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Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 2024-09-08
[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) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases 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-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-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) ML22145A1412022-05-16016 May 2022 Technical Specification Bases, Manual ML22125A1272022-05-0404 May 2022 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML22108A2822022-04-27027 April 2022 Summary of Regulatory Audit Regarding the License Amendment Request to Revise TS to Adopt TSTF 505, Rev. 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)2021-10-22022 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020 Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2020-09-23023 September 2020 Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-072, Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03)2019-07-14014 July 2019 Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03) ML19151A5842019-05-31031 May 2019 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases 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 ML17333A4012017-11-29029 November 2017 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-03-13013 March 2017 Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) CNL-16-011, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)2016-03-11011 March 2016 Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01) CNL-15-128, Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8 ML15176A6822015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8 ML15176A6792015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 ML15176A7182015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 6 of 8 ML15176A6642015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8 ML15176A7402015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 ML15176A7482015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 8 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 82015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 82015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 82015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 82015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 82015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8 NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 82015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 ML15176A6812015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8 CNL-14-176, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03)2014-12-0202 December 2014 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) ML14342B0042014-12-0101 December 2014 Cycle 19 - 180-Day Steam Generator Tube Inspection Report ML13193A0392013-07-0505 July 2013 Revisions to the Technical Requirements Manual and Specification Bases ML11249A0612011-08-31031 August 2011 Application for Temporary Change to TS to Allow Use of Penetrations in Shield Building Dome During Modes 1 Through 4;and Request for Specific Usage of Alternate Source Term Methodology for Calculating Radiation Doses Associated. ML11195A1172011-07-29029 July 2011 Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956) ML11129A1882011-05-0606 May 2011 TS 11-06, Emergency Technical Specification Change for One-Time Extension of Surveillance Requirements Associated with Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation ML1014701582010-05-24024 May 2010 Revisions to Technical Requirements Manual and Technical Specification Bases 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 ML0833701212008-12-0101 December 2008 Revisions to the Technical Requirements Manual (TRM) and Technical Specification (TS) Bases (Unit 1 Revisions 31, 32, and 33; Unit 2 Revisions 30, 31 and 32) ML0710101532007-04-0202 April 2007 Additional Information for Technical Specification Change 05-09 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity and Deletion of License Condition ML0702500312007-01-12012 January 2007 Technical Specification (TS) Change 06-06 - Revised Steam Generator (SG) Voltage-Based Repair Criteria - Probability of Prior Cycle Detection (Popcd) ML0634700292006-12-0707 December 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information ML0635302012006-11-30030 November 2006 Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818 ML0635302082006-11-30030 November 2006 Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819 ML0622300952006-08-0202 August 2006 Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) ML0622301112006-08-0202 August 2006 Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) ML0621401022006-07-12012 July 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes 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 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-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-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) ML22125A1272022-05-0404 May 2022 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML22108A2822022-04-27027 April 2022 Summary of Regulatory Audit Regarding the License Amendment Request to Revise TS to Adopt TSTF 505, Rev. 