| 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) | 18 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) | Safe Shutdown
Anticipated operational occurrence |
| 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- | 20 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 | Coatings
Surveillance Frequency Control Program
Fuel cladding |
| 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) | 2 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) | Coatings
Surveillance Frequency Control Program
Fuel cladding |
| 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) | 31 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) | Surveillance Frequency Control Program |
| 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) | 27 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) | Anticipated operational occurrence
Pressure and Temperature Limits Report
Fuel cladding |
| 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) | 13 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) | Surveillance Frequency Control Program
Pressure Boundary Leakage |
| 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) | 13 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) | Post Accident Monitoring
Nondestructive Examination |
| ML22165A105 | 12 July 2022 | Issuance of Amendment Nos. 357 and 351 Regarding Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation | Anticipated operational occurrence
Probabilistic Risk Assessment
Rod Drop Event |
| 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) | 13 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) | Time of Discovery
Incorporated by reference
Missed surveillance |
| ML22115A002 | 17 May 2022 | Correction to Amendment No. 350 Regarding One-Time Change to Technical Specification3.4.12, Low Temperature Overpressure Protection System, | |
| CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) | 13 May 2022 | Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) | Safe Shutdown
FLEX
Offsite Circuit |
| ML22125A127 | 4 May 2022 | Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases | |
| CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf | 28 April 2022 | Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf | Hot Short
Safe Shutdown
Boric Acid
Ultimate heat sink
Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Thermoset
Design basis earthquake
Large early release frequency
Maintenance Rule Program
Offsite Circuit |
| CNL-22-001, 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) | 4 April 2022 | 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) | Post Accident Monitoring
Nondestructive Examination |
| CNL-21-085, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) | 24 February 2022 | License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) | Safe Shutdown
High winds
Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
Earthquake |
| CNL-21-001, Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01) | 29 November 2021 | Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01) | Anticipated operational occurrence
Probabilistic Risk Assessment
Rod Drop Event
Fuel cladding |
| CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) | 22 October 2021 | Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) | Anticipated operational occurrence
Pressure and Temperature Limits Report
COVID-19
Fuel cladding |
| CNL-21-026, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) | 5 August 2021 | License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) | Safe Shutdown
High winds
Ultimate heat sink
Internal Flooding
Probabilistic Risk Assessment
Incorporated by reference
FLEX
Surveillance Frequency Control Program
Large early release frequency
Flooding Focused Evaluation
Earthquake
Turbine Missile
Offsite Circuit |
| CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN8 | 29 April 2021 | Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- | Fitness for Duty
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Coatings
Nondestructive Examination
Cyber Security
B.5.b
Process Control Program
Fire Protection Program
Grace period |
| CNL-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) | 23 September 2020 | Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) | |
| CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) | 14 August 2020 | License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) | Shutdown Margin
High Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Post Accident Monitoring
Hydrostatic
Pressure and Temperature Limits Report
Scram Discharge Volume
Process Control Program |
| CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance | 31 July 2020 | Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re | Deep Dose Equivalent |
| CNL-20-042, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05) | 17 April 2020 | Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05) | Boric Acid
Shutdown Margin
Anticipated operational occurrence
Power change |
| CNL-20-010, Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) | 24 February 2020 | Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) | Anticipated operational occurrence
Nondestructive Examination
Locked High Radiation Area |
| CNL-19-066, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) | 14 January 2020 | Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) | Safe Shutdown
High winds
Ultimate heat sink
Commercial Grade Dedication
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Temporary Modification
FLEX
Earthquake |
| CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) | 16 November 2019 | Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) | Boric Acid
Shutdown Margin
Anticipated operational occurrence
Power change |
| CNL-19-005, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SQN-TS-19-01) | 1 February 2019 | Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SQN-TS-19-01) | Surveillance Frequency Control Program |
| CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays | 19 November 2018 | Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays | Safe Shutdown
Anticipated operational occurrence
Surveillance Frequency Control Program
Offsite Circuit |
| CNL-18-085, License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme | 15 June 2018 | License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme | |
| CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) | 16 March 2018 | Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) | Safe Shutdown
High winds
Ultimate heat sink
Mission time
Internal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
Large early release frequency
Turbine Missile |
| CNL-17-150, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) | 9 March 2018 | Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) | Safe Shutdown |
| NL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) . | 8 February 2018 | Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .. | Surveillance Frequency Control Program |
| CNL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, 'Reactor Trip System (RTS) | 8 February 2018 | Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, 'Reactor Trip System (RTS) .. | Surveillance Frequency Control Program |
| NL-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 System | 17 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. | Safe Shutdown
Reactor Vessel Water Level
Anticipated operational occurrence
Surveillance Frequency Control Program
Open Phase Condition
Offsite Circuit |
| CNL-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 Syste | 17 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. | Safe Shutdown
Reactor Vessel Water Level
Anticipated operational occurrence
Surveillance Frequency Control Program
Open Phase Condition
Offsite Circuit |
| CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) | 7 August 2017 | License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) | Anticipated operational occurrence
Surveillance Frequency Control Program
Fuel cladding |
| NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) | 7 August 2017 | Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) | Anticipated operational occurrence
Surveillance Frequency Control Program
Fuel cladding |
| 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) | 13 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) | Anticipated operational occurrence
Surveillance Frequency Control Program
Offsite Circuit |
| CNL-16-121, Supplemental Information Regarding 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 | 22 July 2016 | Supplemental Information Regarding 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 | Ultimate heat sink |
| CNL-16-001, Application to Modify Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) | 26 May 2016 | Application to Modify Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) | Safe Shutdown
Fire Barrier
Stroke time
Anticipated operational occurrence
Surveillance Frequency Control Program
Offsite Circuit |
| CNL-16-018, License Amendment Request (SQN-TS-16-03) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 | 16 May 2016 | License Amendment Request (SQN-TS-16-03) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 | Cyber Security |
| CNL-15-178, License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482) | 28 August 2015 | License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482) | Aging Management |
| CNL-15-164, Second Annual Update, License Renewal Application | 14 August 2015 | Second Annual Update, License Renewal Application | Coatings
Aging Management
Moisture barrier |
| CNL-14-075, Redacted Version of License Amendment Request (SQN-TS-14-01) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 | 27 May 2014 | Redacted Version of License Amendment Request (SQN-TS-14-01) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 | Cyber Security |
| ML13329A717 | 22 November 2013 | Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) | Probabilistic Risk Assessment |
| ML13281A806 | 6 August 2013 | Operating License Renewal, Site 40HA22 and Revision to Phase I Cultural Resources Survey Final Report, Hamilton County, Tn | |
| ML13199A281 | 3 July 2013 | Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) | Design basis earthquake
Fuel cladding |
| ML13024A007 | 7 January 2013 | License Renewal Application, Part 5 of 8 | Safe Shutdown
Boric Acid
High winds
Grab sample
Offsite Dose Calculation Manual
Internal Flooding
Probabilistic Risk Assessment
Nondestructive Examination
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Open House
License Renewal
Fuel cladding
Environmental Justice
Power Uprate
Depleted uranium |
| ML13024A011 | 7 January 2013 | Sequoyah Nuclear Plant, Units 1 and 2 - License Renewal Application, Part 1 of 8 | |
| ML13024A006 | 7 January 2013 | License Renewal Application, Part 4 of 8 | |