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ML20059C973
Show incoming properties 
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20059C973  +
Agency
Federal Emergency Management Agency +
Atomic Element
Carbon +, Lead +  and Mercury +
CFR
10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 19 +, 10 CFR 50.61 +  and 10 CFR 50.66 +
Committee
Advisory Committee on Reactor Safeguards +
Cornerstone
Emergency Preparedness +  and Initiating Events +
Correspondence
SECY-93-087 +, SECY-90-016 +, SECY-93-143 +  and SECY-93-157 +
Docket
05000373  +  and 05000374  +
Equipment trip
Reactor Trip +
FR
58 FR 34067 +
From
Advisory Committee on Reactor Safeguards +  and Wilkins J +
Generic letter
NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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>.
ML20059C973 +, ML20059C973 +, ML20059C973 +, ML20059C973 +, ML20059C973 +, ML20059C973 +, ML20059C973 +, ML20059C973 +  and ML20059C973 +
Issue date
September 8, 1993  +
Manufacturer
General Electric +  and Westinghouse +
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08:04:49, 17 December 2024  +
NUREG
NUREG/CR-6075 +, NUREG/CR-1275 +  and NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +
Page count
42  +
SECY
SECY-93-087 +, SECY-90-016 +, SECY-93-143 +  and SECY-93-157 +
SSC
1E-5 +
Site
LaSalle +
Start date
September 8, 1993  +
State
Maryland +, Washington +, Virginia +  and Oregon +
System
Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +  and Decay Heat Removal +
TS
TS-3.2.2.1 +
Title
Summary of 400th ACRS Meeting on 930805-06 in Bethesda,Md Re Proposed Resolution of GSI 57, Effects of Fire Protection Sys Actuation on Safety-Related Equipment & Lessons Learned from LaSalle Fire & Report on ABWR Fire Safety Issues  +
To
Advisory Committee on Reactor Safeguards +
Topic
Safe Shutdown +, Fire Barrier +, Backfit +  and Control Room Habitability +
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http://pbadupws.nrc.gov/docs/ML2005/ML20059C973.pdf  +
Vendor
Vega +
 
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