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Copper +, Hydrogen +, Lead +, Silicon +  and Calcium +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.49 +  and 10 CFR 50.54#f +

Minnesota +  and Xcel Energy +

NRC Generic Letter 79-36, Adequacy of Station Electric Distribution Systems Voltages +, NRC Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54 +, NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, 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 +

ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +, ML23006A150 +  and ML23006A150 +

0.0231 d (0.556 hours, 0.00331 weeks, 7.61e-4 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.00231 d (0.0556 hours, 3.306878e-4 weeks, 7.61e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

IEEE 279 +  and IEEE-450 +

05000263/LER-1984-024, :on 840627,during Cold Shutdown,Reactor Bldg Ventilation Isolation & Standby Gas Treatment Sys Initiation Occurred.Channel a Reactor Bldg Vent Wide Range Gas Monitor Deenergized.Caused by Personnel Error +  and ML20100J938 +

115KV +, 4.16KV +, 4kV +  and 345kV +

TAC:MD9990 +, TAC:ME9601 +, TAC:MB3042 +, TAC:M93487 +, TAC:M81483 +, TAC:68569 +  and TAC:71092 +

Regulatory Guide 1.137 +, Regulatory Guide 1.155 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.192 +

NEDC-33322P +  and NEDO-22087 +

07-27-43A +  and 07-79-01B +

Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Primary containment +, Main Turbine +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Decay Heat Removal +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Fire Barrier +, Post Accident Monitoring +, Operator Manual Action +, Emergency Lighting +, High Energy Line Break +, Open Phase Condition +, Notice of Violation +, Earthquake +, Power-Operated Valves +, Power Operated Valves +, Power Uprate +, Overspeed trip +, Overspeed +  and Manual Operator Action +