| 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-22-030, 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 |
| 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 |
| 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-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-21-062, 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 |
| 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-20-058, 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-20-053, 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-20-040, 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-20-016, 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-20-005, 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-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program... | 17 January 2020 | Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program... | Shutdown Margin
Ultimate heat sink
Post Accident Monitoring
Surveillance Frequency Control Program
Battery sizing
Tritium Producing Burnable Absorber Rods
Offsite Circuit |
| CNL-19-051, 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 | 17 January 2020 | 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 | Reactor Vessel Water Level
Loop seal
Coatings
Cyber Security
Finite Element Analysis
Fuel cladding
Fire Protection Program |
| CNL-20-004, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) | 17 January 2020 | Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) | Open Phase Condition |
| CNL-19-110, Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10) | 17 December 2019 | Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10) | Safe Shutdown
Anticipated operational occurrence
Qualified Offsite Circuit
FLEX
Offsite Circuit |
| CNL-19-077, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10) | 6 December 2019 | Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10) | Anticipated operational occurrence
Safe Shutdown Earthquake
Fuel cladding |
| CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) | 30 September 2019 | Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) | Anticipated operational occurrence
Safe Shutdown Earthquake
Post Accident Monitoring
Nondestructive Examination
Power change |
| CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) | 29 August 2019 | Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) | Safe Shutdown
Surveillance Frequency Control Program |
| CNL-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02) | 7 June 2019 | License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02) | Time of Discovery
High Radiation Area
Ultimate heat sink
Stroke time
Post Accident Monitoring |
| CNL-19-014, Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07) | 7 February 2019 | Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07) | Safe Shutdown
Ultimate heat sink
Earthquake
Fuel cladding |
| CNL-18-118, Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09) | 29 November 2018 | Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09) | Safe Shutdown
Anticipated operational occurrence
Emergency Lighting
Battery sizing |
| CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24) | 29 November 2018 | Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24) | Safe Shutdown
Ultimate heat sink
Internal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
Fukushima Dai-Ichi
Surveillance Frequency Control Program
Large early release frequency
Tritium Producing Burnable Absorber Rods
Turbine Missile
Fire Protection Program |
| CNL-18-119, Application to Revise Watt Bar Nuclear Plant, Units 1 & 2, Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9, Regarding Electrical Power Systems (WBN-TS-1808) | 26 November 2018 | Application to Revise Watt Bar Nuclear Plant, Units 1 & 2, Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9, Regarding Electrical Power Systems (WBN-TS-1808) | Safe Shutdown
Anticipated operational occurrence
FLEX
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 |