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 Issue dateTitleTopic
LR-N24-0044, Relief Request VR-046 August 2024Relief Request VR-04
LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding24 July 2024Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod CladdingAnticipated operational occurrence
Exemption Request
Fuel cladding
LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves28 June 2024License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves
LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response22 May 2024Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator ResponseMet Tower
FLEX
B.5.b
Severe Accident Management Guideline
Earthquake
Fuel cladding
Siren
LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle20 May 2024License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel CycleSafe Shutdown
Reactor Vessel Water Level
Packing leak
Water Inventory Control
Probabilistic Risk Assessment
Squib
Missed surveillance
Corrosion bonding
Surveillance Frequency Control Program
Scram Discharge Volume
Excess Flow Check Valve
Safeguards Contingency Plan
Maintenance Rule Program
Grace period
Overspeed trip
LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage6 May 2024Steam Generator Tube Inspection Report - Twenty-ninth Refueling OutageNon-Destructive Examination
Nondestructive Examination
Operational leakage
LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)30 April 20242023 Annual Radioactive Effluent Release Report (ARERR)Annual Radioactive Effluent Release Report
LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)30 April 20242023 Annual Radiological Environmental Operating Report (AREOR)Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary26 April 2024Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days7 December 2023Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days
LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion29 November 2023Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow ConversionLoop seal
LR-N23-0072, Core Operating Limits Report Cycle 301 November 2023Core Operating Limits Report Cycle 30
LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2 October 2023Submittal of 2023 Annual 10 CFR 50.46 Report
LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement8 September 2023and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement
LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days3 August 2023Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days
LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.131 July 2023Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1
LR-N23-0054, In-Service Inspection Activities26 July 2023In-Service Inspection Activities
LR-N23-0042, Spent Fuel Cask Registration12 July 2023Spent Fuel Cask Registration
LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 202310 July 2023Emergency Plan Document Revisions Implemented June 28, 2023Deep Dose Equivalent
Power change
LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies23 June 2023License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesHot Short
Safe Shutdown
Boric Acid
High winds
Weld Overlay
Internal Flooding
Probabilistic Risk Assessment
Coatings
Emergency Lighting
Incorporated by reference
FLEX
Aging Management
Test box
Thermoset
Local Leak Rate Testing
Foreign Material Exclusion
Large early release frequency
Integrated leak rate test
Moisture barrier
License Renewal
Fuel cladding
Power Uprate
LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)27 April 20232022 Annual Radioactive Effluent Release Report (ARERR)Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station27 April 20232022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating StationOffsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Annual Radiological Effluent Release Report
Tritium
LR-N23-0033, Core Operating Limits Report Cycle 2726 April 2023Core Operating Limits Report Cycle 27
LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location21 April 2023License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower LocationOffsite Dose Calculation Manual
LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains18 April 2023License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) TrainsUltimate heat sink
Anticipated operational occurrence
GOTHIC
Manual Operator Action
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes29 March 2023Submittal of Hope Creek Generating Station Technical Specification Bases ChangesSafe Shutdown
Shutdown Margin
Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
High Radiation Area
Fire Barrier
Anticipated operational occurrence
Tornado Missile
Water Inventory Control
Internal Flooding
Hydrostatic
High Energy Line Break
Missed surveillance
Abnormal operational transient
Surveillance Frequency Control Program
Scram Discharge Volume
Feedwater Controller Failure
Excess Flow Check Valve
Fast acting solenoid valve
Spiral reload
Overtravel
Control of Heavy Loads
Power Operated Valves
Turbine Missile
Fuel cladding
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
Scaffolding
Power change
Unidentified leakage
Failure to Scram
Operational leakage
Water hammer
LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations24 March 2023Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage InstallationsDecommissioning Funding Plan
Authorized possession limits
LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums21 March 2023and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums
LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments28 February 2023and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and ExperimentsTemporary Modification
LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges27 February 2023Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges
LR-N23-0012, Annual Property Insurance Status Report24 February 2023Annual Property Insurance Status Report
LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.71723 February 2023Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717Fitness for Duty
LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2111 February 2023Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211Nondestructive Examination
VT-2
Incorporated by reference
Aging Management
Thermal fatigue
LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage19 January 2023In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage
LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination5 January 2023and Salem Generating Station, Units 1 and 2 - Request for Threshold DeterminationOffsite Dose Calculation Manual
LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 202220 December 2022Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022Loop seal
LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 202214 December 2022Emergency Plan Document Revisions Implemented November 21, 2022Fire Watch
Siren
LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG9 December 2022Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDGProbabilistic Risk Assessment
FLEX
LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2 December 2022Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments
LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)17 November 2022Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)Probabilistic Risk Assessment
Fukushima Dai-Ichi
Large early release frequency
LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem10 November 2022Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for SalemOpen Phase Condition
Open Phase Initiative
LR-N22-0075, 2022 Annual 10 CFR 50.46 Report30 September 20222022 Annual 10 CFR 50.46 Report
LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations27 September 2022Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited ExaminationsVT-2
Intergranular Stress Corrosion Cracking
Large early release frequency
Liquid penetrant
Pressure Boundary Leakage
Unidentified leakage
Operational leakage
Thermal fatigue
LR-N22-0074, Emergency Plan Evacuation Time Estimate15 September 2022Emergency Plan Evacuation Time EstimatePandemic
Coronavirus
LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)31 August 2022License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)Safe Shutdown
Surveillance Frequency Control Program
LR-N22-0063, Spent Fuel Cask Registration10 August 2022Spent Fuel Cask Registration
LR-N22-0068, In-Service Inspection Activities - 90-Day Report10 August 2022In-Service Inspection Activities - 90-Day Report
LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature7 August 2022License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and TemperatureShutdown Margin
High Radiation Area
Offsite Dose Calculation Manual
Anticipated operational occurrence
Hydrostatic
Incorporated by reference
Pressure and Temperature Limits Report
Surveillance Frequency Control Program
Process Control Program
License Renewal
Exemption Request
Pressure Boundary Leakage
Unidentified leakage
Power Uprate
Measurement Uncertainty Recapture
Affidavit
Water hammer
LR-N22-0062, Spent Fuel Cask Registration21 July 2022Spent Fuel Cask Registration
LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days29 June 2022License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days