Category:Letter
MONTHYEARML24351A0952024-12-17017 December 2024 Senior Reactor and Reactor Operator Initial License Examinations LR-N24-0071, Supplement to License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-12-0606 December 2024 Supplement to License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0069, Independent Spent Fuel Storage Installation - Report of 10 CFR 72.48 Changes, Tests and Experiments2024-12-0202 December 2024 Independent Spent Fuel Storage Installation - Report of 10 CFR 72.48 Changes, Tests and Experiments IR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 ML24295A3742024-10-23023 October 2024 Project Manager Assignment ML24291A0572024-10-17017 October 2024 License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle IR 05000272/20244032024-09-25025 September 2024 And Salem Nuclear Generating Station, Units 1 and 2, Cybersecurity Inspection Report 05000354/2024403, 05000272/2024403, and 05000311/2024403 (Cover Letter Only) IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves ML24197A0552024-07-15015 July 2024 Requalification Program Inspection ML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves IR 05000272/20245012024-06-12012 June 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20240112024-04-0101 April 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML24080A3962024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges 05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-02-12012 February 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 – Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 2024-09-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram 05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-02-12012 February 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram 05000354/LER-2023-001-02, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable2023-09-25025 September 2023 Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable 05000354/LER-2023-001-01, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable2023-09-11011 September 2023 Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable 05000354/LER-2023-001, Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable2023-06-20020 June 2023 Technical Specification Required Shutdown Due to Declaring the Suppression Chamber and Primary Containment Inoperable 05000354/LER-1922-002, Inoperable Isolation Actuation Instrumentation Caused by Failure to Remove Electrical Jumper2023-01-18018 January 2023 Inoperable Isolation Actuation Instrumentation Caused by Failure to Remove Electrical Jumper 05000354/LER-2022-001, B EDG Inoperable Resulting in a Condition Prohibited by Technical Specifications2022-03-18018 March 2022 B EDG Inoperable Resulting in a Condition Prohibited by Technical Specifications 05000354/LER-2021-001, Safety Relief Valve (SRV) As-Found Setpoint Failures2021-08-13013 August 2021 Safety Relief Valve (SRV) As-Found Setpoint Failures 05000354/LER-2019-002, Safety Relief Valve (SRV) As-found Set-point Failures2020-01-0606 January 2020 Safety Relief Valve (SRV) As-found Set-point Failures 05000354/LER-2019-001, Manual Scram and Manual Actuation of Reactor Core Isolation Cooling2019-10-0202 October 2019 Manual Scram and Manual Actuation of Reactor Core Isolation Cooling 05000354/LER-2018-004, High Pressure Coolant Injection System Inoperable Due to Failed Fuse2018-11-20020 November 2018 High Pressure Coolant Injection System Inoperable Due to Failed Fuse 05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure2018-10-0303 October 2018 Safety Relief Valve L (SRV) As-Found Setpoint Failure 05000354/LER-2018-003-01, Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit2018-09-12012 September 2018 Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit LR-N18-0065, Safety Relief Valve (SRV) As-Found Setpoint Failure2018-06-18018 June 2018 Safety Relief Valve (SRV) As-Found Setpoint Failure 05000354/LER-2018-001, Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment2018-06-18018 June 2018 Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment 05000354/LER-2018-003, Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit2018-06-18018 June 2018 Feedwater Isolation Valve Leakage Exceeded Technical Specification Limit 05000354/LER-1917-001, Regarding Secondary Containment Door Not Latched in Closed Position2017-07-0707 July 2017 Regarding Secondary Containment Door Not Latched in Closed Position 05000354/LER-2016-006, Regarding Mode Change Without B Channel Level Instrumentation Operable2017-01-0909 January 2017 Regarding Mode Change Without B Channel Level Instrumentation Operable 05000354/LER-2016-005, Regarding Reactor Protection System Actuation While the Reactor Was Shutdown2017-01-0404 January 2017 Regarding Reactor Protection System Actuation While the Reactor Was Shutdown 05000354/LER-2016-004, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment2016-12-20020 December 2016 Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment 05000354/LER-2016-003, Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit2016-12-20020 December 2016 Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit 05000354/LER-2016-002, Regarding High Pressure