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ML20247E303
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Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
ASME section
ASME Section II +
Accession number
ML20247E303  +
Atomic Element
Lead +
CFR
10 CFR 50.46 +
Correspondence
L 01 +
Docket
05000289  +  and 00289  +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Office of Nuclear Reactor Regulation +  and Hernan R +
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ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +, ML20247E303 +  and ML20247E303 +
Issue date
March 28, 1989  +
L
L 01 +
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>.
02:02:46, 2 December 2024  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
32  +
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ML20247E303 +
Project
TAC:48208 +
Project reference
TAC:48208 +
Project stage
Approval  +
Site
Crane +
Start date
March 28, 1989  +
State
Pennsylvania +, Maryland +, Washington +, Virginia +, New Jersey +  and Idaho +
System
Steam Generator +, Reactor Coolant System +, Feedwater +  and Auxiliary Feedwater +
Title
Forwards Safety Evaluation Stating That BAW-1976 Satisfies TMI Item II.K.3.31 Re Small Break Loca.Nrc Agrees W/ Conclusion That Analyses Confirm B&W 177FA lowered-loop Reactor Plant Conformance to Criteria of 10CFR50.46  +
To
FirstEnergy +  and Hukill H +
Topic
Loop seal +, Loss of Offsite Power +  and Fuel cladding +
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http://pbadupws.nrc.gov/docs/ML2024/ML20247E303.pdf  +
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