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ML20224A521 +
SECY-93-087 +, SECY-83-293 +, SECY 94-084 +, SECY-94-084 +, SECY-11-0098 +, SECY-90-016 +, SECY 95-132 +, SECY 90-016 +, SECY 83-293 + and SECY-00-0198, Letter to R. Beedle Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on risk-informed Changes to 10 CFR 50.44 (Combustible Gas Control) +
73 FR 60612 + and 68 FR 54123 +
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>.
ML20224A521 +, ML20224A521 +, ML20224A521 +, ML20224A521 +, ML20224A521 +, ML20224A521 +, ML20224A521 +, ML20224A521 + and ML20224A521 +
July 29, 2020 +
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>.
08:20:19, 23 May 2025 +
NUREG-1493 +, NUREG/CR-6838 +, NUREG-0711 +, NUREG-1273 +, NUREG-1780 +, NUREG-1791 +, NUREG-1777 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated + and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
102 +
Other +
SECY-93-087 +, SECY-83-293 +, SECY 94-084 +, SECY-94-084 +, SECY-11-0098 +, SECY-90-016 +, SECY 95-132 +, SECY 90-016 +, SECY 83-293 + and SECY-00-0198, Letter to R. Beedle Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on risk-informed Changes to 10 CFR 50.44 (Combustible Gas Control) +
July 29, 2020 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel +, Residual Heat Removal +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Control Room Envelope +, Control Rod +, Main Steam + and Emergency Feedwater System +
Safe Shutdown +, Shutdown Margin +, Ultimate heat sink +, Non-Destructive Examination +, Grab sample +, Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +, Stress corrosion cracking +, Loss of Offsite Power +, Severe Accident Management Guideline +, Exemption Request +, Fuel cladding +, Core Exit Thermocouple +, Failure to Scram + and Gas accumulation +
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