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ML24109A106
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI/ANS-58.2 +  and ANSI/ANS-58.2-1980 +
ASME section
ASME Section I +
Accession number
ML24109A106  +
Atomic Element
Zinc +  and Hydrogen +
CFR
10 CFR 50 Appendix A +
Cornerstone
Mitigating Systems +
Correspondence
ND-100482 +  and ND-100483 +
Docket
05000263  +  and 00263  +
Engineering change
EC-24933 +
From
Xcel Energy +  and Minnesota +
GE SIL
SIL 331 +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +  and NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +
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ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +, ML24109A106 +  and ML24109A106 +
In package
ML24109A128 +
Issue date
April 17, 2024  +
Letter
ML20024G660 +, ML20202H675 +  and ML20024G182 +
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>.
23:37:24, 24 November 2024  +
ND
ND-100482 +  and ND-100483 +
NRC LIC
LIC-100 +
NUREG
NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
Page count
1  +
Power source
4kV +
Procedure
SP +
Project reference
TAC:61788 +  and TAC:MD9990 +
Project stage
Request  +
SSC
C4A-16-GB +, C4B-16-GB +, C8A-1 +, C8B-1 +, V72B-1 +, C4A-1 +  and C4B-1 +
Site
Monticello +
Start date
April 17, 2024  +
System
Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Stator Water Cooling +, Standby Liquid Control +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +
Title
1 to the Updated Safety Analysis Report, Appendix I, Evaluation of High Energy Line Breaks Outside Containment  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Ultimate heat sink +, High Energy Line Break +, Feedwater Heater +, Scram Discharge Volume +, Excess Flow Check Valve +  and Power Uprate +
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/ML2410/ML24109A106.pdf  +
 
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