ML19338E395
| ML19338E395 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/13/1973 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19338E392 | List: |
| References | |
| 50-010-73-03, 50-10-73-3, NUDOCS 8009260702 | |
| Download: ML19338E395 (2) | |
Text
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l ENCLOSURE
(
Commonwealth Edison Company i
Docket No. 50-10
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Certain activities under your license identified below appear to be in violation of AEC requirements.
A.
The following apparent violations are considered to be of Category II severity:
10 CFR Part 50, Appendix B, Criterion V, states in part that,
" Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions."
Contrcry to the abover 1.
The replacement of the motor on emergency condenser condensate valve MO-101, on April 15, 1973, was not performed in accordance with Commonwealth Edison Company Quality Assurance Manual, Quality Procedure Q.P. 8-52, and Station Administrative Procedure on Quality Control, Q.C.P. 3-51.1/8-52.1, Rev. O, in that the two-part stock tag was not used on this safety related item, therefore, tracebility of the used item to its purchase order was lost.
2.
Testing of the Unit 1 fire diesel pump following the replacement of its prime mover was not accomplished in accordance with Commonwealth Edison Company Quality Assurance Manual, Quality Requirement No. 11.0, until approximately one month after the unit had been placed in service. Quality Requirement No. ll.0, states that test programs will be established and documented following maintenance activities to assure that design and performance criteria have been satisfied.
B.
The following apparent violation is considered to be of Category III severity:
Technical Specification J.5.c(1) requires that substantial variance in the performance of a system or component designed to prevent or mitigate the consequences of nuclear accidents be reported in writing to the Commission within 30 days.
Contrary to the above, several cases of nuclear instrumentation power range channels scraa setpoint drift above the limits established in the Technical Specifications were not reported. For the period inspected (June 1,1972, to July 31, 1973), 12 occasions of channel 8009260 7CR
1 drift above the maximum allowable setting of 123 percent of rated power were noted. These ranged from 124 percent to as high as 140 percent of rated power, and involved as many as three of the six channels on two occasions. Nine of the twelve events were not reported prior to June 16, 1973.
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