Browse wiki

ANSI B31.1 +, ANSI N13.1-1969 +, ANSI N13.10-1974 +, ANSI B16.5 +, ANSI B31.1.0 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

ASME Section XI +, ASME Section III +, ASME Section IX +, ASME Section IV +, ASME Section V +, ASME Section II +  and ASME Section VIII +

Environmental Protection Agency +  and Federal Energy Regulatory Commission +

Boron +, Strontium +, Iodine +, Cesium +, Uranium +, Iron +, Yttrium +, Rubidium +, Germanium +, Nickel +, Krypton +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Chlorine +, Zirconium +, Lead +, Zinc +, Tellurium +, Barium +, Lanthanum +, Plutonium +  and Cerium +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 20.2202 +, 10 CFR 50 Appendix K +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 30 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1001 +, 10 CFR 71 +, 10 CFR 19 +, 10 CFR 54 +, 10 CFR 19.12 +, 10 CFR 19.13 +, 10 CFR 20.2106 +, 10 CFR 20.1003 +, 10 CFR 20.1201 +, 10 CFR 20.1301 +, 10 CFR 20.2101 +, 10 CFR 50.49 +, 10 CFR 50.62 +...

Barrier Integrity +, Initiating Events +  and Physical Protection +

P.4(s) +, H.2(s) +, H.2(y) +, P.1(x) +, P.1(s) +  and P.3(s) +

05000321  +, 05000366  +  and 00321  +

Turbine Trip +  and Reactor Trip +

Orenak M D +  and Plant Licensing Branch II +

SIL 502 +  and SIL 589 +

GDC 34 +, GDC 15 +, GDC 50 +, GDC 10 +, GDC 12 +, GDC 56 +, GDC 35 +, GDC 60 +, GDC 18 +, GDC 13 +, GDC 30 +, GDC 64 +, GDC 23 +, GDC 28 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 26, Reactivity control system redundancy and capability +

ML17010A361 +, ML17010A361 +, ML17010A361 +, ML17010A361 +, ML17010A361 +, ML17010A361 +, ML17010A361 +, ML17010A361 +, ML17010A361 +  and ML17010A361 +

IEEE 344 +, IEEE 323 +, IEEE 383-1974 +, IEEE 308 +  and IEEE-450 +

Tritium +, Am-241 +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Y-90 +, Ni-63 +, Kr-85 +, I-131 +, Cu-64 +, N-16 +, Nitrogen-16 +, C-14 +, H-3 +, Mo-99 +, Mn-54 +  and Deuterium +

Alternate Source Term +  and License Renewal Application +

Westinghouse +, General Electric +  and Target Rock +

NRC Bulletin 79-14 +, NRC Bulletin 80-25 +  and NRC Bulletin 80-01 +

NUREG-1433 +, NUREG/CR-1276 +, NUREG-0597 +, NUREG/CR-6190, Ltr to D. Walters, NEI from: G. M. Tracy Subject: to Provide NEI an Updated Copy of NUREG/CR-6190 (SGI) +, NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AOP +, SP +, TP +, CP +, Emergency Operating Procedure +  and CP-3 +

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.155 +, Regulatory Guide 1.52 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.105 +, Regulatory Guide 1.26 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 1.8 +, Regulatory Guide 1.29 +, Regulatory Guide 1.32 +, Regulatory Guide 1.140 +, Regulatory Guide 1.68 +, Regulatory Guide 1.80 +, Regulatory Guide 1.112 +  and Regulatory Guide 5.68 +

NEDC-32749P +, NEDC-31858P +, NEDO-31331 +, NEDC-33085P +, NEDO-10173 +, NEDO-10505 +, NEDO-10871 +, NEDO-10751 +, NEDE-11146 +, NEDO-10734 +, NEDO-21506 +, NEDO-21778 +, NEDC-30474 +, NEDC-32938 +, NEDE-22224 +, NEDO-10802 +, NEDC-32749 +, NEDO-10527 +, NEDC-32720P +, NEDC-32424P +, NEDC-32938P +, NEDO-31400 +, NEDO-10585 +  and NEDC-32973P +

1R24-S026 +, 1R23-S003 +, 10E-9 +, 2T48-F310 +, 2B21-F028A +, 2E-6 +, 5E-1 +, 4E-4 +, 2E-3 +, 5E-3 +, 2T47-B007A +, 15A-1 +, 1Z41-F018A +, 14A-2 +, 14B-2 +, 1E11-C002C +, 1E11-C001C +, 1P41-C001C +, 1R24-S048 +, 2E11-C002C +, 2E11-C001C +, 2P41-C001C +, 2R23-S003 +, 2R24-S048 +, 2P51-A001 +, 2P52-A001 +, 2P52-A018 +, 2B21-A002 +, 2B21-A002-A +, 2P51-A002 +...

Manual Scram +  and Automatic Scram +

Georgia +, Minnesota +, California +, New York +  and Florida +

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 Transformer +, Main Turbine +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +, Residual Heat Removal Service Water +, Core Standby Cooling System +...

TS-5.4.1 +, TS-5.5.4 +  and TS-5.5.5 +

Safe Shutdown +, High winds +, Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Stroke time +, Anticipated operational occurrence +, Tornado Missile +, Water Inventory Control +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, Operating Basis Earthquake +, Operator Manual Action +, Squib +, Emergency Lighting +, Incorporated by reference +, Aging Management +, Tornado Missile Protection +, Design basis earthquake +, Feedwater Heater +, Scram Discharge Volume +, Shift Technical Advisor +, Microbiologically influenced corrosion +, Process Control Program +...

Turbine bypass valve +  and Main Turbine Control Valve +

Vega +  and GE Hitachi Nuclear Energy +