ML20236R691

Insp Rept 70-0820/87-02 on 870827-28.No Violations Noted. Major Areas Inspected:Status of Decommissioning of Site & Bldgs & Conduct of Verification Survey by NRC Contractor. Water Samples from Selected Wells Obtained

ML20236R691
Person / Time
Site:	Wood River Junction
Issue date:	11/18/1987
From:	Pasciak W, Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20236R683	List: ML20236R680 ML20236R691
References
70-0820-87-02, 70-820-87-2, NUDOCS 8711230428
Download: ML20236R691 (4)

Text

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U. S. NUCLEAR REGULATORY COMMISSION REGION I Report No. 70-820/87-02 Docket No.70-820 License No. SNM-777 Priority 1 Category URD Licensee: United Nuclear Corporation Recovery Systems Wood River Junction, Rhode Island 02894 Facility Name: UNC Recovery Systems l

Inspection At: Wood River Junction, Rhode Island Inspection Conducted: August 27-28, 1987 Inspectors: ,. //- // /7 87 J th, Project Engineer date Approved by: k- / fan &v i fi /# 7 l W. J. Pasciak, Chief, ' date Effluents Radiation Pro (tection Section, DRSS-l Insoection Summary: Inspection on August 27-28, 1987 (Inspection Report No.

70-320/87-02).

Areas Inspected: Special announced inspection by one region-based inspector for the purpose of obtaining water samples from selected monitoring wells, to examine the status of decommissioning the site and'the buildings and to observe the conduct of a verification survey by an NRC csntractor.

Results: No violations were identified.

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8711230428 871118 PDR ADOCK 07000920t C ,

PDR

DETAILS

1. Persons Contacted i K. Helgeson, Ma' nager Nuclear and Industrial Safety J. Murphy, Health Physics Technician

2. Monitoring Well Water Sampling The inspector observed the sampling of each monitoring well. Prior to sampling, each well was pumped for about 10 minutes in order to clear the lines of standing water. This water was discarded. The licensee took a i five (5) gallon sample from each well and the NRC samples (one (1) l gallon) were taken (split) from the licensee's samples, i

a. Well Water Sampling The condition under which each well sample was obtained are shown in the enclosed table.

b. Sample Analysis The well water samples marked in the table above with an

• were split by the NRC inspector with the licensee. Samples obtained by the NRC were sent to the USD0E Radiological and Environmental Services Laboratory (RESL) located in Idaho Falls, Idaho, for analysis. The licensee's samples were sent to Controls for Environ-mental Pollution, Inc., located in Santa Fe, New Mexico. Samples in excess of 5 picocuries/ liter gross alpha and/or 50 picocuries/ liter gross beta will be further analyzed, as necessary, for strontium-90, cesium-137, uranium isotopic, thorium isotopic, and gamma spectroscopy.

c. Sample Analysis Results The sample analysis results from each laboratory will be compared by Region I. This comparison and a trend analysis, utilizing results from prior years, will be addressed in a subsequent inspection report. This is an Inspector Followup Item (IFI 87-02-01).

3. NRC Independent Review

a. Observations Concerning the Status of Site Decontamination Subsequent to Inspection No. 70-820/86-02 the licensee completed removal of contaminated soil from grid blocks previously identified as contaminated. Those grid blocks included Grid Nos. D-64, D-70/71, D-94, D-96 and B-126. During this inspection, the inspec-i tor was accompanied to the site by the NRC contractor, Oak Ridge Associated Universities (0RAU) for the purpose of conducting a verification survey of the decontaminated grid blocks.

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3 Radiation surveys were conducted and soil samples were taken from each grid block. The soil samples were obtained by compositing soil removed from the four corners and the center of each block, while being observed by the inspector and licensee representatives. The soil samples were transported to the ORAU laboratories in Oak Ridge, l Tennessee where they were subsequently ground, mixed and split into I

three fractions. One fraction was to be analyzed by ORAU, the second fraction was sent to the licensee's contractor, Controls for Environmental Pollution, Inc. for analysis and the third fraction was retained for the NRC by ORAU for referee analysis, if required.

Following analysis, each laboratory is to provide the inspector with the analytical results for review and evaluation. If the analytical results from each laboratory are similar and are lower than the NRC guidance value of 30 picocuries total uranium per gram of soil, Region I will recommend that NRC-NMSS release the licensee's outside area, within the restricted area fence, for unrestricted use. If the analytical results are not similar, the referee sample will be sent to RESL for analysis. If the sample analysis results indicate that further soil decontamination is required, the licensee will be informed. This was identified as an Inspector Followup Item (87-02-02).

4. Licensee Discussions The inspector held continuing discussions with Mr. K. Helgeson during the inspection. The findings were presented as they were identified. At no time during this inspection written material provided to the licensee by the inspector. the enclosed table.

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WELL WATER SAMPLES l

Specific j Well Sampling Sampling Conductivity Water Well  ;

No. Date Time (umhos) Level (ft) Depth (ft) i T-1 8/27 1348 50 19 65 T-2 8/27 1250 70 22 57 T-3* 8/27 1054 68 22 62 T-4 8/28 0933 96 22 62 T-5 8/27 0925 58 24 65 T-6* 8/27 0940 86 23.5 52 T-7* 8/28 0948 66 24 65 T-8* 8/27 1024 52 19 65 T-9 8/27 1008 72 24 53 PW-1 NOT IN SERVICE -- -- --

PW-2* 8/28 0857 52 -- --

W-A NOT IN SERVICE -- -- --

W-B* 8/27 1235 64 22 28 W-D 8/27 1118 62 23 30 W-E* 8/27 1416 42 19 28 W-3* 8/27 1307 62 22 25 W-5 8/27 1345 60 19 26 W-6 8/27 1321 60 20 26 W-7* 8/27 1131 62 --

26 W-8A* 8/27 1107 84 22 30 W-9 8/28 0915 56 20 33 W-10 8/28 0835 40 18 35 W-11 NOT IN SERVICE -- -- --

W-12* 8/27 1042 94 22 35 76-U* 8/28 1005 200 --

75 77-B* 8/28 1040 2600 18 75 77-D* 8/28 1024 84 25 85 DH-1* 8/27 0954 88 22 23-35 DH-1-1 NOT IN SERVICE -- -- --

DH-2-1 NOT IN SERVICE -- -- --

DH-2-2 NOT IN SERVICE -- -- --

DH-2-2 NOT IN SERVICE -- -- --