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ML22111A212
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +
Accession number
ML22111A212  +
Area
Switchyard +
Atomic Element
Boron +, Nitrogen +, Carbon +, Hydrogen +, Chlorine +  and Lead +
CFR
10 CFR 50 Appendix J +  and 10 CFR 20 +
Correspondence
RS-22-048, 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls) +
Docket
05000461  +
Emergency Facility
Emergency Operations Facility +
Equipment trip
Turbine Trip +
From
Constellation +
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>.
ML22111A212 +, ML22111A212 +, ML22111A212 +, ML22111A212 +, ML22111A212 +, ML22111A212 +, ML22111A212 +, ML22111A212 +, ML22111A212 +  and ML22111A212 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +
In package
ML22111A226 +
Issue date
March 31, 2022  +
Manufacturer
General Electric +
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>.
07:50:28, 7 February 2025  +
Page count
160  +
Power source
345kV +
Procedure
ST +, SP +  and CP +
Project stage
Request  +
RS
RS-22-048, 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls) +
Regulatory Guide
Regulatory Guide 1.108 +, Regulatory Guide 1.8 +  and Regulatory Guide 1.20 +
Report
NEDC-32975P +
SSC
1E51-C002F +
Scram
Manual Scram +
Site
Clinton +
Start date
March 31, 2022  +
State
Illinois +
System
Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +, Steam Jet Air Ejector +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Main Condenser +, Control Rod +...
Test
Bench test +
Title
2 to Updated Safety Analysis Report, Chapter 14, Initial Test Program  +
To
Office of Nuclear Reactor Regulation +
Topic
Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Stroke time +, Hydrostatic +, Emergency Lighting +, Feedwater Heater +, Scram Discharge Volume +, Shift Technical Advisor +, Loss of Offsite Power +, Excess Flow Check Valve +, Power change +, Flow Induced Vibration +  and Overspeed +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2211/ML22111A212.pdf  +
 
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