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ML20137B162
Show incoming properties 
Category
LEGAL TRANSCRIPTS & ORDERS & PLEADINGS, TRANSCRIPTS, DEPOSITIONS  and NARRATIVE TESTIMONY
Accession number
ML20137B162  +
Atomic Element
Carbon +  and Lead +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
L 5410 06 +
Equipment trip
Reactor Trip +
From
Advisory Committee on Reactor Safeguards +
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>.
ML20137B162 +, ML20137B162 +, ML20137B162 +, ML20137B162 +, ML20137B162 +, ML20137B162 +  and ML20137B162 +
Issue date
January 10, 1986  +
L
L 5410 06 +
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>.
05:20:37, 12 December 2024  +
NUREG
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 +  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
174  +
Person
Bill Russell +  and Harold Denton +
Procedure
MP +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20137B162 +
SSC
2E-ll +, 80G-336-66 +, 80C-36-6646 +  and 7mo-Pu +
Start date
January 10, 1986  +
State
Tennessee +, Washington +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Reactor Pressure Vessel +, Decay Heat Removal +  and Main Steam +
Title
Transcript of ACRS 309th General Meeting on 860110 in Washington,Dc.Pp 1-146.Supporting Documentation Encl  +
Topic
Shift Technical Advisor +, Backfit +, Overspeed trip +, Overspeed +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML2013/ML20137B162.pdf  +
 
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