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ML18026A331
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML18026A331  +
Atomic Element
Nitrogen +, Hydrogen +  and Chlorine +
Docket
05000387  +, 05000388  +, 00387  +  and 00388  +
From
Curtis N +  and Pennsylvania Power and Light Company +
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>.
ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +, ML18026A331 +  and ML18026A331 +
IEEE
IEEE 344-1975 +
Issue date
March 17, 1981  +
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>.
08:48:48, 7 January 2025  +
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-24788 +  and NEDE-25250 +
SSC
17A-1 +, 10A-1 +, 03B-14 +, P12A-2 +, P15B-1 +, P16A-2 +  and 16A-3 +
Site
Susquehanna +
Start date
March 17, 1981  +
State
Pennsylvania +  and Washington +
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
Forwards Responses to Questions 123.1 - 123.9 Per 810202 Request for Addl Info.Info Will Be Incorporated Into Next Revision of Facility FSAR  +
To
Youngblood B +  and 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-65B-11 +, J-69B-1 +, J-70-2 +, J-92-5 +, J-65B-1 +  and J-69-1 +
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http://pbadupws.nrc.gov/docs/ML1802/ML18026A331.pdf  +
 
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