ML19320B468
| ML19320B468 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/05/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19320B461 | List: |
| References | |
| 50-413-80-05, 50-413-80-5, 50-414-80-05, 50-414-80-5, NUDOCS 8007100426 | |
| Download: ML19320B468 (2) | |
Text
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APPENDIX A NOTICE OF VIOLATION Duke Power Company License Nos. CPPR-116 Catawba Nuclear Station
& CPPR-117 Based on the NRC inspection March 5-31, 1980, certain of your activities were apparently not conducted in full compliance with NRC requirements as indicated below. These items have been categorized as described in correspondence to you dated December 31, 1974.
A.
As required by Criterion XIII of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.13, measures shall be established to control the handling, storage and preservation of material and equipment to prevent damage.
Contrary to the above, procedures and their implementation failed to prevent rigging from installed Class IE electrical cable tray as demonstrated by the following:
(1) The applicable site procedure contained no provisions to warn cgainst using adjacent Class IE equipment for support during installation of plant equipment.
(2) A motor control center was attached through rigging and hoisting equipment to an installed Class IE electrical cable tray.
This is an infraction.
B.
As required by Criterion XVI of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.16.2, nonconforming conditions shall be analyzed and appropriate corrective action taken to preclude repetition.
Contrary to the above, appropriate corrective action was not taken for site nonconformance reports numbered 5756 (closed September 5,1979) and 6104 (closed November 29, 1979); as site drawings are still not being properly identified as nuclear safety related documents.
This is an infraction.
C.
As required by Criterion III of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.3, design engineering places emphasis on assuring conformance with standards and SAR design commitments.
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Duke Power Company Appendix A Catawba Nuclear Station Notice of Violation o
Contrary to the above, design has failed to translate into drawings or speci-fications SAR requirements that all Class IE equipment be distinctively identifiable to their respective safety trains.
This is an infraction.
D.
As required by Criterion V of Appendix -B -to CFR-50, as-implemented-by Duke's Topical Report, paragraph 17.1.5.2, work is to be accomplished in acccrdance with drawings.
Contrary to the above, Class IE equipment has not been installed and inspected in accordance with the designated drawings.
This is a deficiency.
E.
As required by Criterion V of Appendix B to 10 CFR 50, as implemented _by_.
Duke's Topical Report, paragraph 17.1.5.2, activities affecting quality shall be prescribed and conducted in accordance with documented procedures.
Contrary to the above, the procedure for the qualification of nondestructive examination (NDE) personnel did not make allowances for the site to have a limited level II NDE radiographer.
This is a deficiency.
F.
As required by Criterion V of Appendix B to 10 CFR 50, as implemented by Duke's Topical Report, paragraph 17.1.5, the corperate quality assurance program procedures specify the quantitative and qualitative criteria to assure satisfactory work performance and quality.
Contrary to the above, the procedure for qualification of site inspection personnel does not have provisions for allowing:
(1) Electrical inspection personnel to be visually examined to assure that they can distinguish between the various colors that inspections require.
(2) Level I inspectors to be designated as technical first line supervisors responsible for supervising and directing all of that particular inspection group's daily efforts.
This is a deficiency.
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