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ML18017A426
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI/ANS-58.2 +  and ANSI/ANS-58.2-1980 +
AR
AR 01131913 +
ASME section
ASME Section I +
Accession number
ML18017A426  +
Atomic Element
Hydrogen +, Lead +  and Zinc +
CFR
10 CFR 50 Appendix A +
Correspondence
ND-100482 +  and ND-100483 +
Docket
05000263  +  and 00263  +
Engineering change
EC-24933 +
Equipment trip
Turbine Trip +
From
Xcel Energy +
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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ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +, ML18017A426 +  and ML18017A426 +
Hours
9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +
In package
ML18017A380 +
Issue date
January 11, 2018  +
Letter
ML20024G660 +
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>.
10:46:32, 7 January 2025  +
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
79  +
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
January 11, 2018  +
State
Minnesota +
System
Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, 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 +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +
Title
5 to Updated Safety Analysis Report, Appendix I, Evaluation of High Energy Line Breaks Outside Containment  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, High Energy Line Break +, Feedwater Heater +, Scram Discharge Volume +, Loss of Offsite Power +, Excess Flow Check Valve +, Fuel cladding +  and Power Uprate +
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http://pbadupws.nrc.gov/docs/ML1801/ML18017A426.pdf  +
 
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