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ML20058N641 +
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50.55 +, 10 CFR 50.9 +, 10 CFR 50.44 +, 10 CFR 50.109 +, 10 CFR 50.97 +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.55a#g +, 10 CFR 50.55a#f +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g6i +, 10 CFR 50.55a#f4 +, 10 CFR 50.55a#f5iii +, 10 CFR 50.55a#f4ii +, 10 CFR 50.55a#f4iv +, 10 CFR 50.55a#f6 +, 10 CFR 50.55a#f5ii +, 10 CFR 50.55a#f5iv +, 10 CFR 50.109#a4i + and 10 CFR 50.55a#gii +
March 15, 1976 +
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 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, 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 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance + and NRC Generic Letter 89-47 +
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>.
ML20058N641 +, ML20058N641 +, ML20058N641 +, ML20058N641 +, ML20058N641 +, ML20058N641 +, ML20058N641 + and ML20058N641 +
TI 2515/110 + and TI 2515/114 +
November 30, 1993 +
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>.
22:33:14, 26 May 2025 +
Information Notice 87-01 +, Information Notice 91-56 +, Information Notice 92-27 +, Information Notice 89-62 +, Information Notice 90-21 +, Information Notice 85-84 +, Information Notice 88-70 +, Information Notice 91-37 +, Information Notice 86-50 +, Information Notice 92-31 +, Information Notice 91-45 +, Information Notice 89-32 +, Information Notice 88-15 +, Information Notice 88-85 +, Information Notice 90-02 +, Information Notice 83-54 +, Information Notice 91-74 +, Information Notice 83-03 + and Information Notice 82-08 +
NUREG/CR-5124 +, NUREG/CR-5102 +, NUREG/CP-0123 +, NUREG-148 +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-1350, News Release-25-011: Latest Edition of NRC Information Digest Now Available Online +, NUREG-1982 + and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
200 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
November 30, 1993 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Main Steam Safety Valve +, Remote shutdown +, Residual Heat Removal Service Water +, Reactor Building Closed Loop Cooling +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +, Main Steam + and Containment Spray +
Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Stroke time +, Hydrostatic +, Anchor Darling +, Squib +, Incorporated by reference +, Local Leak Rate Testing +, Scram Discharge Volume +, Excess Flow Check Valve +, Cold shutdown justification +, Earthquake +, Power-Operated Valves +, Power Operated Valves +, Grace period +, Backfit + and Operational convenience +
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