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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 2023Application 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
ML23277A0464 October 2023Revisions 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 2023Supplement 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-23-03Coatings
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 2023Application 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 2023Application 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 2022and 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
ML22145A14116 May 2022Technical Specification Bases, ManualShutdown Margin
Ultimate heat sink
Water Inventory Control
Post Accident Monitoring
Hydrostatic
Abnormal operational transient
Surveillance Frequency Control Program
Scram Discharge Volume
Fuel cladding
ML22125A1274 May 2022Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
ML22108A28227 April 2022Summary 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 4bProbabilistic 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 2021Exigent 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 2020Response 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 2020Application 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 2019Exigent 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 2019Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable - Exigent Amendment (SQN-TS-2019-03)
ML19151A58431 May 2019Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification BasesSafe 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 Relays19 November 2018Revised Application to Modify the Technical Specifications for Unbalanced Voltage RelaysSafe Shutdown
Anticipated operational occurrence
Surveillance Frequency Control Program
Offsite Circuit
ML17333A40129 November 2017Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification BasesHigh 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 2017Proposed 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 2016Proposed 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 819 June 2015Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8Shutdown Margin
Mission time
Internal Flooding
Probabilistic Risk Assessment
Surveillance Frequency Control Program
Process Control Program
Large early release frequency
Control of Heavy Loads
ML15176A68219 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8Shutdown Margin
Reactor Vessel Water Level
Post Accident Monitoring
Missed surveillance
Surveillance Frequency Control Program
Recently irradiated fuel
ML15176A67919 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8High Radiation Area
Fire Barrier
Anticipated operational occurrence
Condition Adverse to Quality
Surveillance Frequency Control Program
Fuel cladding
Power change
ML15176A71819 June 2015Sequoyah 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
ML15176A66419 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8Shutdown Margin
Anticipated operational occurrence
Surveillance Frequency Control Program
Process Control Program
ML15176A74019 June 2015Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8Safe 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
ML15176A74819 June 2015Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 8 of 8Safe 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 819 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8Shutdown 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 819 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8High 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 819 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8Safe 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 819 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8Shutdown 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 819 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8Shutdown 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 819 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8Safe 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
ML15176A68119 June 2015Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8Safe 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 2014Application 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
ML14342B0041 December 2014Cycle 19 - 180-Day Steam Generator Tube Inspection ReportNondestructive Examination
ML13193A0395 July 2013Revisions to the Technical Requirements Manual and Specification BasesSafe 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
ML11249A06131 August 2011Application 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
ML11195A11729 July 2011Issuance of Amendments Regarding the Cyber Security Plan (TS-09-06) (TACs ME4955 and ME4956)Cyber Security
ML11129A1886 May 2011TS 11-06, Emergency Technical Specification Change for One-Time Extension of Surveillance Requirements Associated with Reactor Trip System and Engineered Safety Feature Actuation System InstrumentationSafe Shutdown
Anticipated operational occurrence
Internal Flooding
Large early release frequency
Earthquake
Fuel cladding
Grace period
ML10147015824 May 2010Revisions to Technical Requirements Manual and Technical Specification BasesSafe Shutdown
High Radiation Area
Grab sample
Stroke time
Incorporated by reference
B.5.b Mitigating Strategies
Fuel cladding
Pressure Boundary Leakage
ML09295034020 October 2009License 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 09-19Safe Shutdown
ML0833701211 December 2008Revisions 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)
ML0710101532 April 2007Additional Information for Technical Specification Change 05-09 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity and Deletion of License ConditionShutdown 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
ML07025003112 January 2007Technical Specification (TS) Change 06-06 - Revised Steam Generator (SG) Voltage-Based Repair Criteria - Probability of Prior Cycle Detection (Popcd)Nondestructive Examination
ML0634700297 December 2006Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental InformationSafe Shutdown
Boric Acid
Ultimate heat sink
Coatings
Biofouling
ML06353020130 November 2006Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818Time of Discovery
Liquid penetrant
ML06353020830 November 2006Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819Time of Discovery
Liquid penetrant
ML0622300952 August 2006Tech Spec Pages for Amendment 309 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)Shutdown Margin
ML0622301112 August 2006Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)Shutdown Margin
ML06214010212 July 2006Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation ChangesSafe Shutdown
Shutdown Margin
Ultimate heat sink
Anticipated operational occurrence
Safe Shutdown Earthquake
Earthquake