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ML20128D207
Show incoming properties
Category
MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
Accession number
ML20128D207  +
Atomic Element
Hydrogen +
CFR
10 CFR 50.55#e +  and 10 CFR 100 Appendix A +
Committee
Advisory Committee on Reactor Safeguards +
Cross cutting aspect
P.3(c) +
Docket
05000458  +
Emergency Facility
Technical Support Center +
Equipment trip
Turbine Trip +
FR
48 FR 44291 +
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>.
ML20128D207 +, ML20128D207 +, ML20128D207 +, ML20128D207 +, ML20128D207 +, ML20128D207 +, ML20128D207 +  and ML20128D207 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +
IEEE
IEEE 323-1974 +  and IEEE 323-1975 +
Issue date
July 17, 1984  +
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19:26:42, 12 December 2024  +
NUREG
NUREG/CR-2100 +, 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 +, NUREG-0978, Informs That CRGR Meeting 44 on 830803 Rescheduled for 830810 in Bethesda,Md.Proposed NUREG-0978 Re Generic Issue B-10, Behavior of BWR Mark III Containments, Will Be Discussed +, NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +, NUREG-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +  and NUREG-1070, 07-18-84 ACRS Report on NUREG-1070, NRC Policy on Future Reactor Designs - Decisions on Severe Accident Issues +
Page count
28  +
Procedure
AM +
Project stage
Meeting  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.60 +
SSC
G5R-15 +
Site
River Bend +
Start date
July 17, 1984  +
State
Texas +, Washington +, Louisiana +  and Mississippi +
System
Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Standby Gas Treatment System +, Shield Building +, Remote shutdown +, Decay Heat Removal +  and Containment Spray +
Title
Summary of ACRS Subcommittee on River Bend 840607-08 Meetings W/Research Group in Baton Rouge,La Re OL Application  +
To
Advisory Committee on Reactor Safeguards +
Topic
Safe Shutdown +, Ultimate heat sink +, Hydrostatic +, Emergency Lighting +, Scram Discharge Volume +, Loss of Offsite Power +, Earthquake +, Siren +  and Water hammer +
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/ML2012/ML20128D207.pdf  +
Ultimate Heat Sink
Cooling Tower +  and Mississippi River +
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