ML19290E032
| ML19290E032 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/18/1980 |
| From: | Martin T Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML19290E031 | List: |
| References | |
| NUDOCS 8003040033 | |
| Download: ML19290E032 (3) | |
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Thomas J. Martin Public Service Electric and Gas Com;:any 60 Park P! ace Newark, N.J. 07101 201/430-6316 Vice President Engineering and Construction January 18, 1980 Mr. Bo yce H.
Grier, Director U.
S. Nucle ar Re gulatory Commission Office of Inspection and Enf orcement Re gion 1 -
631 Park Avenue King of Prussia, Pennsylvania 19406 De ar Mr. G rie r :
WELD WIRE DOCUMENTATION 10CFR5 0. 5 5 (e ) : "SIGNIFICANT DEFICIENCY" NO. 1 AND 2 UNITS HOPE CREEK GENERATING STATION On August 31, 1979 a verbal report was made to Region 1, Office of Inspection and Enf orcement rep re senta tive Mr.
L.
- Narrow, advising of a p otential significant item regarding a discrep ancy in the p rocurement o f weld wire.
This verbal rep ort was p rovide d in accordance wit h t he p rovisions of 10CFR5 0.55 (e).
Supp lemental inf ormation wa s submitted in writing to Region 1, Office of Inspection and Enforcement on' Sep tembe r 26, 19 79 w it h the indication that analysis and corrective actions de scribe d we re continuing with an expected comple tion. date of January 18, 1980.
T he following information is a second interim rep ort conce rning Pittsburgh De s Moine s' u se o f 8 018-C3 weld fille r me tal.
The fille r =e tal was used in p o st-weld he a t-t re a te d we ldme n t s for NF app lications, but was tasted f or only the a s-welde d condition.
The following activitie s. have been comp le ted since the first interim report:
8003040()3'}
Mr.
B.
H.
Grier 1/18/80 1.
PDM has issued a new electrode specification, ES-7.5.2, Revision A, which requires testing of E8018-C3 filler metal in both the as-welded and the post-welded heat-created (PWHT) condition.
2.
PDM has issued the following revisions to welding procedure specifications:
WPS 70-71, Revision A WPS 70-72, Revision B WPS 73-73, Revision H requiring electrodes to be tested in the post-weld heat-created condition for welds that will be post-wel d heat-treated.
3.
PDM has completed their investigation which revealed that only four of the heats of filler metal procured under Electrode Specification ES-7.5.1, Revision A, were improperly used in containment fabrication.
These PDM I.D.
Nos. are:
A3297 for Unit 1 A2138 for Unit 1 A2988 for Unit 1 A8913 for Unit 2 4.
PDM has issued Engineering Corrective Action Requests 15675-138 (9/16/79) and 15676-74 (11/20/79) addressing the following filler metal heats:
I.D.
A2988 - Tests qualifying this heat in the PWHT condition have been located.
Revision of CMTR's is addressed.
I.D. A2138 - Tests qualifying these heats in I.D. A8913 the PWHT condition could not be located, however, several weld joints, where only these heats of electrodes were used, have been isolated.
Issuance of a repair procedure, RP-19 (Revisions 0 & A), and removal of specimens from weld seams for testing are addressed.
-S G C0 u 40$
Mr.
B.
H.
Grier 1/18/80 I.D. A3297 - Tests qualifying this heat in the PWHT condition could not be located.
In addition, welds where only this heat was used could not be isolated.
Removal of questionable weld metal from weld joints, and replacement of it with acceptable material are addressed.
5.
PDM has completed the coupon removal and testing program for heats A2138 and A8913; the testing results are acce table.
6.
Repe:.r Procedure RP-19, Revisi n B, which addresses the repair of the stiffeners, where the coupons were removed, and weld removal and replacement for heat I.D.
A3297, has been accepted by Bechtel.
Future activities to be completed are listed as f o llowr, :
1.
PDM will amend the original CMTR's'for heat I.D.
A2988 and recertify them for use in the post-weld heat-treated condition.
2.
PDM will repair the stiffeners where the coupons were removed, and will complete removal and rewelding of seams of heat I.D.
A3297 by January 25, 1980.
The investigation into the analysis of safety implications and corrective actions as described above are continuing with an expected completion date of March 14, 1980, at which time a complete report will be filed.
Should you require additional in f o rma t io n, we vill be pleased to discuss it with you.
Very truly yours,
' /
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CC:
Office of Inspection a2d Enfore ment Division of Reactor Construction Inspection Washington, D.
C.