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ML20079P165
Show incoming properties
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML20079P165  +
Atomic Element
Lead +
Correspondence
RA 12 +
Cross cutting aspect
P.0(i) +
Docket
05000302  +  and 00302  +
Equipment trip
Reactor Trip +
From
Duke Energy +  and Westafer G +
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>.
ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +, ML20079P165 +  and ML20079P165 +
Issue date
February 28, 1983  +
Letter
ML20070M758 +
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>.
03:57:08, 15 December 2024  +
NRC information notice
Information Notice 82-30 +
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 +
Page count
2  +
Procedure
AM +, SP +  and RT +
Project stage
Request  +
RA
RA 12 +
SSC
0conee-1 +, 3F-0283-28 +, 2e-32 +  and 3F-283-28 +
Site
Crystal River +
Site license
Crystal River +
Start date
February 28, 1983  +
State
Colorado +, Maryland +, Washington +, Virginia +, Florida +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +  and Control Rod +
Title
Forwards B&W 177 Fuel Assembly Owners Group Safe End Task Force Rept on Generic Investigation of Hpi/Mu Nozzle Component Cracking, Per Util 830121 Commitment.Thermal Sleeves in HPI Sys Will Be Inspected During Refuel IV  +
To
Stolz J +  and Office of Nuclear Reactor Regulation +
Topic
Non-Destructive Examination +, Finite Element Analysis +, Stress corrosion cracking +, Dissimilar Metal Weld +, Flow Induced Vibration +, Unidentified leakage +  and Thermal fatigue +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML2007/ML20079P165.pdf  +
Retrieved from "https://kanterella.com/Special:Browse/:ML20079P165"