05000313/LER-1978-019-01, B&W Discovered That Weld Filler Wire Atypical of Submerged Arc Weld Filler Wires Specified,Was Unknowingly Mixed by Supplier.Pressure/Temp Curves Revised Then Later Reverted to Original Curves

B&W Discovered That Weld Filler Wire Atypical of Submerged Arc Weld Filler Wires Specified,Was Unknowingly Mixed by Supplier.Pressure/Temp Curves Revised Then Later Reverted to Original Curves

ML19323D950
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/21/1980
From:	Shively C ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19323D945	List: 05000313/LER-1978-019, Forwards Updated LER 78-019/01X-1 05000313/LER-1978-019-01, B&W Discovered That Weld Filler Wire Atypical of Submerged Arc Weld Filler Wires Specified,Was Unknowingly Mixed by Supplier.Pressure/Temp Curves Revised Then Later Reverted to Original Curves
References
LER-78-019-01X, LER-78-19-1X, NUDOCS 8005220583
Download: ML19323D950 (1)

LER-1978-019, B&W Discovered That Weld Filler Wire Atypical of Submerged Arc Weld Filler Wires Specified,Was Unknowingly Mixed by Supplier.Pressure/Temp Curves Revised Then Later Reverted to Original Curves

Event date:
Report date:
3131978019R01 - NRC Website

text

UPDATE REPORT - PRcVIOUS REPORT 8/18/28 NaC FORM 3t4 U. S. NUCLE AR REGULATORY COMMISSION 5

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LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l l 1 1 1 I lh (PLE ASE PRth7 QR TYPE ALL REQUIRED INFORMATIONI l o t i l i Al R l A l N] O ] 1 lgl 0 j0 l - l0 l 0 l 0l 0l 0 l-l 0 l0 lg(+ l1 l 1 l1 l 1 lgl l [g 7

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W 61 DOCEEr muugge tea 69 EVENT C ATE fa 75 M, ORT DATE 80 EVENT DESCRIPTION' ANO PECS ABLE CONSEQUENCES rTTTl i As a result of chemical analysis performed on archieve weldments, the i

t o t a i i NSSS vendor, B&W, discovered that weld filler wire atvoicei of the sub-I ie,. i i merged arc weld filler wires specified was unknowingly mixed by the sup-t

,,,s,, plier. The atypical weld wire has high Si and low Ni contents. A frac ture mechanics evaluation has demonstraced that the structural integrity i. g ; i 1:171 I of the reactor vessel has not been compromised.

No similar occurrences. I

. n i ; Reportable per T.S. 6.12.3.1(i).

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1.. i i head-to-flan;e L outlet n ::le-to-nozzle beit & :sitline regions.

The i i:i I RCS Pressure-Te nerature cocra tine limits were revised to be more restric i i.,3j l tive based on :reliminary analysis.

Subseouent analysis demonstrated that atypical welcment did not require the revised P. i. curves.

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