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ML25099A263
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI/ANS 6.4-2006 +, ANSI 42.18-2004 +  and ANSI/ANS 6.1.1-1977 +
ASME section
ASME Section XI +
Accession number
ML25099A263  +
Atomic Element
Boron +, Iodine +, Cobalt +, Nickel +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Lead +, Lithium +  and Beryllium +
CFR
10 CFR 20 +, 10 CFR 20 Appendix B +, 10 CFR 2.390 +, 10 CFR 20.1003 +, 10 CFR 20.1201 +, 10 CFR 20.1202 +, 10 CFR 20.1203 +, 10 CFR 20.1204 +, 10 CFR 20.1301 +, 10 CFR 20.1406 +  and 10 CFR 20.1501 +
Docket
05200050  +
Emergency Facility
Technical Support Center +
From
NuScale +
General design criterion
GDC 61 +, GDC 30 +, GDC 63 +  and GDC 4, Environmental and dynamic effects design bases +
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>.
ML25099A263 +, ML25099A263 +, ML25099A263 +, ML25099A263 +, ML25099A263 +, ML25099A263 +, ML25099A263 +, ML25099A263 +  and ML25099A263 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +
IEEE
IEEE 497 +
In package
ML25099A236 +
Isotope
Tritium +, Co-60 +, Cs-137 +, U-235 +, Sr-90 +, Fe-55 +, Y-90 +, Co-57 +, Ni-63 +, Kr-85 +  and I-131 +
Issue date
April 9, 2025  +
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>.
23:34:42, 8 May 2025  +
NUREG
NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +
Page count
1  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.143 +, Regulatory Guide 8.38 +, Regulatory Guide 1.8 +, Regulatory Guide 8.25 +, Regulatory Guide 8.8 +, Regulatory Guide 8.10 +, Regulatory Guide 1.12 +, Regulatory Guide 4.21 +  and Regulatory Guide 1.140 +
SSC
1E-10 +, 1E-6 +, 1E-5 +, 1E-4 +, 1E-7 +, 3E-7 +, 5E-12 +, 1E-05 +, 5E-8 +, 1E-2 +  and 1E-1 +
Site
05200050 +
Start date
April 9, 2025  +
State
Washington +  and New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Emergency Response Data System +, HVAC +, Reactor Pressure Vessel +, Decay Heat Removal +, Control Room Envelope +  and Control Rod +
Title
LLC - Part 2, Chapter 12, Radiation Protection, Revision 2  +
To
Office of Nuclear Reactor Regulation +
Topic
Loop seal +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Anticipated operational occurrence +, Coatings +, Emergency Lighting +, Fuel cladding +, Control Room Habitability +  and Spent fuel rack +
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/ML2509/ML25099A263.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
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