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ML20133B744 +
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>.
ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 +, ML20133B744 + and ML20133B744 +
July 5, 1985 +
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>.
15:04:13, 25 May 2025 +
NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1066, Forwards Table of B&W Plants Comparing Selected TMI Actions from NUREG-1066.Incomplete TMI Items for Facility Listed Per NUREG-0737.NUREG-0737 & Suppl 1 Active Items Re post-implementation Reviews Also Listed +, NUREG-0090, SECY-25-0016: Enclosure 1 - NUREG-0090, Volume 47, Report to Congress on Abnormal Occurrences: Fiscal Year 2024 + and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
103 +
05000000 + and Davis Besse +
July 5, 1985 +
Washington + and Maine +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Safety Parameter Display System +, Residual Heat Removal +, Control Room Emergency Ventilation +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line + and Control Rod +
Forwards Revised Responses to Questions in Congressman Markey Re 850609 Incident at Facility.Rept of Task Force Investigation of Incident Will Be Completed & Made Available by 850724 +
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