ML20204A035
| ML20204A035 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 04/03/1986 |
| From: | Keimig R, Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20204A030 | List: |
| References | |
| 70-0820-86-01, 70-820-86-1, NUDOCS 8605090292 | |
| Download: ML20204A035 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I Report No.
70-820/86-01 Docket No.70-820 License No.
SNM-777 Priority 1
Category UHD I
Licensee: United Nuclear Corporation Recovery Systems i
i Wood River Junction, Rhode Island 02894 Facility Name: UNC Recovery Systems k
Inspection At: Wood River Junction, Rhode Island i
-Inspection Conducted: March 4, 1986 Inspector:
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R g. Keimig, hief, feguards Section, date Nuclear Mate al Saf y and Safeguards Branch, DRS Inspection Summary:
Inspection on March 4, 1986 (Report No. 70-820/86-01) 4 Areas Inspected: Special announced inspection by a region-based inspector for the purpose of examining the status of facility decommissioning, l
Results: No violations were identified. The licensee initiated removal of additional contaminated soil from areas inside the restricted area fence.
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DETAILS 1.
Persons Contacted R. J. Gregg, Plant Manager K. Helgeson, Manager, Nuclear and Industrial Safety
===2.
Background===
During Inspection No. 70-820/85-03, the inspector discussed the contents of the interim Oak Ridge Associated Universities (0RAU) confirmatory survey report concerning the land areas of the site within the former restricted area fence. As shown in Attachment No. I to this report, certain land areas within the confines of the former lagoon area appear to be contaminated in a systematic manner approximately corresponding to some of the walls of the former lagoon trenches.
In addition, subsequent to that inspection, on September 6, 1985 the licensee also discussed the contents of the interim ORAU report with NRC-NMSS personcel. As a result of these discussions, the licensee stated that contaminated soil in the areas identified in Attachment 2 would be removed, packaged and shipped to an approved burial site.
Following removal of the soil, the licensee will sample and analyze the soil for residual radionuclides.
The NRC will verify the licensee's results by indeoendent sampling.
This is an Inspec-tor Follow-up Item (IFI85-03-02).
3.
Inspector Observations The inspector observed, during a tour of the facility, that soil from the solid blocks shown in Attachment No. 2 had been removed to varying depths (from surface removal on paved areas to about five feet deep in other areas).
Additional scil must still be removed from those blocks identified with an X in Attachment No. 2.
The licensee was in the process of packaging the soil that had already been removed into 55 gallon drums.
Full drums were being stored in the former processing butiding, pending shipment to an approved burial site. The licensee stated that all soil removal was expected to be completed by May 1, 1986.
Packaging of the soil should be completed by June 1, 1986.
During examination of the processing building,the inspector observed that, since the last inspection, all internal wall surfaces at the east end of the building had been painted.
4.
1985 NRC Well Water Sample Analysis Results The NRC sample analyses results for well water samples collected on August 22-23, 1985, during Inspection No. 70-820/85-03, are presented in Table 1.
5.
Licensee Discussions The inspector held discussions with the licensee representatives denoted in paragraph 1 throughout the inspection.
Findings of this inspection were presented to the licensee as they were identified. No wricten ma-terial was provided to the licensee by the inspector during this inspec-tion.
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TABLE 1 NRC 198 WELL WATER SAMPLE ANALYSIS Gross Alpha Gross Beta Sr-90 Cs-137 Well No.
DC1/1)
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(pC1/1)
T-1 T-2 0
0 T-3 0
0 T-4 0.2 0.09 0
T-5 T-6 0.41 0.12 35 7
T-7 0
0 T-8 T-9 0.47 0.13 0
PW-1 NOT IN SERVICE PW-2 0.23 0.11 0
W-A NOT IN SERVICE W-B 8.2 0.8 13 1 6 W-D W-E W-3 12 1.1 8
6 W-5 W-6 W-7 W-8A 0.58 ! 0.14 0
w.9 W-10 W-11 NOT IN SERVICE W-12 0.2 0.12 0
76-U 0.5 0.2 29 7
77-B 2.6 0.7 170 20 12 4
0 77-D 0
0 DH-1 0
12 1 6 DH-1-1 NOT IN SERVICE DH-2-1 NOT IN SERVICE DH-2-2 NOT IN SERVICE As indicated in Table 1, none of the gross alpha results exceeded the EPA drinking water limit of 15 pC1/1 and only one of sixteen gross beta results exceeded the EPA limit of 50 pCi/1.
The EPA limits for Sr-90 and Cs-137 are 8 and 200 pCi/1, respectively. Only one Sr-90 result exceeded the EPA limit.
The analytical data shown in Table 1, when compared to the results from prior years, indicate a downward trend in the ground water contamination level. Well water samples will be split with the licensee during a subsequent NRC inspec-tion to be conducted during the summer of 1986.
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