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05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System
Show incoming properties 
Category
Letter, Licensee Event Report (LER)  and Licensee Event Report
Accession number
ML101800151  +
CFR
10 CFR 50.73#a2ivA +, 10 CFR 50.72#b2ivB +  and 10 CFR 50.72#b3ivA +
Correspondence
PLA-6626 +
Docket
05000387  +  and 00387  +
ENS
ENS 45866 +  and ENS 45930 +
Equipment trip
Turbine Trip +
From
Rausch T +  and Susquehanna +
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>.
05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +, 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +  and 05000387/LER-2010-002, For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System +
Hours
0.0122 d (0.292 hours, 0.00174 weeks, 3.999055e-4 months)  +, 0.0266 d (0.639 hours, 0.0038 weeks, 8.755305e-4 months)  +  and 0.0141 d (0.338 hours, 0.00201 weeks, 4.630685e-4 months)  +
Issue date
June 21, 2010  +
LER number
2  +
LER year
2,010  +
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>.
09:22:29, 14 January 2025  +
NRC form
NRC Form 366, Licensee Event Report +  and NRC Form 366A +
NUREG
NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +
Page count
8  +
Project stage
Request  +
Reporting criterion
10 CFR 50.73(a)(2)(iv)(A), System Actuation +, 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition +, 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor +, 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat +, 10 CFR 50.73(a)(2)(v), Loss of Safety Function +, 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability +, 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications +, 10 CFR 50.73(a)(2)(i) +, 10 CFR 50.73(a)(2)(x) +, 10 CFR 50.73(a)(2)(iii) +, 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown +, 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System +, 10 CFR 50.73(a)(2)(viii)(A) +  and 10 CFR 50.73(a)(2)(viii)(B) +
Scram
Automatic Scram +
Site
Susquehanna +
Site license
Susquehanna +
Start date
June 21, 2010  +
State
Washington +
System
Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, Safety Relief Valve +  and Control Rod +
Title
For Susquehanna Steam Electric Station, Regarding Automatic Reactor Scrams Occur During Post-Modification Testing of the Digital Feedwater Integrated Control System  +
To
Document Control Desk +  and Office of Nuclear Reactor Regulation +
Topic
Power Uprate +
Turbine component
Turbine bypass valve +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
https://lersearch.inl.gov/Index.aspx?Page=PDFView?Doc::3872010002R00.pdf  +  and http://pbadupws.nrc.gov/docs/ML1018/ML101800151.pdf  +
 
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