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 Issue dateTitleTopic
ML23335A11215 December 2023Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers
ML21179A23525 June 2021PSEG Salem Generating Station - Incidental Take Report Atlantic Sturgeon 6/24/2021
ML21078A00025 March 2021Review of the Spring 2020 Steam Generator Tube Inspection Report
LR-N21-0007, Report of Changes, Tests, and Experiments28 January 2021Report of Changes, Tests, and Experiments
LR-N19-0010, U.S. Additional Protocol for Salem Unit 1 2018 Report31 January 2019U.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 Conditions25 July 2018Report 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 ConditionsHigh 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 Flooding30 June 2017Focused Evaluation of External FloodingSafe Shutdown
Ultimate heat sink
Fire Barrier
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
LR-N17-0051, Annual Report of Specific Activity Analysis - TS 6.9.1.5c16 February 2017Annual 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 6.9.1.19 February 2017Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1Shutdown Margin
LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 207 February 2017License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20Aging Management
LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal30 December 2016Flood Hazards Mitigating Strategies Assessment (MSA) Report SubmittalHigh winds
Ultimate heat sink
Hydrostatic
FLEX
Fukushima Dai-Ichi
LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal29 December 2016Flood Hazards Mitigating Strategies Assessment (MSA) Report SubmittalHigh 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 2016NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.
ML16256A64112 September 2016NUREG-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 Assessment31 August 2016Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment
ML16256A64031 August 2016Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment
LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.18 July 2016ISG-06 Enclosure B Roadmap, Phase 2 Documents.
ML16256A64318 July 2016ISG-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 2016GNF-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
ML16049A60929 February 2016Staff 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 ClosureSafe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
LR-N16-0026, Annual Report of Specific Activity Analysis - TS 6.9.1.5c26 February 2016Annual Report of Specific Activity Analysis - TS 6.9.1.5c
LR-N15-0218, Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report21 October 2015Revised Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual ReportLoop seal
LR-N15-0207, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report7 October 2015Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual ReportLoop seal
ML15119A16117 April 2015Report 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 Days24 December 2014Special 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 2014Response 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 71-923311 August 2014CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233
ML14113A22130 April 2014NRC 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 DesignBoric 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 Station25 April 2014CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station
ML14316A40931 March 2014Well AA-V Installation Report - Table 5 Well Search Summary
ML14316A40831 March 2014Well AA-V Installation Report - Table 4 Mean Hydraulic Grad Study Results
ML14316A40731 March 2014Well AA-V Installation Report - Table 2 Groundwater Sample Analytical Results Vincentown Wells
ML14316A40631 March 2014Well AA-V Installation Report - Table 1 Well Construction Details
ML14316A40331 March 2014Well AA-V Installation Report - Table 3 Well AA-V Extended Purge Salem Chemistry Screening Results
ML14316A40231 March 2014Well AA-V Installation Report - FIG-06 Potable Well Locations in Lower Alloways Creek Elsinboro and Greenwich Townships
ML14316A40131 March 2014Well AA-V Installation Report - FIG-05 Vincentown Formation Mean Hydraulic Fluctuation Study Results Map - August 2013-5
ML14316A40031 March 2014Well AA-V Installation Report - FIG-02 Regional Cross SECTION-2
ML14316A39831 March 2014Well AA-V Installation Report - FIG-04 Monitoring Wells Screened within the Vincentown FORMATION-4
ML14316A39731 March 2014Well AA-V Installation Report - FIG-03 Facility Cross Section Through AA-V-3
ML14316A37931 March 2014Well AA-V Installation Report - Appendix a - Monitoring Well Certification Form B
ML14316A36931 March 2014Final Well AA-V Installation Report 031214
ML14316A33431 March 2014Well AA-V Installation Report - Appendix F - Well Search Results
ML14316A33331 March 2014Well AA-V Installation Report - Appendix E - Summary, Charts and Raw Data
ML14316A33131 March 2014Well AA-V Installation Report - Appendix D Specific Capacity Test for Well AA-V
ML14316A32931 March 2014Well AA-V Installation Report - Appendix C - AA-V Construction and Boring Logs
ML14316A32831 March 2014Well 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 2014PSEG 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
ML13266A29718 November 2013Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant AccidentUnanalyzed Condition
Hydrostatic
Fukushima Dai-Ichi
Earthquake
LR-N13-0259, Steam Generator Tube Inspection Report - Twenty-Second Refueling Outage (1R22)4 November 2013Steam 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 2013Response 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