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ML19137A163
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML19137A163  +
Atomic Element
Lead +  and Sodium +
CFR
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 50.62 +, 10 CFR 100 Appendix A +  and 10 CFR 50.49#b1 +
Cornerstone
Barrier Integrity +
Docket
05000298  +
Equipment trip
Turbine Trip +
From
Nebraska Public Power District +
General design criterion
GDC 26, Reactivity control system redundancy and capability +
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>.
ML19137A163 +, ML19137A163 +, ML19137A163 +, ML19137A163 +, ML19137A163 +, ML19137A163 +, ML19137A163 +, ML19137A163 +, ML19137A163 +  and ML19137A163 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +
In package
ML19137A206 +
Issue date
April 24, 2019  +
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>.
07:26:01, 5 January 2025  +
Page count
61  +
Project stage
Request  +
Scram
Manual Scram +  and Automatic Scram +
Site
Cooper +
Start date
April 24, 2019  +
System
Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Control Room Emergency Filtration System +, Standby Liquid Control +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Control rod blade +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.7.6 +, TS-3.4.1 +  and TS-3.9.6 +
Title
Rev. 29 to Updated Safety Analysis Report, Appendix G, Nuclear Safety Operational Analysis  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Ultimate heat sink +, Abnormal operational transient +, Feedwater Controller Failure +, Loss of Offsite Power +, Fuel cladding +, Coast down +, Overexposure +  and Loss of condenser vacuum +
Trip
Turbine Control Valve Fast Closure +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML1913/ML19137A163.pdf  +
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