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ML20128G580
Show incoming properties
Category
TEXT-SAFETY REPORT  and TOPICAL REPORT EVALUATION
ASME section
ASME Section II +
Accession number
ML20128G580  +
Atomic Element
Nitrogen +  and Hydrogen +
CFR
10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +  and 10 CFR 50 Appendix X +
Docket
00269  +, 00270  +, 00287  +, 00289  +, 00320  +, 00302  +, 00313  +, 00312  +, 00330  +, 00329  +, 00346  +, 00438  +, 00439  +, 00460  +  and 00513  +
Equipment trip
Reactor Trip +
From
NRC +
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>.
ML20128G580 +, ML20128G580 +, ML20128G580 +, ML20128G580 +, ML20128G580 +  and ML20128G580 +
In package
ML20128G563 +
Issue date
June 27, 1985  +
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>.
18:55:17, 12 December 2024  +
NUREG
NUREG-0623 +, 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-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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
50  +
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ML20128G580 +
Start date
June 27, 1985  +
State
Maryland +, Virginia +, Idaho +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +  and Decay Heat Removal +
Title
Topical Rept Evaluation of BAW-10092(P),Rev 3 & BAW-10154(NP), CRAFT2- Fortran Program for Digital Simulation of Multinode Reactor Plant During Loss of Coolant. Repts Acceptable  +
Topic
Loop seal +, Loss of Offsite Power +  and Gas accumulation +
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http://pbadupws.nrc.gov/docs/ML2012/ML20128G580.pdf  +
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