ML19351G091
| ML19351G091 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/02/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19351G078 | List: |
| References | |
| 50-293-80-26, NUDOCS 8102230100 | |
| Download: ML19351G091 (1) | |
Text
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O APPENDIX A NOTICE OF VIOLATION Boston Edison Company Docket No. 50-293 Based on the results of an NRC inspection conducted on August 1-31, 1980, it appears that certain of your activities were not conducted in full compliance with your NRC Facility License No. DPR-35, as indicated below.
Item A is cate-gorized as an infraction and Item B is a deficiency.
A.
Technical Specification 2.1. A.1.a states in part that:
...the APRM flux scram trip setting shall be :S<.65 W + 55% 2 loop where S = setting in percent of rated thennal power-(1998 mwt); W = percent of drive flow."
i Contrary to the above, on July 28, 1980, the reactor was operating in the RUN mode with the APRM flux scram settings (at 100% drive flow) as high as 122.9 percent of rated thermal power.
B.
Technical Specification 2.1. A.1.a requires that the APRM flux scram trip settings not exceed 120% of rated thermal power for all combinations of loop flow and core power.
Technical Specification 6.9.B.2.a requires a 30 day report to the NRC whenever a reactor protection system instrument setting is found to be less conservative than those established by the Technical Specifications, but which do not prevent fullfillment of the functional requirements of affected systems.
Contrary to the above, a 30 day report to the NRC was not made when the Channel 'F' APRM 120% clamp trip setpoint was found to be outside the technical specification limits during performance of Procedure 8.M.1-4 "APRM Flow Bias Signal Calibration" Revision 6, on July 1,1980.
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