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ML20137K702
Show incoming properties
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20137K702  +
Atomic Element
Lead +
Correspondence
NRC 85-261 +
Docket
05000482  +  and 00482  +
Equipment trip
Reactor Trip +
From
KANSAS GAS & ELECTRIC CO. +  and Koester G +
Generic letter
NRC Generic Letter 85-12, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps +
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>.
ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +, ML20137K702 +  and ML20137K702 +
Issue date
November 27, 1985  +
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>.
04:02:06, 12 December 2024  +
NRC
NRC 85-261 +
NUREG
NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +
Page count
10  +
Procedure
ES-02 +, ES-01 +, ES-04 +, ES-05 +  and ES-06 +
Project stage
Request  +
SSC
07-83-10c +
Scram
Automatic Scram +
Site
Wolf Creek +
Start date
November 27, 1985  +
State
Washington +  and Kansas +
System
Steam Generator +, Reactor Coolant System +, Auxiliary Feedwater +  and Decay Heat Removal +
Title
Forwards Info Requested in Generic Ltr 85-12 Re Matl Delineated in Section IV of Safety Evaluation,Parts A,B & C on TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps  +
To
Office of Nuclear Reactor Regulation +  and Harold Denton +
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http://pbadupws.nrc.gov/docs/ML2013/ML20137K702.pdf  +
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