ML15251A139
| ML15251A139 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/27/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15251A138 | List: |
| References | |
| 50-270-80-16, NUDOCS 8007280421 | |
| Download: ML15251A139 (1) | |
Text
APPENDIX A NOTICE OF VIOLATION Duke Power Company License No. DPR-47 Oconee Unit 2 Based on the NRC inspection May 28-30,
- 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 Section III.A.1(d) of Appendix J to 10 CFR 50, portions of systems open directly to the containment under post-accident conditions shall be drained and vented to the extent necessary to expose the isolation valves to containment air test pressure and to assure they will be subjected to post-accident differential pressure.
Technical Specification 6..4.1 requires, in part, that procedures will be provided and followed in the performance of safety-related periodic tests.
Periodic tests PT/0/150/A/3 "Reactor Building Integrated Leak Rate Test" requires that the pipe caps be removed from vent and drain lines on those systems required to be vented to the containment atmosphere during the integrated leak rate test.
Contrary to the above, during the valve lineups performed in the period on or about May 28-30, 1980, 18 pipe caps were not removed from vent and drain lines which were required to be vented to the containment atmosphere during the integrated leak rate test.
This is an infraction.
B.
As required by Section III.A.1(d) of Appendix J to 10 CFR 50, portions of systems open directly to the containment under post-accident conditions shall be drained and vented to the extent necessary to expose the isolation valves to containment air test pressure and to assure they will be subjected to post-accident differential pressure.
Technical Specification 6.4.1 requires, in part, that procedures used in the performance of safety-related periodic tests will contain appropriate instructions and check off lists.
Periodic test procedure PT/0/150/A/3, "Reactor Building Integrated Leak Rate Test" is the procedure used to control and accomplish test prerequi sites such as the proper venting and draining of systems required to be drained for the integrated leak rate test.
Contrary to the above, PT/0/150/A/3 did not contain appropriate instructions and check-off lists to accomplish proper system draining.
Five of 17 systems were inadequately drained during preparation for integrated leak rate test in the period on or about May 28-30, 1980.
This is an infraction.
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