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Technical Specification, Bases Change  and Letter type:LR

Boron +, Iodine +, Nickel +, Copper +, Nitrogen +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Lead +, Sulfur +  and Plutonium +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 20 Appendix B +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50.54#f +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c2 +, 10 CFR 50.36#d2ii +, 10 CFR 50.65#a4 +  and 10 CFR 70.39#c +

05000354  +  and 00354  +

ML083040052 +  and ML113640138 +

Reactor Trip +  and Turbine Trip +

PSEG +  and Montgomery R +

GDC 54 +, GDC 60 +, GDC 17, Electric power systems +  and GDC 19, Control room +

NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +

LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +, LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +  and LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes +

4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 0.00926 d (0.222 hours, 0.00132 weeks, 3.044e-4 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 0.00579 d (0.139 hours, 8.267196e-4 weeks, 1.9025e-4 months)  +

IEEE 279 +, IEEE 603 +  and IEEE-450 +

General Electric +  and Target Rock +

Information Notice 86-74 +, Information Notice 94-52 +  and Information Notice 84-81 +

NUMARC 93-01 +  and NUMARC 91-06 +

NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.45 +, Regulatory Guide 1.108 +, Regulatory Guide 1.93 +, Regulatory Guide 1.160 +, Regulatory Guide 1.182 +, Regulatory Guide 1.106 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.129 +

NEDO-31466 +, NEDC-32410P +, NEDO-21888 +, NEDC-33075P +, NEDC-30851P +, NEDO-24154 +, NEDO-10349 +, NEDC-30936P +, NEDO-24222 +, NEDC-33864P +, NEDC-31677P +, NEDO-32291 +, NEDC-33153P +  and NEDC-33928P +

SR-4.8.1.1.2 +, SR-4.0.1 +, SR-4.0.3 +, SR-4.0.2 +, SR-4.0.4 +, SR-4.8.1.2 +, SR-4.5.2.2 +, SR-4.5.2.4 +, SR-4.5.2.5 +, SR-4.5.2.1 +, SR-4.5.2.6 +, SR-4.5.2.7 +, SR-4.5.2.8 +, SR-4.1.3.2 +, SR-4.1.3.3 +, SR-4.1.3.5 +, SR-4.6.5.1.a +, SR-4.6.1.1.b +, SR-4.1.3.3.d +, SR-4.1.3.3.c +, SR-4.3.12 +, SR-4.3.10.a +, SR-4.3.10.b +, SR-4.3.10.c +, SR-4.3.10.d +  and SR-4.7.2.1.2 +

Manual Scram +  and Automatic Scram +

Washington +  and New Jersey +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Control Room Emergency Filtration System +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Rod Worth Minimizer +, Control rod blade +...

TS-3.6.4.1 +, TS-3.0.3 +, TS-3.8.1 +, TS-3.6.1.1 +, TS-3.0.1 +, TS-3.5.2 +, TS-3.0.4 +, TS-3.8.2 +, TS-3.8.1.1 +, TS-3.3.2 +, TS-3.1.3.1 +, TS-3.1.3.3 +, TS-3.3.1 +, TS-3.1.5 +, TS-3.1.4 +, TS-3.3.6 +, TS-3.0.4.a +, TS-3.0.4.b +, TS-3.0.2 +, TS-3.0.5 +, TS-3.3.12 +, TS-3.1.3.5 +, TS-3.0.9 +, TS-4.0.2 +, TS-3.0.4.c +, TS-6.12 +, TS-4.0.1 +, TS-3.0.8.a +, TS-3.0.8.b +, TS-6.15.d +...

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, High Radiation Area +, Fire Barrier +, Anticipated operational occurrence +, Tornado Missile +, Water Inventory Control +, Internal Flooding +, Hydrostatic +, High Energy Line Break +, Missed surveillance +, Abnormal operational transient +, Surveillance Frequency Control Program +, Scram Discharge Volume +, Feedwater Controller Failure +, Loss of Offsite Power +, Excess Flow Check Valve +, Fast acting solenoid valve +, Spiral reload +, Overtravel +, Control of Heavy Loads +, Power Operated Valves +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Recently irradiated fuel +, Offsite Circuit +, Scaffolding +...

Turbine bypass valve +  and Main Turbine Control Valve +