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 Issue dateTitleTopic
LR-N02-0192, Correction of Technical Specification Page Issued with Amendment 24516 May 2002Correction of Technical Specification Page Issued with Amendment 245
LR-N02-0344, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.23 October 2002Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.High Radiation Area
Offsite Dose Calculation Manual
Process Control Program
LR-N03-0014, Request for Change to Technical Specifications Administrative and Editorial Changes29 January 2003Request for Change to Technical Specifications Administrative and Editorial Changes
LR-N03-0018, TS Bases Change24 January 2003TS Bases Change
LR-N03-0022, Revision to Request for Change to Technical Specifications14 February 2003Revision to Request for Change to Technical SpecificationsBoric Acid
Shutdown Margin
LR-N03-0092, Request for Change to TSs Explosive Gas Mixture6 June 2003Request for Change to TSs Explosive Gas MixtureAnticipated operational occurrence
LR-N03-0126, Correction of Bases Pages Issued with Amendments 251 & 23220 March 2003Correction of Bases Pages Issued with Amendments 251 & 232Ultimate heat sink
LR-N04-0021, Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report26 April 2004Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis ReportPacking leak
Probabilistic Risk Assessment
Deep Dose Equivalent
Fuel cladding
Power Uprate
LR-N04-0022, Technical Specification Bases Change S03-09B4 March 2004Technical Specification Bases Change S03-09BSafe Shutdown
Offsite Circuit
LR-N04-0238, Request for Change to Technical Specifications, to Modify Definition of Operable23 July 2004Request for Change to Technical Specifications, to Modify Definition of OperableShutdown Margin
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Pressure Boundary Leakage
Offsite Circuit
LR-N05-0018, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational.23 February 2005Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational.Safe Shutdown
Offsite Dose Calculation Manual
Hydrostatic
Operating Basis Earthquake
Nondestructive Examination
Annual Radioactive Effluent Release Report
Process Control Program
Earthquake
Pressure Boundary Leakage
Fire Protection Program
LR-N05-0319, Technical Specification Bases Change S05-05B Re Radiation Monitoring Channels22 July 2005Technical Specification Bases Change S05-05B Re Radiation Monitoring Channels
LR-N05-0377, Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System11 August 2005Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling SystemHigh Radiation Area
LR-N05-0469, Technical Specification Bases Changes Re Boration Systems, Steam Generator Tube Integrity & Containment Ventilation System27 December 2005Technical Specification Bases Changes Re Boration Systems, Steam Generator Tube Integrity & Containment Ventilation SystemBoric Acid
Shutdown Margin
Nondestructive Examination
Pressure Boundary Leakage
LR-N05-0479, Supplement to Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, and Steam Generator Tube Inspection Report and to Revise Reactor Coolant21 September 2005Supplement to Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, and Steam Generator Tube Inspection Report and to Revise Reactor CoolantSafe Shutdown
Offsite Dose Calculation Manual
Nondestructive Examination
Annual Radioactive Effluent Release Report
Process Control Program
Pressure Boundary Leakage
Fire Protection Program
LR-N06-0055, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requiremen6 April 2006Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage RequirementsSafe Shutdown
Offsite Dose Calculation Manual
Hydrostatic
Nondestructive Examination
Annual Radioactive Effluent Release Report
Process Control Program
Earthquake
Pressure Boundary Leakage
Fire Protection Program
LR-N06-0201, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process7 June 2006Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement ProcessIncorporated by reference
LR-N06-0263, Supplement to License Change Request S05-09; Request for Change to Technical Specifications Refueling Operations and Special Test Exceptions20 July 2006Supplement to License Change Request S05-09; Request for Change to Technical Specifications Refueling Operations and Special Test Exceptions
LR-N07-0030, License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System16 March 2007License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling SystemUltimate heat sink
Stroke time
Coast down
LR-N08-0046, Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-0111 March 2008Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-01Shutdown Margin
Ultimate heat sink
Probabilistic Risk Assessment
Design basis earthquake
LR-N09-0034, License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications9 April 2009License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical SpecificationsUnanalyzed Condition
Shutdown Margin
Probabilistic Risk Assessment
Control of Heavy Loads
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)14 October 2010Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)Safe Shutdown
Unanalyzed Condition
Time of Discovery
High winds
Reactor Vessel Water Level
Packing leak
Ultimate heat sink
Offsite Dose Calculation Manual
Internal Flooding
Met Tower
Operating Basis Earthquake
Earthquake
Turbine Missile
Pressure Boundary Leakage
Recently irradiated fuel
Power change
Operability Assessment
Unidentified leakage
Failure to Scram
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)14 October 2010Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)Safe Shutdown
Unanalyzed Condition