Coolant Injection System Inoperable2016-10-0505 October 2016 Regarding High Pressure Coolant Injection System Inoperable 05000354/LER-2016-001, Regarding High Pressure Coolant Injection System Found to Be Inoperable During Testing2016-10-0404 October 2016 Regarding High Pressure Coolant Injection System Found to Be Inoperable During Testing 05000354/LER-2015-005, Regarding Reactor Scram Due to Invalid RRCS Actuation2015-11-24024 November 2015 Regarding Reactor Scram Due to Invalid RRCS Actuation 05000354/LER-2015-004, Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit2015-07-30030 July 2015 Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit 05000354/LER-2015-003, Regarding Conditions Prohibited by Technical Specifications Due to Low Pressure ECCS2015-07-0606 July 2015 Regarding Conditions Prohibited by Technical Specifications Due to Low Pressure ECCS 05000354/LER-2015-002, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment2015-06-10010 June 2015 Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment 05000354/LER-2015-001, Regarding Conditions Prohibited by Technical Specifications Due to Core Spray Lnoperabilities2015-05-29029 May 2015 Regarding Conditions Prohibited by Technical Specifications Due to Core Spray Lnoperabilities 05000354/LER-2013-011, Regarding Filtration, Recirculation, and Ventilation System Exceeded Technical Specification Allowed Outage Time2015-03-25025 March 2015 Regarding Filtration, Recirculation, and Ventilation System Exceeded Technical Specification Allowed Outage Time 05000354/LER-2013-010, Regarding Loss of Both Control Room Chillers2014-02-18018 February 2014 Regarding Loss of Both Control Room Chillers 05000354/LER-2013-009, Regarding Automatic Actuation of the Reactor Protection System Due to a Main Turbine Trip2014-01-28028 January 2014 Regarding Automatic Actuation of the Reactor Protection System Due to a Main Turbine Trip 05000354/LER-2013-008, Regarding Automatic Actuation of the Reactor Protection System Due to a Main Turbine Trip2014-01-28028 January 2014 Regarding Automatic Actuation of the Reactor Protection System Due to a Main Turbine Trip 05000354/LER-2013-007, Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit2014-01-16016 January 2014 Regarding As-Found Values for Safety Relief Valve Lift Set Points Exceed Technical Specification Allowable Limit 05000354/LER-2013-006, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable2013-12-24024 December 2013 Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment Operable 05000354/LER-2013-005, Regarding Low-Low Set Safety/Relief Valve Pilot Solenoid Operated Valve Failed As-Found Testing2013-12-17017 December 2013 Regarding Low-Low Set Safety/Relief Valve Pilot Solenoid Operated Valve Failed As-Found Testing 05000354/LER-2013-004, Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment2013-12-10010 December 2013 Regarding Operations with a Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment 05000354/LER-2013-003, Through-wall Flaw Discovered on RHR Shutdown Cooling Return Vent Line2013-08-0808 August 2013 Through-wall Flaw Discovered on RHR Shutdown Cooling Return Vent Line 05000354/LER-2013-002, Regarding Reactor Scram Due to Degrading Condenser Vacuum2013-08-0808 August 2013 Regarding Reactor Scram Due to Degrading Condenser Vacuum 05000354/LER-2013-001, Regarding High Pressure Coolant Injection System Inoperable Due to Control Relay Failure2013-06-0505 June 2013 Regarding High Pressure Coolant Injection System Inoperable Due to Control Relay Failure 05000354/LER-2012-004-01, Regarding As-found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable2012-12-10010 December 2012 Regarding As-found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable 05000354/LER-2012-006, High Pressure Coolant Injection System Inoperable2012-10-31031 October 2012 High Pressure Coolant Injection System Inoperable 05000354/LER-2012-005, Regarding RCIC Bearing Low Oil Pressure Indication on Remote Shutdown Panel Inoperable2012-08-23023 August 2012 Regarding RCIC Bearing Low Oil Pressure Indication on Remote Shutdown Panel Inoperable 05000354/LER-2012-004, As Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable2012-07-0303 July 2012 As Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable 05000354/LER-2012-003, Regarding Operation with the Potential to Drain the Reactor Vessel2012-05-14014 May 2012 Regarding Operation with the Potential to Drain the Reactor Vessel 05000354/LER-2012-002, Regarding High Pressure Coolant Injection System Inoperable2012-05-14014 May 2012 Regarding High Pressure Coolant Injection System Inoperable 05000354/LER-2012-001, Regarding Average Power Range Monitor Flow Unit Summers Out of Tech Spec Tolerance2012-05-0303 May 2012 Regarding Average Power Range Monitor Flow Unit Summers Out of Tech Spec Tolerance LR-N12-0114, Retraction of Licensee Event Report 2011-0012012-04-13013 April 2012 Retraction of Licensee Event Report 2011-001 LR-N05-0143, Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration2005-03-31031 March 2005 Special Report 05-001-01 Regarding the Cause of Failure and Channel Restoration 2024-09-05
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