ML19326C617
| ML19326C617 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/23/1975 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326C599 | List: |
| References | |
| 50-313-75-15, NUDOCS 8004230716 | |
| Download: ML19326C617 (2) | |
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. Arkansas Nuclear One, Unit 1 Docket No.-50-313 License ~No. DPR :+5 APPENDIX A a=E
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-Based on the results of the NRC inspection conducted during the period December 3-5 and December 8-9, 1975, it appears that certain of your
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- activities were not conducted in full compliance with your Reactor License
.ces or_NRC Regulations as indicated below:
- 1.
10 CFR 50,; Appendix.B, Criterion 10, states in part that, "A program for inspection of. activities affecting quality shall be established and executed by or-for the organization performing the activity to 7:F verify conformance with the documented instructions, procedures, and drawings.for accomplishing the activity." Section 2, Table 2-2 of the Arkansas Power and Light Quality Assurance Manual Operations states in part, "1004.8 QC Inspections This procedure provides guidance for inspection planning (including inspection hold points),
performance of inspection, and reporting for all activities affect-ing quality.
These inspections are mandatory for Q-list items and are optional for BOP items." 1004.08 QC Inspections, Section 5.2 states in part, "The QCE, or his representetive, performs general
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inspections, using inspection form QC-2 (Exhibit I), on such items as the repair of plant equipeent and the execution of Quality Control procedures.
If the inspection is performed by someone other than the QCE, the complete QC-2 form is forwarded to the QCE for review and distribution."
a.
Contrary to the above, the inspector found during thd review of approximately 100 Job Orders associated with Q-listed items, that form QC-2's had not been prepared and that there was no documented inspection.
b.
Contrary to the above, the licensee could not provide documentation
' of the inspection (QC-2) for preventative maintenance or the pre-operational baseline in-service inspection program, with the exception of the automatic ultrasonic examination.
This isLan' infraction.
-2.
10-CFR 50,- Appendix-3, Criterion V states in part, " Activities affect-ing quality shall be prescribed by documented instructions,
. and shall be accomplished in accordance with these instructions,..
The Arkansas Power and Light Quality Assurance Program Operation,
-Section 5.1.1 states in part, " Instructions, procedures and drawings
.shall'be provided as necessary for the control of those activities which affect quality."
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- e7 a.
Contrary'to the'above, and procedure 1304.58 "In-service
. Inspection," section 5.2, the inspector did not find that-revisions to procedure 1304.58, subsequent to its initial March 22, 1975 issue, have been reviewed by the Plant Safety gg Committee.
- b.. Contrary to the'above, and procedure 1304.58 "In-service Inspection," section 5.6, the inspector did not find that the final preservice ir section report was reviewed by the Plant Safety Committee.
c.
Contrary.to the above, and Quality Control Procedure 1004.12
" Operational ".est Control," section 3.1.2, the inspector did not find that a Technical bervice Department Test Control Chart had been provided, and the Maintenance Department Test Control Chart was not being maintained current.
This is an infraction.
3.
Criterion.IV, 10 CFR 50, Appendix B, requires that, " Measures shall be established to assure that regulatory requirements, design bases and other requirements which are necessary to assure adequate quality are included-or referenced'in the documents for procurement of material, equipment, and services, whether purchased by the applicant or by its contractors or subcontractors."
Contrary to the above, primary coolant-chemicals and steam generator seccndary chemicals are not classified as "Q" items, and therefore, are not controlled as required by the ANO-Unit 1 Quality Assurance Procedures.
This item is an infraction.
4.
Technical Specification 6.7 requires that changes to procedures for maintenance operations involving nuclear safety shall be reviewed by the Plant Safety Committee and approved by the Plant Superintendent prior to implementation.
Contrary to the above, a maintenance procedure for venting the Control Rod Drive mechanism was changed without being reviewed by the Plant Safety Committee or' approved by the Plant Superintendent.
This item is an infraction.
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