rods (TPBARS) in the Reactor Core ML0616502672006-06-12012 June 2006 Technical Specifications (TS) Change WBN-TS-05-10 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity - Request for Additional Information ML0526500612005-09-20020 September 2005 T.S. for License Amendment, Regarding Alternative Means for Monitoring Control or Shutdown Rod Position ML0509802082005-03-21021 March 2005 Tech Spec Pages for Amendment No. 57, Elimination of Monthly Report Requirement on Operating & Occupational Reports (TS-04-15) 2023-09-20
[Table view] |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-19-097 October 23, 2019 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391
Subject:
Watts Bar Nuclear Plant, Units 1 and 2, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)
Reference:
- 1. TVA letter to NRC, CNL-17-034, "Application to Modify Technical Specification for Browns Ferry Nuclear Plant (TS-512), Sequoyah Nuclear Plant (TS-17-03) and Watts Bar Nuclear Plant (TS-17-20) to resolve Open Phase Issue Identified in NRC Bulletin 2012-01, 'Design Vulnerability in Electrical Power System,' "dated November 17, 2017 (ML17324A349)
- 2. TVA Letter to NRC, CNL-18-130, Revised Application to Modify the Technical Specifications for the Browns Ferry Nuclear Plant (TS-512),
Sequoyah Nuclear Plant (TS-17-03) and Watts Bar Nuclear Plant (TS-17-20) to Incorporate New Technical Specification for Unbalanced Voltage Relays, dated November 19, 2018 (ML18324A609)
- 3. NRC Letter to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection (EPID L-2017-LLA-0391)," dated August 27, 2019 (ML18277A110)
In References 1 and 2, Tennessee Valley Authority (TVA) submitted a fleet-wide license amendment request (LAR) to change the Technical Specifications (TS) for the TVA fleet to propose adding a new level of protection, Unbalanced Voltage, to the TS for the loss of power (LOP) instrumentation for the Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN). In Reference 3, the Nuclear Regulatory Commission (NRC) approved the LAR for BFN (Amendment Nos. 309, 332, and 292), SQN (Amendment Nos. 345 and 339), and WBN (Amendment Nos. 128 and 31). The license amendments are required to be implemented no later than December 25, 2019.
U.S. Nuclear Regulatory Commission CNL-19-097 Page 2 October 23, 2019 After the issuance of Reference 3, TVA identified the following three incorrect instrument values in WBN Units 1 and 2 TS Table 3.3.5-1, LOP DG Start Instrumentation, Function 5, 6.9 kV Emergency Bus Undervoltage (Unbalanced Voltage).
The Allowable Value (AV) for the unbalanced voltage relay (UVR) low trip voltage The AV for the UVR high trip time delay The Trip Setpoint for the UVR high trip time delay The above errors were attributable to transcription errors in References 1 and 2. The correct instrument values were reflected in the TVA UVR setpoint calculation that was in effect when References 1 and 2 were submitted to the NRC. This issue has been entered into the TVA Corrective Action Program.
The UVR low trip voltage AV, as approved by the NRC in Reference 3, exceeds the designated AV in the TVA setpoint calculation as well as the calculated analytical limit. Thus, it will provide an incorrect indicator of degraded channel performance. The UVR high trip time delay AV, as also approved by the NRC in Reference 3, exceeds the designated AV in the TVA setpoint calculation. Thus, it will also provide an incorrect indicator of degraded channel performance.
The UVR high trip relay time delay Trip Setpoint, as also approved by the NRC, has inadequate margin to the analytical limit, and also exceeds the AV established by the TVA UVR setpoint calculation. Accordingly, calibrating that instrument function to the NRC-approved trip setpoint could result in immediate inoperability of that channel. In summary, implementation of WBN License Amendments 128/31 will result in the implementation of a non-conservative TS.
