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05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event
Show incoming properties 
Category
Letter, Licensee Event Report (LER)  and Licensee Event Report
Accession number
ML093130070  +
Atomic Element
Tin +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.73 +  and 10 CFR 50.73#a2vA +
Docket
05000259  +, 05000260  +, 05000296  +, 00259  +, 00260  +  and 00296  +
From
West R +  and Tennessee Valley Authority +
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>.
05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +, 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +  and 05000259/LER-2009-005-01, Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event +
Issue date
November 3, 2009  +
LER number
5  +
LER year
2,009  +
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>.
13:22:59, 14 January 2025  +
NRC form
NRC Form 366, Licensee Event Report +  and NRC Form 366A +
Page count
9  +
Power source
4kV +
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)(ii)(A), Seriously Degraded +, 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) +
Site
Browns Ferry +
Site license
Browns Ferry +
Start date
November 3, 2009  +
State
Tennessee +, Washington +  and Alabama +
System
Primary containment +, Core Spray +  and Residual Heat Removal +
Title
Regarding Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event  +
To
Document Control Desk +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Reactor Vessel Water Level +  and Fuel cladding +
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::2592009005R01.pdf  +  and http://pbadupws.nrc.gov/docs/ML0931/ML093130070.pdf  +
 
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