ML19326B604
| ML19326B604 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/28/1975 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19326B602 | List: |
| References | |
| 50-313-75-14, NUDOCS 8004160384 | |
| Download: ML19326B604 (2) | |
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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 November 10-14, 1975, it appears that certain of your activities were not conducted in full compliance with your Reactor License or NRC Regulations as indicated below:
A.
Criterion II, Appendix B, 10 CFR 50 requires that, "The applicant shall identify... the major organizations participating in the program, together with the designated functions of,these organizations," and section 1.6.1.2 of the AP&L Quality Assurance Manual - Operations states that, "The committee shall meet at least quarterly during plant operation. A majority of the QAC members is required for a quorum."
Contrary to the above requirement, the quarterly meeting requirement p
was not satisfied because a quorum was not present at the June 25, 1975 v)
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meeting.
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B.
Technical Specification 6.4.1.g.4 requires that the Plant Safety Committee shall review proposed changes or modifications to plant systems or equipment.
Contrary to the above, Amendment A was made to Design Change Request 187
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(Steam Line Break Instrument and Control), and Design Change Request 266 1
(Removal of the Ten Inch Building Spray Crossover Line), without Plant Safety Committee review.
This item is an infraction.
C.
Criterion V of Appendix B to 10 CFR 50 requires in part that, " Activities affecting quality shall be prescribed by documented instructions, procedures or drawings,... and shall be accomplished in accordance with these instructions, procedures, or drawings."
Contrary to the above requirement the following licensee procedures /
instrve.tions were not adhered to:
(1)
ANO-1 Administrative Procedure 1005.12 requires that Standing Orders be approved by an individual holding a Senior Reactor Operator (SRO) license.
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Standing Order No. 12 was not approved by an individual with an SRO license.
(2)
ANO-1 Administrative Procedure 1005.12 requires that. Standing Orders may be removed with the approval of the Plant Super-intendent or Assistant Plant Superintendent.
Standing Order No. 10 was removed without the above required approvals, i
(3)
Section 5.2.5 of the licensee's Quality Assurance Manual requires that the format and control of procedures shall comply with the guidelines in ANSI Standard N18.7 - 1972.
The content of the licensee's maintenance procedures do not comply with the ANSI N18.7 guidelines.
This is an infraction, i
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