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SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per
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Category
Pages with broken file links, CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20207N030  +
Docket
05000322  +  and 00322  +
From
John Leonard +  and Long Island Lighting Company +
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>.
SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +, SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +  and SNRC-1299, Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per +
Issue date
January 9, 1987  +
Letter
05000322/LER-1986-042, :on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010 +
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>.
01:17:44, 7 December 2024  +
Page count
2  +
Project stage
Request  +
Site
Shoreham +
Start date
January 9, 1987  +
State
Washington +
System
Feedwater +, Main Steam Isolation Valve +  and Remote shutdown +
Title
Discusses Bounding Thermal Hydraulic Analysis Performed to Determine Amount of Time Taken for Reactor Water Level to Reach Top of Active Fuel If Control Room Fire Causes Loss of Feedwater,Per  +
To
Office of Nuclear Reactor Regulation +  and Harold Denton +
Topic
Safe Shutdown +
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.
http://pbadupws.nrc.gov/docs/ML2020/ML20207N030.pdf  +
 
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