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ANSI/ANS 58.8 +  and ANSI/ANS 3.5-1993 +

Boron +, Iodine +, Iron +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Lead +, Aluminum +  and Zinc +

10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 62 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix I +, 10 CFR 51.21 +, 10 CFR 20.1101 +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50.48#a +  and 10 CFR 50.46#d +

RS-01-281 +, SECY-97-042 +, RS-01-189 +, RS-01-207 +, RS-01-225 +, RS-01-241 +, RS-01-246 +, RS-01-247 +, RS-01-255 +, RS-01-261 +, RS-01-273 +, RS-01-271 +, RS-01-277 +, RS-01-279 +, RS-01-282 +, RS-01-278 +, RS-01-297 +, RS-01-302 +, RS-01-305 +, RS-01-311 +, RS-01-312 +, RS-02-068, Response to Request for Additional Information Re Proposed Power Uprate +, RS-02-062, Revised Risk Analysis Sensitivity Case Support the License Amendment Request to Permit Extended Power Uprate Operation for Clinton Power Station +, RS-02-057, Feedwater Nozzle Safe End Fatigue Evaluation Supporting the License Amendment Request to Permit Uprated Power Operations +, RS-02-005, Additional Mechanical Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation +, RS-02-019, Supplemental Reactor Systems Information Supporting License Amendment Request to Permit Uprated Power Operation at Clinton Power Station +, RS-02-014, Additional Mechanical Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation +, RS-02-011, Additional Testing Information Supporting the License Amendment Request to Permit Uprated Power Operation +  and U-603489 +

05000461  +  and 00461  +

Turbine Trip +  and Reactor Trip +

67 FR 6758 +  and 67 FR 16459 +

GDC 20 +, GDC 15 +, GDC 10 +, GDC 12 +, GDC 17, Electric power systems +  and GDC 19, Control room +

NRC Generic Letter 99-02 +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +, ML021650543 +...

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0 d (0 hours, 0 weeks, 0 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)  +, 0.00605 d (0.145 hours, 8.647487e-4 weeks, 1.990015e-4 months)  +, 7.060185e-4 d (0.0169 hours, 1.008598e-4 weeks, 2.32105e-5 months)  +, 0.00155 d (0.0372 hours, 2.215608e-4 weeks, 5.0987e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

Tritium +, Co-60 +  and N-16 +

RS-02-019, Supplemental Reactor Systems Information Supporting License Amendment Request to Permit Uprated Power Operation at Clinton Power Station +  and IR 05000461/2001016 +

NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, 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 +

4.16kV +  and 345kV +

AOP +  and Emergency Operating Procedure +

RS-01-281 +, RS-01-189 +, RS-01-207 +, RS-01-225 +, RS-01-241 +, RS-01-246 +, RS-01-247 +, RS-01-255 +, RS-01-261 +, RS-01-273 +, RS-01-271 +, RS-01-277 +, RS-01-279 +, RS-01-282 +, RS-01-278 +, RS-01-297 +, RS-01-302 +, RS-01-305 +, RS-01-311 +, RS-01-312 +, RS-02-068, Response to Request for Additional Information Re Proposed Power Uprate +, RS-02-062, Revised Risk Analysis Sensitivity Case Support the License Amendment Request to Permit Extended Power Uprate Operation for Clinton Power Station +, RS-02-057, Feedwater Nozzle Safe End Fatigue Evaluation Supporting the License Amendment Request to Permit Uprated Power Operations +, RS-02-005, Additional Mechanical Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation +, RS-02-019, Supplemental Reactor Systems Information Supporting License Amendment Request to Permit Uprated Power Operation at Clinton Power Station +, RS-02-014, Additional Mechanical Systems Information Supporting the License Amendment Request to Permit Uprated Power Operation +  and RS-02-011, Additional Testing Information Supporting the License Amendment Request to Permit Uprated Power Operation +

Regulatory Guide 1.174 +, Regulatory Guide 1.52 +, Regulatory Guide 1.49 +  and Regulatory Guide 1.7 +

NEDO-32465 +, NEDO-32047 +, NEDC-32989P +, NEDC-32424P +, NEDC-32523P +, NEDC-33004P +, NEDO-30832 +, NEDE-24011P +, NEDO-24222 +, NEDO-24548 +, NEDC-32851P +, NEDO-32164 +, NEDC-32464P +  and NEDC-32424 +

SR-3.3.1.1.2 +, SR-3.3.1.1 +, SR-3.3.2.1.2 +, SR-3.7.3.5 +, SR-3.7.3.6 +, SR-3.3.2.1.4 +, SR-3.3.2.1.5 +, SR-3.3.4.1.4 +, SR-3.4.11.8 +  and SR-3.4.11.9 +

1E-6 +  and 1E-7 +

Pennsylvania +, Illinois +, North Carolina +, California +  and Maine +

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

TS-3.3.1.1 +, TS-3.7.5 +, TS-3.4.3 +, TS-1.1 +, TS-3.7.6 +, TS-3.2.3 +, TS-3.1.7 +, TS-3.1.6 +, TS-3.4.1 +, TS-3.1.3 +, TS-3.2.2 +, TS-3.2.1 +, TS-3.3.4.1 +  and TS-2.1.1.1 +

Safe Shutdown +, High winds +, Shutdown Margin +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, High Radiation Area +, Ultimate heat sink +, Fire Barrier +, Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +, High Energy Line Break +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Large early release frequency +, MELLLA +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Power-Operated Valves +, Fuel cladding +, Fire Protection Program +, Flow Induced Vibration +, Power Uprate +, Failure to Scram +, Overspeed trip +, Simmer margin +, Subsequent actuation +...