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) | |
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 | |
ML22363A392 | 28 December 2022 | Cycle 14 Mellla+ Eigenvalue Tracking Data | |
CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) | 9 December 2022 | to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) | Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Abnormal operational transient Feedwater Controller Failure MELLLA |
CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information | 18 July 2022 | Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information | Stroke time Anticipated operational occurrence Abnormal operational transient |
ML22154A404 | 3 June 2022 | Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data | |
CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use | 27 May 2022 | to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use | |
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 |
ML21277A123 | 4 October 2021 | Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation | Finite Element Analysis |
CNL-21-072, TVA Nuclear Calculation Coversheet/ Ecm Metadata Update | 13 August 2021 | TVA Nuclear Calculation Coversheet/ Ecm Metadata Update | |
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 |
ML21140A028 | 14 May 2021 | Gravel Lot Restoration Project, Construction General Permit, Notice of Intent | |
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-21-011, 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 |
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 | |
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 |
ML20350B720 | 15 December 2020 | Discharge Monitoring Report Quality Assurance Study 40 Final Report 2020 | |
ML20308A476 | 2 November 2020 | 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report | Boric Acid Shutdown Margin Stroke time Anticipated operational occurrence Anchor Darling Temporary Modification Weak link Overspeed trip |
ML20304A403 | 28 October 2020 | Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual | Unanalyzed Condition Boric Acid Time of Discovery High winds Shutdown Margin Anticipated operational occurrence Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Functionality Assessment Incorporated by reference Pressure and Temperature Limits Report Design basis earthquake Earthquake Maintenance Rule Program |
ML20255A000 | 24 September 2020 | Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic | Internal Flooding Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Large early release frequency Earthquake Backfit |
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) | |
ML20112F485 | 6 May 2020 | Staff Assessment of Flooding Focused Evaluation | Safe Shutdown Internal Flooding Hydrostatic FLEX Fukushima Dai-Ichi Flooding Focused Evaluation |
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 |
CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report | 4 September 2019 | Extended Power Uprate - Flow Induced Vibration Summary Report | 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 |
CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | 7 June 2019 | Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | FLEX Design basis earthquake Spent Fuel Pool Instrumentation Severe Accident Management Guideline Hardened vent |
CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report | 16 April 2019 | Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report | Flow Induced Vibration Power Uprate |
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 |
CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information | 13 March 2019 | Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information | |
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 |
ML18352A229 | 17 December 2018 | Pressure Temperature Limits Report, Revision 7 | Hydrostatic |
ML18340A030 | 30 November 2018 | Tennessee Valley Authority - Sequoyah, Study to Confirm Calibration of Numerical Model | |
CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report | 29 November 2018 | Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report | |
ML18283B547 | 10 October 2018 | Responding to Letter of 11/18/1977 from E. G. Case to G. Williams, Providing Environmental Qualification Information for Electrical Connectors in Reference of IE Bulletins 77-05 & 77-05A | |
CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report | 13 September 2018 | Extended Power Uprate - Flow Induced Vibration Summary Report | Flow Induced Vibration |
ML18136A495 | 15 May 2018 | Pressure Temperature Limits Report, Revision 6 | Hydrostatic |
ML18061A036 | 2 March 2018 | IAEA Report of the Operational Safety Review Team (Osart) Mission to the Sequoyah Nuclear Power Plant | Boric Acid Ultimate heat sink Grab sample Anticipated operational occurrence Probabilistic Risk Assessment Locked High Radiation Area FLEX Aging Management Foreign Material Exclusion Severe Accident Management Guideline Earthquake Scaffolding |
ML18079B140 | 23 February 2018 | Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus | |
ML17356A269 | 20 December 2017 | Construction Lessons Learned Report | Significance Determination Process |
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 |
ML17222A328 | 5 September 2017 | Flood Hazard Mitigation Strategies Assessment | FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment |
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 | |
ML17114A371 | 20 April 2017 | Errata for BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry, Unit 2, 120 Degree Capsule | |
CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision | 28 October 2016 | Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision | |