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ML20004D543
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20004D543  +
Docket
05000341  +  and 00341  +
From
DTE Energy +  and Colbert W +
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>.
ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +, ML20004D543 +  and ML20004D543 +
IEEE
IEEE 323-1974 +, IEEE 279 +  and IEEE 344-1975 +
Issue date
June 4, 1981  +
Letter
NRC Generic Letter 1980-11 +  and ML19276F777 +
Manufacturer
General Electric +  and Target Rock +
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16:05:58, 23 December 2024  +
NRC order
CLI-20-81 +
NUREG
NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
26  +
Project stage
Request  +
Site
Fermi +
Start date
June 4, 1981  +
State
Maryland +
System
Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Automatic Depressurization System +  and Control Rod +
Title
Submits Responses to NUREG-0737,Items II.K.3.22 Re Auto Switchover of Reactor Core Isolation cooling,II.D.1 Re Safety/Relief Valve Tests & II.D.3 Re Valve Position Indication  +
To
Office of Nuclear Reactor Regulation +  and Kintner L +
Topic
Scram Discharge Volume +, Feedwater Controller Failure +, Loss of Offsite Power +, Power change +  and Subsequent actuation +
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http://pbadupws.nrc.gov/docs/ML2000/ML20004D543.pdf  +
 
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