In accordance with the guidance in NRC Administrative Letter 98-10, Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety, this license amendment request (LAR) is required to resolve non-conservative TS and is not a voluntary request from a licensee to change its licensing basis. Therefore, this request is not subject to forward fit considerations as described in the letter from S. Burns (NRC) to E. Ginsberg (NEI), dated July 14, 2010 (ML101960180). Because WBN License Amendments 128/31 have not yet been implemented, the incorrect trip setpoint values pose no immediate operational or operability concern.
TVA is requesting NRC review of this non-voluntary LAR on an expedited basis with a requested approval date of December 13, 2019, with a proposed implementation date of December 25, 2019, which coincides with the implementation date of the Reference 3 license amendments.
The Enclosure provides a description and technical evaluation of the proposed changes, a regulatory evaluation, and a discussion of environmental considerations. Attachment 1 to the Enclosure provides the affected Amendment 128/31 WBN Unit 1 and Unit 2 TS pages, marked up to show the proposed changes. Attachment 2 to the Enclosure provides the revised (clean) respective WBN Unit 1 and Unit 2 TS pages. No TS Bases changes were required.
U.S. Nuclear Regulatory Commission CNL-19-097 Page 3 October 23, 2019 TVA has determined that there are no significant hazards considerations associated with the proposed change and that the IS change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). In accordance with 10 CFR 50.91, "Notice for Public Comment; State Consultation," a copy of this application, with the Enclosure is being provided to the designated Tennessee Official.
Please address any questions regarding this request to Kimberly D. Hulvey, Fleet Licensing Manager, at 423-751-3275. There are no new regulatory commitments contained in this submittal.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 23rd day of October 2019.
Respectfully, J^es T. Polickoski Director, Nuclear Regulatory Affairs Enclosure; Evaluation of Proposed Change cc: (with Enclosure);
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant Division of Radiological Health - Tennessee Department of Environment and Conservation
Enclosure Evaluation of the Proposed Change
Subject:
Watts Bar Nuclear Plant, Units 1 and 2, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)
Table of Contents 1.0
SUMMARY
DESCRIPTION ............................................................................................... 2 2.0 DETAILED DESCRIPTION ................................................................................................ 2 2.1 Background .................................................................................................................... 2 2.2 Description of the Proposed Change .............................................................................. 2 2.3 Reason for the Proposed Change .................................................................................. 3
3.0 TECHNICAL EVALUATION
............................................................................................... 4 3.1 Trip Setpoint ................................................................................................................... 4 3.2 Allowable Values ............................................................................................................ 4
4.0 REGULATORY EVALUATION
........................................................................................... 6 4.1 Precedent ....................................................................................................................... 6 4.2 Significant Hazards Consideration ................................................................................. 6
5.0 ENVIRONMENTAL CONSIDERATION
............................................................................. 8
6.0 REFERENCES
................................................................................................................... 8 - Proposed Technical Specification Changes (Unit 1 and 2 Markup) - Proposed Technical Specification Changes (Unit 1 and 2 Re-Typed)
CNL-19-097 E-1 of 8
Enclosure 1.0
SUMMARY
DESCRIPTION In accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.90, "Application for amendment of license, construction permit, or early site permit," Tennessee Valley Authority (TVA) is requesting a license amendment to the Watts Bar Nuclear Plant (WBN) Units 1 and 2 Technical Specifications (TS). This non-voluntary license amendment request (LAR) proposes to revise WBN Units 1 and 2 TS Table 3.3.5-1, LOP DG Start Instrumentation, Function 5, 6.9 kV Emergency Bus Undervoltage (Unbalanced Voltage), for the following instrument setpoint values.
The Allowable Value (AV) for the unbalanced voltage relay (UVR) low trip voltage The AV for the UVR high trip time delay The Trip Setpoint for the UVR high trip time delay 2.0 DETAILED DESCRIPTION
2.1 BACKGROUND
In References 1 and 2, TVA submitted a fleet-wide LAR to change the TS for the TVA fleet to propose adding a new level of protection, Unbalanced Voltage, to the TS for the loss of power (LOP) instrumentation for the Browns Ferry Nuclear Plant (BFN),
Sequoyah Nuclear Plant (SQN), and WBN. In Reference 3, the Nuclear Regulatory Commission (NRC) approved the LAR for BFN (Amendment Nos. 309, 332, and 292),
SQN (Amendment Nos. 345 and 339), and WBN (Amendment Nos. 128, and 31). The license amendments are required to be implemented no later than December 25, 2019.
