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ML20211F102
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20211F102  +
Atomic Element
Lead +
Cornerstone
Initiating Events +
From
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +  and Thadani A +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
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>.
ML20211F102 +, ML20211F102 +, ML20211F102 +, ML20211F102 +, ML20211F102 +, ML20211F102 +  and ML20211F102 +
IEEE
IEEE 279 +
Issue date
July 16, 1999  +
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>.
04:35:09, 6 December 2024  +
NUREG
NUREG/CR-4550 +, NUREG/CR-4627 +, NUREG/CR-2800 +, NUREG/CR-4792 +, NUREG/CR-6395 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
17  +
Procedure
CP +
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ML20211F102 +
Regulatory Guide
Regulatory Guide 1.75 +  and Regulatory Guide 1.46 +
Start date
July 16, 1999  +
State
Washington +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Control Rod +  and Main Steam +
Title
Informs That Memo Approves Res/Dsar Taking Appropriate Actions,Within Current Resource Allocations,To Resolve Generic Safety Issue 156.6.1, Pipe Break Effects on Systems & Components Inside Containment  +
To
Rossi C +  and NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +
Topic
Internal Flooding +, Failure to Scram +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2021/ML20211F102.pdf  +
 
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