ML20107K547
| ML20107K547 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/21/1985 |
| From: | Danni Smith COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 85-02, 85-2, 9794N, NUDOCS 8502280322 | |
| Download: ML20107K547 (2) | |
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@ One First National Plaza Chicago, Illinois Commonwealth Edison Address Reply to: Post Office Box 767 Chicago, Illinois 60690 February 21, 1985 Mr. James G. Keppler Regional Administrator U.
S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
SUBJECT:
Braidwood Station Units 1 and 2 10 CFR 50.55(e) No. 85-02 30-day Report Tank and Heat Exchanger Welding NRC Docket Nos. 50-456/457
Dear Mr. Keppler:
On January 22, 1985, the Commonwealth Edison Company notified your office of a potential deficiency reportable pursuant to 10 CFR 50.55(e) regarding deficient welds on certain ASME Section III tanks and Heat Exchangers at our Braidwood Station.
This letter provides information concerning this matter to fulfill the thirty day reporting requirement.
For tracking purposes, this deficiency was assigned Number 85-02.
DESCRIPTION OF DEFICIENCY Welding on certain safety related ASME Section III Tanks and Heat Exchangers do not meet drawing, specification and in some cases Code requirements.
The deficient areas are divided into two categories:
- 1) CB&I field erected tanks.
The associated weld deficiencies include undersized fillet welds, improper fit-up gap, unacceptable weld profile, improper weld configurations and missing welds.
- 2) Various vendor supplied safety related ASME Section III tanks and heat exchangers.
Thus far, weld deficiencies in this category are limited to undersized fillet welds on integral vessel supports and reinforcing fillet welds on vessel nozzles.
At this time, issue scope is still being defined.
FEB251985.
8502280322 50221 PDR ADOCK 05000456 S
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' ANALYSIS OF SAFETY IMPLICATIONS At this time, a definitive analysis of safety implications cannot be made.
Such an analysis will be conducted following development of NCR dispositions as discussed below.
CORRECTIVE ACTION TAKEN Commonwealth Edison Company NCR's 694 (category 1) and 711 (category 2) have been issued to track this issue.
The actions required for resolution have not yet been determined.
Consequently, an interim report will be submitted by April 8, 1985, to identify and status corrective actions as well as discuss the safety implications of this issue.
-Please address any questions that you or your staff may have concerning this matter to this office.
Veg truly y urs,
[(
David H. Smith Nuclear Licensing Administrator cc:
NRC Resident Inspector - Braidwood Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 (9794N)
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