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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23270B836 | 26 September 2023 | Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards | Nondestructive Examination Aging Management License Renewal Operational leakage |
| 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 |
| ML23025A075 | 25 January 2023 | American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle . | |
| ML22363A392 | 28 December 2022 | Cycle 14 Mellla+ Eigenvalue Tracking Data | |
| CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval | 12 December 2022 | Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval | Safe Shutdown Stroke time Incorporated by reference Scram Discharge Volume Weak link |
| 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 |
| ML22269A388 | 7 September 2022 | 02-Gamma Spectroscopy of Concrete Pucks | |
| 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 | |
| ML21277A123 | 4 October 2021 | Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation | Finite Element Analysis |
| ML21246A294 | 29 September 2021 | Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIs | Decommissioning Funding Plan Authorized possession limits |
| ML21246A295 | 29 September 2021 | Memo to File | Decommissioning Funding Plan |
| 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 | |
| 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 |
| RA-20-0280, Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw | 14 September 2020 | Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw | Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis |
| ML20112F485 | 6 May 2020 | Staff Assessment of Flooding Focused Evaluation | Safe Shutdown Internal Flooding Hydrostatic FLEX Fukushima Dai-Ichi Flooding Focused Evaluation |
| 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 |
| ML19242C728 | 28 August 2019 | Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T | Safe Shutdown Internal Flooding Flow Accelerated Corrosion Time Critical Operator Action Through-Wall Leakage Coast down GOTHIC Affidavit |
| 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 |
| RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | 30 May 2019 | Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 | |
| 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 |
| 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 | |
| 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 |
| CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | 31 May 2018 | Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | FLEX Hardened vent |
| 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 | |
| ML17222A328 | 5 September 2017 | Flood Hazard Mitigation Strategies Assessment | FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment |
| ML17170A073 | 15 June 2017 | Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233 | Weak link |
| 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 | |
| ML17033B164 | 2 February 2017 | American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs | |
| ML17031A431 | 26 January 2017 | Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Emergency Lighting FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Earthquake GOTHIC Unidentified leakage |
| ML17024A036 | 31 December 2016 | Operating Data Report for 2016 | Temporary Modification Biofouling Power change Coast down |
| 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 | |
| ML16230A282 | 17 August 2016 | Duke Power Company Oconee Nuclear Station Unit 2 Integrated Leak Rate Test of the Reactor Containment Building | Boric Acid Power Operated Valves |
| ML16196A088 | 5 August 2016 | Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation | Ultimate heat sink FLEX Fukushima Dai-Ichi Earthquake |
| ML16152A052 | 31 May 2016 | ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis | Non-Destructive Examination Stress corrosion cracking |
| ML16146A018 | 25 May 2016 | Special Report 296/2016-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation | Post Accident Monitoring |
| ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) | 15 February 2016 | Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) | Safe Shutdown Unanalyzed Condition Tornado Missile Commercial Grade Dedication Arc flash Finite Element Analysis Aging Management Large early release frequency Earthquake |
| ML16028A295 | 29 January 2016 | 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration | |
| ML16027A059 | 27 January 2016 | Snubbers Added to Lnservice Testing Program | |
| ML16034A325 | 31 December 2015 | Revision 0 to Summary of Methodology Used for Seismic Capacity Evaluation of GMRS Mitigation Components | Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML15356A654 | 22 December 2015 | Submittal of 10 CFR 50.46 30-Day Report | |
| CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) | 25 September 2015 | Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) | Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA |
| ML15282A240 | 21 September 2015 | Startup Test Plan | Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level High Radiation Area Anticipated operational occurrence Probabilistic Risk Assessment Water level shrink MELLLA Flow Induced Vibration |
| ML15282A239 | 21 September 2015 | Flow Induced Vibration Analysis and Monitoring Program | Flow Induced Vibration |
| ML15282A181 | 21 September 2015 | Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 | |
| NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan | 21 September 2015 | Browns Ferry, Units 1, 2, and 3, Startup Test Plan | Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level High Radiation Area Anticipated operational occurrence Probabilistic Risk Assessment Water level shrink MELLLA Flow Induced Vibration |
| NL-15-169, Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 | 21 September 2015 | Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 |