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ML20071M109
Show incoming properties 
Category
TEXT-SAFETY REPORT  and GENERAL EXTERNAL TECHNICAL REPORTS
ASME code
IWB-3640 +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML20071M109  +
Atomic Element
Tin +
Correspondence
L 19 +
Docket
05000366  +
From
INC. +, NUTECH ENGINEERS +  and Gustin H +
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>.
ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +, ML20071M109 +  and ML20071M109 +
In package
ML20071M062 +
Issue date
May 31, 1983  +
L
L 19 +
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>.
11:14:22, 15 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
91  +
Procedure
ES +  and RT +
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.
ML20071M109 +
Project
TAC:51407 +
Project reference
TAC:51407 +
Project stage
Draft Other  +
Report
NEDC-25146 +
SSC
2B31-1RC-12B +, 20RS-3 +, 2B31-1RC-12A +, 28B-15 +, 2B31-lRC-12A +, 2B31-1RC-22A +, 2B31-1RC-22B +, 2B31-1RC-28A-10 +, 2B31-1RC-28A-3 +, 2B31-1RC-28A-4 +, 2B31-1RC-28A-7 +, 2B31-1RC-28B-3 +, 2B31-1RC-28B-7 +, 2B31-1RC-28B-8 +, 2B31-1RC-28B-10 +, 2B31-1RC-28B-15 +, 2E11-1RilR-20R +, 2E11-1RilR-24B +, 2B31-lRC-12B +, 12BRC-4 +, 12BR-C3 +, 24BR-ll +, 24BP-14 +, 2E11-1RHR-20R +  and 2E11-1RHR-24B +
Site
Hatch +
Start date
May 31, 1983  +
State
Georgia +  and California +
System
Reactor Coolant System +
Title
Draft Rev a to Design Rept for Weld Overlay Repairs & Flaw Evaluation in Recirculation & RHR Sys, Preliminary Rept  +
Topic
Non-Destructive Examination +, Weld Overlay +, Stress corrosion cracking +, Liquid penetrant +, Unidentified leakage +, Leak-Before-Break +  and Leak Before Break +
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http://pbadupws.nrc.gov/docs/ML2007/ML20071M109.pdf  +
 
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