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TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT

ASME Section I +  and ASME Section XI +

Iodine +, Krypton +, Carbon +, Xenon +, Lead +, Helium +, Aluminum +, Silicon +, Mercury +, Zinc +, Hafnium +  and Plutonium +

10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 50.59 +, 10 CFR 50.65 +, 10 CFR 50.120 +, 10 CFR 50.59#b2 +  and 10 CFR 50.71#e +

9-5 +, 9-32 +, 9-14 +, 9-16 +, 9-9 +  and 9-28 +

05000259  +, 05000260  +, 05000296  +, 00259  +, 00260  +  and 00296  +

Turbine Trip +  and Reactor Trip +

NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML18039A258 +, ML18039A258 +, ML18039A258 +, ML18039A258 +, ML18039A258 +, ML18039A258 +, ML18039A258 +, ML18039A258 +, ML18039A258 +  and ML18039A258 +

0.021 d (0.505 hours, 0.003 weeks, 6.913685e-4 months)  +, 0.0247 d (0.593 hours, 0.00353 weeks, 8.116065e-4 months)  +, 0.0208 d (0.5 hours, 0.00298 weeks, 6.849e-4 months)  +, 0.0133 d (0.318 hours, 0.00189 weeks, 4.356725e-4 months)  +, 0.0175 d (0.419 hours, 0.00249 weeks, 5.73794e-4 months)  +, 0.0053 d (0.127 hours, 7.572751e-4 weeks, 1.74269e-4 months)  +  and 0.0116 d (0.278 hours, 0.00166 weeks, 3.808805e-4 months)  +

Tritium +, Co-60 +  and N-16 +

Foxboro +, Limitorque +, General Electric +  and Target Rock +

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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, 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 +

4kV +  and 24kV +

NEDC-32410P +, NEDC-32433P +, NEDO-20566 +, NEDE-31758P +, NEDO-24580 +  and NEDE-32198P +

10E-7 +, 6E-01 +, 10B-equival +, 245N2412-1 +, 13x1-1 +, 245N2756-5 +, 2M12-I +, 2M12-1 +, 2MI-IIis +, 2MI-II(lifted) +, 2M1-II +, 45E763-4 +, 345E724-6 +  and 1B-8272 +

Manual Scram +  and Automatic Scram +

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 +, Standby Gas Treatment System +, Automatic Depressurization System +, Stator Cooling Water +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Core Standby Cooling System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Main Condenser +...

TS-3.7 +, TS-3.6.D +, TS-4.7.A +, TS-3.9.B +, TS-3.9.A +, TS-4.9.A +, TS-6.8.3.2 +  and TS-6.9.1.2 +

Safe Shutdown +, Loop seal +, High Radiation Area +, Grab sample +, Offsite Dose Calculation Manual +, Stroke time +, Anticipated operational occurrence +, Nondestructive Examination +, Abnormal operational transient +, Corrosion bonding +, Local Leak Rate Testing +, Design basis earthquake +, Feedwater Heater +, Scram Discharge Volume +, MELLLA +, Stress corrosion cracking +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Earthquake +, Power Operated Valves +, Fire Protection Program +, Scaffolding +, Coast down +  and Water rod +