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Issue date | Title | Topic | |
---|---|---|---|
ML23103A323 | 13 April 2023 | Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 | Safe Shutdown Non-Destructive Examination Commercial Grade Dedication Aging Management Surveillance Frequency Control Program Open Phase Condition Open Phase Initiative |
LR-N23-0027, Updated Final Safety Analysis Report, Rev. 26, | 13 April 2023 | Updated Final Safety Analysis Report, Rev. 26, | |
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 Salem | 10 November 2022 | 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 Salem | Open Phase Condition Open Phase Initiative |
ML22298A054 | 24 October 2022 | Submittal of Updated Final Safety Analysis Report, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results | Aging Management Open Phase Condition Scaffolding |
LR-N22-0086, Unit 2, Updated Final Safety Analysis Report, Revision 33 | 24 October 2022 | Unit 2, Updated Final Safety Analysis Report, Revision 33 | |
LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem | 17 June 2021 | Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem | |
LR-N19-0102, Revision 31 to Updated Final Safety Analysis Report, Chapter 4, Reactor | 5 December 2019 | Revision 31 to Updated Final Safety Analysis Report, Chapter 4, Reactor | Boric Acid Shutdown Margin Safe Shutdown Earthquake Hydrostatic Design basis earthquake Earthquake Fuel cladding Power change Flow Induced Vibration |
LR-N18-0053, Revision 30 to Updated Final Safety Analysis Report, Appendix a, TMI Lessons Learned | 11 May 2018 | Revision 30 to Updated Final Safety Analysis Report, Appendix a, TMI Lessons Learned | Boric Acid Reactor Vessel Water Level Loop seal Grab sample |
ML17157B265 | 9 May 2017 | Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor | Safe Shutdown FLEX Aging Management Fire Protection Program GOTHIC |
LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re | 9 May 2017 | Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Repor | Safe Shutdown FLEX Aging Management Fire Protection Program GOTHIC |
ML17046A463 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 9.3, Process Auxiliaries | Safe Shutdown Boric Acid Loop seal High Radiation Area Grab sample Hydrostatic Power change |
ML17046A346 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.5-1 to 4.5-4 | |
ML17046A280 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 3.3, Wind and Tornado Loadings | Operating Basis Earthquake Design basis earthquake |
ML17046A590 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Tables A-1 to A-5 | Boric Acid |
ML17046A433 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 7.9, Physical Separation and Electrical Isolation | |
ML17046A498 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 11.3, Gaseous Waste System | Boric Acid Grab sample Offsite Dose Calculation Manual |
ML17046A462 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figures 9.2-1A Through 9.2-11 | |
ML17046A255 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 2.3, Figure 2.3-1, Sources of Meteorological Records | |
ML17046A277 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 3, Table of Contents | Tornado Missile Operating Basis Earthquake Design basis earthquake Earthquake Turbine Missile |
ML17046A410 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 7, Table of Contents | Code Reconciliation |
ML17046A483 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 10.2, Turbine Generator | Turbine Missile Liquid penetrant |
ML17046A501 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 11.4, Radiological Monitoring | Boric Acid Grab sample Fuel cladding |
ML17046A416 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Tables 7.3-1 Through 7.3-9 | |
ML17046A529 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 12.4, ALARA Program | |
ML17046A589 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned | Boric Acid Reactor Vessel Water Level Loop seal Grab sample Anticipated operational occurrence Unidentified leakage |
ML17046A285 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 3.5, Missile Protection | Safe Shutdown Boric Acid Tornado Missile Finite Element Analysis Tornado Generated Missile Earthquake Turbine Missile |
ML17046A460 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 9.2, Water Systems | Boric Acid Tornado Generated Missile |
ML17046A473 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 10, Steam and Power Conversion System - Summary Description | |
ML17139C044 | 30 January 2017 | Redacted Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 5.5-1 Through 5.5-7 | |
ML17046A558 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 14.5, Test Program Organization, Unit 1 | |
ML17046A466 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 9.4, Heating, Ventilation, and Air Conditioning Systems | Offsite Dose Calculation Manual Fuel cladding |
ML17046A556 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 14.4, Initial Testing of the Operating Reactor | |
ML17046A531 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 13, Table of Contents | |
ML17046A572 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figure 15.3-1 Through 15.3-68 | |
ML17046A347 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | Reactor Vessel Water Level Hydrostatic Pressure Boundary Leakage |
ML17046A559 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 14.5, Figure 14.5-1 Through Figure 14.5-2 | |
ML17046A552 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 14.2, Table 14.2-1, Tests Performed Prior to Initial Reactor Fueling | Boric Acid Hydrostatic |
ML17046A414 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figures 7.2-1 Through 7.2-7 | |
ML17046A524 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 12, Radiation Protection | High Radiation Area Anticipated operational occurrence Post Accident Monitoring Locked High Radiation Area |
ML17046A540 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 13.4, Review and Audit | |
ML17046A399 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 6, Table of Contents | Coatings |
ML17046A568 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figure 15.2-1 Through 15.2-46 | Fuel cladding |
ML17046A591 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figures A-1 to A-6, Intentionally Deleted | |
ML17046A232 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Master Table of Contents | Safe Shutdown |
ML17046A469 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figures 9.4-1A Through 9.4-6B | |
ML17046A350 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.1-1 to 5.1-13 | |
ML17046A415 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 7.3, Engineered Safety Features Instrumentation | Safe Shutdown Reactor Vessel Water Level Post Accident Monitoring |
ML17046A496 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Tables 11.2-1, Liquid Waste System Performance Data to 11.2-9 | Tritium |
ML17046A582 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Section 17.1, Quality Assurance During the Design and Construction Phases | |
ML17046A424 | 30 January 2017 | Revision 29 to Updated Final Safety Analysis Report, Figure 7.6-1 |