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| Issue date | Title | Topic | |
|---|---|---|---|
| CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc | 31 March 2014 | Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid | Safe Shutdown Boric Acid Mission time Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Seismically rugged Design basis earthquake Earthquake Seismic Walkdown Report |
| 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 |
| 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 |
| 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 |
| 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-15-131, 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-15-143, 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-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results | 20 August 2015 | Submittal of Electromagnetic Interference (EMI) Survey Results | |
| 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-15-263, 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-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-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-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 | |
| 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 |
| 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 |
| 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-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 |
| 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) | |
| 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-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 |
| 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-21-040, 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 |
| 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-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-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) | |
| IR 05000391/1986060 | 31 July 2014 | WBRD-50-391/86-60 - Final Report and Revised Completion Schedule | Hydrostatic |
| 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 |
| 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 |
| ML020310185 | 6 February 2002 | Relief Request, Evaluation of ISI Program | VT-2 Incorporated by reference Liquid penetrant Dissimilar Metal Weld |
| ML020530458 | 19 February 2002 | Submittal of New (Revision 3) non-proprietary Version of Holtec, International Report HI-2012620. Revisions Identify Appendices a & C to Be Withheld in Accordance with Paragraph (B) (4) of 10 CFR 2.790 | Fuel cladding |
| ML020580082 | 19 February 2002 | Response to Request for Additional Information Re Tritium Production - Holtec Analysis. Submits New non-proprietary Version (Revision 3) of Holtec International Report HI-2012620 | Fuel cladding |
| ML021070404 | 3 April 2002 | Emergency Core Cooling System (ECCS) Evaluation Model Changes, Annual Notification & Reporting for 2001 | |
| ML021490139 | 23 May 2002 | Response to Request for Additional Information Re Radiological Impact | |
| ML022670125 | 19 September 2002 | Commitment Summary Report | |
| ML023030301 | 15 October 2002 | TVA Nuclear Strategic Performance Improvement Initiatives | Power change |
| ML031890474 | 10 July 2003 | Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Browns Ferry, S | Enforcement Discretion |
| ML032580389 | 28 May 2003 | Enclosure 2 - Responses to the NRC Request for Additional Information on the RFA-2 Licensing Submittal (WBN-TS-02-13) for the Watts Bar Nuclear Plant | |
| ML033230496 | 14 November 2003 | Reactor Coolant System Pressure and Temperature Limits Report, Revision 7 | Hydrostatic Pressure and Temperature Limits Report |
| ML040620449 | 26 February 2004 | Fitness-for-Duty (FFD) Program Performance Data for July - December 2003 | Fitness for Duty |
| ML041040261 | 5 April 2004 | to Engineering Report Watts Bar Nuclear Plant, Unit 1, Ultimate Heat Sink - 88oF Maximum Operating Temperature Evaluation. | Safe Shutdown Boric Acid Ultimate heat sink Anticipated operational occurrence Time to boil Safe Shutdown Earthquake Enforcement Discretion Pressure Boundary Leakage GOTHIC |
| ML041130196 | 19 April 2004 | Emergency Core Cooling System (ECCS) Evaluation Model Changes - 30 Day Report and Revised Annual Notification and Reporting for 2003 | |
| ML041140387 | 20 April 2004 | 10 CFR 50.59, Changes, Tests and Experiments Summary Report | Safe Shutdown Boric Acid Offsite Dose Calculation Manual Stroke time Emergency Lighting Pressure Boundary Leakage |
| ML041480437 | 31 March 2004 | Steam Generator Pulled Tube Examination Watts Bar Unit I - Cycle 5 RFO, Chapters 6 Through 10 | |
| ML041610191 | 31 March 2004 | Steam Generator Pulled Tube Examination Watts Bar Unit I - Cycle 5 RFO, Chapters 1 Through 5 | Nondestructive Examination |
| ML051120164 | 19 April 2005 | Emergency Core Cooling System (ECCS) Evaluation Model Changes - Annual Notification and Reporting for 2004 | Stroke time |
| ML052450058 | 26 August 2005 | Radioactive Liquid Effluent Line Abandonment Until Station Decommissioning | Offsite Dose Calculation Manual |
| ML052490346 | 1 September 2005 | Unresolved Item 05000390/2005002-05, Failure to Implement and Maintain Shutdown Procedures Resulting in Pressurizer PORV Actuations | Probabilistic Risk Assessment |
| ML052510007 | 7 September 2005 | IR 05000390-05-013, Watts Bar Nuclear Power Plant, Preliminary Greater than Green Finding | Significance Determination Process |
| ML052780197 | 30 September 2005 | 10 CFR 50.59, Changes, Tests and Experiments Summary Report | Stroke time Fuel cladding |