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ML21294A196
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +
Accession number
ML21294A196  +
Atomic Element
Nickel +, Copper +, Carbon +, Oxygen +, Hydrogen +, Lead +  and Mercury +
CFR
10 CFR 50.55a +  and 10 CFR 2.390 +
Correspondence
PLA-7935, 0 to Updated Final Safety Analysis Report, Section 10.3, Main Steam Supply System +  and PLA-3311 +
Docket
05000388  +  and 05000387  +
Equipment trip
Turbine Trip +
From
Susquehanna +  and Talen Energy +
General design criterion
GDC 5, Sharing of structures, systems, and components +
Generic letter
NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML21294A196 +, ML21294A196 +, ML21294A196 +, ML21294A196 +, ML21294A196 +, ML21294A196 +, ML21294A196 +, ML21294A196 +, ML21294A196 +  and ML21294A196 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML21294A245 +
Issue date
October 12, 2021  +
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>.
02:22:30, 28 November 2024  +
Page count
68  +
Project stage
Request  +
Report
NEDO-32686 +
Site
Susquehanna +
Start date
October 12, 2021  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Remote shutdown +, Core Standby Cooling System +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +
Title
0 to Updated Final Safety Analysis Report, Section 5.4, Component and Subsystem Design  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +, Grab sample +, Safe Shutdown Earthquake +, Hydrostatic +, Abnormal operational transient +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Liquid penetrant +, Overspeed trip +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML2129/ML21294A196.pdf  +
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