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 Issue dateTitleTopic
CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-4711 January 2024Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47EVT-1
CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request1 June 2023Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative RequestsStroke time
VT-2
Incorporated by reference
Surveillance Frequency Control Program
CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-3211 March 2023Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32Non-Destructive Examination
VT-2
Incorporated by reference
Pressure Boundary Leakage
CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .1 December 2022Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .Safe Shutdown
Reactor Vessel Water Level
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
Offsite Circuit
CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.12 September 2022Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.Safe Shutdown Earthquake
Hydrostatic
Nondestructive Examination
Pressure and Temperature Limits Report
CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.1 August 2022Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.Surveillance Frequency Control Program
GOTHIC
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 Information18 July 2022Request 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 InformationStroke time
Anticipated operational occurrence
Abnormal operational transient
CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change9 June 2022Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level ChangeSafe Shutdown Earthquake
Operating Basis Earthquake
Earthquake
CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)6 April 2022Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)Safe Shutdown
Surveillance Frequency Control Program
CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)18 March 2022Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)
CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)21 July 2021Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)
CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components28 April 2021Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and ComponentsHot Short
High winds
Internal Flooding
Probabilistic Risk Assessment
FLEX
Tornado Generated Missile
Surveillance Frequency Control Program
Large early release frequency
CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)29 December 2020Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)High winds
Tornado Missile
Probabilistic Risk Assessment
FLEX
Tornado Missile Risk Evaluator
Turbine Missile
CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)21 December 2020Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)Safe Shutdown
Tornado Missile
Internal Flooding
Probabilistic Risk Assessment
Tornado Generated Missile
Tornado Missile Protection
Surveillance Frequency Control Program
Large early release frequency
Tornado Missile Risk Evaluator
CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals10 August 2020Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals
CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights17 December 2019Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of InsightsSafe Shutdown
Unanalyzed Condition
Mission time
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Operating Basis Earthquake
FLEX
Fukushima Dai-Ichi
Seismically rugged
Large early release frequency
Earthquake
CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...8 August 2019Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...Reactor Vessel Water Level
Water Inventory Control
Incorporated by reference
CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second19 July 2019Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second
CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information25 January 2019Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information
CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus16 January 2019Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis PlusShutdown Margin
Anticipated operational occurrence
Feedwater Controller Failure
MELLLA
CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results16 January 2019Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results
CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information14 December 2018Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information
CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 413 December 2018Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4
CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-4617 October 2018Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46Probabilistic Risk Assessment
CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..11 October 2018Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ...
ML18283A89710 October 2018Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3Shutdown Margin
Half scram
Hydrostatic
Abnormal operational transient
Fast acting solenoid valve
Overtravel
Earthquake
Fuel cladding
Fire Watch
CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-03423 July 2018Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034Decommissioning Funding Plan
Authorized possession limits
CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.19 April 2018Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.
NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre19 April 2018Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec
CNL-18-032, Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program27 March 2018Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing ProgramSafe Shutdown
High winds
Mission time
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
Time Critical Operator Action
Cable Tray Ignition
Fire Protection Program
Very Early Warning Fire Detection
CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)5 February 2018Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)High winds
Safety Limit Minimum Critical Power Ratio
Mission time
Probabilistic Risk Assessment
Large early release frequency
Fire Protection Program
Very Early Warning Fire Detection
CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..23 October 2017Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..Safe Shutdown
Hydrostatic
Cyber Security
Multiple Spurious Operation
Fire Protection Program
CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera18 September 2017Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric GeneratiSafe Shutdown
High winds
Hydrostatic
Probabilistic Risk Assessment
Cyber Security
Multiple Spurious Operation
Large early release frequency
Fire Protection Program
CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels27 July 2017Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action LevelsSafe Shutdown
Time of Discovery
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Operator Manual Action
Spent Fuel Pool Instrumentation
Earthquake
Fuel cladding
Pressure Boundary Leakage
Grace period
CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels7 July 2017Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action LevelsSafe Shutdown
Time of Discovery
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Operating Basis Earthquake
Operator Manual Action
Spent Fuel Pool Instrumentation
Earthquake
Fuel cladding
Pressure Boundary Leakage
Grace period
CNL-17-039, 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 - Withdrawal of Regulatory..10 March 2017Response 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 - Withdrawal of Regulatory..Fukushima Dai-Ichi
CNL-17-035, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information3 March 2017Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information
CNL-17-017, Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects3 February 2017Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects
CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects20 January 2017Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety AspectsProbabilistic Risk Assessment
Flow Induced Vibration
NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf20 January 2017Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe
CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools19 December 2016Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel PoolsB.5.b Mitigating Strategies
CNL-16-161, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..13 October 2016Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..Flow Induced Vibration
CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 3023 September 2016Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30Finite Element Analysis
CNL-16-150, Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 3121 September 2016Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 31Safe Shutdown
Mission time
Stroke time
Battery sizing
CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 715 September 2016Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7Safe Shutdown
Reactor Vessel Water Level
Probabilistic Risk Assessment
Large early release frequency
CNL-16-152, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information12 September 2016Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional InformationUltimate heat sink
Time to boil
CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)24 August 2016Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)Safe Shutdown
Reactor Vessel Water Level
Probabilistic Risk Assessment
CNL-16-129, Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 293 August 2016Response to Request for Additional Information Regarding Proposed Technical Specifications (TS) Change TS-505 License Amendments - Extended Power Uprate (EPU) - Supplement 29Probabilistic Risk Assessment
Job Performance Measure
Large early release frequency
CNL-16-127, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information3 August 2016Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Upgrade (EPU) - Supplement 28, Responses to Requests for Additional Information
CNL-16-114, Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate .3 August 2016Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate .Safe Shutdown
Boric Acid
Ultimate heat sink
Fire Barrier
Coatings
Cyber Security
Zebra Mussel
Multiple Spurious Operation
Aging Management
MELLLA
Severe Accident Management Guideline
Veliger
Hardened vent
Fuel cladding
Biofouling
Fire Protection Program
Scaffolding
Flow Induced Vibration