Time of Discovery
High winds
Reactor Vessel Water Level
Packing leak
Ultimate heat sink
Offsite Dose Calculation Manual
Internal Flooding
Met Tower
Operating Basis Earthquake
Earthquake
Turbine Missile
Pressure Boundary Leakage
Recently irradiated fuel
Power change
Operability Assessment
Unidentified leakage
Failure to Scram
LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix14 October 2010Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison MatrixSafe Shutdown
High winds
Reactor Vessel Water Level
Ultimate heat sink
Internal Flooding
Met Tower
Operating Basis Earthquake
Earthquake
LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)14 October 2010Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)Offsite Dose Calculation Manual
LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance14 October 2010Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and MaintenanceMet Tower
LR-N10-0355, Hope Creek, HC.IC-CC.SE-0002(Q), Rev. 23, Nuclear Instrumentation System - Channel B Source Range Monitor C51-K600B3 June 2008Hope Creek, HC.IC-CC.SE-0002(Q), Rev. 23, Nuclear Instrumentation System - Channel B Source Range Monitor C51-K600B
LR-N10-0355, Hope Creek, HC.IC-CC.SE-0003(Q) - Rev. 27, Nuclear Instrumentation System - Channel C Source Range Monitor C51-K600C16 December 2008Hope Creek, HC.IC-CC.SE-0003(Q) - Rev. 27, Nuclear Instrumentation System - Channel C Source Range Monitor C51-K600C
LR-N10-0355, Hope Creek, HC.IC-CC.SE-0004(Q) - Rev. 25, Nuclear Instrumentation System - Channel D Source Range Monitor C51-K600D9 September 2008Hope Creek, HC.IC-CC.SE-0004(Q) - Rev. 25, Nuclear Instrumentation System - Channel D Source Range Monitor C51-K600D
LR-N10-0355, Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup17 March 2010Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup
LR-N10-0355, Hope Creek, HC.OP-AB.BOP-0002(Q), Rev. 13, Main Turbine20 January 2009Hope Creek, HC.OP-AB.BOP-0002(Q), Rev. 13, Main Turbine
LR-N10-0355, Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment3 May 2010Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment
LR-N10-0355, Hope Creek, HC.OP-AB.CONT-0005(Q), Rev. 3, Irradiated Fuel Damage30 July 2008Hope Creek, HC.OP-AB.CONT-0005(Q), Rev. 3, Irradiated Fuel Damage
LR-N10-0355, Hope Creek, HC.OP-AB.COOL-0004(Q), Rev. 4, Fuel Pool Cooling9 September 2009Hope Creek, HC.OP-AB.COOL-0004(Q), Rev. 4, Fuel Pool Cooling
LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment13 July 2010Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room EnvironmentEmergency Lighting
LR-N10-0355, Hope Creek, HC.OP-AB.IC-0003(Q), Rev. 3, Reactor Protection System25 April 2009Hope Creek, HC.OP-AB.IC-0003(Q), Rev. 3, Reactor Protection System
LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature5 March 2010Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of NatureSafe Shutdown
High winds
Fire impairment
Operating Basis Earthquake
Earthquake
LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer21 April 2010Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer
LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations21 April 2010Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power OscillationsMELLLA
Power change
LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling24 June 2010Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling
LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction24 August 2010Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction
LR-N10-0355, Hope Creek, HC.OP-AB.ZZ.0135(Q), Rev. 29, Station Blackout/Loss of Offsite Power/Diesel Generator Malfunction21 August 2008Hope Creek, HC.OP-AB.ZZ.0135(Q), Rev. 29, Station Blackout/Loss of Offsite Power/Diesel Generator Malfunction
LR-N10-0355, Hope Creek, HC.lC-CC.SE-0001(Q), Rev. 28, Nuclear Instrumentation System - Channel a Source Range Monitor C51-K6OOA9 March 2009Hope Creek, HC.lC-CC.SE-0001(Q), Rev. 28, Nuclear Instrumentation System - Channel a Source Range Monitor C51-K6OOA
LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 2516 April 2010Hope Creek, Offsite Dose Calculation Manual, Revision 25Offsite Dose Calculation Manual
LR-N11-0056, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program23 February 2011Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation27 March 2015License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System InstrumentationSafe Shutdown Earthquake
Operating Basis Earthquake
Surveillance Frequency Control Program
Earthquake
LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems3 April 2015License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring SystemsAnticipated operational occurrence
Fuel cladding
LR-N15-0187, Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications31 August 2015Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical SpecificationsPost Accident Monitoring
Surveillance Frequency Control Program
LR-N16-0003, License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications17 November 2016License Amendment Request to Amend the Accident Monitoring Instrumentation Technical SpecificationsProbabilistic Risk Assessment
Surveillance Frequency Control Program
Severe Accident Management Guideline
Fuel cladding
LR-N16-0114, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line .30 August 2016License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line .Shutdown Margin
Offsite Dose Calculation Manual
Incorporated by reference
Annual Radioactive Effluent Release Report
Surveillance Frequency Control Program
Process Control Program
Pressure Boundary Leakage
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