ML19323B799
| ML19323B799 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/19/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19323B797 | List: |
| References | |
| 50-254-80-04, 50-254-80-4, 50-265-80-06, 50-265-80-6, NUDOCS 8005140282 | |
| Download: ML19323B799 (1) | |
Text
O 8 " s 14 0t"d Appendix A NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-254; 50-265 Based on the inspection conducted on February 4, 1980 thru March 3, 1980, it. appears that certain of your activities were in noncompliance with NRC requirements, as noted below.
Items 1 and 2 are infractions, and item 3 is a deficiency.
1.
Unit 1 Technical Specification, Section 3.2.6, Post Accident Instru-mentation, Table 3.2-4 requires that a minimum of 2 channels be operable. From and after the date that one of these parameters is reduced to one indication, continued operation is not permissible beyond thirty days.
Cont rary to the above, during the period June,1978-January 11, 1980 the differential pressure transmitter which provides one indication of drywell to torusA P for Post Accident monitoring was inoperable and therefore, operation in excess of 30 days with only one operable channel occured during this period.
2.
Unit 1 Technical Specifications, Section 6.2.A.1 requires that operation of the reactor and other systems and components involving nuclear safety of the facility be p aiormed in accordance with detailed written procedures and applicable checkoff lists.
Contrary to the above, on February 22, 1980 while performing surveil-lance test QIS-17-2, "RCIC Low Pressure Functional Test," the operator failed to return the steam inlet valves to their normal operating configuration as stated in Step F.2.I.
3.
Unit 1 and 2 Technical Specifications, Section 6.2.A.1 requires that operation of the reactor and other systems and components in-volving nuclear safety of the facility be performed in accord-ance with detailed wrJtten procedures and applicable checkoff lists.
Contrary to the above, on February 22, 1980 the NRC inspector determined that procedure QOS-005-S1, " Weekly Summary of Daily Sur-veillance", Checklist did not include RCIC steam valves 1301-16 and 1301-17 and HPCI steam valves 2301-3, 2301-4 and 2301-5 to be monitor-ed on panel checks.
The licensee's corrective and preventive actions have been reviewed and appear to be adequate; therefore, no further response to these items is required.
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