ML19276F933
| ML19276F933 | |
| Person / Time | |
|---|---|
| Site: | 07001319 |
| Issue date: | 02/01/1979 |
| From: | Dan Collins, Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19276F926 | List: |
| References | |
| 70-1319-79-01, 70-1319-79-1, NUDOCS 7904250384 | |
| Download: ML19276F933 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION
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.r 101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30303
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Report No.:
70-1319/79-1 Docket No. : 70-1319 License No. : SNM-1315 Licensee:
U. S. Nuclear, Inc.
P. O. Box 680 Oak Ridge, Tennessee 37830 Facility Name:
U. S. Nuclear Fabrication Plant Inspection at: Oak Ridge, Tennessee Inspection conducted: January S-9,1979 Inspector:
D. M. Co in
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Reviewe by:
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g A. F. Gibs hief
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Radiation port Section Fuel Facility and Materials Safety Branch Inspection Summag Inspection on January 8-9, 1979 (Report No. 70-1319/79-1)
Areas Inspected: Special, announced inspection of status of decontamination and decommissioning operations. The inspection involved thirteen inspector-hours on-site by one NRC inspector.
Results: One item of noncompliance was identified (deficiency - failure to provide adequate employee termination reports (79-1-1), paragraph 7).
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1 RII Rpt. No. 70-1319/79-1 DETAILS Prepared by:.h M7 Gc u J/, /?')
D. M. Collins, Radiation Specialist Date Radiation Support Section Fuel Facility and Materials Safety Branch Dates of Inspectio.
nua 8-9, 1979
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Reviewe by:
p A. F. Ggfon, Chief Date Radiath(n Support Section Fuel Facility and Materials Safety Branch 1.
Persons Contacted
- S. Weaver, President G. Carroll, Technician
- Denotes individual present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (0 pen) Noncompliance - Failure to Adequately Survey (78-1-1)
This item concerns the failure to air sample during HEPA filter removal and was originally discussed in IE Report 70-1319/78-1.
A licensee representative stated that he intended to have the workers involved in the decontamination operations lung counted when the operation was completed.
3.
Unresolved Items
~
No new unresolved items were disclosed during this inspection.
4.
Facility Surveys a.
The inspector accompanied a licensee representative while he made total contamination surveys of the floors in the Melt Room, Met Lab, Accountability Lab, Hall, and Powder Room. The inspector made measurements using an NRC instrument in approximately the same locations as the licensee's measurements.
The inspector noted that, in general, the readings recorded on the NRC instrument were approximately twenty percent higher than those recorded on the licensee's instrument.
The inspector checked the licensee's instrument readings by comparing the reading given for an NRC alpha standard.
The licensee's instrument read approximately twenty percent below the actual source value. A licensee representative
I RII Rpt. No. 70-1319/79-1 stated that the values recorded on his instrument would be recorded for the of ficial survey and submitted to the NRC. The inspector examined the records of the licensee's survey instrument calibra-tion dated December 8, 1978.
The inspector had no further questions.
b.
During the surveys, the inspector discussed the survey results with a licensee representative. The inspector commented that the results were being recorded in units of disintegrations per minute (dpm) per probe area but that the limits for contamination were expressed 2
2 in dpm per 100 cm. Since the probe face was 59 cm, the inspector noted that the results would have to be adjusted for comparison to the limit. The licensee representative stated that the adjustments would be made prior to submitting the survey. The inspector had no further questions.
c.
During the survey the inspector observed eight readings by the 2
licensee representative that were above 5000 dpm/100 cm average limit.
The licensee representative stated that further readings would be taken to determine what the average reading was over one square meter.
The survey also showed one location where the 2
readings were above the 15,000 dpm/100 cm maximum.
A licensee representative stated that this and other possible areas would be cleaned.
d.
During the' survey the inspector noted that three pieces of equip-ment in the Melt Room, two presses and one rolling mill, had been stripped of paint.
A licensee representative stated that he planned to sell these items as noncontaminated. He said there was only a few spots on the rolling mill that needed further decon-tamination. The inspector commented that surveys to release the items should also consider the insides of electric motors asso-ciated with the equipment. The inspector had no further questions.
During tours of the plant the inspector observed additional equip-e.
ment in the noncontaminated area. A licensee representative stated that the equipment had been purchased when U.S. Nuclear went into business, had been stored at the Nuclear Ceramic's facility,and it was not supposed to be contaminated. He stated that surveys of the equipment would be made to verify that it was not contaminated.
The inspector surveyed for total ;ontamination, nine pieces of equipment in likely areas of contamination.
The highest reading 2
found was 250 dpm/100 cm,
f.
The inspector surveyed selected building areas, noncontaminated waste, and areas inside of the Powder Room ventilation system. The maximum total contamination reading inside the Powder Room HEPA
RII Rpt. No. 70-1319/79-1 2 filter hou'ing was 1022 dpm/100 cm.
The maximum total contami-2 nation reading found on the Melt Room floor was 7225 dpm/100 cm,
The inspector had no further questions.
g.
During tours of the areas, the inspector observed several pieces of equipment in the noncontaminated area tagged as sold and one press in the Melt Room tagged as sold. A licensee representative stated that such equipment was being sold. The inspector had no further questions.
h.
The inspector observed operations in the noncontaminated area. A licensee representative stated that some nonradioactive work was being done, mostly heat-treating of bellows. The inspector surveyed f our bellows that had been heat-treated and were ready for shipment.
No readings above background were observed.
5.
Instrument Calibration The inspector discussed radiation survey instrument calibration with licensee representatives. The inspector examined records of calibration dated December 8, 1978. No items of noncompliance or deviations were observed by the inspector.
6.
Shipments of Rad-ioactive Material The inspector discussed with a licensee representative the shipment of radioactive waste and the transfer of contaminated equipment to the Department of Energy (DOE).
The inspector examined records of waste shipments dated March 31 and December 7,1978. A licensee representa-tive stated that the records of transfer to DOE were at the Nuclear Ceramics facility. The inspector stated that these and other transfer records would be reviewed in the future. The inspector had no further questions.
7.
Termination Reports The inspector examined records dated March 7 and May 2, 1977, of reports of radiation dose and bioassay results sent to the NRC and to employees upon their termination. The inspector compared the results recorded on the letter to the NRC with those contained in the letter to the selected employees and that recorded in these employees' personnel dosimetry files.
The licensee was required by 10 CFR 20.408 and by 10 CFR 19.13(d) to provide reports of radiation exposure and bioassary results to employees upon their termination of employment.
The licensee was required by Condition 8 of the license to conduct a bioassay program in accordance with Regulatory Guide 8.11.
The inspector noted that the report to the h7C contained only the last urinalysis result, rather than all results or average results, and did not contain the results of lung
RII Rpt. No. 70-1319/79-1 counts. The inspector noted that the reports to individuals included only the last urine and lung count results. The inspector informed licensee representatives that the failure to include a summary of all bioassay results in the reports to the NRC and to individuals would be considered an item of noncompliance (79-1-1).
8.
External Dose The inspector examined the records of film badge monitoring results for the first quarter 1977. The licensee was required by 10 CFR 20.202 and 20.101 to monitor limit dose. No items of noncompliance or deviations were observed by the inspector.
9.
Dosimetry The inspector discussed the transfer of worker personnel dosimetry records to the USNRC upon termination of the license.
A licensee representative agreed to such a transfer and suggested other records might also be transferred.
10.
Exit Interview The inspector met with Dr. S. C. Weaver on January 9, 1978, and discussed the scope and findings of the inspection.
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