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ML20054B728
Show incoming properties 
Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20054B728  +
Atomic Element
Lead +
Docket
05000382  +  and 00382  +
Equipment trip
Reactor Trip +
From
Hanauer S +  and Office of Nuclear Reactor Regulation +
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>.
ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +, ML20054B728 +  and ML20054B728 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
In package
ML20054B726 +
Issue date
April 2, 1982  +
Manufacturer
Westinghouse +
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>.
00:03:53, 18 December 2024  +
NUREG
NUREG-0691 +, NUREG/CR-2322 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG/CR-1205, Lists LERs Re HPCI & RCIC Sys Failures,Not Included in NUREG/CR-1205 on LERs Related to Pumps.Probabilistic Analysis Branch Should Correct Classification Deficiencies +  and NUREG/CR-2497, Forwards Draft Abstract of NUREG/CR-2497, Precursors to Potential Severe Core Damage Accidents:1969-79. Comments Requested by 820220 +
Page count
19  +
Procedure
RT +
Project stage
Request  +
SSC
7x10-5 +  and 6x10-6 +
Site
Waterford +
Start date
April 2, 1982  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +  and Decay Heat Removal +
Title
Forwards Assessment of Feed & Bleed Issue for CE Applicants, Per Request.Immediate Action Not Needed  +
To
Mattson R +  and Office of Nuclear Reactor Regulation +
Topic
Loss of condenser vacuum +  and Loss of Offsite Power +
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http://pbadupws.nrc.gov/docs/ML2005/ML20054B728.pdf  +
 
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