Category:Meeting Briefing Package/Handouts
MONTHYEARML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24191A0642024-07-16016 July 2024 TVA Pre-Submittal Conference Presentation for Proposed LAR Regarding a Revision to Sequoyah Fuel Handling Accident Analysis, Deletion of TS 3.9.4 and Modification of TS 3.3.6 - July 16, 2024 ML24149A1332024-05-29029 May 2024 Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates Public Portion Meeting Slides ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator Testing ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24117A0352024-05-0202 May 2024 TVA Sequoyah Nuclear Plant - 1B Emergency Diesel Generator Regulatory Conference May 02, 2024 -Presentation Slides ML24113A0962024-04-22022 April 2024 RIPE Pre-Submittal Meeting Slides ML24078A2722024-04-10010 April 2024 Subsequent License Renewal Public Scoping Meeting ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML24082A2532024-03-26026 March 2024 Summary of March 18, 2024, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future License Amendment Request Related to Fuel Handling and Fuel Decay Time ML24044A0872024-02-14014 February 2024 TVA Slides - Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request to Revise TS 3.7.11, Main Control Room Area Chilled Water System ML24037A0252024-02-0808 February 2024 Pre-Submittal Presentation - 02/08/2024 - Proposed License Amendment Request Change to the Sequoyah Nuclear Plant Technical Specifications 3.8.1 and 3.8.2 ML24032A2752024-02-0707 February 2024 Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23345A1662023-12-13013 December 2023 Tennessee Valley Authority - Pre-submittal Meeting for Conversion of Nuclear Quality Assurance Plan from ANSI N45.2-1971 to ASME NQA-1-2015 (EPID L-2023-LRM-0103) - Slides ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23052A0362023-02-22022 February 2023 February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22157A4132022-06-0606 June 2022 Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides ML22102A3032022-04-12012 April 2022 Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21343A0282021-12-14014 December 2021 TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule ML21308A4932021-11-0808 November 2021 Pre-submittal Meeting Presentation - License Amendment Request to Revise Sequoyah Operating License to Use Fire and Seismic PRA Models for 10 CFR 50.69 Risk-Informed Categorizations (EPID L-2021-LRM-0109) (Slides) ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21252A3632021-09-15015 September 2021 Pre-Submittal Meeting for License Amendment Request to Eliminate the High Negative Flux Rate Trip ML21250A3652021-09-0808 September 2021 Meeting Slides - Watts Bar Nuclear Plant Unit 2, Presubmittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analyses Report (UFSAR) to Use a Tube Support Plate Locking/Displacement Analysis ML21250A3012021-09-0707 September 2021 TVA Slides for September 7, 2021, Presubmittal Meeting to Discuss Planned Browns Ferry TSTF-505 License Amendment Request ML21217A2872021-08-19019 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed License Amendment Request Re Application to Modify Technical Specification 3.7.8 Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board ML21229A1992021-08-19019 August 2021 Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides) ML21231A0972021-08-18018 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning ML21152A1872021-06-0101 June 2021 TVA Slides for June 1, 2021, Presubmittal Meeting to Discuss Planned Control Bay Chiller Cross-Tie License Amendment Request ML21117A0722021-04-27027 April 2021 Meeting Slides for April 28, 2021 Meeting with TVA 2024-08-15
[Table view] Category:Report
MONTHYEARWBL-24-047, Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program2024-09-25025 September 2024 Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program ML24247A1732024-08-28028 August 2024 Enclosure 5: Joint Frequency Distributions of Wind Speed and Direction 2004 to 2013 SQN Units 1 & 2 ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) WBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report WBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) ML23025A0752023-01-25025 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 . ML22363A3922022-12-28028 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 Interval2022-12-12012 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 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)2022-12-0909 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) WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted 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 Information2022-07-18018 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 ML22154A4042022-06-0303 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 Use2022-05-27027 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 WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) 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 .2021-12-0909 December 2021 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 . ML21277A1232021-10-0404 October 2021 Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw Evaluation ML21246A2942021-09-29029 September 2021 Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIs ML21246A2952021-09-29029 September 2021 Memo to File ML21246A2802021-09-29029 September 2021 Final Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Sequoyah Nuclear Plant ISFSIs ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 CNL-21-072, TVA Nuclear Calculation Coversheet/ Ecm Metadata Update2021-08-13013 August 2021 TVA Nuclear Calculation Coversheet/ Ecm Metadata Update CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report ML21140A0282021-05-14014 May 2021 Gravel 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)2021-03-23023 March 2021 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) ML21060A9132021-03-17017 March 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Watts Bar ISFSI 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)2021-02-25025 February 2021 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) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) ML20350B7202020-12-15015 December 2020 Discharge Monitoring Report Quality Assurance Study 40 Final Report 2020 ML20308A4762020-11-0202 November 2020 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report ML20304A4032020-10-28028 October 2020 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML20255A0002020-09-24024 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 CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) ML20112F4852020-05-0606 May 2020 Staff Assessment of Flooding Focused Evaluation WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis 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)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report2019-09-0404 September 2019 Extended Power Uprate - Flow Induced Vibration Summary Report L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report 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 Conditions2019-06-0707 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 ML19156A2612019-06-0505 June 2019 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report2019-04-16016 April 2019 Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report 2024-09-25
[Table view] Category:Miscellaneous
MONTHYEARWBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23025A0752023-01-25025 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 . 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 Interval2022-12-12012 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 WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 ML19156A2612019-06-0505 June 2019 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-31031 May 2018 Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) ML17278A7592017-10-0505 October 2017 Soarca Sequoyah Updated Draft Executive Summary ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report ML17170A0732017-06-15015 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 ML17033B1642017-02-0202 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 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16146A0182016-05-25025 May 2016 Special Report 296/2016-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program ML16028A2952016-01-29029 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 CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory ML15356A6542015-12-22022 December 2015 Submittal of 10 CFR 50.46 30-Day Report ML15336A9402015-11-26026 November 2015 Submittal of 10 CFR 50.46 Combined Annual and 30-Day Report ML15321A4542015-11-13013 November 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15254A5432015-09-11011 September 2015 Submittal of 10 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage Installation CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List ML15156A3892015-04-28028 April 2015 LTR-SGMP-15-25 Np, Response to NRC Request for Additional Information on the Design Features of the Sequoyah, Unit 2, Replacement Steam Generators. CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 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 Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 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 Accid ML14356A3622015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident CNL-14-210, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-12-22022 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. ML14325A0692014-11-17017 November 2014 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report ML14163A6582014-09-18018 September 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML14259A3382014-09-12012 September 2014 Plant(Sqn) - NPDES Permit No. TN0026450 - Discharge Monitoring Report(Dmr) for August 2014 CNL-14-129, Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Browns Ferry Nuclear Plant2014-08-28028 August 2014 Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Browns Ferry Nuclear Plant CNL-14-130, Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Sequoyah Nuclear Plant2014-08-28028 August 2014 Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Sequoyah Nuclear Plant ML14212A6032014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule IR 05000391/19860602014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule 2024-03-05
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