ML20151M121
| ML20151M121 | |
| Person / Time | |
|---|---|
| Issue date: | 08/06/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20151M117 | List: |
| References | |
| REF-QA-99900824 NUDOCS 9708080209 | |
| Download: ML20151M121 (1) | |
Text
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NOTICE OF NONCONFORMANCE SOR, Inc.
.Lenexa, KS Docket No.: 99900824 l
Based on the results of an NRC inspection conducted on June 16 through 19, 1997, it appears that certain of your activities were not conducted in j
accordance with NRC requirements.
j Criterion V of Appendix B to 10 CFR Part 50, " Instructions, Procedures, and Drawings," requires, in part, that activities affecting quality shall be j
prescribed by documented instructions and procedures of a type appropriate to i
the circumstances, and shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
SOR Nuclear Quality Assurance Manual 8303-100, Section 5.2, " Instructions, Procedures, and Drawings," dated April 14, 1993, requires, in part, that L
instructions, procedures, and drawings must contain acceptance criteria to i
ensure compliance with customer quality requirements.
Contrary to these requirements, S0R did not prescribe instructions or procedures to ensure that epoxy was not applied on insulated lead wires of safety-related pressure, vacuum, and temperature switches, or that quality inspectors examine the switches properly. As a result, a heavy coating of i
epoxy was applied on the insulated wires during manufacture.
The epoxy hardened the insulation causing it to crack when it was bent.
In September 1994, Nebraska Public Power District (for the Cooper Power Station) and Connecticut Yankee Atomic Power Company (for the Haddam Neck Plant) identified cracked insulated lead wires of switches installed in their plants. The cracked insulation had the potential to reduce the wire insulation resistance or cause a short to ground. On October 14, 1994, SOR issued a 10 CFR Part 21 to inform the NRC and applicable customers of this defect and pertinent corrective action.
SOR replaced or repaired the safety-related switches and i
took appropriate steps to prevent epoxy from being applied on the insulation of lead wires.
In a June 19, 1997, letter to the NRC, SOR reported the steps it took (in i
1994) to correct the problen. nd prevent recurrence.
Steps comprised alerting customers about the cracked in.slation, repairing defective switches installed in plants, preparing instructh s and procedures, and implementing new quality control inspections to prevent
'1e use of epoxy on the insulation.
No further response is required (99900824 97-01-01).
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Dated at Rockville, Maryland this 10th day of August 1997 "4
9708080209 970806 PDR GA999 EMVSORNO 99900824 PDR 1
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