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020 Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-03-13013 March 2017 Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) ML11195A1172011-07-29029 July 2011 Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956) ML11129A1882011-05-0606 May 2011 TS 11-06, Emergency Technical Specification Change for One-Time Extension of Surveillance Requirements Associated with Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation 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 ML0635302082006-11-30030 November 2006 Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819 ML0635302012006-11-30030 November 2006 Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818 ML0622301112006-08-0202 August 2006 Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) ML0622300952006-08-0202 August 2006 Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) ML0610102602006-04-0606 April 2006 Technical Specification Pages Re Allowable Value for Reactor Trip System ML0611004082006-03-30030 March 2006 Technical Specification Change 05-11, Revision to TS to Support Third 10-Year Interval Inservice Test Program, Rev 1 ML0600402802005-12-28028 December 2005 TS for Amend 295, TAC MC6881, Relocation of Multiple Technical Specifications ML0600402772005-12-28028 December 2005 TS for Amend 305, TAC MC6881, Relocation of Multiple Technical Specifications ML0507303032005-03-0909 March 2005 Tech Spec Pages Amendments 299 and 288, RCS & ECCS Enhancements ML0434905992004-12-0202 December 2004 Technical Specifications Change 03-13, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process Cliip.) ML0427204482004-09-20020 September 2004 Cycle 12 (U2C12) 12-Month Steam Generator Inspection Report ML0426102902004-09-15015 September 2004 Issuance of Amendment Regarding, Index - Definitions 1.0 ML0407608732004-03-0505 March 2004 Technical Specifications (TS) Change 04-02, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process. ML0407608782004-03-0505 March 2004 Technical Specifications (TS) Change 03-14, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process. ML0227502132002-09-30030 September 2002 Technical Specification Pages for Amendment No. 279. Ice Condenser Basket Weight ML0220005542002-07-10010 July 2002 Unit 2 - Technical Specification (TS) Change No. 02-03, Essential Raw Cooling Water (ERCW) Operability During Movement of Heavy Loads - One Time TS Change in Support of Steam Generator Replacement Project 2023-09-20
[Table view] |
Text
I ennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 March 30, 2006
'rVA-SQN-TS-05-11, Ri 10 CFR 50.90
'J.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SIEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - TECHNICAL SPECIFICATIONS (TS) CHANGE 05-11, "REVISION TO TECHNICAL SPECIFICATION TO SUPPORT THIRD 10-YEAR INTERVAL INSERVICE TEST (IST) PROGRAM," REVISION 1
Reference:
TVA letter to NRC dated December 19, 2005, "Sequoyah Nuclear Plant (SQN) - Units 1 And 2 -
Technical Specifications (TS) Change 05-11,
'Revision To Technical Specification To Support Third 10-Year Interval Inservice Test (IST)
Program'"
PDursuant to 10 CFR 50.90, Tennessee Valley Authority (TVA) is submitting two revised TS pages to supersede the pages previously provided in the referenced letter for SQN TS Change 05-11. The revision is necessary to address NRC concerns regarding Technical Specification Task Force (TSTF) 479, "Changes to Reflect Revision of 10 CFR 50.55a" and the application of the 25 percent extension to test frequencies greater than two years.
The Regulatory Safety Analysis, including the no significant hazard determination, and Environmental Considerations provided in the referenced letter are not affected by this
- cevision; therefore, they are not included in this Submittal.
li~M Udo 147
U.S. Nuclear Regulatory Commission Page 2 March 30, 2006 In accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and enclosures to the Tennessee State Department of Public Health.
TVA continues to request approval of this TS change to support the June 1, 2006 start date of SQN's third 10-year IST program interval.
There are no commitments contained in this submittal.
If you have any questions about this change, please contact me at 843-7170 or Jim Smith at 843-6672.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this v day of 41 tek Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs
Enclosures:
- 1. TVA Evaluation of the Proposed Changes
- 2. Proposed Technical Specifications Change (mark-up) cc: See page 3
U.S. Nuclear Regulatory Commission Page 3 March 30, 2006 Enclosures cc (Enclosures):
Framatome ANP, Inc.
P. 0. Box 10935 Lynchburg, Virginia 24506-0935 ATTN: Mr. Frank Masseth Mr. Donald L. Gillispie Grace Glens Farm 3440 Union Church Road Thaxton, Virginia 24174 Mr. Edgar D. Hux 94 Ridgetree Lane Marietta, Georgia 30068 Mr. Lawrence E. Nanney, Director Division of Radiological Health Third Floor L&C Annex 401 Church Street Nashville, Tennessee 37243-1532 Mr. Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. William T. Russell 400 Plantation Lane Stevensville, Maryland 21666
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY (TVA)
SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2
1.0 DESCRIPTION
This letter provides a revision to SQN Technical Specification (TS) Change 05-11 as originally submitted to NRC by TVA letter dated December 19, 2005. The original TS change contained a proposed change to SQN's inservice test (IST) program Surveillance Requirement (SR) 4.0.5.c that is based on Technical Specification Task Force (TSTF) 479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a."
One of the provisions in TSTF-479 provided a correction to the improved standard TS (NUREG-1431, Revision 3.1) regarding test frequencies in the IST program. The TSTF recognizes there may be non-standard test frequencies utilized in the IST program and applies the provisions of frequency extensions (i.e., SR 3.0.2) to IST program test frequencies.
