Browse wiki

Jump to navigation Jump to search
ML20236X738
Show incoming properties
Category
TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT
Accession number
ML20236X738  +
Atomic Element
Hydrogen +  and Lead +
CFR
10 CFR 100 +
From
Office of Nuclear Reactor Regulation +  and Spano A +
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>.
ML20236X738 +, ML20236X738 +, ML20236X738 +, ML20236X738 +, ML20236X738 +, ML20236X738 +  and ML20236X738 +
Hours
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +  and 0.101 d (2.433 hours, 0.0145 weeks, 0.00333 months)  +
In package
ML20195F761 +
Issue date
February 28, 1987  +
Manufacturer
Westinghouse +
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>.
00:35:37, 3 December 2024  +
NRC bulletin
NRC Bulletin 85-01 +
NRC information notice
Information Notice 84-06 +
NUREG
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-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-1032, Draft Reg Guide,Task SI 501-4, Station Blackout. Draft NUREG-1109 & NUREG-1032 Re Regulatory/Backfit Analysis for Resolution of USI A-44 & Evaluation of Station Blackout Accidents at Nuclear Power Plants,Respectively,Encl +, 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/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +  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 +
Page count
37  +
Procedure
CP +
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.
ML20236X738 +
SOER
SOER 86-3 +
SSC
2x10-3 +
Start date
February 28, 1987  +
State
Texas +  and Maine +
System
Steam Generator +, Feedwater +, Auxiliary Feedwater +  and Decay Heat Removal +
Title
Regulatory Analysis of Generic Safety Issue 93 - Steam Binding of Auxiliary Feedwater Pumps  +
Topic
Probabilistic Risk Assessment +, Backfit +, Water hammer +  and Seal weld +
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.
http://pbadupws.nrc.gov/docs/ML2023/ML20236X738.pdf  +
Retrieved from "https://kanterella.com/Special:Browse/:ML20236X738"