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ML19323A932
Show incoming properties
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML19323A932  +
Atomic Element
Iodine +, Hydrogen +  and Lead +
Docket
05000312  +
Emergency Facility
Technical Support Center +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Hanrahan E +  and NRC OFFICE OF POLICY EVALUATIONS (OPE) +
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>.
ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +, ML19323A932 +  and ML19323A932 +
In package
ML19323A931 +
Issue date
April 24, 1980  +
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>.
04:47:54, 1 January 2025  +
NRC bulletin
NRC Bulletin 79-05 +
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-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, 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 +  and NUREG-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +
Page count
31  +
Person
Harold Denton +
SSC
1NI-2 +, 07-79-05A +, 1MI-2 +, 07-79-05C +, 07-79-058 +, 1HI-2 +, 07-79-054 +  and 07-79-05a +
Scram
Automatic Scram +  and Manual Scram +
Site
Rancho Seco +
Start date
April 24, 1980  +
State
Pennsylvania +, Washington +  and Florida +
System
Steam Generator +, Reactor Coolant System +, Feedwater +  and Auxiliary Feedwater +
Title
Summarizes Evaluation of Impact of post-TMI-2 NRC Requirements on B&W Reactors & Crystal River Transient. Supports B&W Task Force Recommendation Re Developent of Generic Guidelines for Operators  +
To
NRC COMMISSION (OCM) +, Ahearne J +, Gilinsky V +  and Kennedy R +
Topic
Safe Shutdown +, Shift Technical Advisor +  and Loss of Offsite Power +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1932/ML19323A932.pdf  +
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