SQN TS Change 05-11 proposed a change to SR 4.0.5.c to adopt these TSTF provisions. NRC staff has expressed concern about applying frequency extensions to test frequencies in the IST program that are greater than two years. NRC staff has requested a change to TSTF-479 to revise the provision for applying SR 3.0.2 to IST test frequencies. The staff's requested revision to the TSTF will specify frequencies two years or less in the IST program. Based on the staff's position and the proposed revision to TSTF-479, TVA is submitting revised TS pages for both units to specify frequencies two years or less in the IST program. The revised TS pages supersede the pages previously provided by TVA's December 19, 2005 letter.
2.0 PROPOSED CHANGE
TVA's proposed revision to TS Change 05-11 provides new language for SR 4.0.5.c. TVA's originally proposed SR 4.0.5.c and the proposed revision to SR 4.0.5.c are provided below:
TVA's originally proposed 4.0.5.c reads:
- c. "The provisions of SR 4.0.2 are applicable to the above required Frequencies and other normal and accelerated frequencies specified in the Inservice Testing Program for performing inservice testing activities."
The proposed revision to 4.0.5.c reads:
El-l
- c. "The provisions of SR 4.0.2 are applicable to the above required Frequencies and other normal and accelerated frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities."
In summary, TVA is submitting a revision to SQN TS Change 05-11 as previously provided by letter dated December 19, 2005. Two revised TS pages (one TS page for each unit) are provided and include a change in language that specifies test frequencies two years or less for application of SR 4.0.2.
This change in language will provide consistency with the NRC staff recommended changes to TSTF-479.
3.0 BACKGROUND
TSTF-479 is entitled "Changes to Reflect Revision of 10 CFR 50.55a." This TSTF was implemented into the improved standard TS in NUREG-1431, Revision 3;1, to provide consistency between the standard TS and the 10 CFR 50.55a(f)(4) for pumps and valves classified as American Society of Mechanical Engineers (ASME) Code Class 1, 2, and
- 3. By letter dated December 19, 2005, TVA submitted SQN TS Change 05-11 to adopt the provisions from TSTF-479 into the SQN TSs. A February 28, 2006 posting on the Excel website, indicates the industry and NRC have agreed to reconsider a change to TSTF-479 to address an NRC concern regarding the application of frequency extensions to the IST program. The proposed change to TSTF-479 will require SQN TS Change 05-1L be' modified to incorporate the proposed TSTF change.
Accordingly, TVA is submitting two revised TS pages to supersede TS pages previously provided by TS Change 05-11.
4.0 TECHNICAL ANALYSIS
By letter dated December 19, 2005, TVA submitted TS Change 05-11 for SQN to update the improved standard TS 4.0.5 to reflect changes in 10 CFR 50.55a. The need to update TSs to reflect changes to 10 CFR 50.55a is recognized by the Nuclear Industry in TSTF-479, Revision 0. TVA TS Change 05-11 is based on TSTF-479 and provides reference to ASME Code for SQN's IST program that are consistent with the code requirements referenced in 10 CFR 50.55a(f)(4).
One of the provisions in TSTF-479 provided a correction to the improved standard TS (NUREG-1431, Revision 3.1) regarding the IST program. A provision in the TSTF recognizes there may be non-standard test frequencies utilized in the IST program and applies the provisions of SR 3.0.2 to IST program E1-2
test frequencies for frequency extensions. SQN TS Change 05-11 proposed a change to SR 4.0.5.c to adopt these TSTF provisions. NRC staff has expressed concern about applying frequency extensions to test frequencies in the IST program that may be greater than two years. NRC staff has requested a change to TSTF-479 to revise the provision for applying SR 3.0.2 to IST test frequencies. The requested TSTF revision would specify frequencies two years or less in the IST program. Based on the staff's position regarding TSTF-479, TVA is submitting revised TS pages for both units to specify frequencies two years or less in the IST program..
The revised TS pages supersede the pages previously provided in TVA's December 19, 2005 letter.
5.0 REFERENCES
- 1. 10 CFR 50.55a(f), "Inservice testing requirements."
- 2. American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants, 2001 Edition through 2003 Addenda.
3.. Technical Specification Task Force TSTF 479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a."
