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ML24240A362
Show incoming properties 
Category
Inservice/Preservice Inspection and Test Report
Accession number
ML24240A362  +
Atomic Element
Nitrogen +  and Lead +
CFR
10 CFR 100 +, 10 CFR 50.55a +  and 10 CFR 50.55a#b3iiD +
Correspondence
NRC-24-0049, Inservice Testing Program for Pumps and Valves, Part 11: 1st Program Valve Basis, Revision 2 +
Docket
05000341  +
From
DTE Energy +
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>.
ML24240A362 +, ML24240A362 +, ML24240A362 +, ML24240A362 +, ML24240A362 +, ML24240A362 +, ML24240A362 +, ML24240A362 +, ML24240A362 +  and ML24240A362 +
In package
ML24240A352 +
Issue date
February 3, 2021  +
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>.
18:13:19, 24 November 2024  +
NRC
NRC-24-0049, Inservice Testing Program for Pumps and Valves, Part 11: 1st Program Valve Basis, Revision 2 +
NUREG
NUREG-0677 +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
1  +
Project stage
Request  +
Site
Fermi +
Start date
February 3, 2021  +
System
Feedwater +, Service water +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Decay Heat Removal +  and Main Steam +
Title
Inservice Testing Program for Pumps and Valves, Part 9: IST Program Refueling Outage Justifications, Revision 4  +
To
Office of Nuclear Reactor Regulation +
Topic
Stroke time +, Time to boil +  and Stress corrosion cracking +
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http://pbadupws.nrc.gov/docs/ML2424/ML24240A362.pdf  +
 
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