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ML21294A126
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
Accession number
ML21294A126  +
Atomic Element
Nitrogen +, Hydrogen +  and Chlorine +
Correspondence
PLA-7935, 0 to Updated Final Safety Analysis Report, Section 10.3, Main Steam Supply System +
Docket
05000388  +  and 05000387  +
From
Susquehanna +  and Talen Energy +
General design criterion
GDC 2, Design bases for protection against natural phenomena +
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>.
ML21294A126 +, ML21294A126 +, ML21294A126 +, ML21294A126 +, ML21294A126 +, ML21294A126 +, ML21294A126 +, ML21294A126 +, ML21294A126 +  and ML21294A126 +
IEEE
IEEE 344 +  and IEEE 344-1975 +
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>.
02:24:24, 28 November 2024  +
NUREG
NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +
Page count
29  +
Power source
4kV +
Project stage
Request  +
Report
NEDE-25250 +
SSC
6A-2 +, P12A-2 +, P15B-1 +, P16A-2 +, E119A-2 +, J65B-1 +  and J65B-11 +
Site
Susquehanna +
Start date
October 12, 2021  +
System
Feedwater +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Remote shutdown +, Safety Relief Valve +, Control Rod +  and Main Steam +
Title
0 to Updated Final Safety Analysis Report, Questions 123  +
To
Office of Nuclear Reactor Regulation +
Topic
Loss of Offsite Power +, Excess Flow Check Valve +, Earthquake +  and Pressure boundary leak +
Training curricula
J-03B-1 +, J-05A-14 +, J-05B-1 +, J-59-1 +, J-65-1 +, J-65-4 +, J-69B-1 +, J-70-2 +, J-92-1 +, J-92-5 +, J-03B-14 +, J-59-10 +, J-70-1 +, J-038-1 +, J-038-14 +, J-058-1 +, J-658-11 +  and J-698-1 +
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http://pbadupws.nrc.gov/docs/ML2129/ML21294A126.pdf  +
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