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 |
ML23277A046 | 4 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- | 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-22-008, 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 |
ML22145A141 | 16 May 2022 | Technical Specification Bases, Manual | Shutdown Margin Ultimate heat sink Water Inventory Control Post Accident Monitoring Hydrostatic Abnormal operational transient Surveillance Frequency Control Program Scram Discharge Volume Fuel cladding |
ML22125A127 | 4 May 2022 | Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases | |
ML22108A282 | 27 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 | Probabilistic Risk Assessment FLEX |
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-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) | 23 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) | Nondestructive Examination |
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-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-19-072, Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03) | 14 July 2019 | Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03) | |
ML19151A584 | 31 May 2019 | Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases | Safe Shutdown Shutdown Margin Surveillance Frequency Control Program B.5.b Mitigating Strategies Offsite Circuit |
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 |
ML17333A401 | 29 November 2017 | Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases | High Radiation Area Ultimate heat sink Stroke time Anticipated operational occurrence Surveillance Frequency Control Program Power change |
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-16-011, 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) | 11 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) | Safe Shutdown Boric Acid Ultimate heat sink Surveillance Frequency Control Program Design basis earthquake Earthquake Fuel cladding |
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 8 | 19 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 | Shutdown Margin Mission time Internal Flooding Probabilistic Risk Assessment Surveillance Frequency Control Program Process Control Program Large early release frequency Control of Heavy Loads |
ML15176A682 | 19 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 | Shutdown Margin Reactor Vessel Water Level Post Accident Monitoring Missed surveillance Surveillance Frequency Control Program Recently irradiated fuel |
ML15176A679 | 19 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 | High Radiation Area Fire Barrier Anticipated operational occurrence Condition Adverse to Quality Surveillance Frequency Control Program Fuel cladding Power change |
ML15176A718 | 19 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 | |
ML15176A664 | 19 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 | Shutdown Margin Anticipated operational occurrence Surveillance Frequency Control Program Process Control Program |
ML15176A740 | 19 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 | Safe Shutdown Unanalyzed Condition Shutdown Margin Anticipated operational occurrence Probabilistic Risk Assessment Qualified Offsite Circuit Surveillance Frequency Control Program Battery sizing Recently irradiated fuel Offsite Circuit Power change |
ML15176A748 | 19 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 | Safe Shutdown Time of Discovery Anticipated operational occurrence Probabilistic Risk Assessment Qualified Offsite Circuit Surveillance Frequency Control Program Recently irradiated fuel Offsite Circuit |
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 8 | 19 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 | Shutdown Margin Anticipated operational occurrence Surveillance Frequency Control Program Process Control Program |
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 8 | 19 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 | High Radiation Area Fire Barrier Anticipated operational occurrence Condition Adverse to Quality Surveillance Frequency Control Program Fuel cladding Power change |
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 8 | 19 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 | Safe Shutdown Ultimate heat sink Anticipated operational occurrence Probabilistic Risk Assessment Incorporated by reference Surveillance Frequency Control Program Earthquake Recently irradiated fuel Offsite Circuit |
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 8 | 19 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 | Shutdown Margin Reactor Vessel Water Level Post Accident Monitoring Missed surveillance Surveillance Frequency Control Program Recently irradiated fuel |
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 8 | 19 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 | Shutdown Margin Probabilistic Risk Assessment Surveillance Frequency Control Program Process Control Program Control of Heavy Loads Recently irradiated fuel |
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 8 | 19 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 | Safe Shutdown Unanalyzed Condition Shutdown Margin Anticipated operational occurrence Probabilistic Risk Assessment Qualified Offsite Circuit Surveillance Frequency Control Program Battery sizing Recently irradiated fuel Offsite Circuit Power change |
ML15176A681 | 19 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 | Safe Shutdown Ultimate heat sink Anticipated operational occurrence Probabilistic Risk Assessment Incorporated by reference Surveillance Frequency Control Program Earthquake Recently irradiated fuel Offsite Circuit |
CNL-14-176, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) | 2 December 2014 | Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) | Safe Shutdown High winds Mission time Internal Flooding Probabilistic Risk Assessment Coatings Large early release frequency Moisture barrier License Renewal Earthquake |
ML14342B004 | 1 December 2014 | Cycle 19 - 180-Day Steam Generator Tube Inspection Report | Nondestructive Examination |
ML13193A039 | 5 July 2013 | Revisions to the Technical Requirements Manual and Specification Bases | Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Fire Barrier Anticipated operational occurrence Nondestructive Examination Incorporated by reference Abnormal operational transient Pressure and Temperature Limits Report B.5.b Mitigating Strategies Fuel cladding Pressure Boundary Leakage Offsite Circuit |
ML11249A061 | 31 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. | Safe Shutdown High winds Shutdown Margin Mission time Fire Barrier Tornado Missile Internal Flooding Probabilistic Risk Assessment Large early release frequency Earthquake Offsite Circuit Scaffolding |
ML11195A117 | 29 July 2011 | Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956) | Cyber Security |
ML11129A188 | 6 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 | Safe Shutdown Anticipated operational occurrence Internal Flooding Large early release frequency Earthquake Fuel cladding Grace period |
ML101470158 | 24 May 2010 | Revisions to Technical Requirements Manual and Technical Specification Bases | Safe Shutdown High Radiation Area Grab sample Stroke time Incorporated by reference B.5.b Mitigating Strategies Fuel cladding Pressure Boundary Leakage |
ML092950340 | 20 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 | Safe Shutdown |
ML083370121 | 1 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) | |
ML071010153 | 2 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 | Shutdown Margin Offsite Dose Calculation Manual Tornado Missile Hydrostatic Operating Basis Earthquake Nondestructive Examination Pressure and Temperature Limits Report Annual Radioactive Effluent Release Report Process Control Program Earthquake Pressure Boundary Leakage |
ML070250031 | 12 January 2007 | Technical Specification (TS) Change 06-06 - Revised Steam Generator (SG) Voltage-Based Repair Criteria - Probability of Prior Cycle Detection (Popcd) | Nondestructive Examination |
ML063470029 | 7 December 2006 | Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information | Safe Shutdown Boric Acid Ultimate heat sink Coatings Biofouling |
ML063530201 | 30 November 2006 | Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818 | Time of Discovery Liquid penetrant |
ML063530208 | 30 November 2006 | Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819 | Time of Discovery Liquid penetrant |
ML062230095 | 2 August 2006 | Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) | Shutdown Margin |
ML062230111 | 2 August 2006 | Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02) | Shutdown Margin |
ML062140102 | 12 July 2006 | Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes | Safe Shutdown Shutdown Margin Ultimate heat sink Anticipated operational occurrence Safe Shutdown Earthquake Earthquake |