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ML19210C772
Show incoming properties 
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML19210C772  +
Atomic Element
Nitrogen +, Carbon +, Hydrogen +  and Tin +
Correspondence
L 30 +  and NRC 571 +
Equipment trip
Reactor Trip +
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>.
ML19210C772 +, ML19210C772 +, ML19210C772 +, ML19210C772 +, ML19210C772 +  and ML19210C772 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
July 30, 1979  +
L
L 30 +
Manufacturer
Westinghouse +  and General Electric +
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>.
02:45:22, 5 January 2025  +
NRC
NRC 571 +
NRC bulletin
NRC Bulletin 79-05 +, NRC Bulletin 79-06 +  and NRC Bulletin 79-65 +
NUREG
NUREG-0557, Forwards NUREG-0557, Evaluation of Long-Term Post-Accident Core Cooling of Tmi. W/O Encl +
Page count
60  +
Procedure
ST +, CH +  and CP +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML19210C772 +
Regulatory Guide
Regulatory Guide 1.1 +  and Regulatory Guide 1.101 +
SSC
07-79-06A +, 07-79-06B +, 07-79-05A +, N0r-condens +, T9e-e +, 2a-ncur +  and 9tI-2 +
Start date
July 30, 1979  +
State
Tennessee +, Washington +, California +, Florida +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +  and Decay Heat Removal +
TS
TS-3.15 +
Title
Summary of 790430,0501 & 09 Meetings of ACRS Ad Hoc Subcommittee on TMI-2 Accident Implications Re Nuclear Power Plant Design in Washington,Dc Re Nuclear Safety Design, Policy,Criteria Research & Plant Operation  +
To
Advisory Committee on Reactor Safeguards +
Topic
Loop seal +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1921/ML19210C772.pdf  +
 
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