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ML063250258
Show incoming properties 
Category
Letter, Report  and Technical
Accession number
ML063250258  +
Atomic Element
Boron +, Oxygen +  and Lead +
BWROG
BWROG-06036 +
Correspondence
TSTF-06-13 +
Docket
05000352  +, 05000353  +  and PROJ0691  +
Equipment trip
Reactor Trip +
From
Boiling Water Reactor Owners Group +  and Bunt R +
GE SIL
SIL 139 +  and SIL 148 +
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>.
ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +, ML063250258 +  and ML063250258 +
Issue date
November 16, 2006  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +
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>.
10:01:28, 15 January 2025  +
NUREG
NUREG-0479 +  and NUREG/CR-5500, Discusses Issuance of Final Rept, Reliability Study Auxiliary Emergency Feedwater System 1987-1995, (NUREG/CR-5500,Vol 1).Summary of Comment Resolutions Encl +
Page count
16  +
Person
Michelle Honcharik +
Project stage
Response to RAI  +
Site
Limerick +  and Boiling Water Reactor Owners Group +
Start date
November 16, 2006  +
State
Washington +
System
Reactor Protection System +  and Control Rod +
TSTF
TSTF-475 +
TSTF letter
TSTF-06-13 +
Title
Response to NRC Request for Additional Information Regarding TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Dated March 21, 2005  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Probabilistic Risk Assessment +, Intergranular Stress Corrosion Cracking +  and Stress corrosion cracking +
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http://pbadupws.nrc.gov/docs/ML0632/ML063250258.pdf  +
 
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