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ML20111A248
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML20111A248  +
Act
Atomic Energy Act of 1954 +
Area
Switchyard +
Atomic Element
Uranium +, Carbon +, Hydrogen +, Thorium +  and Plutonium +
CFR
10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50 Appendix I +  and 10 CFR 50.71#e +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
RS-20-029, Technical Specification Bases +
Docket
05000373  +, 05000374  +, 07200070  +, 00373  +  and 00374  +
From
Exelon +
Fuel cladding
Zircaloy +
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>.
ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +, ML20111A248 +  and ML20111A248 +
Hours
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +
In package
ML20111A244 +
Isotope
Uranium-233 +
Issue date
April 13, 2020  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
06:20:53, 13 December 2024  +
NEI
NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +
Page count
50  +
Project stage
Request  +
RS
RS-20-029, Technical Specification Bases +
Regulatory Guide
Regulatory Guide 1.70 +  and Regulatory Guide 1.181 +
Site
LaSalle +
Site license
LaSalle +
Start date
April 13, 2020  +
State
Illinois +  and Washington +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, 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 +, Core Standby Cooling System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Electrohydraulic Control +, Rod Worth Minimizer +, Main Condenser +...
Title
4 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant  +
To
Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Incorporated by reference +, Abnormal operational transient +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Earthquake +, Fuel cladding +, Accidental discharge +, Power Uprate +, Measurement Uncertainty Recapture +  and Overspeed +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2011/ML20111A248.pdf  +
 
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