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| Issue date | Title | |
|---|---|---|
| CNL-21-009, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative | 31 March 2022 | License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative |
| ML22049B317 | 4 October 2021 | Amendment 29 to Updated Final Safety Analysis Report, Chapter 2, Section 2.4, Hydrology, Water Quality, and Aquatic Biology - Redacted |
| ML21075A076 | 30 April 2021 | Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis |
| CNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529) | 17 July 2020 | Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529) |
| CNL-20-044, License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis | 6 May 2020 | License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis |
| ML19324C987 | 4 October 2019 | Amendment 28 to Updated Final Safety Analysis Report, Chapter 2, Site - Redacted |
| ML19010A212 | 18 March 2019 | Final Safety Evaluation for Tennessee Valley Authority Topical Report TVA Overall Basin Probable Maximum Precipitation |
| ML19010A274 | 18 March 2019 | Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority |
| ML18057A637 | 23 February 2018 | NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) |
| ML16196A088 | 5 August 2016 | Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation |
| ML15282A261 | 21 September 2015 | Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped) |
| NL-15-169, Browns Ferry, Units 1, 2, and 3, Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped) | 21 September 2015 | Browns Ferry, Units 1, 2, and 3, Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped) |
| ML15090A745 | 21 April 2015 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insight |
| 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 |
| ML12056A050 | 12 March 2012 | Enclosure 4 - Recommendation 2.3: Flooding |
| ML12053A340 | 12 March 2012 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 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 Accident |
| ML12056A048 | 12 March 2012 | Enclosure 2 - Recommendation 2.1: Flooding |
| ML12056A047 | 12 March 2012 | Enclosure 1 - Recommendation 2.1: Seismic |
| ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
| ML11132A118 | 5 May 2011 | Bellefonte, Units 1 and 2 - Proposed Regulatory Framework for the Possible Completion of Construction Activities |
| ML091730242 | 18 August 2009 | License Amendment, the Amendments Revise the Technical Specifications (Tss) to Adopt the Content of Technical Specification Task Force (TSTF) Change Traveler TSTF-448, Revision 3, Control Room Habitability |
| ML063350404 | 6 March 2007 | License Amendment, Five Percent Uprate (TAC No. MD3048) (TS-418) |
| ML050560337 | 23 February 2005 | (BFN) - Response to Nrc'S Acceptance Review Letter and Request for Additional Information Related to Technical Specifications Change No. TS-418 - Request for Extended Power Uprate Operation (Tac Nos MC3743 and MC3744) |
| ML050560150 | 23 February 2005 | Response to NRC Acceptance Review Letter and Request for Additional Information Related to Technical Specifications Change No. TS-431 - Request for Extended Power Uprate Operation |
| ML071650168 | 1 April 1999 | NEI Report: RCP Lube Oil Collection System Current Trend Abstract, April 1999 (Revision 1) |
| ML020030170 | 13 April 1993 | License Amendments 195, 210, & 167, Revising the Technical Specifications to Reflect a Design Change of Refuel Zone and Reactor Building Ventilation Radiation Monitoring System That Replaces Existing Analog Components |
| ML20155E765 | 7 October 1988 | Responds to NRC Re Violations Noted in Insp Repts 50-259/88-16,50-260/88-16 & 50-296/88-16.Corrective Actions: Std Cable Insp & Tests MA-45,Step 6.10 Revised to Include Note Providing Crafts Personnel W/Adequate Instructions |
| ML20154K889 | 12 September 1988 | Notice of Violation from Insp on 880501-0611.Violation Noted:Three Fire Brigade Members Who Entered Drywell for Fire Fighting Operations Not Qualified & Q-list Equipment Data Package (Sys 1) Not in Compliance W/Nuclear QA Manual |
| NRC Generic Letter 1987-02 | 19 February 1987 | NRC Generic Letter 1987-002: Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors, Unresolved Safety Issue A-46 |
| ML18026B137 | 9 August 1984 | Forwards Response to NRC 831012 Request for Addl Info Re Reactor Protection Sys Power Monitoring Sys Design Mods. Tech Specs Will Be Submitted in future.W/12 Oversize Drawings.Aperture Cards Available in PDR |
| NRC Generic Letter 1984-01 | 5 January 1984 | NRC Generic Letter 1984-001: NRC Use of the Terms, Important to Safety and Safety Related |
| ML20078M243 | 20 October 1983 | Forwards Responses to 830920 & 21 Requests for Addl Info Re Analog Instrumentation Installation.Startup Projected for 831128 |