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ML18052A438
Show incoming properties
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML18052A438  +
Atomic Element
Boron +, Hydrogen +  and Gold +
Correspondence
NRC 860317 +  and L 65 +
Docket
05000255  +  and 00255  +
Equipment trip
Reactor Trip +
From
Consumers Energy +  and Berry K +
Generic letter
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +
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>.
ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +, ML18052A438 +  and ML18052A438 +
Issue date
May 19, 1986  +
L
L 65 +
Letter
05000255/LER-1986-016, :on 860310,LPSI Pump P-67B Inadvertently Started.Caused by Closing Corresponding Pair of Contacts on DBA Sequencer During Cleaning Procedure.New Tool Used During Cleaning.Incident Discussed W/Personnel +, 05000255/LER-1985-008, :on 850723,plant Shutdown Occurred Due to Inoperable Control Room Emergency Air Cleanup Sys.Caused by Removal of Exhaust Fan Ducting Leading to Unisolable Path to External Environ.Drawings Review Planned +  and ML18052A343 +
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14:45:23, 6 January 2025  +
NRC
NRC 860317 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
31  +
Procedure
ES +  and ST +
Project stage
Request  +
Site
Palisades +
Start date
May 19, 1986  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Shutdown Cooling +, Safety Parameter Display System +, Critical Function Monitoring System +  and Main Steam +
Title
Forwards Response to NRC 860317 Request for Addl Info Re Spds,Including Range of Displayed Neutron Flux,Reactor Vessel Level,Radiation Monitoring of Isolated Steam Generator,Per Generic Ltr 82-33 & Suppl 1 to NUREG-0737  +
To
Office of Nuclear Reactor Regulation +
Topic
Reactor Vessel Water Level +, Main Steam Line Radiation Monitor +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML1805/ML18052A438.pdf  +
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