ML20246P355
| ML20246P355 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/15/1989 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20246P327 | List: |
| References | |
| 50-313-89-10, 50-368-89-10, NUDOCS 8905220154 | |
| Download: ML20246P355 (2) | |
Text
._
APPENDIX A NOTICE OF VIOLATION Arkansas Power & Light Company Dockets: 50-313 Arkansas Nuclear One, Units 1 & 2 50-368 Licenses: DPR-51 NPF-6 During an NRC inspection conducted during the period March I through April 15, 1989, two violations of the NRC requirements were identifitad. The violations involved the failure to properly implement a procedure required by the Technical Specification (TS) and a violation of the scheduler requirement for implementation of anticipated transients without scram (ATWS) modification specifications of 10 CFR Part 50.62.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violations are listed below:
A.
Unit 1, TS 6.8.1 requires that written procedures be established, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33, November 1972. Appendix A, Item 8.b(1)(j) requires procedures for the surveillance tests, inspections, and calibrations of the emergency core cooling system.
Plant TestProcedure(PTP) 1304.013, Revision 8 "HPI/LPI and Reactor Building Spray Flow Inst. Sury. Red Channel," has been established in accordance with this TS requirement.
Section 8.7 of PTP 1304.013 provides instructions for the calibration of Transmitter PDT-1401 which provides a flow signal for Train A of the low pressure injection and decay heat removal systems. These instructions require isolation and venting of the transmitter prior to actual calibration.
Contrary to the above, on March 14, 1989, Transmitter PDT-1402 was inadvertently isolated when the work instructions directed that Transmitter PDT-1401 be calibrated. This action caused the loss of decay heat removal flow indication and the subsequent securing of the decay heat removal pump by the operators due to loss 01 indicated flow.
This is a Severity Level IV violation.
(Supplements)(313/8910-02)
B.
It CFR 50.62 states in Section (d) that an implementation schedule is required from licensees to indicate " final implementation." by the second refueling outage after July 26, 1984, or, if justified, a later date should be mutually agreed upon by the Commission and the licensee. The second refueling outage implementation deadline was extended to the third refueling outage for AN0-2 in a March 2,1987, letter from the Office of NuclearReactorRegulation(NRR)ANO, Unit 2,ProjectManagerto Mr. T. G. Campbell.
Contrary to the above, the third refueling outage for AN0-2 following the July 26, 1984, date, 2R6, was completed in May of 1988, and no ATWS l
8905220154 epo33,
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, l related equipment was installed by that date.
Further, no request for l
scheduler extension had been requested by AP&L or approved by the NRC.
This is a Severity Level IV violation, (Supplements)(368/8910-03)
Pursuant to the provisions of 10 CFR 2.201, Arkansas Power & Light Company is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation:
(1) the reason for the violations if admitted, (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full comp..ance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
Dated at Arlington, Tex s, this /$ day of 77 1989.
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