Following the issuance of Reference 3, TVA identified the following three incorrect instrument values in WBN Units 1 and 2 TS Table 3.3.5-1, LOP DG Start Instrumentation, Function 5, 6.9 kV Emergency Bus Undervoltage (Unbalanced Voltage).
The AV for the UVR low trip voltage The AV for the UVR high trip time delay The Trip Setpoint for the UVR high trip time delay The above errors were attributable to transcription errors in References 1 and 2. The correct instrument values were reflected in the TVA UVR setpoint calculation that was in effect when References 1 and 2 were submitted to the NRC.
2.2 DESCRIPTION
OF THE PROPOSED CHANGE The changes described below are being made to Function 5 (6.9 kV Emergency Bus Undervoltage (Unbalanced Voltage)) of WBN Units 1 and 2 TS Table 3.3.5-1.
CNL-19-097 E-2 of 8
Enclosure 2.2.1 Trip Setpoint The Trip Setpoint associated with the UVR high trip time delay function:
18.13 V at 3.95 sec (High) is revised to read 18.13 V at 3.45 sec (High) 2.2.2 Allowable Values The Allowable Value associated with the UVR low trip voltage function:
3.35 V at 10 sec (Lo) is revised to read 3.3 V at 10 sec (Lo)
The Allowable Value associated with the UVR high trip time delay function:
20.0 V at 4 sec (High) is revised to read 20.0 V at 3.50 sec (High) 2.3 REASON FOR THE PROPOSED CHANGE The UVR low trip voltage AV, as approved by the NRC in Reference 3, exceeds the calculated AV in the TVA setpoint calculation as well as the calculated analytical limit.
Thus, it will provide an incorrect indicator of degraded channel performance. The UVR high trip time delay AV, as also approved by the NRC in Reference 3, exceeds the calculated AV in the TVA setpoint calculation. Thus, it will also provide an incorrect indicator of degraded channel performance. The UVR high trip relay time delay Trip Setpoint, as also approved by the NRC, has inadequate margin to the analytical limit, and also exceeds the AV established by the TVA UVR setpoint calculation.
Accordingly, calibrating that instrument function to the NRC-approved trip setpoint could result in immediate inoperability of that channel.
In summary, implementation of WBN License Amendments 128/31 will result in the implementation of a non-conservative TS. Accordingly, this LAR is being submitted as a non-voluntary LAR in accordance with the guidance in NRC Administrative Letter 98-10, Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety.
This issue has been entered into the TVA Corrective Action Program.
CNL-19-097 E-3 of 8
Enclosure
3.0 TECHNICAL EVALUATION
3.1 TRIP SETPOINT The technical basis for the UVR Trip Setpoints was described in Section 3.4 of Enclosure 1 to Reference 2. The setpoint methodology utilized the square root sum of the squares (SRSS) methodology for combining uncertainty terms that are random and independent. SRSS is an established and accepted analytical technique, and ensures that the protective function will occur before the analytical limits are reached.
Using the correctly transposed UVR High Trip time delay Trip Setpoint, as proposed for TS Table 3.3.5-1, will restore conformance with the WBN UVR setpoint calculation.
The UVR high voltage time delay Trip Setting was calculated as follows:
Setpoint AL - dbe where AL is the analytical limit and dbe is the Total Loop Uncertainty AL was calculated to be 4.0 seconds dbe was calculated to be +/-0.1106 seconds thus Setpoint 4.0 - 0.1106 Setpoint 3.88 seconds Therefore, the proposed TS Trip Setpoint of 3.45 seconds provides an additional 0.43 seconds of margin.
