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CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)10 January 2024Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
ML23192A44731 July 2023Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards InformationProbabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)10 April 2023Revised 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 Sche20 March 2023Application 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
ML22363A39228 December 2022Cycle 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 2022to 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 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
ML22154A4043 June 2022Unit 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 Use27 May 2022to 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 Report16 December 2021Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final ReportSafe 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 2021Application 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 2021Revised Pressure and Temperature Limits Report (PTLR)Hydrostatic
Pressure and Temperature Limits Report
ML21277A1234 October 2021Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw EvaluationFinite Element Analysis
CNL-21-072, TVA Nuclear Calculation Coversheet/ Ecm Metadata Update13 August 2021TVA Nuclear Calculation Coversheet/ Ecm Metadata Update
CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report20 July 2021Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final ReportSafe Shutdown Earthquake
Nondestructive Examination
Downpower
ML21140A02814 May 2021Gravel 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 2021Supplement 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 2021Expedited 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 Report11 February 2021Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final ReportSafe Shutdown Earthquake
Nondestructive Examination
Downpower
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User16 December 202010 CFR 71.95 Report for 3-60B Casks User
WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)16 December 2020Revised Pressure and Temperature Limits Report (PTLR)Hydrostatic
Pressure and Temperature Limits Report
ML20350B72015 December 2020Discharge Monitoring Report Quality Assurance Study 40 Final Report 2020
ML20308A4762 November 202010 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary ReportBoric Acid
Shutdown Margin
Stroke time
Anticipated operational occurrence
Anchor Darling
Temporary Modification
Weak link
Overspeed trip
ML20304A40328 October 2020Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements ManualUnanalyzed 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
ML20255A00024 September 2020Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: SeismicInternal 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 2020Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
ML20112F4856 May 2020Staff Assessment of Flooding Focused EvaluationSafe 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 Program16 April 2020Analysis 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 2019License 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 Report4 September 2019Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report18 June 2019Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) ReportPost 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 Conditions7 June 2019Tennessee 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 ConditionsFLEX
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 Report16 April 2019Extended Power Uprate - Unit 1 Flow Induced Vibration Summary ReportFlow Induced Vibration
Power Uprate
L-19-026, Revised Pressure and Temperature Limits Report (PTLR)4 April 2019Revised 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 Information13 March 2019Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information
ML19039A0498 February 2019Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional RedactionsHot 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
ML18352A22917 December 2018Pressure Temperature Limits Report, Revision 7Hydrostatic
ML18340A03030 November 2018Tennessee Valley Authority - Sequoyah, Study to Confirm Calibration of Numerical Model
CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report29 November 2018Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report
ML18283B54710 October 2018Responding 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 Report13 September 2018Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
ML18136A49515 May 2018Pressure Temperature Limits Report, Revision 6Hydrostatic
ML18061A0362 March 2018IAEA Report of the Operational Safety Review Team (Osart) Mission to the Sequoyah Nuclear Power PlantBoric 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
ML18079B14023 February 2018Browns 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
ML17356A26920 December 2017Construction Lessons Learned ReportSignificance 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 Evaluations13 October 2017Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity EvaluationsHydrostatic
Aging Management
ML17222A3285 September 2017Flood Hazard Mitigation Strategies AssessmentFLEX
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 Index30 May 2017Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index
ML17114A37120 April 2017Errata 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 Revision28 October 2016Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision