ML20148A151
| ML20148A151 | |
| Person / Time | |
|---|---|
| Site: | 07000820 |
| Issue date: | 10/12/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20148A121 | List: |
| References | |
| 70-0820-78-21, 70-820-78-21, NUDOCS 7812280245 | |
| Download: ML20148A151 (2) | |
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APPENDIX A NOTICE OF VIOLATION United Nuclear Corporation Docket No.70-820 Wood River Junction, Rhode Island License No. SNM-777 Based on the results of an NRC inspection conducted on September 12-15, 1978, it appears that certain of your activities were not conducted in full compliance with NRC regulations and the conditions of your facility license as indicated below. Items A and B are infractions. Item C is a deficiency.
A. Condition 9 of your facility license, which incorporates Section 205, " Process Control" of your approved license application, dated October 13, 1975, requires in part, in paragraph 205.1, " General ,"
that supervision at all levels assure themselves that suitable control measures are prescribed and that all pertinent regulations, controls and procedures relative to nuclear criticality safety or radiological safety are followed by supervision and all operating personnel.
SOP III-A, Revision V, dated October 19, 1976, " Receiving SNM,"
requires, in part, under " Procedures" that, "tne ':ransporting vehicles shall be cleared by NIS before le6vi w Ine plant site."
S0P III-C, Revision I, issued May 1, 1976, "Frocedures for Packaging Product Containers and Outgoing SNM Shipment" requires, in part, under " Procedures" that " prior to departure from the plant site, the transporting vehicles will be monitored by the NIS Department or their authorized representative for radiation and contamination levels."
Contrary to the above,
- 1. On September 13, 1978, supervision did not assure themselves that suitable contro" measures were prescribed for the proper precautions to be taken when using contaminated gloves in that procedures have not been established to prevent the spread of contamination in the process area. Contaminated gloves were observed being removed from process equipment without regard to contamination control practices.
- 2. Between January 1, 1978, and June 29, 1978, supervision did not assure themselves that procedures relative to radiological safety were followed, in that, 37 of 41 transporting vehicles bringing SNM into the facility were not cleared by NIS before leaving the site and 38 of 45 transporting veheicles carrying SNM from the facility, were not monitored for radiation and contamination levels by the NIS Department or their authorized representative.
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. Appendix A 2 B. Title 10 CFR 21.21(a) " Notification of failure to comply or existence of a defect" requires that, "Each individual, corporation, partnership or other entity subject to the regulations in this part shall adopt appropriate procedures to (1) provide for (i) evaluating deviations or (ii) informing the licensee or purchaser of the deviation in order that the licensee or purchaser may cause the deviation to be evaluated unless the deviation has been corrected; and (2) assure .
that a director or responsible officer is informed if the construction or operation of a facility, or activity, or a basic component supplied for such facility or activity: (i) Fails to comply with - t the Atomic Energy Act of 1954, as amended, or any applicable rule, regulation, order or license of the Commission relating to a substantial safety hazard, or, (ii) Contains a defect."
Contrary to the above, on September 15, 1978, appropriate procedures had not been adopted, approved, and implemented pursuant to the ,
regulations in this part. It was noted that the appropriate draft ,
procedures were available for use by the licensee.
C. Condition 9 of your facility license, which incorporates Section 307, " Marking and Labeling" of your approved license application, ,
dated December 31, 1974, requires, in part, in paragraph 307.1
" Criticality Limits" that " signs listing approved nuclear criticality safety limits shall be posted so that inf armation is readily discernible to employees." Paragraph 307.2 " Process Containers" requires, in part, that, " empty containers used for SNM shall be identified or . .
marked as empty."
Contrary to the above, on September 13, 1978, signs listing approved nuclear criticality safety limits were not posted so that information is readily discernible to employees on the muffle box storage rack, the 1-L-3C hood and the 4-L-2A hood. In addition, two empty muffle ,
boxes used for SNM were not identified or marked as being empty.
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