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ML20045D474
Show incoming properties
Category
CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE
ASME section
ASME Section III +
Accession number
ML20045D474  +
Area
Switchyard +
Atomic Element
Boron +, Lead +  and Tin +
Correspondence
SECY 93-087 +  and SECY 90-016 +
Docket
05200001  +
From
GENERAL ELECTRIC CO. +  and Fox J +
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>.
ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +, ML20045D474 +  and ML20045D474 +
Issue date
June 23, 1993  +
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>.
16:39:41, 19 December 2024  +
NUREG
NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +
Page count
39  +
Project stage
Request  +
SECY
SECY 93-087 +  and SECY 90-016 +
SSC
1E-6 +, 3E-5 +, 2E-8 +, 4E-9 +, 3E-1 +, 2E-3 +, 8E-4 +, 3E-9 +, 7E-2 +  and 4E-3 +
Site
05200001 +
Start date
June 23, 1993  +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +  and Control Rod +
Title
Forwards Mod to Paper Entitled, Important Features Identified by ABWR PRA, Submitted on 930602  +
To
Office of Nuclear Reactor Regulation +  and Poslusny C +
Topic
Safe Shutdown +, Loop seal +, Ultimate heat sink +, Fire Barrier +, Internal Flooding +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Excess Flow Check Valve +, License Renewal +, Failure to Scram +  and Basic Component +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2004/ML20045D474.pdf  +
Retrieved from "https://kanterella.com/Special:Browse/:ML20045D474"