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ML20054G565
Show incoming properties 
Category
CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC, TEXT-PROCUREMENT & CONTRACTS  and RESEARCH AND TECHNICAL ASSISTANCE REPORTS
Accession number
ML20054G565  +
Atomic Element
Nitrogen +, Sodium +, Hydrogen +, Lead +  and Plutonium +
Cross cutting aspect
H.2(n) +
Docket
05000537  +
Engineering change
EC-6054 +
From
Brookhaven National Laboratory +, Ami Agrawal +, Buslik A +  and Bari R +
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>.
ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +, ML20054G565 +  and ML20054G565 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
April 30, 1982  +
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>.
22:51:38, 17 December 2024  +
NUREG
NUREG/CR-0405 +  and NUREG-0358, Forwards NRC Review of Fast Flux Test Facility Power Addition Safety Documents,Per Vaughn .Concludes That Proper Issues Being Addressed & That DOE Plan for Addressing Issues Appears Adequate +
Page count
97  +
Procedure
AM +
Project stage
Request  +
SSC
31F-30 +
Site
Clinch River +
Start date
April 30, 1982  +
State
Arizona +, Maryland +, Washington +, California +  and New York +
System
Steam Generator +, Feedwater +, Auxiliary Feedwater +, Decay Heat Removal +  and Control Rod +
Title
Review of Status of Crbr Licensing Technical Issues Re Heat Removal Sys & Severe Accident Analysis  +
To
Office of Nuclear Reactor Regulation +  and Morris W +
Topic
Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Stress corrosion cracking +, Loss of Offsite Power +  and Leak Before Break +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2005/ML20054G565.pdf  +
 
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