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ML20136F580
Show incoming properties 
Category
TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT
Accession number
ML20136F580  +
Atomic Element
Boron +, Hydrogen +  and Lead +
Cornerstone
Initiating Events +  and Mitigating Systems +
Docket
05000382  +  and 05000528  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Office of Nuclear Reactor Regulation +  and Davis S +
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>.
ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +, ML20136F580 +  and ML20136F580 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
In package
ML20136F585 +
Issue date
September 20, 1984  +
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>.
05:56:06, 12 December 2024  +
NUREG
NUREG-0646 +, NUREG/CR-3495 +, NUREG/CR-0400, Forwards NRC Policy Statement Re Reactor Safety Study,Review by the Lewis Committee (NUREG/CR-0400) & Survey of NRC Uses of WASH-1400.All Documents Have Been Furnished to ASLB & Aslab Panel Members.W/O Encl +, 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 +, 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-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +
Page count
250  +
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.
ML20136F580 +
Project stage
Request  +
Site
Palo Verde +  and Waterford +
Start date
September 20, 1984  +
State
New York +, Florida +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Containment Spray +  and Emergency Feedwater System +
Title
Insights Gained from Pras  +
Topic
Mission time +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Earthquake +  and Failure to Scram +
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/ML2013/ML20136F580.pdf  +
 
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