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ML062900306 +
10 CFR 50 Appendix R +, 10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 71 +, 10 CFR 20.1302 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.62#c4 +, 10 CFR 50.62#c3 +, 10 CFR 50.55a#f +, 10 CFR 50.55a#o + and 10 CFR 50.55#a1 +
PLA-6076, Proposed License Amendment No. 285 for Unit 1 and Proposed License Amendment No. 253 for Unit 2, Extended Power Uprate Application - Supplement +, PLA-5931, Proposed License Amendment Numbers 279 and 248 Arts/Mellla Implementation +, RS-001 +, PLA-5963, Calculation EC-RADN-1135, Justification of AST 60 Isotope Radtrad Source Term for Direct Shine + and PLA-5933, Proposed Amendment No. 280 to Unit 1, and Proposed Amendment No. 249 to Unit 2, Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits +
GDC 20 +, GDC 38 +, GDC 41 +, GDC 44 +, GDC 34 +, GDC 15 +, GDC 50 +, GDC 16 +, GDC 54 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 61 +, GDC 35 +, GDC 14 +, GDC 60 +, GDC 24 +, GDC 11 +, GDC 13 +, GDC 46 +, GDC 31 +, GDC 40 +, GDC 25 +, GDC 64 +, GDC 28 +, GDC 62 +, GDC 22 +, GDC 29 +, GDC 42 +, GDC 27 +...
NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, 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 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations + and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 +, ML062900306 + and ML062900306 +
October 11, 2006 +
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10:46:33, 15 January 2025 +
Information Notice 2005-23, Vibration-Induced Degradation of Butterfly Valves +, Information Notice 97-90 +, Information Notice 95-16 +, Information Notice 2004-06, Loss of Feedwater Isokinetic Sampling Probes at Dresden Units 2 and 3 +, Information Notice 97-85 +, Information Notice 96-48 +, Information Notice 96-49 +, Information Notice 00-17 +, Information Notice 02-26 + and Information Notice 2002-26, July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH 56, NRC Information Notice 2002-26, Supplement 2: Additional Flow-Induced Vibration Failures After a Recent Power Uprate +
NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors + and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
149 +
Request +
Regulatory Guide 1.25 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.147 +, Regulatory Guide 1.84 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +, Regulatory Guide 1.68 +, Regulatory Guide 1.95 +, Regulatory Guide 1.161 +, Regulatory Guide 1.154 +, Regulatory Guide 8.12 +, Regulatory Guide 8.14 + and Regulatory Guide 8.3 +
October 11, 2006 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Shield Building +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Main Steam Safety Valve +, Spray Pond +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +...
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Anticipated operational occurrence +, Time to boil +, Hydrostatic +, Coatings +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, MELLLA +, Loss of Offsite Power +, Fuel cladding +, Fire Protection Program +, Flow Induced Vibration +, Coast down +, Power Uprate +, Overspeed trip +, Overspeed +, Loss of condenser vacuum +, Control Room Habitability + and Leak-Before-Break +
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