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ML20041D057
Show incoming properties
Category
NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT
Accession number
ML20041D057  +
Atomic Element
Iodine +, Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Lead +, Lithium +, Calcium +, Titanium +, Chromium +  and Tin +
CFR
10 CFR 50.59 +  and 10 CFR 20 +
From
Cheng C +  and Office of Nuclear Reactor Regulation +
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>.
ML20041D057 +, ML20041D057 +, ML20041D057 +, ML20041D057 +, ML20041D057 +, ML20041D057 +  and ML20041D057 +
Isotope
Cobalt-60 +
Issue date
February 28, 1982  +
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>.
00:51:17, 20 December 2024  +
NUREG
NUREG-0571 +, NUREG/CR-1595 +, NUREG-0886, Responds to Expressing Concern Re Manner in Which NRC Deals W/Problem of Steam Generator Tube Integrity.Nrc Is Adequately Addressing Problem.Steam Generator Insp History,Abstract of NUREG-0886 & NRR Budget Analysis Encl +, NUREG/CR-1490 +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-886 +, NUREG/CR-0199, Forwards NUREG/CR-0199, Radiological Assessment of Steam Generator Removal & Replacement, in Response to . Util Has Made No Request to Replace Steam Generators.W/O Encl +  and NUREG-0523, Forwards NUREG-0523, Summary of Operating Experience W/Recirculating Steam Generators, Which Focuses on Recent Problems W/Degradation.Believes Continued Plant Operation Does Not Constitute Undue Risk +
Page count
67  +
Procedure
CH +  and ST +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20041D057 +
Regulatory Guide
Regulatory Guide 1.121 +
Start date
February 28, 1982  +
State
Tennessee +, Maryland +, Washington +, Virginia +, New York +, Florida +, Arkansas +  and Maine +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Main Turbine +, Main Steam Line +  and Moisture Separator Reheater +
Title
Steam Generator Tube Experience  +
Topic
Boric Acid +, Hydrostatic +, Nondestructive Examination +, Feedwater Heater +, Stress corrosion cracking +, Eddy Current Testing +, Scaffolding +, Flow Induced Vibration +  and Eddy Current Test +
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/ML2004/ML20041D057.pdf  +
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