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Issue date | Title | Topic | |
---|---|---|---|
ML23335A112 | 15 December 2023 | Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers | |
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-N21-0007, Report of Changes, Tests, and Experiments | 28 January 2021 | Report of Changes, Tests, and Experiments | |
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 | |
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-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-N17-0051, 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 |
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 |
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. | |
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, 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 | |
ML16256A640 | 31 August 2016 | Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment | |
LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents. | 18 July 2016 | ISG-06 Enclosure B Roadmap, Phase 2 Documents. | |
ML16256A643 | 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 |
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 | |
LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. | 9 December 2014 | Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. | Safe Shutdown High winds High Radiation Area Ultimate heat sink FLEX Fukushima Dai-Ichi Severe Accident Management Guideline |
LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 | 11 August 2014 | CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 | |
ML14113A221 | 30 April 2014 | NRC Staff Review of the Documentation Provided by PSEG Nuclear LLC for the Salem Generating Station Units 1 and 2 Concerning Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design | Boric Acid Mission time Grab sample Coatings Foreign Material Exclusion Scaffolding |
LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station | 25 April 2014 | CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station | |
ML14316A409 | 31 March 2014 | Well AA-V Installation Report - Table 5 Well Search Summary | |
ML14316A408 | 31 March 2014 | Well AA-V Installation Report - Table 4 Mean Hydraulic Grad Study Results | |
ML14316A407 | 31 March 2014 | Well AA-V Installation Report - Table 2 Groundwater Sample Analytical Results Vincentown Wells | |
ML14316A406 | 31 March 2014 | Well AA-V Installation Report - Table 1 Well Construction Details | |
ML14316A403 | 31 March 2014 | Well AA-V Installation Report - Table 3 Well AA-V Extended Purge Salem Chemistry Screening Results | |
ML14316A402 | 31 March 2014 | Well AA-V Installation Report - FIG-06 Potable Well Locations in Lower Alloways Creek Elsinboro and Greenwich Townships | |
ML14316A401 | 31 March 2014 | Well AA-V Installation Report - FIG-05 Vincentown Formation Mean Hydraulic Fluctuation Study Results Map - August 2013-5 | |
ML14316A400 | 31 March 2014 | Well AA-V Installation Report - FIG-02 Regional Cross SECTION-2 | |
ML14316A398 | 31 March 2014 | Well AA-V Installation Report - FIG-04 Monitoring Wells Screened within the Vincentown FORMATION-4 | |
ML14316A397 | 31 March 2014 | Well AA-V Installation Report - FIG-03 Facility Cross Section Through AA-V-3 | |
ML14316A379 | 31 March 2014 | Well AA-V Installation Report - Appendix a - Monitoring Well Certification Form B | |
ML14316A369 | 31 March 2014 | Final Well AA-V Installation Report 031214 | |
ML14316A334 | 31 March 2014 | Well AA-V Installation Report - Appendix F - Well Search Results | |
ML14316A333 | 31 March 2014 | Well AA-V Installation Report - Appendix E - Summary, Charts and Raw Data | |
ML14316A331 | 31 March 2014 | Well AA-V Installation Report - Appendix D Specific Capacity Test for Well AA-V | |
ML14316A329 | 31 March 2014 | Well AA-V Installation Report - Appendix C - AA-V Construction and Boring Logs | |
ML14316A328 | 31 March 2014 | Well AA-V Installation Report - Appendix B - Cb Abandonment Report | |
LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... | 28 March 2014 | PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... | Safe Shutdown High winds Safe Shutdown Earthquake Hydrostatic Probabilistic Risk Assessment Operating Basis Earthquake Fukushima Dai-Ichi Design basis earthquake Earthquake Seismic Walkdown Report |
ML13266A297 | 18 November 2013 | Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident | Unanalyzed Condition Hydrostatic Fukushima Dai-Ichi Earthquake |
LR-N13-0259, Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22) | 4 November 2013 | Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22) | Nondestructive Examination |
LR-N13-0083, Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, ... | 26 April 2013 | Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, ... | Safe Shutdown High Radiation Area FLEX Fukushima Dai-Ichi Severe Accident Management Guideline |