3.2 ALLOWABLE VALUES The AV is a value or values that the setpoint can have when tested periodically, beyond which the instrument channel shall be evaluated for operability. The AV ensures that sufficient allocation exists to account for instrument uncertainties that either are not present or are not measured during periodic testing (defined as unmeasurables). The AV is determined by calculating the instrument channel uncertainty without including the normal measurable uncertainties such as drift, calibration uncertainties, and uncertainties observed during normal operations. This resultant is defined as the unmeasurable uncertainties of the instrument channel. Using the correctly transposed UVR Low Trip voltage and High Trip time delay AV as proposed in TS Table 3.3.5-1 will restore conformance with the WBN UVR setpoint calculation.
The UVR Low Trip voltage AV was calculated as follows:
The maximum and minimum AV for an increasing setpoint (SP) is defined by the following:
AV (max) = AL - (lAdbel - lAnfl) where Adbe is the Total Loop Uncertainty and Anf is the Normal Measurable Accuracy AV (min) = SP + lAnfl CNL-19-097 E-4 of 8
Enclosure AL was calculated as 3.329 volts Adbe was calculated to be +/- 0.07541 volts Anf was calculated to be +/- 0.06633 volts SP was calculated to be 2.96 volts AV (max) = 3.329 - (l0.07541l - l0.06633l)
= 3.319 volts AV (min) = 2.96 + l0.06633l
= 3.027 volts The selected AV must satisfy the following:
AV (min) AV AV (max), or 3.027 volts AV 3.319 volts The proposed UVR Low Trip voltage AV of 3.3 volts meets this criterion.
The UVR High Trip time delay AV was calculated as follows:
The maximum and minimum AV for an increasing SP is defined by the following:
AV (max) = AL - (lAdbel - lAnfl)
AV (min) = SP + lAnfl AL was calculated as 4 seconds Adbe was calculated to be +/- 0.1106 seconds Anf was calculated to be + 0.036946 seconds, - 0.041802 seconds SP was calculated to be 3.45 seconds AV (max) = 4 - (l0.1106l - l0.03694l)
= 3.926 seconds AV (min) = 3.45 + l0.041802l
= 3.492 seconds The selected AV must satisfy the following:
AV (min) AV AV (max), or 3.492 seconds AV 3.926 seconds The proposed UVR High Trip time delay AV of 3.5 seconds meets this criterion.
CNL-19-097 E-5 of 8
Enclosure 3.3 Conclusion TVA has concluded that the revised Trip Setpoint and Allowable Values are appropriate for this application.
4.0 REGULATORY EVALUATION
4.1 PRECEDENT Reference 3 provides precedence for this application.
4.2 SIGNIFICANT HAZARDS CONSIDERATION Tennessee Valley Authority (TVA) is requesting an amendment to Facility Operating Licenses NPF-90 and NPF-96 for Watts Bar Nuclear Plant (WBN), Units 1 and 2, respectively. The proposed amendment would modify Technical Specifications (TS) to correct three instrument values on TS Table 3.3.5-1. Specifically:
- 1) Revising the Function 5 Trip Setpoint associated with the unbalanced voltage relay (UVR) high trip time delay function from 18.13 V at 3.95 sec (High) to 18.13 V at 3.45 sec (High).
- 2) Revising the Function 5 Allowable Value associated with the UVR low trip voltage function from 3.35 V at 10 sec (Lo) to 3.3 V at 10 sec (Lo).
- 3) Revising the Function 5 Allowable Value associated with the UVR high trip time delay function from 20.0 V at 4 sec (High) to 20.0 V at 3.50 sec (High).
These changes are required due to transcription errors from the UVR setpoint calculation in the revised License Amendment Request that resulted in License Amendments 128/31 for WBN Unit 1 and 2, respectively.
TVA evaluated the proposed changes to the TS using the criteria in Section 50.92 to Title 10 of the Code of Federal Regulations and has determined that the proposed changes do not involve a significant hazards consideration. As required by 10 CFR 50.91(a), the TVA analysis of the issue of no significant hazards consideration is presented below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequence of an accident previously evaluated?
Response: No.
