ML20133F855
| ML20133F855 | |
| Person / Time | |
|---|---|
| Issue date: | 01/10/1997 |
| From: | Cwalina G NRC (Affiliation Not Assigned) |
| To: | Reindl R AFFILIATION NOT ASSIGNED |
| References | |
| REF-QA-99901307 NUDOCS 9701150047 | |
| Download: ML20133F855 (2) | |
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4 UNITED STATES j
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,j NUCLEAR REGULATORY COMMISSION i
WASHINGTON. D.C. 20666 4001 o% *****/
January 10, 1997 1
Mr. Roy P. Reindl, Branch Manager ACCUTECH i
A Division of B&G Manufacturing Co. Inc.
3873 W. Oquendo Road Las Vegas, NV 89118 i
Dear Mr. Reindl:
This letter summarizes the results of the December 19, 1996 telephone conference between Messrs. U. Potapovs and B. Rogers of the Nuclear Regulatory Commission (NRC) and you and Messrs. W. Edmonds and G. Keller of ACCUTECH and confirms the upcoming inspection of ACCUTECH on January 28 through 31, 1997.
The purpose of this telephone conference was to develop additional information concerning your 10 CFR Part 21 reportability evaluation of safety related fasteners that were improperly heat treated and supplied to NRC licensees during 1989-1996 time period.
During the December 19, 1996 telephone conference, the following information was provided to the NRC:
l The potentially nonconforming heat treat lots identified as a result of I
ACCUTECH's evaluation comprise approximately 6% of AISI 4140 (SA 193, Grade B7) material heat treated in the suspect oven during the 1989-1996 period.
i ACCUTECH considers that nonconforming fasteners from two additional lots i
subsequently identified by customer or ACCUTECH's direct testing were too far outside the suspect lot parameters defined by the earlier evaluation to conclude that these lots also received improper heat treatment.
ACCUTECH considers the nonconforming fasteners in the two additional lots as isolated events, possibly caused by commingling of material.
4 ACCUTECH reviewed the heat treatment records for material other than AISI 4140 that was heat treated in the suspect furnace during the same 7
time period and concluded that, based on the bounding parameters identified during their earlier evaluation, all other material should I
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have received proper heat treatment.
Sh The NRC inspection will review available documents ud records to evaluate the bases for these conclusions as they relate to ACCUTECH's responsibilities 67d under 10 CFR Part 21.
The inspection will also review selected portions of your quality assurance program and its implementation.
We are planning to i
d conduct an entrance meeting at your manufacturing plant at 8:30 am on January l
28, 1997, and expect to hold an exit meeting at 4:00 pm on January 30, 1997.
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I Mr. Roy P. Reindl s Your cooperation in providing the support needed to complete the~ scope of our inspection are appreciated. Should you'have any questions regarding this letter, please contact Mr. Potapovs at (301) 415-2959.
4 Sincerely,.
ORIGINAL SIGNED BY:
1 Gregory C'. Cwalina, Chief J
Vendor Inspection Section Special Inspection Branch Division of Inspection and Support Programs Office of Nuclear Reactor Regulation Docket No.: 99901307 Distribution:
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