Browse wiki

IWB-3514 +, IWB-3500 +, IWB-2500 +, IWB-3000 +, IWB-5222 +, IWB-2412 +, IWB-2000 +, IWB-1220 +, IWB-5221 +, IWB-3510 +, IWB-2200 +, IWB-3400 +, IWB-4000 +, IWA-2240 +, IWA-2200 +, IWA-4000 +, IWA-2232 +, IWA-2221 +, IWA-5240 +  and IWA-2222 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Cobalt +, Iron +, Nickel +, Vanadium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +, Phosphorus +, Sulfur +, Titanium +  and Niobium +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +  and 10 CFR 50.55a +

05200001  +  and 05200045  +

Turbine Trip +  and Reactor Trip +

GDC 15 +, GDC 37 +, GDC 27 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 5, Sharing of structures, systems, and components +

M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +, M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +, M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +, M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +, M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +, M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +, M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +  and M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

IEEE 279 +  and IEEE 308 +

Nitrogen-16 +  and Cobalt-60 +

NUREG/CR-4287 +  and NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +

Regulatory Guide 1.1 +, Regulatory Guide 1.147 +, Regulatory Guide 1.45 +, Regulatory Guide 1.84 +, Regulatory Guide 1.82 +, Regulatory Guide 1.26 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.50 +, Regulatory Guide 1.31 +, Regulatory Guide 1.68 +, Regulatory Guide 1.2 +, Regulatory Guide 1.44 +, Regulatory Guide 1.36 +, Regulatory Guide 1.56 +, Regulatory Guide 1.71 +, Regulatory Guide 1.139 +, Regulatory Guide 1.85 +, Regulatory Guide 1.150 +, Regulatory Guide 1.66 +  and Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants +

NEDO-21778 +, NEDO-10029 +  and NEDE-30637 +

5A-1 +, 5A-2 +, 5A-3 +, 5B-1 +, 5B-2 +, 5A-4 +, 5A-5 +, 5A-6 +, 5A-7 +, 5B-3 +, 5B-4 +, 5B-5 +, 3E-22 +, 700A-NB-023 +, 40A-SLC-4 +, 200A-RHR-107 +, 250A-RHR-106 +, 200A-RHR-207 +, 200A-RHR-206 +, 350A-RHR-010 +, 350A-RHR-211 +, 350A-RHR-110 +, 200A-HPCF-008 +, 150A-RCIC-033 +, 150A-CUW-24-CS +, 65A-CUW-20-55 +, 200A-CUW-1-CS +, 65A-CUW-20-SS +  and 200A-CUM-1-CS +

05200001 +  and 05200045 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Stroke time +, Water Inventory Control +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Nondestructive Examination +, VT-2 +, Abnormal operational transient +, Design basis earthquake +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Power-Operated Valves +, Fuel cladding +, Liquid penetrant +, Weak link +, Unidentified leakage +, Unidentified leak +, Overspeed trip +, Overspeed +, Subsequent actuation +, Manual Operator Action +, Water hammer +...