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TECHNICAL SPECIFICATIONS  and TECHNICAL SPECIFICATIONS & TEST REPORTS

ASME Section XI +  and ASME Section III +

Iodine +, Oxygen +, Chloride +  and Lead +

10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.50 +, 10 CFR 50.92 +  and 10 CFR 50.54 Appendix J +

JPN-89-084, Forwards Application for Amend to License DPR-59,revising Tech Specs to Permit Continued Plant Operation W/Two Safety Relief Valves out-of-svc & to Change Setpoints for All Eleven Safety Relief Valves to Single Nominal Setpoint +, JPTS-91-025 +, JPTS 91-025 +, JPN 92-028 +, JPN-92 028 +, JPN 92 028 +, JPTS 91025 +, JPN-926 +, JPN 92028 +, JPTS-89017 +, JPN 926 +  and JPN-92-028, Forwards Application for Amend to License DPR-59,increasing Authorized Max Power Level by Approx 4.1% to 2536 Mwt from Current Limit of 2436 Mwt.Proprietary TRs NEDC-32016P & NEDC-31317P-1,encl.Without Proprietary TRs +

05000333  +, 00333  +  and 00205  +

ML20154D252 +, ML20154D252 +, ML20154D252 +, ML20154D252 +, ML20154D252 +, ML20154D252 +, ML20154D252 +, ML20154D252 +, ML20154D252 +  and ML20154D252 +

JPN-89-084, Forwards Application for Amend to License DPR-59,revising Tech Specs to Permit Continued Plant Operation W/Two Safety Relief Valves out-of-svc & to Change Setpoints for All Eleven Safety Relief Valves to Single Nominal Setpoint +, JPN 92-028 +, JPN-92 028 +, JPN 92 028 +, JPN-926 +, JPN 92028 +, JPN 926 +  and JPN-92-028, Forwards Application for Amend to License DPR-59,increasing Authorized Max Power Level by Approx 4.1% to 2536 Mwt from Current Limit of 2436 Mwt.Proprietary TRs NEDC-32016P & NEDC-31317P-1,encl.Without Proprietary TRs +

JPTS-91-025 +, JPTS 91-025 +, JPTS 91025 +  and JPTS-89017 +

NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  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 +

ES +, CH +  and RT +

NEDC-31317P +, NEDE-24011 +, NEDC-31897P +, NEDO-30832 +, NEDO-21082 +, NEDC-31984P +, NEDO-24281 +, NEDO-21662 +, NEDC-32016P +, NEDC-24361P +, NEDO-21882 +, NEDC-reference +, NEDC-31607P +  and NEDC-24381P +

Crane +  and FitzPatrick +

New York +  and California +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, Hydrostatic +, Abnormal operational transient +, Scram Discharge Volume +, Stress corrosion cracking +, Fast acting solenoid valve +, Fuel cladding +, Fire Protection Program +, Power Uprate +, Affidavit +  and Simmer margin +