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ML20148T189 +
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>.
ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 +, ML20148T189 + and ML20148T189 +
April 10, 1990 +
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15:34:07, 11 December 2024 +
NUREG-1377 +, NUREG/CR-5021 +, NUREG-1190, Transcript of Commission 860122 Briefing in Washington,Dc Re San Onofre & Status of Rancho Seco.Pp 1-105.Supporting Documentation & NUREG-1190, Loss of Power & Water Hammer Event at San Onofre,Unit 1 on 851121 Encl +, 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-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-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-1286, Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues +, 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 +
27 +
April 10, 1990 +
Steam Generator +, Feedwater +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Emergency Response Data System +, Safety Parameter Display System +, Core Spray +, Residual Heat Removal +, Emergency Feedwater Initiation and Control + and Main Steam +
Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed +
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