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ML20083N636
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Category
TEXT-SAFETY REPORT  and GENERAL EXTERNAL TECHNICAL REPORTS
ASME code
IWB-3640 +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML20083N636  +
Atomic Element
Tin +
Cross cutting aspect
S.5(t) +  and P.8(o) +
Docket
05000366  +  and 00366  +
From
INC. +, NUTECH ENGINEERS +, Gustin H +, Charnley J +  and Mcinnes I +
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>.
ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +, ML20083N636 +  and ML20083N636 +
In package
ML20083N623 +
Issue date
March 19, 1983  +
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>.
10:18:12, 14 December 2024  +
NUREG
NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +
Page count
105  +
Procedure
RT +  and Emergency Plan +
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.
ML20083N636 +
Project
TAC:51407 +
Project reference
TAC:51407 +
Project stage
Other  +
Report
NEDC-25146 +
SSC
20RS-3 +, 28A-4 +, 28B-15 +, 12BR-C-3 +, 12BR-C-4 +, 7FGl6-7-13 +, 2H31-IRC-12H +, 2H31-lRC-12H +, 2H31-lRC-12b +, 2H31-1RC-12A +, 2H31-lRC-12A +, 2H31-IRC-12A +, 23B-15 +, 24B-R-ll +, 2B31-lRC-28 +, 2B31-IRC-28A-4 +, 2H31-lRC-28A-7 +, 2B31-lRC-28A-10 +, 2B31-lRC-288-3 +, 2B31-lRC-288-7 +  and 2Hll-lRHR-248-R +
Site
Hatch +
Start date
March 19, 1983  +
State
Georgia +, California +  and Michigan +
System
Reactor Coolant System +, Reactor Pressure Vessel +  and Residual Heat Removal +
Title
Rev 1 to Design Rept for Weld Overlay Repairs & Flow Evaluations in Recirculation & RHR Sys  +
Topic
Non-Destructive Examination +, Weld Overlay +, Finite Element Analysis +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Liquid penetrant +, Unidentified leakage +, Leak-Before-Break +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML2008/ML20083N636.pdf  +
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