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ML14010A310
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI N45.2.9 +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML14010A310  +
Atomic Element
Nitrogen +, Carbon +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 Appendix B +  and 10 CFR 61 +
Correspondence
GO2-13-174, Final Safety Analysis Report, Amendment 62, Appendix J - Shielding Evaluation Report +
Docket
05000397  +
Equipment trip
Turbine Trip +
From
Energy Northwest +
GO2
GO2-13-174, Final Safety Analysis Report, Amendment 62, Appendix J - Shielding Evaluation Report +
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>.
ML14010A310 +, ML14010A310 +, ML14010A310 +, ML14010A310 +, ML14010A310 +, ML14010A310 +, ML14010A310 +, ML14010A310 +  and ML14010A310 +
In package
ML14010A476 +
Isotope
Krypton-85 +
Issue date
December 30, 2013  +
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>.
04:58:28, 11 January 2025  +
Page count
160  +
Power source
24V +
Procedure
SP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.58 +, Regulatory Guide 1.68 +, Regulatory Guide 1.20 +, Regulatory Guide 1.88 +  and Regulatory Guide 1.68.1 +
Site
Columbia +
Start date
December 30, 2013  +
System
Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, 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 +, Spray Pond +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Rod Worth Minimizer +, Rod Sequence Control System +...
Test
Bench test +
Title
Final Safety Analysis Report, Amendment 62, Chapter 14 - Initial Test Program  +
To
Office of Nuclear Reactor Regulation +
Topic
Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Stroke time +, Hydrostatic +, Emergency Lighting +, Feedwater Heater +, Process Control Program +, Integrated leak rate test +, Power change +  and Overspeed trip +
Turbine component
Turbine bypass valve +  and Main Turbine Control Valve +
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http://pbadupws.nrc.gov/docs/ML1401/ML14010A310.pdf  +
 
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