The proposed changes correct the TS to reflect the UVR setpoint calculation. The Trip Setpoint and Allowable Value changes restore the UVR instrumentation function to its analyzed design, and so the probability of an accident previously evaluated is not affected. The changes to the Trip Setpoint will ensure that there is acceptable margin to the associated analytical limit, and the Allowable Values will provide proper indicators of degraded channel performance. Thus, the consequences of an accident with the incorporation of these changes will not be increased.
CNL-19-097 E-6 of 8
Enclosure Based on the above, it is concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes correct the TS to reflect the UVR setpoint calculation. The proposed changes ensure the affected UVR channels are in conformance with the existing plant design, and will operate as credited in and as constrained by existing accident analyses.
Based on the above, it is concluded that the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed changes correct the TS to reflect the UVR setpoint calculation. The changes result in ensuring the Trip Setpoint has acceptable margin to the associated analytical limits, and that the Allowable Values will provide proper indicators of degraded channel performance. The safety analysis acceptance criteria are not affected by this change. The proposed changes will not result in plant operation in a configuration outside of the design basis.
Based on the above, it is concluded that the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, TVA concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.
Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
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Enclosure
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. TVA letter to NRC, CNL-17-034, "Application to Modify Technical Specification for Browns Ferry Nuclear Plant (TS-512), Sequoyah Nuclear Plant (TS-17-03) and Watts Bar Nuclear Plant (TS-17-20) to resolve Open Phase Issue Identified in NRC Bulletin 2012-01, 'Design Vulnerability in Electrical Power System,' "dated November 17, 2017 (ML17324A349)
- 2. TVA Letter to NRC, CNL-18-130, Revised Application to Modify the Technical Specifications for the Browns Ferry Nuclear Plant (TS-512), Sequoyah Nuclear Plant (TS-17-03) and Watts Bar Nuclear Plant (TS-17-20) to Incorporate New Technical Specification for Unbalanced Voltage Relays, dated November 19, 2018 (ML18324A609)
- 3. NRC Letter to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection (EPID L-2017-LLA-0391)," dated August 27, 2019 (ML18277A110)
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Attachment 1 to CNL-19-097 Proposed Technical Specification Changes (Unit 1 and 2 Markup)
(2 total pages)
CNL-19-097
LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 2 of 2)
LOP DG Start Instrumentation REQUIRED SURVEILLANCE TRIP ALLOWABLE FUNCTION CHANNELS REQUIREMENTS SETPOINT VALUE PER BUS 1.30 V at 2.95 s 1.5 Vat sec
- 5. 6.9 kV Emergency Bus 3 SR 3.3.5.1 sec (Permissive (Permissive Undervoltage SR 3.3.5.2 3.3 Alarm) Alarm)
(Unbalanced Voltage)
SR 3.3.5.3 2.96 Vat s 3.35 Vat 9.95 sec (Lo) 10 sec (Lo) 18.13 Vat s 20.0 Vat 3.95 sec (High) 4 sec (High) 3.45 3.50 Watts Bar-Unit 1 3.3-51a Amendment 36, 128 I
LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)
LOP DG Start Instrumentation REQUIRED CHANNELS SURVEILLANCE TRIP ALLOWABLE FUNCTION PER BUS REQUIREMENTS SETPOINT VALUE 1, 6.9 kV Emergency Bus Undervoltage (Loss of Voltage)
- a. Bus Undervoltage 3 SR 3.3.5.1 ~ 5994 Vand ;;: 5967.6 V SR 3.3.5.2 s 6006 V
- b. Time Delay 2 SR 3.3.5.3 ~ 0.73 sec and <'.. 0.58 sec and s 0.77 sec s 0.94 sec
- 2. 6.9 kV Emergency Bus Undervoltage (Degraded Voltage)
- a. Bus Undervoltage 3 SR 3.3.5.1 ~ 6593.4 V and <'..6570 V SR 3.3.5.2 s 6606.6 V
- b. Time Delay 2 SR 3.3.5.3 <'.. 9. 73 sec and ;;: 9.42 sec and s 10.27 sec s 10.49 sec
- 3. Diesel Generator Start 2 SR 3.3.5.1 ;;: 4733.4 V and <'.. 2295.6 V with SR 3.3.5.2 s 4926.6 V with an internal time an internal time delay of delay of 0.56 sec at
~ 0.46 sec and zero volts s 0.54 sec
- 4. Load Shed 4 SR 3.3.5.1 ~ 4733.4 V and <'.. 2295.6 V with SR 3.3.5.2 s 4926.6 V with an internal time an internal time delay of delay of s 3.3 sec at zero
~ 2.79 sec and volts.
