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ML20049A610
Show incoming properties 
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20049A610  +
Act
Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +
Atomic Element
Lead +
CFR
10 CFR 50 +
From
Hodges W +  and Office of Nuclear Reactor Regulation +
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>.
ML20049A610 +, ML20049A610 +, ML20049A610 +, ML20049A610 +, ML20049A610 +, ML20049A610 +, ML20049A610 +  and ML20049A610 +
In package
ML20049A611 +
Issue date
July 2, 1981  +
Manufacturer
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>.
11:10:17, 19 December 2024  +
NUREG
NUREG-046 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
Page count
58  +
Procedure
AM +, ST +, CH +  and TOP +
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ML20049A610 +
Report
NEDE-20566P +
Scram
Automatic Scram +  and Manual Scram +
Start date
July 2, 1981  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, High Pressure Core Spray +, Core Spray +, Standby Liquid Control +, Emergency Core Cooling System +, Control Rod +  and Low Pressure Coolant Injection +
Title
Summary of 810529 Meeting W/Ge & NUS in Bethesda,Md Re Proposed ECCS Approach for Bwrs.Agenda & Viewgraphs Encl  +
To
Mattson R +  and Office of Nuclear Reactor Regulation +
Topic
Probabilistic Risk Assessment +, Scram Discharge Volume +, Backfit +  and Failure to Scram +
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http://pbadupws.nrc.gov/docs/ML2004/ML20049A610.pdf  +
 
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