ML20008E193
| ML20008E193 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/07/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20008E184 | List: |
| References | |
| 50-219-80-19, 50-219-80-21, NUDOCS 8010240347 | |
| Download: ML20008E193 (1) | |
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APPENDIX A NOTICE OF VIOLATION Jersey Central Power and Light Company Docket No. 50-219 Based on the results of NRC inspections conducted over the period May 6, 1980 to May 30, 1980, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Facility License DPR-16 as indicated below.
Items A and B are Infractions.
A.
Technical Specification 6.8.1 states in part " Written procedures shall be established, implemented...."
Procedure 501, " Annunciators and Alarms" Section 3F.G, " Fuel Pool High Level or High Temperature", states,. in part:
" Adjust fuel pool level as necessary by draining system to either the hotwell...or rad waste...,".
Contrary to the above, on May 8, 1980 at approximately 12 noon, a fuel pool high level alarm was annunciated on panel 3FG.
The high level alarm was investigated at that time, however, no attempt was made to lower the fuel pool level in accordance with procedure 501.
This, in conjunction with the failure to perform subsequent observations of fuel pool level during the time the high level alarm was annunciated (12 Noon to 6:00 p.m.),
resulted in the overflow of approximately 1000 gallons of slightly radio-activity contaminated water into the reactor building ventilation ducts via the fuel pool ventilation skimmers.
B.
Technical Specification 6.8.1 states in part, " Written procedures shall be established, implemented, and maintained that meet or exceed the require-ments of Section 5.1 and 5.3 of American National Standard N18.7-1972....".
American National Standard N18.7-1972, Section 5.3 states, in part:
" Nuclear power plants shall be operated in accordance with written procedures....
Each procedure shall be sufficiently detailed for a qualified individual to perform the required function without direct supervision...,".
Contrary to the above, inadequacies in Procedure 205.7, " Fuel Cell Unload-ing/ Loading" permitted the interlocks, which prevent withdrawal of more i
than one control rod while the reactor is in the " refuel" mode, to be l
improperly bypassed on control rods 10-23 and 14-15.
This condition existed from February 18, 1980 to May 16, 1980.
l soiom 347