Category:Letter type:L
MONTHYEARL-2024-199, Special Report - Post Accident Monitoring Instrumentation2024-12-10010 December 2024 Special Report - Post Accident Monitoring Instrumentation L-2024-191, Reply to a Notice of Violation: NOV 05000250/2024003 and 05000251/20240032024-11-22022 November 2024 Reply to a Notice of Violation: NOV 05000250/2024003 and 05000251/2024003 L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-11-12012 November 2024 Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis L-2024-187, Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-11-12012 November 2024 Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-014, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2024-02-0909 February 2024 Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owners Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owners Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owners Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owners Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-09-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing2023-12-13013 December 2023 Unplanned Automatic Scram During RPS Testing 05000250/LER-2023-003, Grid Disturbance in Switchyard Causes Automatic Reactor Trip2023-11-20020 November 2023 Grid Disturbance in Switchyard Causes Automatic Reactor Trip ML23318A1782023-11-13013 November 2023 FAQ 23-03- Turkey Point IE01 05000250/LER-2023-002, Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure2023-10-0202 October 2023 Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure 05000250/LER-2023-001, RCS Pressure Boundary Degraded2023-06-14014 June 2023 RCS Pressure Boundary Degraded 05000250/LER-2021-003, Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown2021-12-0202 December 2021 Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown 05000250/LER-2021-002, Unrecognized Technical Specification Surveillance Requirement Non-Compliance2021-06-0303 June 2021 Unrecognized Technical Specification Surveillance Requirement Non-Compliance 05000250/LER-2021-001, Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction2021-04-29029 April 2021 Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction 05000250/LER-2020-005-01, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1)2021-03-0505 March 2021 Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1) 05000250/LER-2020-002-01, Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1)2021-03-0505 March 2021 Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1) 05000250/LER-2020-005, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel2020-10-14014 October 2020 Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel 05000250/LER-2020-004, Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump2020-10-0707 October 2020 Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump 05000250/LER-2020-003, Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup2020-09-29029 September 2020 Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup 05000250/LER-2020-002, Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve2020-09-23023 September 2020 Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve 05000251/LER-2020-001, Automatic Reactor Trip Caused by Main Generator Lockout Due to Exciter Fault2020-08-28028 August 2020 Automatic Reactor Trip Caused by Main Generator Lockout Due to Exciter Fault 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units2020-06-24024 June 2020 Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units L-2019-127, Manual Reactor Trip Following Grid Disturbance2019-06-27027 June 2019 Manual Reactor Trip Following Grid Disturbance 05000250/LER-2018-002, As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits2018-11-21021 November 2018 As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits 05000250/LER-2018-001, Inoperable Containment Purge Exhaust Penetration2018-11-21021 November 2018 Inoperable Containment Purge Exhaust Penetration 05000251/LER-2018-001, Inoperable Auxiliary Feedwater Steam Supply Flowpath2018-06-27027 June 2018 Inoperable Auxiliary Feedwater Steam Supply Flowpath 05000251/LER-1917-001, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control2017-11-0707 November 2017 Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control 05000250/LER-1917-001, Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function2017-05-16016 May 2017 Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function L-2017-090, LER Special Report Regarding Accident Monitoring Instrumentation2017-05-11011 May 2017 LER Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2016-001, Regarding Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection Instrument Channel2016-06-30030 June 2016 Regarding Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection Instrument Channel 05000250/LER-2016-001, Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed2016-04-0707 April 2016 Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed 05000250/LER-2015-001, Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation2016-01-19019 January 2016 Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation L-2015-217, Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation2015-08-27027 August 2015 Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2015-002, Regarding Reactor Trip Resulting from Generator Differential Lockout2015-07-13013 July 2015 Regarding Reactor Trip Resulting from Generator Differential Lockout 05000251/LER-2015-001, Regarding Automatic Auxiliary Feedwater System Actuation During a Planned Reactor Trip2015-01-29029 January 2015 Regarding Automatic Auxiliary Feedwater System Actuation During a Planned Reactor Trip 05000251/LER-2014-003, Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement2014-11-10010 November 2014 Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement 05000250/LER-2014-004, Regarding Ultimate Heat Sink Temperature Limit Exceeded Due to Environmental Conditions2014-09-18018 September 2014 Regarding Ultimate Heat Sink Temperature Limit Exceeded Due to Environmental Conditions 05000251/LER-2014-001, Regarding Incorrect Feedwater Flow Transmitter Calibration Caused RPS Channels to Be Inoperable2014-06-24024 June 2014 Regarding Incorrect Feedwater Flow Transmitter Calibration Caused RPS Channels to Be Inoperable 05000250/LER-2014-003, Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter2014-06-18018 June 2014 Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter 05000250/LER-2014-002, Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld2014-05-15015 May 2014 Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld L-2014-139, Special Report Regarding Accident Monitoring Instrumentation2014-05-14014 May 2014 Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2014-002, Regarding Automatic Actuation of the Reactor Protection System Due to Low Main Condenser Vacuum2014-04-24024 April 2014 Regarding Automatic Actuation of the Reactor Protection System Due to Low Main Condenser Vacuum 05000250/LER-2014-001, Regarding Missed Surveillance Test Resulted in a SG Pressure Instrument Channel to Be Inoperable Longer than AOT2014-03-0404 March 2014 Regarding Missed Surveillance Test Resulted in a SG Pressure Instrument Channel to Be Inoperable Longer than AOT 05000250/LER-2013-009, Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT2013-11-27027 November 2013 Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT 05000250/LER-2013-008, Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT2013-08-19019 August 2013 Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT 05000250/LER-2013-007, Regarding Manual Reactor Trip Due to Generator Load Drop2013-07-0808 July 2013 Regarding Manual Reactor Trip Due to Generator Load Drop 05000251/LER-2013-002, Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing2013-06-18018 June 2013 Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing 05000251/LER-2013-001, Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads2013-05-22022 May 2013 Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads 05000250/LER-2013-006, Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps2013-05-13013 May 2013 Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps 05000250/LER-2013-005, Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves2013-05-10010 May 2013 Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves 05000250/LER-2013-004, Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position2013-04-29029 April 2013 Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position 05000250/LER-2013-003, Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage2013-04-19019 April 2013 Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage 05000250/LER-2013-002, Regarding Automatic Reactor Trip Due to Low Condenser Vacuum2013-04-11011 April 2013 Regarding Automatic Reactor Trip Due to Low Condenser Vacuum 05000250/LER-2013-001, Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications2013-03-0101 March 2013 Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications 2024-07-10
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