| CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) | 10 January 2024 | Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) | |
| ML23346A138 | 3 January 2024 | Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods | Tritium Producing Burnable Absorber Rods |
| ML23192A447 | 31 July 2023 | Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information | Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake |
| WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR) | 10 April 2023 | Revised Pressure and Temperature Limits Report (PTLR) | Hydrostatic
Pressure and Temperature Limits Report |
| 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 | |
| WBL-22-034, Update to Fire Protection Report Figures Redacted | 1 August 2022 | Update to Fire Protection Report Figures Redacted | |
| WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | 16 December 2021 | Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | Safe Shutdown Earthquake
Nondestructive Examination
Downpower |
| 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 |
| WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR) | 9 December 2021 | Revised Pressure and Temperature Limits Report (PTLR) | Hydrostatic
Pressure and Temperature Limits Report |
| ML21244A345 | 20 September 2021 | Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves | Grace period |
| CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | 20 July 2021 | Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | Safe Shutdown Earthquake
Nondestructive Examination
Downpower |
| CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | 23 March 2021 | Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | Nondestructive Examination
Foreign Material Exclusion
Coast down |
| ML21060A913 | 17 March 2021 | Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Watts Bar ISFSI | Decommissioning Funding Plan
Authorized possession limits |
| CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | 25 February 2021 | Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | Anticipated operational occurrence |
| WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | 11 February 2021 | Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | Safe Shutdown Earthquake
Nondestructive Examination
Downpower |
| WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR) | 16 December 2020 | Revised Pressure and Temperature Limits Report (PTLR) | Hydrostatic
Pressure and Temperature Limits Report |
| CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User | 16 December 2020 | 10 CFR 71.95 Report for 3-60B Casks User | |
| CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | 28 August 2020 | Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | |
| WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program | 16 April 2020 | Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program | |
| CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | 10 October 2019 | License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | Safe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Anticipated operational occurrence
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Coatings
Operating Basis Earthquake
Cyber Security
Emergency Lighting
FLEX
Pressure and Temperature Limits Report
Annual Radioactive Effluent Release Report
Process Control Program
Time Critical Operator Action
Earthquake
Maintenance Rule Program
Fuel cladding
Fire Protection Program
Flow Induced Vibration |
| L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | 18 June 2019 | Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | Post Accident Monitoring |
| L-19-026, Revised Pressure and Temperature Limits Report (PTLR) | 4 April 2019 | Revised Pressure and Temperature Limits Report (PTLR) | Hydrostatic
Pressure and Temperature Limits Report |
| ML19039A049 | 8 February 2019 | Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions | Hot Short
Safe Shutdown
Boric Acid
High winds
Loop seal
Ultimate heat sink
Grab sample
Fire Barrier
Tornado Missile
Time to boil
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Operator Manual Action
VT-2
Tornado-Generated Missile
Tornado Generated Missile
Design basis earthquake
Tritium Producing Burnable Absorber Rods
Earthquake
Fuel cladding |
| ML19003A569 | 16 January 2019 | Review of the Fall 2017 Steam Generator Tube Inspection Report | |
| ML18242A038 | 30 August 2018 | Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | Post Accident Monitoring |
| CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) | 1 August 2018 | Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) | Safe Shutdown |
| CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information | 10 April 2018 | Seismic Probabilistic Risk Assessment Supplemental Information | Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Large early release frequency
Earthquake |
| ML17356A269 | 20 December 2017 | Construction Lessons Learned Report | Significance Determination Process |
| ML17313A128 | 9 November 2017 | Revised Pressure and Temperature Limits Report (PTLR) | Hydrostatic
Pressure and Temperature Limits Report |
| CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations | 13 October 2017 | Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations | Hydrostatic
Aging Management |
| ML17272A019 | 29 September 2017 | Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | Post Accident Monitoring |
| ML17263A116 | 20 September 2017 | Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | Post Accident Monitoring |
| ML17209A554 | 28 July 2017 | Cycle 14 Steam Generator Tube Inspection Report | Nondestructive Examination |
| CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index | 30 May 2017 | Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index | |
| ML16215A104 | 2 August 2016 | Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report | Post Accident Monitoring
Past operability |
| ML16113A020 | 22 April 2016 | Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report | Temporary Modification
Foreign Material Exclusion
Fuel cladding |
| CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information | 31 March 2016 | Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information | Offsite Dose Calculation Manual
Anticipated operational occurrence
Tritium |
| CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program | 19 February 2016 | TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program | |
| CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory | 29 December 2015 | Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory | |
| CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit | 21 September 2015 | Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit | GOTHIC |
| CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results | 20 August 2015 | Submittal of Electromagnetic Interference (EMI) Survey Results | |
| CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report | 31 July 2015 | the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report | Commercial Grade Dedication |
| CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 3 | 15 July 2015 | Individual Plant Examination of External Events (IPEEE) Report, Revision 3 | Earthquake
Weak link |
| CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information | 8 July 2015 | 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information | |
| CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 16 June 2015 | Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Ultimate heat sink
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Fukushima Dai-Ichi
Earthquake |
| ML15121A656 | 1 May 2015 | NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List | |
| CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals | 10 April 2015 | Severe Accident Management Alternatives for Reactor Coolant Pump Seals | Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
Earthquake |
| CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc | 25 March 2015 | Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid | Ultimate heat sink
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Fukushima Dai-Ichi
Earthquake |
| ML15030A508 | 30 January 2015 | Tritium Production Program, Updated Plans for Cycle 13 Operation and Updated Evaluation of the Radiological Impacts of Tritium Permeation Into the Reactor Coolant System | Offsite Dose Calculation Manual |
| CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident | 30 December 2014 | Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident | Safe Shutdown
Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Seismically rugged
Earthquake
Power Operated Valves |