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ML22365A019
Show incoming properties 
Category
Letter, Report  and Technical
ANSI code
ANSI N14.6 +
ASME section
ASME Section III +
Accession number
ML22365A019  +
Atomic Element
Boron +, Nitrogen +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 Appendix J +, 10 CFR 52 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50 Appendix I +, 10 CFR 50.55a +  and 10 CFR 50.34#f2vii +
Cornerstone
Physical Protection +
Docket
05200050  +  and 99902078  +
Document
ML20055E565 +, ML22325A349 +, ML22145A460 +  and ML22305A518 +
Equipment trip
Reactor Trip +
From
NuScale +  and Fosaaen C +
General design criterion
GDC 61 +, GDC 23 +, GDC 52 +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +
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>.
ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +, ML22365A019 +  and ML22365A019 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
IEEE
IEEE 384 +, IEEE 603-1991 +, IEEE 603 +, IEEE 323-2003 +, IEEE 497 +, IEEE 829 +, IEEE 572 +  and IEEE 344-2013 +
Issue date
December 31, 2022  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
00:24:37, 3 January 2025  +
NEI
NEI 00-01, Guidance for Post Fire Safe Shutdown Circuit Analysis +
NFPA
NFPA 804 +
Page count
1  +
Person
Michael Dudek +, Brian Smith +, David Drucker +  and Getachew Tesfaye +
Procedure
RT-1 +
Project stage
Other  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.189 +, Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.45 +, Regulatory Guide 1.143 +, Regulatory Guide 8.8 +, Regulatory Guide 1.29 +, Regulatory Guide 1.197 +, Regulatory Guide 4.21 +, Regulatory Guide 1.152 +  and Regulatory Guide 1.209 +
SR
SR-3.0.1 +
SSC
07-52-050 +
Scram
Manual Scram +  and Automatic Scram +
Site
99902078 +  and 05200050 +
Start date
December 31, 2022  +
State
Oregon +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, HVAC +, Reactor Pressure Vessel +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +  and Main Steam +
Title
LLC Submittal of the NuScale Standard Design Approval Application - Part 8, License Conditions; Inspections, Tests, Analyses, and Acceptance Criteria, Revision 0  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Boric Acid +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Anticipated operational occurrence +, Commercial Grade Dedication +, Safe Shutdown Earthquake +, Internal Flooding +, Nondestructive Examination +, Emergency Lighting +, Incorporated by reference +, Pressure Boundary Leakage +, Fire Protection Program +, Control Room Habitability +  and Pre-application +
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http://pbadupws.nrc.gov/docs/ML2236/ML22365A019.pdf  +
 
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