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Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation  and Technical Specifications

Boron +, Iodine +, Gadolinium +, Sodium +, Zirconium +  and Lead +

10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.4 +, 10 CFR 50.44 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50.120 +, 10 CFR 50 Appendix I +, 10 CFR 73.21 +, 10 CFR 50.54#p +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c5 +, 10 CFR 50.62#c4 +, 10 CFR 50.62#c3 +  and 10 CFR 73.55#51 +

Barrier Integrity +  and Physical Protection +

SECY-92-223 +, SECY 93-087 +, SECY 11-0014 +, NRC-2014-0250 +  and RS-001 +

05000277  +, 05000278  +, 00277  +  and 00278  +

Regulatory Guide 1.183 +, Regulatory Guide 1.174 +, ML051400209 +, ML003763736 +, ML071700658 +, ML070670253 +, ML12324A013 +, ML070160661 +, ML100680577 +, ML070550060 +, ML033640024 +, ML003708056 +, ML070740002 +, ML072640413 +, ML070710376 +, ML14247A503 +, ML102780586 +, ML070740003 +, ML111330278 +, ML123130130 +, ML110970401 +, ML070540139 +, ML110550791 +, ML16034A372 +, ML031150300 +, ML14133A046 +, ML031110021 +, ML091800530 +, ML082320406 +, ML15274A467 +...

Turbine Trip +  and Reactor Trip +

36 FR 3255 +, 32 FR 10213 +, 79 FR 71454 +  and 79 FR 71450 +

Richard Ennis +  and Plant Licensing Branch I +

GDC 57 +, GDC 20 +, GDC 41 +, GDC 49 +, GDC 15 +, GDC 10 +, GDC 12 +, GDC 14 +, GDC 13 +, GDC 30 +, GDC 31 +, GDC 40 +, GDC 25 +, GDC 28 +, GDC 22 +, GDC 29 +, GDC 37 +, GDC 42 +, GDC 8 +, GDC 9 +, GDC 27 +, GDC 32 +, GDC 51 +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 26, Reactivity control system redundancy and capability +

NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, 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 +

ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +, ML16034A372 +...

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

Nitrogen-16 +  and N-16 +

05000278/LER-2004-002, Loss of High Pressure Coolant Injection System Automatic High Level Trip as a Result as a Result of Lifted Lead +, CAC:MF4760 +, ML15274A467 +, ML15187A391 +, ML15037A502 +, ML15247A088 +, ML15299A084 +, ML15230A235 +, ML062750099 +, LR-N06-0249, Units 2 and 3, Nuclear Facilities, NRC Decommissioning Funding Status Report +  and ML043020352 +

NUREG-1764 +, NUREG-0711 +, 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 +

George Thomas +, Chakrapani Basavaraju +, Jerry Dozier +, Jose March-Leuba +, Shie-Jeng Peng +  and Brian Green +

AOP +, TP +  and Emergency Operating Procedure +

Regulatory Guide 1.183 +, Regulatory Guide 1.174 +, Regulatory Guide 1.82 +  and Regulatory Guide 1.17 +

NEDC-33178P +, NEDC-33006P +, NEDE-24011 +, NEDC-33173P +, NEDC-33075P +, NEDC-33147P +, NEDE-32906P +, NEDC-32906P +, NEDE-24222 +, NEDC-33173 +, NEDC-33720P +, NEDC-32983P +  and NEDE-33147P +

SECY-92-223 +, SECY 93-087 +  and SECY 11-0014 +

SR-3.3.1.1 +, SR-3.3.1.1.1 +, SR-3.3.1.1.8 +, SR-3.3.1.1.5 +, SR-3.3.1.1.6 +, SR-3.4.9 +, SR-3.1.7 +, SR-3.3.1.1.l +  and SR-3.3.l.1 +

3P-A +  and 2RPT-ATWSI +

Pennsylvania +, Maryland +  and Washington +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +...

TS-3.3.1.1 +, TS-3.0.4 +, TS-5.5.12 +, TS-3.2.3 +, TS-3.4.1 +, TS-3.3.3.1 +, TS-3.2.2 +, TS-5.6.5 +, TS-3.2.1 +, TS-5.5.10 +, TS-5.6.8 +, TS-5.6.3 +  and TS-5.6.5.a +

Exelon +  and Bryan Hanson +

Safe Shutdown +, Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, Anticipated operational occurrence +, Post Accident Monitoring +, Hydrostatic +, Probabilistic Risk Assessment +, Cyber Security +, High Energy Line Break +, Surveillance Frequency Control Program +, Feedwater Heater +, Feedwater Controller Failure +, Large early release frequency +, MELLLA +, Stress corrosion cracking +, Loss of Offsite Power +, Time Critical Operator Action +, Safeguards Contingency Plan +, Hardened vent +, Fuel cladding +, Fire Protection Program +, Power change +, Power Uprate +, Stretch Power Uprate +, Measurement Uncertainty Recapture +, Failure to Scram +, Water rod +  and Pressure Temperature Limits Report +