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ML20148P048 +
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>.
ML20148P048 +, ML20148P048 +, ML20148P048 +, ML20148P048 +, ML20148P048 +, ML20148P048 +, ML20148P048 + and ML20148P048 +
March 31, 1988 +
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>.
15:53:12, 11 December 2024 +
NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-1177, Advises That Facility May Resume Power Operations Based on Operational Readiness of Plant & 850910 & 861210 Responses to NRC Concerns.Changes in Organizational Structure Subj to NRC Approval +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-1231, Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco +, 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 + and 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 +
126 +
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.
2E-6 +, 1R-001-ICS +, 1R-039-1C5 +, 1R-050-M55 +, 1R-078-MFW +, 1R-161-EFW +, 1MI-86-02 + and 0C-3-86-04 +
March 31, 1988 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Main Turbine +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Emergency Feedwater Initiation and Control +, Decay Heat Removal +, Main Steam Line +, Electrohydraulic Control +, Control Rod +, Main Steam + and Emergency Feedwater System +
Safety Evaluation Report Related to Babcock and Wilcox Owners Group Plant Reassessment Program +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.