ML20009D881
| ML20009D881 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 04/30/1981 |
| From: | Robert Carlson, Crocker H, Kinney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20009D874 | List: |
| References | |
| 70-0820-81-27A, 70-820-81-27A, NUDOCS 8107240458 | |
| Download: ML20009D881 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Supplemental Report No.
70-820/80-27A Docket No.70-820 License No.
SNM-777 Priority 1
Category UR Licensee:
United Nuclear Corporation UNC Recovery Systems Wood River Junction, Rhode Island 02894 Facility Name:
Fuel Recovery Operation Investigation at:
Wood River Junction, Rhode Islrd Investigation conducted:
March 3, 1981 M.D/P/
Investigators:
/ date 41gne'd H. W. Crocker, Chief, Fuel Facility Projects Secti n l
EM W.' W. Kinfey, Fupf Facility Inspector date signed
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, LS hof Y-L WI R. I. Shephet nv'estigation Specialist date signed Approved by:
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R. T. Carlson, Director, Enforcement and date signed Investigation Staff i
l Investigation Summary:
Investigation on March 3, 1981 (Report No. 70-820/fc-27A)
Areas Investigated:
NRC Region I personnel sampled and analyzed the soil at additional locations ta the general area where the licensee allegedly discharged lagoon liquid waste onto the ground during 1978.
Results:
The NRC's analys'.s of the above soil samples indicated no uranium or cesium in the soil where the lagoon waste was allegedly discharged onto the ground.
8107240458 810707 DR ADOCK 07000 l
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SUMMARY
This report supplements NRC Region I Invc;tigation Report No. 70-8?0/80-27 concerning allegations that the licensee pumped radioactive liquid waste from an evaporation lagoon onto the ground during 1978 and that the discharged liquid eroded the soil under the security fence such that a person could, crawl under it.
NRC Region I personnel sampled and analyzed the soil at various points along the east side of the protected area where the security fence was situated during 1978 when the alleged pumping of liquid waste onto the ground occurred.
No uranium or cesium was detected in the above samples.
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DETAILS As reported in NRC Region I Investigation Report Nc. 70-820/80-27, NRC Region I personnel sampled and analyzed the soil at various locations in the general area where the licensee allegedly pumped radioactive liquid water from an evaporation lagoon onto the ground during 1978.
The above soil samples were taken on December 12, 1980 and the analyses of the samples indicated that lagoon material was not present.
On March 3, 1981, NRC Region I personnel obtained additional soil samples at the UNC site.
These samples were taken at various points along the east side of the protected area where the security tence was situated during 1978 when the alleged pumping of liquid waste onto the ground occurred.
The licensee relocated the east side of the security fence on or about February 1979 when he enlarged the protected area boundary.
The above soil samples were taken at points along the old security fence line which measured 60 feet, 90 feet and 120 feet south of the northeast corner of the fence, at depths of 12 inches, 30 inches and 48 inches at each location.
Portions of the samples were also given to the licensee and the Rhode Island Department of Health.
The core of the sampling device which was used in taking the above samples measured approxi-mately 6 inches long and 3 inches in diameter.
No uranium or cesium was detected in the above samples.
The results of the NRC's analyses of the above samples are listed in Table I (Exhibit 1).
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STATUS OF IN'/ESTIGATION The status of this investigation is CLOSED.
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ENCLOSURES 1.
Soil Sample Analyses, Table I e
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TABLE I SOIL SAMPLE ANALYSES Distance from Northeast Sample Depth Results*
Sample No.
Corner of Fence (in feet)
(in inches)
(pCi/cm)
AA-1 60 9-15 Ra-226**0.65 + 0.11 Ra-228 1.3 10.4 AA-2 60 27-33 Ra-226 0.83 + 0.12 Ra-228 2.1 10.3 AA-3 60 45-51 Ra-226 0.57 + 0.11 Ra-228 1.0 }0.3 88-1 90 9-15 Ra-226 0.91 + 0.10 Ra-228 0.9510.26 88-2.
90 27-33 Ra-226 1.10 + 0.13 Ra-223 1.5 }0.3 BB-3 90 45-51 Ra-226 0.43 + 0.10 Ra-228 0.7 }0.4 CC-1 120 9-15 Ra-226 0.70 + 0.12 Ra-228 1.5 30.2 CC-2 129 27-33 Ra-226 0.71 + 0.12 Ra-228 1.4 {0.3 CC-3 120 4S-51 Ra-226 0.51 + 0.13 l
Ra-228 1.1 10.2
- Gamma spectroscopic analysis results are + 1 standard deviation counting error and should include a systematic error of + 50%.
- Ra-226 background typically is 0.8 pCi/gm for the U.S.
(NCRP Report No. 50).
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