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ML23291A422
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML23291A422  +
Atomic Element
Boron +, Uranium +, Nitrogen +, Lead +, Neptunium +  and Plutonium +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix B +  and 10 CFR 2.390 +
Correspondence
PLA-8081, 1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.21 +
Docket
05000387  +  and 05000388  +
Engineering change
EC-964987 +  and EC-935947 +
Equipment trip
Reactor Trip +
From
Susquehanna +
General design criterion
GDC 24 +  and GDC 13 +
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>.
ML23291A422 +, ML23291A422 +, ML23291A422 +, ML23291A422 +, ML23291A422 +, ML23291A422 +, ML23291A422 +, ML23291A422 +, ML23291A422 +  and ML23291A422 +
IEEE
IEEE 279 +  and IEEE 279-1971 +
In package
ML23291A105 +
Issue date
October 12, 2023  +
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>.
13:14:54, 25 November 2024  +
Page count
100  +
Procedure
CP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.56 +
Report
NEDC-31336 +, NEDE-24011 +  and NEDO-10466 +
Scram
Manual Scram +
Site
Susquehanna +
Start date
October 12, 2023  +
System
Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Permanent Magnet Generator +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Rod Worth Minimizer +, Rod Sequence Control System +, Control rod blade +, Main Condenser +, Control Rod +  and Main Steam +
Title
1 to Updated Final Safety Analysis Report, Chapter 7, Section 7.7, Controls Systems Not Required for Safety  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Anticipated operational occurrence +, Operator Manual Action +, Squib +, Feedwater Heater +, Scram Discharge Volume +, Loss of Offsite Power +, Overtravel +, Earthquake +, Pressure Boundary Leakage +, Power change +, Coast down +  and Overspeed +
Trip
Turbine Control Valve Fast Closure +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML2329/ML23291A422.pdf  +
 
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