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SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

ANSI 5.1 +  and ANSI B31.1 +

Boron +, Iodine +, Nitrogen +, Oxygen +, Hydrogen +  and Lead +

10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +  and 10 CFR 51.21 +

JPTS-91-025 +, JPN-92-089 +, JPN-96-045, Forwards Correct Response to RAI Re Power Uprate Submittal. Supersedes & Replaces to NRC +  and JPN 046 +

05000333  +  and 00333  +

Turbine Trip +  and Reactor Trip +

SIL 377 +  and SIL 480 +

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

ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +, ML20132C369 +  and ML20132C369 +

4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

JPN-92-089 +, JPN-96-045, Forwards Correct Response to RAI Re Power Uprate Submittal. Supersedes & Replaces to NRC +  and JPN 046 +

NEDC-31317P +, JPN-96-040, Forwards Relief Request V61 for Second Ten Yr Interval IST Program +, JAFP-96-0470, Forwards Revised Response to RAI Re Porous Concrete sub-foundation +, JPN-96-043, Forwards Response to RAI Re Power Uprate Submittal +, JAFP-92-0570, Special Rept:On 920703,CO-2 Fire Door Required to Close on CO-2 Sys Activation Did Not Fully Close When Released.Fire Door Repaired & Tested Satisfactorily +  and JAFP-91-0651, Monthly Operating Rept for Sept 1991 for Ja Fitzpatrick Nuclear Power Plant +

NUREG-1262, Discusses Review of Plant Simulation Facility Development Plan,Submitted on 880526.Overall Approach of Plan Acceptable Due to Reliance on Util Simulation Facility Group Baseline Document.Issues Requiring Resolution Stated +, 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 +

ML20132C369 +  and ML20132C369 +

Regulatory Guide 1.3 +, Regulatory Guide 1.52 +, Regulatory Guide 1.49 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.139 +

NEDC-31317P +, NEDC-31336 +, NEDC-31336P +, NEDO-32205 +, NEDE-24011 +, NEDC-31897P +, NEDE-24222 +, NEDO-30832 +, NEDC-31984P +, NEDE-2422 +, NEDC-31897 +, NEDC-31697P +, NEDC-32016P +, NEDC-24361P +, NEDC-32018P +, NEDC-31397P +  and NEDC-2435P +

70M0V-108 +  and 70DNPR-105 +

Washington +  and New York +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Stator Cooling Water +, Residual Heat Removal Service Water +, Reactor Building Closed Loop Cooling +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +...

TS-3.1.A +, TS-4.5.C +, TS-4.6.E +, TS-2.2.1.B +, TS-4.7.D +, TS-2.1.A +, TS-4.11.A +  and TS-4.5.E +

Safe Shutdown +, Safety Limit Minimum Critical Power Ratio +, Ultimate heat sink +, Tornado Missile +, Hydrostatic +, Temporary Modification +, High Energy Line Break +, Abnormal operational transient +, Flow Accelerated Corrosion +, Feedwater Controller Failure +, Main Steam Line Radiation Monitor +, Turbine Missile +, Fuel cladding +, Power change +, Power Uprate +, Overspeed +, Simmer margin +  and Control Room Habitability +

Cooling Tower +  and Lake Ontario +