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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-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-15-097, 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-15-143, 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-15-204, 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-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-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) | |
| 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 | |
| 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 | |
| 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 |
| 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 |
| ML052510007 | 7 September 2005 | IR 05000390-05-013, Watts Bar Nuclear Power Plant, Preliminary Greater than Green Finding | Significance Determination Process |
| ML060110110 | 17 January 2006 | Letter Cycle 6 SG ISI Reports Review Summary Letter | |
| ML062910513 | 24 August 2004 | TVAW001-RPT-001, Rev. 0, Report on Watts Bar, Unit 1 Containment Building Walkdowns for Emergency Sump Strainer Issues. | |
| ML062910522 | 5 November 2003 | WB1-DWD-024A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1. | |
| ML062920051 | 31 October 2003 | WB1-DWD-005A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1. | Fire Barrier |
| ML063060251 | 15 October 2003 | WB1-DWD-015A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1. | |
| ML080230484 | 14 January 2008 | Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report | Earthquake |
| ML080230485 | 14 January 2008 | Evaluation of 2002 USGS National Seismic Hazard Assessment, Final Report | Earthquake |
| ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
| ML083260671 | 30 April 2008 | Package of Nuclear Safety Review Staff Repts for Which Complete Resolution of safety-related Issues Not Achieved. W/One Oversize Drawing. Continuation of Nuclear Safety Review Staff Repts | Safe Shutdown Pressure Boundary Leakage Pressure boundary leak Scaffolding |
| ML090090044 | 31 December 2008 | Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle | |
| ML090210107 | 11 February 2009 | Status of Regulatory Framework for the Completion of Corrective Action and Special Programs and Unresolved Safety Issues | Condition Adverse to Quality Fire Protection Program |
| ML090360589 | 21 January 2009 | Enclosure 1 - Watts Bar, Unit 2 Severe Accident Management Alternatives Analysis | Boric Acid High winds Mission time Fire Barrier Tornado Missile Internal Flooding Hydrostatic Probabilistic Risk Assessment Tornado Generated Missile Earthquake Maintenance Rule Program Biofouling |
| ML090400795 | 4 February 2009 | GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version | Safe Shutdown Probabilistic Risk Assessment Severe Accident Management Guideline Generic Issues Program |
| ML100540144 | 31 December 2009 | WCAP-17044-NP, Revision 0, Westinghouse Setpoint Methodology for Protection Systems, Watts Bar Unit 2. | |
| ML100550651 | 31 December 2009 | WCAP-17035-NP, Revision 2, Watts Bar, Unit 2, Heatup and Cooldown Limit Curves for Normal Operation and PTLR Support Documentation | Hydrostatic Aging Management Exemption Request |
| ML101200206 | 3 March 2010 | TVA Watts Bar Nuclear Plant, Unit 2 - MRS-FSR-1796-WBT, Revision 0, Steam Generator Eddy Current Inspection Report, Baseline Inspection, Volume 1 | |
| ML101241188 | 3 March 2010 | TVA Watts Bar Nuclear Plant, Unit 2 - MRS-FSR-1796-WBT, Revision 0, Steam Generator Eddy Current Inspection Report, Baseline Inspection, Volume 3 | |
| ML101241190 | 30 April 2010 | TVA Watts Bar Nuclear Plant, Unit 2 - MRS-FSR-1796-WBT, Revision 0, Steam Generator Eddy Current Inspection Report, Baseline Inspection, Volume 2 | Nondestructive Examination |
| ML101600490 | 3 June 2010 | Chapter 12 - Question 6 - Calculations | |
| ML101600502 | 3 June 2010 | Chapter 12 - Question 8 - Calculation | |
| ML101870619 | 30 June 2010 | WNA-LI-00058-WBT-NP, Revion 0, Tennessee Valley Authority (TVA) Watts Bar Unit 2 (WBN2) Post-Accident Monitoring System (Pams) Licensing Technical Report. | Post Accident Monitoring |