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ML24128A101
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +
Accession number
ML24128A101  +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Uranium +, Nitrogen +, Oxygen +, Hydrogen +, Xenon +, Chlorine +  and Lead +
CFR
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.2 +, 10 CFR 2.390 +  and 10 CFR 50.71#e4 +
Docket
05000282  +  and 05000306  +
Emergency Facility
Technical Support Center +
Engineering change
EC-15220 +, EC-12653 +, EC-12518 +, EC-18326 +  and EC-17242 +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Xcel Energy +  and Minnesota +
General design criterion
GDC 33 +, GDC 18 +, GDC 11 +, GDC 37 +, GDC 27 +, GDC 32 +, GDC 36 +, GDC 70 +, GDC 65 +, GDC 1, Quality standards and records +  and GDC 5, Sharing of structures, systems, and components +
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ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +, ML24128A101 +  and ML24128A101 +
Hours
3.009259e-4 d (0.00722 hours, 4.298942e-5 weeks, 9.893e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
IEEE
IEEE 279 +
In package
ML24128A092 +
Issue date
April 30, 2024  +
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>.
20:55:04, 2 January 2025  +
Page count
1  +
Power source
345kV +
Procedure
AM +, ES +  and SP +
Project stage
Request  +
SSC
10-2MS-18 +
Scram
Manual Scram +
Site
Prairie Island +
Site license
Wolf Creek +  and Prairie Island +
Start date
April 30, 2024  +
State
Minnesota +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Shield Building +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
Title
Updated Safety Analysis Report (Usar), Revision 38, Section 1, Introduction and Summary Description, Redacted  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Loop seal +, Operating Basis Earthquake +, FLEX +, Surveillance Frequency Control Program +, Design basis earthquake +, Feedwater Heater +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Fire Protection Program +  and Power change +
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http://pbadupws.nrc.gov/docs/ML2412/ML24128A101.pdf  +
Ultimate Heat Sink
Cooling Tower +  and Mississippi River +
 
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