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ML20009C147
Show incoming properties
Category
Pages with broken file links, REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)  and TEXT-SAFETY REPORT
Accession number
ML20009C147  +
Atomic Element
Hydrogen +, Zirconium +  and Lead +
Cornerstone
Initiating Events +
Docket
05000322  +  and 00322  +
From
GENERAL ELECTRIC CO. +
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>.
ML20009C147 +, ML20009C147 +, ML20009C147 +, ML20009C147 +, ML20009C147 +, ML20009C147 +, ML20009C147 +, ML20009C147 +, ML20009C147 +  and ML20009C147 +
In package
ML20009C138 +
Issue date
July 6, 1981  +
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>.
06:18:10, 23 December 2024  +
NRC bulletin
NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +  and NRC Bulletin 79-05 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
24  +
Procedure
ESP +
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ML20009C147 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
Report
NEDO-24708 +
Site
Shoreham +
Start date
July 6, 1981  +
State
Pennsylvania +  and Washington +
System
Feedwater +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Main Turbine +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Reactor Water Cleanup +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Low Pressure Coolant Injection +
Title
GE Evaluation of Need for BWR Core Thermocouples  +
Topic
Reactor Vessel Water Level +, Post Accident Monitoring +, Probabilistic Risk Assessment +, Operator Manual Action +, Fuel cladding +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML2000/ML20009C147.pdf  +
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