ML19309E330
| ML19309E330 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 11/09/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19309E310 | List: |
| References | |
| 70-1100-79-09, 70-1100-79-9, NUDOCS 8004210143 | |
| Download: ML19309E330 (3) | |
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APPENDIX A NOTICE OF VIOLATION Combustion Engineering, Inc.
Docket No. 70-1100 Based on the results of an NRC inspection conducted on October 9-12, 1979, it appears that certain of your activities were not conducted in full compliance with conditions of your NRC License No. SNM-1067 and federal regulations as indicated below.
Items' A through D are infractions.
Item E is a deficiency.
A.
License Condition 9 incorporates Section 8.1, " Nuclear Laboratories," of the licensee's approved license application, Page VIII-2, Revision 4, dated September 16, 1978, and Section 8.2, " Nuclear Fuel Manufactoring-Windsor,"
of the licensee's approved license application, Page VIII-5, Revision 4, dated March 15, 1978, which require, in part, that Management is responsible for the nuclear safety and radiological safety related to all Special Nuclear and Source Material used and will assure that all operations involving nuclear materials have been analyzed to establish required safety units and controls.
In addition, Section 8 states that written operating procedures are provided for all operations...
Contrary to the above, on October 9-11, 1979:
1.
Management did not assure that nuclear and radiological safety controls had been established in that " Operations Sheet OS-1462, dated December 20, 1979", did not address the procedure for removing
" knockdown" filter pieces from the glovebox; assuring that other SNM had been removed from the criticality control zones in the sinterability test hood prior to initiating the liner washing operation; radiological protection procedures to assure that contamination of personnel and the work area is minimized; assuring that the sinterability test hood was posted with criticality control signs reflecting limits for the operation being conducted; the frequency for changing wash and rinse water.
2.
Management did not assure that radiological safety controls had been established in that personnel exiting the unclad fuel handling area of Building 17 were not required to survey their bodies, clothes, and shoes for radioactive contamination.
3.
Management did not assure that radiological safety controls had been established in that fixed alpha radioactive contamination surveys are not conducted in clean areas.
4.
Management did not assure that written operating procedures are provided for the use of a vacuum cleaning system located in the Building 5 ceramics laboratory.
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t APPENDIX A 2
l B.
License Condition 9 incorporates Section 8.2, " Nuclear Fuel Manufacturing-Windsor," of the licensee's approved license application, Page VIII-5, l
Revision 4, dated March 15, 1978, which requires, in part, that Management t
is responsible for the nuclear safety and radiological safety related to l
all Special Nuclear and Source Material used and will assure that all l
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operations involving nuclear materials have been analyzed to establish required safety units and controls.
Section 8.2 also states that the
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Nuclear Licensing and Safety Supervisor must review and approve proposed changes and that all such approvals shall be recorded.in a log maintained under the direct supervision of the Nuclear Licensing and Safety Supervisor.
j Contrary to the above, on October 9-12,1979:
1.
Management did not assure that the use of open not-safe-by geometry containers in the unclad fuel handling areas of Building 17, had been analyzed to establish required safety units and controls, and, t
had been reviewed and approved by the Nuclear Licensing and Safety l
Supervisor.
l 2.
Approval for the storage of closed contaminated waste drums (containing i
up to 150 grams U-235) anywhere in the unclad fuel handling areas of Building 17 was not recorded in a log maintained under the direct i
supervision of the Nuclear Licensing and Safety Supervisor.
j C.
License Condition 9 incorporates Section 3.5 "In-Process Rod Storage Racks," Page C-108, dated January 20, 1978, of the demonstration section of the license application into the facility license.
Section 3.5 states, in part, that each box is equipped with a tight fitting aluminum cover which overlaps the outside edge of the box by a minimum of one inch.
One box may remain uncovered for short periods of time... provided that personnel are in attendance.
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Contrary to the above, on October 9, 1979, a " rod" box, stored on one of the in process rod storage racks in work station #M-129, was not fully covered as required and was not attended by personnel.
l D.
License Condition 9 incorporates Section 15.3, " Area Delineations," of the licensee's approved license application, which, in Paragraph 15.3.5,
" Clean Areas," Page XV-6, Revision 3, dated March 15, 1974, states, in part, that a clean area is'an area which.is free from radioactive contam-j ination... significantly greager than background.
A maximum removable j
alpha level of 100 dpm/100 cm is permitted.
Contrary to the above, on October 9, contamination level of 100 dpm/100 cm}979, the maximum removable alpha was exceeded on the' clean side of i
the mens change room, a clean area, in that a removable contamination 2
level of 244 dpm/100 cm was observed.
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e APPENDIX A 3
E.
License Condition 9 incorporates Section 8.2, " Nuclear Fuel Manufacturing-Windsor," of the licensee's approved license application, which requires on Page VIII-6, Revision 7, dated March 15, 1978, in part, that signs, including criticality limits as approved by the Nuclear Licensing and Safety Supervisor, are posted near the appropriate work station...
Contrary to the above, on October 9-11, 1979:
1.
Signs, including criticality limits, for a transfer cart located in the Rod Box Storage Area near the Fluoroscope Area, for the storago of closed contamination drums in the unclad fuel handling area and for the storage of the nondestructive assay unit calibration drums were not posted near the appropriate work station.
2.
A sign, including the appropriate criticality limits for the operation being conducted, had not been posted at work station P-23.
Other signs, which were not applicable to the operation being conducted, were posted at this work station.
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