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ML031070133 +
NextEra Energy + and Jefferson W +
NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 91-08, Removal of Component Lists from Technical Specifications +, NRC Generic Letter 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation + and NRC Generic Letter 94-01, Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +, L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 + and L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4 +
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) +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months) +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months) +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months) +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months) +, 6.25e-4 d (0.015 hours, 8.928571e-5 weeks, 2.0547e-5 months) +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months) +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months) +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months) +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months) +, 0.0137 d (0.328 hours, 0.00195 weeks, 4.4899e-4 months) + and 0.0172 d (0.414 hours, 0.00246 weeks, 5.66945e-4 months) +
April 14, 2003 +
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>.
15:47:49, 16 January 2025 +
NUMARC 93-01 + and NUMARC 91-06 +
101 +
Request +
April 14, 2003 +
Washington + and Florida +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Control Room Emergency Ventilation +, Shield Building +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod + and Containment Spray +
TS-3.0.3 +, TS-3.5.2 +, TS-3.6.2.1 +, TS-3.8.1.1 +, TS-3.1.1.1 +, TS-6.8.4.j +, TS-6.8.4.i + and TS-3.1.1.2 +
Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Ultimate heat sink +, Stroke time +, Anticipated operational occurrence +, Hydrostatic +, Missed surveillance +, Stress corrosion cracking +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Recently irradiated fuel +, Power change +, Unidentified leakage +, Control Room Habitability + and Operational convenience +
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