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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 | |
| 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 |
| 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 |
| 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 |
| ML15282A181 | 21 September 2015 | Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 | |
| 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 |
| 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 | |
| NL-15-169, Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program | 21 September 2015 | Browns Ferry Units 1, 2 and 3, Flow Induced Vibration Analysis and Monitoring Program | Flow Induced Vibration |
| 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 |
| ML15282A182 | 31 August 2015 | ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 | |
| NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 | 31 August 2015 | ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 | |
| NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). | 31 August 2015 | ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). | |
| NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). | 31 August 2015 | ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). | |
| NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. | 31 August 2015 | NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. | Anticipated operational occurrence Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Earthquake Flow Induced Vibration |
| ML15282A236 | 31 August 2015 | NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis. | Anticipated operational occurrence Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Earthquake Flow Induced Vibration |
| ML15282A184 | 31 August 2015 | ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). | |
| ML15282A185 | 31 August 2015 | ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). | |
| 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-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical | 3 June 2015 | Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical | Stroke time Fuel cladding |
| ONS-2015-065, TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay | 22 May 2015 | TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay | Offsite Circuit Backfit Manual Operator Action |
| ML16272A217 | 6 March 2015 | Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Pp. 1-70, Dated March 6, 2015 (Redacted) | Safe Shutdown Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
| ML16272A218 | 6 March 2015 | Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Appendices, Dated March 6, 2015 (Redacted) | Safe Shutdown |
| CNL-14-208, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Pl | 17 December 2014 | Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plan | Hot Short Safe Shutdown High Radiation Area Mission time Fire Barrier Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Multiple Spurious Operation Incorporated by reference FLEX Thermoset Large early release frequency Severe Accident Management Guideline Fire Protection Program Fire Watch Very Early Warning Fire Detection |
| CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) | 11 December 2014 | (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) | Reactor Vessel Water Level Stroke time Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding Power change |
| ML14176A961 | 24 June 2014 | Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 | Fire Barrier Coatings Foreign Material Exclusion |