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05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated
Show incoming properties 
Category
LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT  and Licensee Event Report
Accession number
ML20070F695  +
Atomic Element
Nitrogen +, Oxygen +  and Hydrogen +
CFR
10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.73#a2iiB +
Control panel
09-4 +
Correspondence
JAFP-94-0343 +  and JAFP-94-343 +
Docket
05000333  +  and 00333  +
From
Power Authority of the State of New York +, Harry Salmon +  and Holliday D +
General design criterion
GDC 56 +
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>.
05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +, 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +  and 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +
Issue date
July 9, 1994  +
JAFP
JAFP-94-0343 +  and JAFP-94-343 +
LER number
4  +
LER year
1,994  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
14:43:02, 16 December 2024  +
NRC form
NRC Form 366A +, NRC Form 366, Licensee Event Report +  and NRC Form 3664 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +
Page count
8  +
Procedure
ES +
Regulatory Guide
Regulatory Guide 1.97 +
Reporting criterion
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition +, 10 CFR 50.73(a)(2)(v), Loss of Safety Function +, 10 CFR 50.73(a)(2)(iv), System Actuation +, 10 CFR 50.73(a)(2)(x) +, 10 CFR 50.73(a)(2) +  and 10 CFR 50.73(a)(2)(1) +
SSC
16A-K60 +, 31I0-0104 +  and 16A-K59 +
Site
FitzPatrick +
Start date
July 9, 1994  +
State
New York +  and Washington +
System
Primary containment +  and Secondary containment +
TS
TS-3.7.D +
Title
:on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated   +
Title:
On 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated +
To
Office of Information Resources Management +
Topic
Grab sample +  and Integrated leak rate test +
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::3331994004R01.pdf  +  and http://pbadupws.nrc.gov/docs/ML2007/ML20070F695.pdf  +
 
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