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ML11280A133 +
10 CFR 50 Appendix R +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50.49 +, 10 CFR 50.68 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.54#o +, 10 CFR 50.36#c2ii +, 10 CFR 50.65#a4 +, 10 CFR 50.68#b4 +, 10 CFR 50.68#b +, 10 CFR 50.55a#g + and 10 CFR 50.55a#c +
GDC 38 +, GDC 41 +, GDC 34 +, GDC 15 +, GDC 10 +, GDC 55 +, GDC 35 +, GDC 14 +, GDC 18 +, GDC 11 +, GDC 13 +, GDC 30 +, GDC 39 +, GDC 40 +, GDC 28 +, GDC 29 +, GDC 42 +, GDC 43 +, GDC 17, Electric power systems +, GDC 19, Control room + and GDC 26, Reactivity control system redundancy and capability +
NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" + and NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +
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NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +, NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases + and NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months) +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months) +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months) +, 4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months) +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months) +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months) +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months) +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months) +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months) +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months) +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months) +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months) +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months) +, 6.25e-4 d (0.015 hours, 8.928571e-5 weeks, 2.0547e-5 months) +, 9.027778e-4 d (0.0217 hours, 1.289683e-4 weeks, 2.9679e-5 months) +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months) +, 9.722222e-4 d (0.0233 hours, 1.388889e-4 weeks, 3.1962e-5 months) +, 6.944444e-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months) +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months) +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months) +, 3.703704e-4 d (0.00889 hours, 5.291005e-5 weeks, 1.2176e-5 months) +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months) +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months) +, 7.523148e-4 d (0.0181 hours, 1.074735e-4 weeks, 2.47325e-5 months) +, 8.449074e-4 d (0.0203 hours, 1.207011e-4 weeks, 2.77765e-5 months) +, 5.208333e-4 d (0.0125 hours, 7.440476e-5 weeks, 1.71225e-5 months) +, 0.00128 d (0.0308 hours, 1.835317e-4 weeks, 4.22355e-5 months) +, 0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months) +...
IEEE 485 +, IEEE 279-1968 +, IEEE 308 +, IEEE 485-1983 +, IEEE-450 +, IEEE 387 +, IEEE 387-1995 + and IEEE 308-1978 +
October 6, 2010 +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
02:32:44, 3 August 2018 +
NUMARC 93-01 + and NUMARC 91-06 +
661 +
Request +
Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.196 +, Regulatory Guide 1.163 +, Regulatory Guide 1.137 +, Regulatory Guide 1.9 +, Regulatory Guide 1.45 +, Regulatory Guide 1.93 +, Regulatory Guide 1.121 +, Regulatory Guide 1.182 +, Regulatory Guide 1.105 +, Regulatory Guide 1.6 +, Regulatory Guide 1.99 +, Regulatory Guide 1.32 +, Regulatory Guide 1.129 + and Regulatory Guide 1.68 +
SR-3.5.1.4 +, SR-3.5.4.2 +, SR-3.5.1.1 +, SR-3.5.4.1 +, SR-3.8.1.3 +, SR-3.4.4.1 +, SR-3.3.5.3 +, SR-3.8.1 +, SR-3.8.1.1 +, SR-3.7.5.2 +, SR-3.8.1.7 +, SR-3.8.7.1 +, SR-3.0.3 +, SR-3.7.5.1 +, SR-3.7.5.3 +, SR-3.0.1 +, SR-3.7.11.1 +, SR-3.4.13.1 +, SR-3.8.3.2 +, SR-3.6.1.1 +, SR-3.7.1.1 +, SR-3.6.6.3 +, SR-3.4.10.1 +, SR-3.4.3.1 +, SR-3.2.3.1 +, SR-3.7.2.2 +, SR-3.8.3.4 +, SR-3.4.14.2 +, SR-3.3.3.3 +, SR-3.5.2.1 +...
October 6, 2010 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam + and Containment Spray +
TS-3.4.14 +, TS-3.0.3 +, TS-3.5.1 +, TS-3.8.1 +, TS-3.7.4 +, TS-3.7.3 +, TS-3.0.1 +, TS-3.4.13 +, TS-3.5.2 +, TS-3.8.7 +, TS-3.9.2 +, TS-3.5.3 +, TS-3.7.1 +, TS-3.3.3 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.5.4 +, TS-3.0.4 +, TS-3.6.5 +, TS-3.4.5 +, TS-3.6.3 +, TS-3.8.2 +, TS-3.6.1 +, TS-3.4.16 +, TS-3.7.10 +, TS-3.4.4 +, TS-3.7.5 +, TS-3.4.8 +, TS-3.4.12 +, TS-3.4.3 +...
Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases +
Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Stroke time +, Anticipated operational occurrence +, Time to boil +, Post Accident Monitoring +, Hydrostatic +, Qualified Offsite Circuit +, High Energy Line Break +, Missed surveillance +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Battery sizing +, Earthquake +, Power Operated Valves +, Fuel cladding +, Pressure Boundary Leakage +, Recently irradiated fuel +, Offsite Circuit +, Power change +, Core Exit Thermocouple +, Operability Assessment +, Unidentified leakage +...
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