E1-3
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2 Revised Technical Specification Pages I. AFFECTED PAGE LIST Unit 1 3/4 0-3 Unit 2 3/4 0-3 II. MARKED PAGES See attached.
E2 -1
V APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 (Continued)
- a. Provisions that inservice testing of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a;
- b. The provisions of SR 4.0.2 are applicable to the frequencies for performing inservice inspection activities;
- c. Inspection of each reactor coolant pump flywheel per the recommendation of Regulation Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975 or in lieu of Position c.4.b(1) and c.4.b(2), a qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the removed flywheels may be conducted at 20-year intervals (the provisions of SR 4.0.2 are not applicable); and
- d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirement of any TS. _
Inservice Testing Program the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) I This program provides controls for nservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:
- a. Provisions that inservice testi g of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance wit Gion XI of the ASME Boilor and Proesuro Voesol Codo and applicable Addenda as required by 10 CFR 50.55a; .
^ *.a. .
- b. Testing Frequencies.cifeddXoction air ._ r ..
)Al of Me AWL boileor and lF-rocuro V8ool Code and applicable Addenda as folows I applicable to the ASME OM Code I ASAeoilor and Pro1curo V86'6'o 1 Code and applicable Addenda Required frequencies for terminoloav for inservice Derformina inservice testing activities testing activities and oth er normal and acc,elerated Weekly At least once per 7 days frequen icies Monthl) At least once per 31 days specifiEed as 2 Quarter ly or every 3 months At least once per 92 days years or less in the Semiar Irually or every 6 months At least once per 184 days Inservicce Testing Every 9I nonths At least once per 276 days Prograr n Yearly iOxannually At least once per 366 days BienniaIly or every 2 years At least once per 731 day
- c. The provisions of SR 4.0.2 are applicable to the above required Frequencies or performing inservice testing activities;
- d. The provisions of SR 4.0.3 are applicable to inservice testing and activities; and
- e. Nothing in the ASME Bioilr and Proccuro VAssel Code shall be construed to supersede the requirements of any April 11, ;'005 SEQUOYAH - UNIT 1 3/4 0-3 Amendment No. 78, 162, 202, 208, 274, 280, 293 E2 -2
APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 (Continued)
- a. Provisions that inservice testing of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section Xi of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a;
- b. The provisions of SR 4.0.2 are applicable to the frequencies for performing inservice inspection activities;
- c. Inspection of each reactor coolant pump flywheel per the recommendation of Regulation Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975 or in lieu of Position c.4.b(1) and c.4.b(2),
a qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the removed flywheels may be conducted at 20-year intervals (the provisions of SR 4.0.2 are not applicable); and
- d. No:hing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirement of any TS. I . _ _ _ ..
the ASME-Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code)
Inservice Testing Program I
This program provides controls for i service testing of ASME Code Class 1, 2, and 3 components including applicable supports. The ogram shall include the following:
- a. Pmovisions that inservice testi g of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section Xi of thR ASME Boilor and Procsure Vocsol Codo and applicable Addenda as required by 10 CFR 50.55a;
- b. Testing frequencies pf i tionX of the ASME goilor and Pressuro-Vese! Code-and applicable Addenda as A Oapplicable to the ASME OM Code (MlbrBr-InoArrlln\
ILZJ 1A.DIVIEZ B r Code and applicable Addenda Required frequencies for terminology for inservice performing inservice testing activities testing activities and other rormal and accele ated Weekly At least once per 7 days frequencies MDnthly At least once per 31 days specified as 2 Quarterly or every 3 months At least once per 92 days years or less in Semiannually or every 6 months At least once per 184 days the Inservice Test Every 9 months At least once per 276 days Program Yearly or annually At least once per 366 days Bi9nnially or every 2 years At least once per 731 days
- c. Th.e provisions of SR 4.0.2 are applicable to the above required Frequencies Or performing inservice testing activities;
- d. TI-e provisions of SR 4.0.3 are applicable to inservice testing and activities; and
- e. Nothing in the ASME Rl Code shall be construed to supersede the RirnPeu requirements of any TS.
April 1'1. 2005 SEQUOYAH - UNIT 2 3/4 0-3 Amendment No. 69, 152, 198, 263, 271, 283 E2-3