| 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-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) | 7 August 2023 | License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) | Incorporated by reference
Pressure and Temperature Limits Report |
| 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-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) | 4 May 2023 | Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) | Safe Shutdown Earthquake
Operating Basis Earthquake
Pressure and Temperature Limits Report
Pressure Boundary Leakage |
| CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche | 20 March 2023 | Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu | |
| CNL-23-015, Expedited Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-22-08) | 27 February 2023 | Expedited Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-22-08) | Surveillance Frequency Control Program |
| 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-22-071, 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 |
| 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 |
| 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-22-003, Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010) | 17 February 2022 | Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010) | Anticipated operational occurrence |
| CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . | 9 December 2021 | Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . | Safe Shutdown
Shutdown Margin
Surveillance Frequency Control Program
Pressure Boundary Leakage |
| 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-21-062, Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019) | 29 September 2021 | Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019) | Safe Shutdown
Ultimate heat sink
Surveillance Frequency Control Program
Earthquake
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 |
| ML21202A224 | 2 July 2021 | Tennessee Valley Authority (TVA)- Watts Bar Nuclear Plant (WBN)- NPDES Permit No. TN0020168-Application Request for Permit Renewal | Grab sample |
| CNL-21-038, Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (W | 1 June 2021 | Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (WBN | Anticipated operational occurrence |
| 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-21-013, Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06) | 11 March 2021 | Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06) | Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Cyber Security
Fire Protection Program |
| CNL-21-015, Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as | 3 March 2021 | Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as N | Anticipated operational occurrence |
| CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05) | 2 March 2021 | License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05) | Boric Acid
Ultimate heat sink
Anticipated operational occurrence
Surveillance Frequency Control Program |
| CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID | 26 January 2021 | Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID L | Reactor Vessel Water Level
Loop seal
Coatings
Cyber Security
Finite Element Analysis
Fuel cladding
Fire Protection Program |
| CNL-20-104, Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for (WBN TS-391-20-024) | 23 December 2020 | Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for (WBN TS-391-20-024) | Anticipated operational occurrence
Hydrostatic
Liquid penetrant |
| CNL-20-093, Supplement to Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 'Containment Leakage Rate Testing Program' (WBN-TS-19-01) | 15 December 2020 | Supplement to Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 'Containment Leakage Rate Testing Program' (WBN-TS-19-01) | |
| CNL-20-087, Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017) | 15 December 2020 | Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017) | Anticipated operational occurrence
Safe Shutdown Earthquake
Surveillance Frequency Control Program
Nonconservative Technical Specifications
Fuel cladding |
| CNL-20-078, Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sa | 13 October 2020 | Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Samp | Non-Destructive Examination
Nondestructive Examination
Foreign Material Exclusion |
| CNL-20-006, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 Containment Leakage Rate Testing Program (WBN-TS-19-01) | 2 October 2020 | Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 Containment Leakage Rate Testing Program (WBN-TS-19-01) | |
| 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-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27) | 27 August 2020 | Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27) | Anticipated operational occurrence
Surveillance Frequency Control Program |
| 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-20-063, Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | 27 July 2020 | Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | |
| CNL-20-040, License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) | 17 July 2020 | License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) | Incorporated by reference
Surveillance Frequency Control Program
Pressure Boundary Leakage
Power change |
| CNL-20-053, Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-39 | 17 July 2020 | Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-390- | Anticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Locked High Radiation Area |
| CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) | 22 June 2020 | Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) | Reactor Vessel Water Level
Anticipated operational occurrence
Post Accident Monitoring |
| CNL-20-012, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-18-16) | 19 May 2020 | Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-18-16) | Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Temporary Modification
Surveillance Frequency Control Program |
| 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-20-005, License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02) | 3 April 2020 | License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02) | Surveillance Frequency Control Program |
| CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific | 2 March 2020 | Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat | Safe Shutdown
Boric Acid
Shutdown Margin
Anticipated operational occurrence
Surveillance Frequency Control Program
Fuel cladding
Fire Protection Program
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 |