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| Issue date | Title | Topic | |
|---|---|---|---|
| ML23335A112 | 15 December 2023 | Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers | |
| ML23249A262 | 6 September 2023 | Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) | |
| 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 Temperature | 7 August 2022 | 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 Temperature | Shutdown 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 Exemption Request Pressure Boundary Leakage |
| ML21179A235 | 25 June 2021 | PSEG Salem Generating Station - Incidental Take Report Atlantic Sturgeon 6/24/2021 | |
| ML21078A000 | 25 March 2021 | Review of the Spring 2020 Steam Generator Tube Inspection Report | |
| LR-N21-0004, U.S Additional Protocol for Salem, Unit 1 | 31 January 2021 | U.S Additional Protocol for Salem, Unit 1 | |
| LR-N21-0007, Report of Changes, Tests, and Experiments | 28 January 2021 | Report of Changes, Tests, and Experiments | |
| LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report | 6 December 2020 | License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report | Anticipated operational occurrence Hydrostatic Incorporated by reference Pressure and Temperature Limits Report B.5.b Mitigating Strategies Exemption Request Pressure Boundary Leakage |
| ML20274A076 | 25 September 2020 | PSEG to NRC, Biological and Engineering Evaluation of Alternatives in Connection with Reinitation of Endangered Species Act Section 7 Consultation | NJPDES Biofouling Weak link |
| LR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology | 24 April 2020 | License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology | Grab sample Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Surveillance Frequency Control Program Fuel cladding Liquid penetrant Pressure Boundary Leakage Pressure boundary leak Through-Wall Leak |
| ML20121A133 | 3 March 2020 | Biological Opinion 2019 Annual Incidental Take Report | |
| LR-N19-0103, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2019 | 26 November 2019 | Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2019 | Loop seal |
| LR-N19-0010, U.S. Additional Protocol for Salem Unit 1 2018 Report | 31 January 2019 | U.S. Additional Protocol for Salem Unit 1 2018 Report | |
| ML19029B017 | 29 January 2019 | Containment Building, Salem Nuclear Generating Station, Structural Analysis & Design | |
| LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | 25 July 2018 | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | High winds High Radiation Area Stroke time FLEX Tornado Missile Protection Design basis earthquake Foreign Material Exclusion Severe Accident Management Guideline Containment Hardened Vent Battery sizing Hardened vent |
| LR-N18-0057, Pressure and Temperature Limits Report, Revision 1 | 8 June 2018 | Pressure and Temperature Limits Report, Revision 1 | Pressure and Temperature Limits Report |
| ML18337A326 | 30 January 2018 | Sturgeon Incidental Take Report and Data Collection Form for April 11, 2018 (1 of 2) | |
| ML18337A325 | 30 January 2018 | Sturgeon Incidental Take Report and Data Collection Form for March 28, 2018 | |
| ML18337A324 | 30 January 2018 | Sturgeon Incidental Take Report and Data Collection Form for February 6, 2018 | |
| LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary | 9 November 2017 | License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary | Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding |
| LR-N17-0076, Focused Evaluation of External Flooding | 30 June 2017 | Focused Evaluation of External Flooding | Safe Shutdown Ultimate heat sink Fire Barrier FLEX Fukushima Dai-Ichi Flooding Focused Evaluation |
| LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report | 28 April 2017 | Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report | Pressure and Temperature Limits Report |
| ML17188A267 | 31 March 2017 | Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) | |
| LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) | 31 March 2017 | Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) | |
| LR-N17-0051, Annual Report of Specific Activity Analysis - TS 6.9.1.5c | 16 February 2017 | Annual Report of Specific Activity Analysis - TS 6.9.1.5c | |
| LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 | 9 February 2017 | Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 | Shutdown Margin |
| LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 | 7 February 2017 | License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 | Aging Management |
| ML17188A265 | 31 December 2016 | Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi | |
| LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve | 31 December 2016 | Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi | |
| LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | 30 December 2016 | Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | High winds Ultimate heat sink Hydrostatic FLEX Fukushima Dai-Ichi |
| LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | 29 December 2016 | Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal | High winds Ultimate heat sink Hydrostatic FLEX Fukushima Dai-Ichi |
| ML16256A641 | 12 September 2016 | NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | |
| LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | 12 September 2016 | NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. | |
| ML16256A640 | 31 August 2016 | Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | |
| ML16256A642 | 31 August 2016 | NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. | Safe Shutdown Earthquake Operating Basis Earthquake Cyber Security |
| ML16280A523 | 31 August 2016 | Technical Evaluation Report Salem Generating Station Storm Surge Hazard Reevaluation Review | Mission time Hydrostatic Earthquake |
| LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. | 31 August 2016 | NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. | Safe Shutdown Earthquake Operating Basis Earthquake Cyber Security |
| LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | 31 August 2016 | Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | |
| ML16256A643 | 18 July 2016 | ISG-06 Enclosure B Roadmap, Phase 2 Documents. | |
| LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents. | 18 July 2016 | ISG-06 Enclosure B Roadmap, Phase 2 Documents. | |
| LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. | 31 May 2016 | GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. | Minimum Critical Power Ratio Fuel cladding |
| ML16049A609 | 29 February 2016 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Earthquake |
| LR-N16-0026, Annual Report of Specific Activity Analysis - TS 6.9.1.5c | 26 February 2016 | Annual Report of Specific Activity Analysis - TS 6.9.1.5c | |
| LR-N15-0218, Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report | 21 October 2015 | Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report | Loop seal |
| LR-N15-0207, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report | 7 October 2015 | Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report | Loop seal |
| LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. | 30 September 2015 | NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. | |
| LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) | 30 September 2015 | NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) | |
| ML16256A644 | 30 September 2015 | NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. | |
| ML15119A161 | 17 April 2015 | Report of Impingement of Atlantic Sturgeon | |
| LR-N14-0268, Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days | 24 December 2014 | Special Report 272/2014-008, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater than 30 Days |