ML20127K567

Discusses Problem W/Stainless Steel Cladding in Reactor Vessel Base Metal

ML20127K567
Person / Time
Site:	Monticello
Issue date:	01/31/1968
From:	Porse L US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9211200435
Download: ML20127K567 (1)

Text

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I- R. C. DeYoung, Chief N' j Containment & Comiponent Technology Breach i Division of Reester 1&osasias l

! 1. Beree Contaimanat & Camposest Esshanlagy Essash, DRL j l

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i ass.icac a:Is ar.y$ , .6bd5 6 ..

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. chiens, arsass 6 Isen (est) promemana'the puuh3am essoustosed 9th tbs' t

appliention of ataaatag to the someter wooel knee metal. During eased.untian I i

of a messie it uns $sume that the Sorrito esateat uns only 14, while assaal '

presties has esteh11shed a 5-10$ somes as boias moraal to peevost surftee erecking. Ensktreaking it was Spuma that a hamna ersor la enleulatias j the ferrite % in the qualification pseeedure naa y.wb1 adjustasat af the flux consosittaa, the sesult thas betag outside the aorumi neceptease reage as displayed in a ashmeffler Stagsen.

Remedial action was un8ertaken by grinding off the affected arwas to reacrve i the surtnee crack indiestions, and in masas where the elad thickness booman lessthan5/16tachmadittomais*=<=1==ssteelwasseeeposited.  !

This incident is typical of mistakes made by others also in Quality Control I efforts to maintain the proceduru standards, and anny a vessel has been mooepted with this type of variMee, d

set 8. Iavine

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