ML20077G222
| ML20077G222 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/25/1983 |
| From: | Hall D ILLINOIS POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 55-83-07, 55-83-7, U-10074, NUDOCS 8308030415 | |
| Download: ML20077G222 (3) | |
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g g ILLIN0/8 POWER COMPANY CLINTON POWER STATION. P.O. BOX 678. CLINTON, ILLINOIS 61727 July 25, 1983 Docket No. 50-461 Mr. James G. Keppler Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Potential Deficiency 55-83-07 10CFR50.55(e)
Pipe Shop Welds by Southwest Fabricating
Dear Mr. Keppler:
On June 14, 1983, Illinois Power Company notified Mr. F.
Jablonski, NRC Region III (Ref:
IP memorandum Y-15971, 1605-L, dated June 14, 1983) of a potentially reportable deficiency concerning the adequacy of shop welds on pipe spools fabricated by Southwest Fabricating and Welding Company.
Our investigation of this matter continues, and this letter represents an interim report in accordance with 10CFR50.55 (e)(3), for this potentially reportable deficiency.
Statement of Potentially Reportable Deficiency Questionable indications were found in the root area of shop welds produced by Southwest Fabricating and Welding Company during a re-review of radiographic film.
The welds in question are ASME Code Class II found in safety-related piping systems.
An investigation is being conducted to ascertain if the subject welds are acceptable as documented by the original radiographic inspections.
Background / Investigation Results During examination of a field radiograph of a shop weld repaired by Baldwin Associates at CPS, questionable indications were noted in the root area of the Southwest Fabricating shop weld away from the repair.
The weld repair was necessary due to overgrinding of the shop weld while " flat topping" in preparation for in-service inspection baseline examination.
The questionable indications were also noted in a re-review of Southwest Fabricating shop radiographic films of this weld.
Further investigation of shop radiographic film identified three additional shop welds with questionable indications.
It was noted that all the shop films in question were originally h
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Mr. Jcmes G. Kcppler Page 2 July 25, 1983 g
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evaluated at receipt by the same Baldwin Associates Quality Assurance inspector.
Baldwin Associates performed a re-review of radiographs originally interpreted by the aforementioned inspector.
Sixty-eight (68) welds were selected at random for review.
Fourteen of these welds were found to contain questionable indications.
The films of five (5) additional welds show surface conditions that pos-sibly could mask defects.
Corrective Action (Interim) l The subjective nature by which weld quality is evaluated l
through radiographic film interpretation has not produced a concensus on-the actual condition of these welds.
In general,
'the-parties involved (Illinois Power, Baldwin Associates and Southwest Fabricating) have concluded that certain of these welds can be.re-evaluated with surface cleaning and' visual inspection while others may necessitate re-radiographing to acquire improved density / sensitivity to evaluate the weld.
The following actions are being taken:
1.
A plan has been developed detailing the actions required to achieve a satisfactory eval'uation.
This plan includes a review of this issue by an independent third party.
2.
A review will be performed by Baldwin Associates, Southwest Fabricating and an independent third party of the re-examination evidence.
3.
Further investigative and corrective actions, both specific and generic in nature, will be determined upon completion of steps 1 and 2 above.
Safety Implications / Significance The investigation of this potentially reportable deficiency continues toward determinitig the acceptability of the welds questioned as a result of the re-review of radiographic film.
The extent and significance of this condition cannot be de-s termined until further evaluation / examination of the questionable welds is performed.
Once the re-examination evidence has been obtained and evaluated, it'will then be possible to provide a i
conclusion as to the condition's extent and significance, and to determine generic and specific corrective actions.
It'is antic-ipated that approximately ninety (90) days will be required to complete the investigation, determine reportability, and file our final-report on this potentially reportable deficiency.
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Mr. Jcmas G. Kappler Page 3 July 25, 1983 We trust that this interim letter provides sufficient information to perform a general assessment of this deficiency and adequately describes our overall approach to resolve the problem.
Sincerely yours,
. P. Hall Vice President REC /j f cc:
H. H. Livermore, NRC Resident Inspector Director, Office of I&E, USNRC, Washington, D.C.
20555 Illinois Office of Nuclear Safety Manager-Quality Assurance INPO Records Center
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