ML20150B869
| ML20150B869 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/01/1988 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20150B859 | List: |
| References | |
| 50-254-88-16, 50-265-88-16, NUDOCS 8807120221 | |
| Download: ML20150B869 (1) | |
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I Commonwealth Edison Company Docket No. 50-254 Docket No. 50-265 As a result of the inspection conducted on June 7-15, 1988, and in accordance
- with.10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1987), ~ the following violation was identified:
- 10 CFR Part 50, Appendix B, Criterion V, as implemented by Commonwealth Edison Quality Assurante Manual, states that activities affecting quality shall be prescribed by documented procedures or instructions and shall be accomplished in accordance with those procedures or instructions.
Quad-Cities Equipment Out-of-Service Procedure QAP-300-14 requires that all safety-related equipment out-of-services and temporary lifts shall be independently field verified.
Contrary to the above, on July 12, 1988, the operator in charge of performing the temporary lift on the 2A Containment Atmospheric Mor.itoring (CAM)
Post-Accident H /02 system did not field verify tne status of the monitors.
2 Consequently, the monitor which was disconnected caused the drywell to leak excessiv'ely into the Reactor Building prior to the start of the integrated leak rate test.
j This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement er explanation in reply, including for each violation:
(1) corrective action t3 ken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
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Dated Hube g J. Miller, Director Division of Reactor Safety 8807120221 090701 PDR ADOCK 05000254
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