Tony Brown# QUERYd66e8e8ad0bfd79a94a04c0ca57f2702
Tony Brown
Tony Brown# QUERYd3e6812c6588f131b01bf6ec440cbf12
Tony Brown# QUERYbf5f448d594e86014ead4ebb2d8d78a7
Tony Brown OR Tony Brown
Tony Brown# QUERY67fd74b410f0ed6a9b4f7d8c26755300
Tony Brown# QUERY3610895edd42cae6287aec4ab6e08022
Tony Brown# QUERYf5d2fd75e78c619e61923c5d65accb7e
Tony Brown# QUERYb576e4088a0a3192b1991eaccc3640dd
Tony Brown# QUERY66c8863951fd6ea3097c61a44ee138e8
False
Tony Brown# QUERY600bb62cdec9e3bca7c4ea81d1f9984f
True
Tony Brown# QUERYea8d93abe6e4c24534553889ca4241ff
Nuclear Energy Institute
Tony Brown# QUERYbccd8c030dd7760504b4ee22b2a90b26
Tony Brown# ERR1dd423a8697e32d6813ecd1a7aae482c
WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program
DCL-16-002, Notification of Full Compliance with Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
WBL-20-016, Annual Radiological Environmental Operating Report - 2019
WBL-20-036, Of the Unit Cycle 2 Cycle 3 Core Operating Limits Report (COLR)
CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24)
WBL-20-049, Augmented Inservice Test Program, Revision 2
NOC-AE-15003255, Supplement to Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - Phase 2 Staffing Assessment
WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)
WBL-19-048, Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-042
WBL-20-039, 10 CFR 50.59 Summary Report for October 28, 2018 to June 5, 2020
DCL-16-003, Notification of Full Compliance with Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
NOC-AE-15003257, Notification of Compliance with Orders EA-12-049 for Mitigation Strategies for Beyond-Design-Basis External Events and EA-12-051 for Reliable Spent Fuel Pool Instrumentation
Press Release-IV-12-010, NRC Names New Resident Inspector at Palo Verde Nuclear Generating Station
CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays
WBL-20-008, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2020-01 - Preparation and Scheduling of Operator Licensing Examinations
Press Release-IV-11-001, NRC Names New Senior Resident Inspector at Palo Verde Nuclear Power Plant
WBL-21-052, Of the Unit 1 Cycle 18 Core Operating Limits Report (COLR)
05000391/LER-2021-001, Automatic Reactor Trip on Main Turbine Trip Caused by Main Feed Pump Trip Due to Low Condenser Vacuum
05000390/LER-2021-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open
WBL-21-013, Of Cycle 4 Core Operating Limits Report
05000391/LER-2020-004, Steam Generators Degraded Due to Axial Outside Diameter Stress Corrosion Cracking
05000391/LER-2020-003, Re Low RHR Flow in Mode 6 Results in a Condition Prohibited by Technical Specifications
05000390/LER-2020-005, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 2A-A Shutdown Board
05000391/LER-2020-002, Re Two Pressurizer Safety Valves Outside of Technical Specification Limits Due to Set Point Drift
WBL-21-008, American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 3 Operation
WBL-20-058, Of the Unit 1 Cycle 17 Core Operating Limits Report (COLR) and Revision 0 of the Unit 2 Cycle 4 Core Operating Limits Report (COLR)
WBL-20-042, American Society of Mechanical Engineers, Section XI, Third 10-Year Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 16 Operation
05000391/LER-2020-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open
05000390/LER-2020-002, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board
05000390/LER-2020-001, Manual Reactor Trip Due to Lowering Steam Generator Level Caused by a Hand Station Failure
05000390/LER-2019-004, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open
WBL-19-058, Statement of Payment of Civil Penalty
05000390/LER-2019-003, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed
WBL-19-041, Cycle 2 Steam Generator Tube Inspection Report
05000391/LER-2019-002, Breach Due to Penetration Boot Seal Separation Results in Shield Building Inoperability
05000390/LER-2019-002, Loss of Control Room Emergency Air Temperature Control System Due to Air Filter Failure
05000391/LER-2019-001, Regarding Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed
WBL-19-036, Notification of Readiness for NRC Inspection Procedure 95001 Inspection
05000390/LER-2020-003, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open
L-16-323, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to CFR 50.54(f) Regarding Recommendation 2.1 of the Near Term Task Force Review of Insights from Fukushima Dai-inchi Accident
L-20-132, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-20-231, Physical Security Plan. Training and Qualification Plan. and Safeguards Contingency Plan (Revision 24)
L-20-313, Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force
L-20-280, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic
L-21-070, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic
L-21-131, Response to Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations
L-21-140, 2020 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-21-218, Submittal of Rev. 35 to Emergency Plan
L-21-223, Request for Relaxation of Confirmatorv Action Commitment (EA-04-224)
L-21-214, Proposed Inservice Inspection Alternative RR-A2
L-21-217, CFR 50.55a Requests RP-1, RP-2, RP-3, and RP-4 Regarding Inservice Pump and Valve Testing
L-21-255, Response to NRC Inspection Report 05000346/2021401, EA-21-105
L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-176
L-21-285, Response to NRC Inspection Report 05000346/2021090, EA-21-155
L-20-289, Emergency Plan Amendment Request
L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2
L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3
L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding
L-22-102, Report of Facility Changes, Tests, and Experiments
L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage
L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report
L-22-149, Post Accident Monitoring Report
L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding
L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A2
L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events
L-22-203, Submittal of Evacuation Time Estimates
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 5
L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)
L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002
L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report
L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications
L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements
L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage
L-24-029, Post-Exam Package Cover Letter
L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments
L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023
05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
05000346/LER-2022-002, Strong Winds Result in Ultimate Heat Sink Low Water Level
05000346/LER-2022-001, Plant Heatup with Inoperable Decay Heat Pump Due to Oil Leak Induced by Constant Level Oiler
L-24-227, Response to Request for Additional Information for Relief Request RR-A 1
05000346/LER-2021-001-02, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
L-24-233, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles
L-24-247, Davis-Nesse Nuclear Power Station, Unit 1 - License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
L-25-021, Response to Request for Confirmatory Information Regarding the IR23 Steam Generator Tube Inspection Report
L-20-236, LTR Licensee Outline Submittal
05000346/LER-2021-003, Reactor Trip Due to Failed Uninterruptible Power Supply and Steam Feedwater Rupture Control System Actuations
05000346/LER-2021-002, For Davis Besse Nuclear Power Station, Unit 1, Failure of Auxiliary Feedwater Rooms Interconnecting Door to Latch Due to Worn Interlock
L-25-099, Response to NRC Regulatory Issue Summary 2025-03, Preparation and Scheduling: of Operator Licensing: Examinations
L-25-077, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2024
L-25-128, Application to Revise Technical Specifications to Adopt TST-597, Eliminate LCO 3.0.3 Mode 2 Requirement
L-25-158, Twentieth Inservice Inspection Summary Report
L-25-127, 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-25-171, Special Report: Inoperable Post Accident Monitoring Instrumentation
L-25-203, Cancellation of Licensee Event Report 2024-05-00