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ML20053C513
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Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
ASME section
ASME Section II +
Accession number
ML20053C513  +
Atomic Element
Boron +, Uranium +, Carbon +, Sodium +, Hydrogen +, Lead +  and Tin +
CFR
10 CFR 50 Appendix K +
From
Advisory Committee on Reactor Safeguards +
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>.
ML20053C513 +, ML20053C513 +, ML20053C513 +, ML20053C513 +  and ML20053C513 +
Issue date
January 12, 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>.
08:36:24, 18 December 2024  +
NUREG
NUREG-0795 +, NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0864 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
48  +
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ML20053C513 +
SSC
3D-PROGRAM +
Start date
January 12, 1982  +
State
Washington +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +  and Decay Heat Removal +
Title
Summary of ACRS Nuclear Safety Research Program 820106 Meeting in Washington,Dc Re FY83 Budget for NRC Safety Research Programs  +
To
Advisory Committee on Reactor Safeguards +
Topic
Loop seal +, Probabilistic Risk Assessment +, Water hammer +  and Pre-application +
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http://pbadupws.nrc.gov/docs/ML2005/ML20053C513.pdf  +
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