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ML19350B019
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ASME section
ASME Section XI +
Accession number
ML19350B019  +
Atomic Element
Lead +
CFR
10 CFR 100 +  and 10 CFR 50.46 +
Docket
05000313  +  and 00313  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Entergy +  and Trimble D +
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>.
ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +, ML19350B019 +  and ML19350B019 +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +
Issue date
March 12, 1981  +
Letter
05000368/LER-1981-004, Forwards LER 81-004/03L-0 +  and ML19345E505 +
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>.
01:20:48, 24 December 2024  +
Page count
18  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.77 +
Scram
Automatic Scram +
Site
Arkansas Nuclear +
Site license
DPR-313 +
Start date
March 12, 1981  +
State
Arkansas +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Emergency Feedwater System +
Title
Forwards Response to 810112 Request for Info Re Emergency Feedwater Sys Design.Tech Specs Modified Nov 1977 to Conform W/Std Wording for Valve Testing for Eccs.Emergency Procedure 1202.26 Identifies Supply Requirements  +
To
Reid R +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Stroke time +, Loss of Offsite Power +, Fuel cladding +  and Manual Operator Action +
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http://pbadupws.nrc.gov/docs/ML1935/ML19350B019.pdf  +
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