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ML19318D215
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML19318D215  +
Atomic Element
Lead +
CFR
10 CFR 50.46 +
Docket
05000289  +  and 00289  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
FirstEnergy +  and Herbein 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>.
ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +, ML19318D215 +  and ML19318D215 +
Issue date
June 30, 1980  +
Letter
ML19199A420 +
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01:14:31, 2 January 2025  +
NUREG
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-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +  and NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +
Page count
100  +
Project stage
Request  +
Site
Crane +
Site license
Crane +
Start date
June 30, 1980  +
State
Pennsylvania +, Washington +, Florida +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Decay Heat Removal +  and Emergency Feedwater System +
Title
Forwards Resolutions to long-term Generic Issues Re May 1979 Commission Orders & Addl Info Requested Concerning Small Break LOCA  +
To
Office of Nuclear Reactor Regulation +  and Harold Denton +
Topic
Loss of Offsite Power +
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http://pbadupws.nrc.gov/docs/ML1931/ML19318D215.pdf  +
 
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