ML19326B571
| ML19326B571 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/08/1976 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326B558 | List: |
| References | |
| 50-313-76-05, 50-313-76-5, NUDOCS 8004160353 | |
| Download: ML19326B571 (2) | |
Text
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Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51 APPENDIX A NOTICE'OF' VIOLATION Based on the results of the NRC inspection conducted during the period March 23-25, 1976, it appears that certain of your activities were not conducted in full compliance with your Reactor License or NRC Regulations as indicated below:
1.
Technical Specification 6.7 requires in part that procedures be prepared, approved and adhered to for preventive or corrective maintenance operations involving nuclear safety of the facility.
Contrary to the above, procedures were not followed in the control of hold cards as required by procedure 1004.19, Hold, Caution and QC Tagging Procedure.
This item is an infraction.
j 2.
Technical Specification 6.7.3 requires that temporary changes to safety related operating procedures which do not involve a change of intent be approvec by two members of the plant staff, at least one of whom shall be a shift supervisor.
Contrary to the above requirement, two temporary changes to operat-ing procedures for safety related systems, temporary change 1 to procedure 1104.03, revision 4, " Chemical Addition," and temporary change 2 to procedure 1103.06, revision 1, " Reactor Coolant Pump Operation," were in effect but had been approved by only one plant staff member.
This item is an infraction.
3.
10 CPR 50.59(b) requires in part that the licensee maintain records of changes to procedures as described in the safety analysis report and that such records shall include a written safety evaluation which provides the bases for the determination that the change does not constitute an unreviewed safety question.
Contrary to the above requirement, no written safety evaluation to provide the baces for the determination that the change did not constitute an unreviewed safety question were maintained for three changes to procedures described in the FSAR, procedures 1102.06, s
(continued) 80041603(?
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revision 2, " Reactor Trip Recovery," 1202.32, revision 2, " Loss of Decay Heat Removal," and 1202.03, revision 3, "CRD Malfunction Action."
This item is a Jeficiency.
4.
Technical Specification 6.7 requires in part that detailed written proa.edures, covering Emergency and off-normal conditions shall be Prepared, approved and adhered to for all systems and components involving nuclear safety.
Contrary to the above procedures were not provided for the action to be taken in the event of dropping a group of rods in the regulating or safety groups.
This item is a deficiency.
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