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ML20040F224
Show incoming properties 
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20040F224  +
Area
Switchyard +
Atomic Element
Iron +, Carbon +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix E +
Committee
Advisory Committee on Reactor Safeguards +
Cornerstone
Emergency Preparedness +
Docket
05000483  +
Equipment trip
Reactor Trip +
FR
46 FR 47903 +
From
Advisory Committee on Reactor Safeguards +
General design criterion
GDC 19, Control room +
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>.
ML20040F224 +, ML20040F224 +, ML20040F224 +, ML20040F224 +, ML20040F224 +, ML20040F224 +, ML20040F224 +  and ML20040F224 +
Hours
0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +
Issue date
January 9, 1982  +
Manufacturer
Westinghouse +
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>.
02:17:29, 20 December 2024  +
NUREG
NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, 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 +  and NUREG-0830, Advises That Condition 2.c.(3)(a) of License NPF-30 Fulfilled,Based on & 860117 Rept Re Environ Qualification Program for Electrical Equipment.Program Previously Accepted Per NUREG-0830,Section 3.11 +
Page count
25  +
Procedure
CP +
Project stage
Meeting  +
SSC
K0MV-TV +
Site
Callaway +
Start date
January 9, 1982  +
State
Arizona +, Illinois +, Washington +  and Missouri +
System
Steam Generator +, Service water +, Emergency Diesel Generator +, Safety Parameter Display System +, Reactor Pressure Vessel +, Remote shutdown +  and Decay Heat Removal +
Title
Certified Minutes of ACRS Subcommittee on Callaway Unit 1 811104-05 Public Meeting in Columbia,Mo Re Review of Util OL Application.Tentative Schedule Encl  +
To
Advisory Committee on Reactor Safeguards +
Topic
Safe Shutdown Earthquake +, Internal Flooding +, Operating Basis Earthquake +, Shift Technical Advisor +, Loss of Offsite Power +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2004/ML20040F224.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
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