- 3.21 sec
- 5. 6.9 kV Emergency Bus 3 1.30 V at 2.95 s 1.5 V at 3 sec Undervoltage (Unbalanced SR 3.3.5.1 sec (Permissive (Permissive SR 3.3.5.2 3.3 Voltage) Alarm) Alarm)
SR 3.3.5.3 2.96 Vat s 3.35 Vat 9.95 sec (Lo) 10 sec (Lo) 18.13Vat s20.0 Vat 3.50 3.45 Watts Bar - Unit 2 3.3-53 Amendment 31
Attachment 2 to CNL-19-097 Proposed Technical Specification Pages (Unit 1 and 2 Re-Typed)
(2 total pages)
CNL-19-097
LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 2 of 2)
LOP DG Start Instrumentation REQUIRED SURVEILLANCE TRIP ALLOWABLE FUNCTION CHANNELS REQUIREMENTS SETPOINT VALUE PER BUS 1.30 V at 2.95 1.5 V at 3 sec
- 5. 6.9 kV Emergency Bus 3 SR 3.3.5.1 sec (Permissive (Permissive Undervoltage SR 3.3.5.2 Alarm) Alarm)
(Unbalanced Voltage)
SR 3.3.5.3 2.96 V at 3.3 V at 9.95 sec (Lo) 10 sec (Lo) 18.13 V at 20.0 V at 3.45 sec (High) 3.50 sec (High)
Watts Bar-Unit 1 3.3-51a Amendment 36, 128, ___
LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)
LOP DG Start Instrumentation REQUIRED CHANNELS SURVEILLANCE TRIP ALLOWABLE FUNCTION PER BUS REQUIREMENTS SETPOINT VALUE
- 1. 6.9 kV Emergency Bus Undervoltage (Loss of Voltage)
- a. Bus Undervoltage 3 SR 3.3.5.1 5994 V and 5967.6 V SR 3.3.5.2 6006 V
- b. Time Delay 2 SR 3.3.5.3 0.73 sec and 0.58 sec and 0.77 sec 0.94 sec
- 2. 6.9 kV Emergency Bus Undervoltage (Degraded Voltage)
- a. Bus Undervoltage 3 SR 3.3.5.1 6593.4 V and 6570 V SR 3.3.5.2 6606.6 V
- b. Time Delay 2 SR 3.3.5.3 9.73 sec and 9.42 sec and 10.27 sec 10.49 sec
- 3. Diesel Generator Start 2 SR 3.3.5.1 4733.4 V and 2295.6 V with SR 3.3.5.2 4926.6 V with an internal time an internal time delay of delay of 0.56 sec at 0.46 sec and zero volts 0.54 sec
- 4. Load Shed 4 SR 3.3.5.1 4733.4 V and 2295.6 V with SR 3.3.5.2 4926.6 V with an internal time an internal time delay of delay of 3.3 sec at zero 2.79 sec and volts.
3.21 sec
- 5. 6.9 kV Emergency Bus 3 1.30 V at 2.95 1.5 V at 3 sec Undervoltage (Unbalanced SR 3.3.5.1 sec (Permissive (Permissive Voltage) SR 3.3.5.2 Alarm) Alarm)
SR 3.3.5.3 2.96 V at 3.3 V at 9.95 sec (Lo) 10 sec (Lo) 18.13 V at 20.0 V at 3.45 sec (High) 3.50 sec (High)
Watts Bar - Unit 2 3.3-53 Amendment 31, ___