ML20036C114
| ML20036C114 | |
| Person / Time | |
|---|---|
| Site: | 05000124 |
| Issue date: | 08/10/1987 |
| From: | Murphy G OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 9306140091 | |
| Download: ML20036C114 (2) | |
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Oak Ridge Manpower EaucaDon Associated Post Office Box 117 Researcn and Traininc
' Universities Oak Ridge, Tennessee 37831-0117 D m or August 10, 1987 Mr. Charles liosey p\\
Nuclear Regulatory Commission Region 11 Suite 2900 101 Marietta St.
Atlanta, CA 30323 Subj ec t :
CONFIRMATORY RADIOLOGICAL SURVEY OF THE ARGONAUT REACTOR FACILITY, VIRGINIA POLYTECHNIC INSTITUTE, BLACKSBURG, VIRGINIA
Dear Mr. Hosey:
During the period of July 27 - 31, 1987, Oak Ridge Associated Universit[es (ORAU) performed a confirmatory radiological survey of the Argonaut Reactor Facility, Virginia Polytechnic Institute (VPI), Blacksburg, Virginia. The purpose of the survey was to confirm that the site had been decontaminated to guidelines established by the Nuclear Regulatory Commission (NRC) for release for unrestricted use.
The survey was conducted in accordance with a proposed survey plan submitted to NRC Region 11 for review and concurrance. The areas surveyed included rooms 6, 6A, 8, 8A, 10, and 108.
The survey identified one small area of contamination exceeding the beta-gamma surf ace contamination guidelines.
The area was remediated, resurveyed, and found to be within the beta-ganma surf ace contamination 2
2 guidelines (15,000 dpm/100 cm maximum and 5,000 dpm/100 cm average). All data generated during the survey support the licensee's final close-out survey report, that the residual contamination levels are within the guidelines for release for unrestricted use.
Based on these results, it is ORAU's opinion that the licensee 's report accurately and adequately represents the radiological conditions of the VP1 Reactor Facility, and that the f acility complies with NRC guidelines for release for unrestricted use.
ORAU was also asked to address the issue of disposal of materials related to the decommissioning effort at the VPI landfill.
Concrete shield material and soil excavated f rom beneath the reactor floor were surveyed for direct gamma exposure rate levels at one meter, and released to the landfill.
During our.
survey, we f ound an area within the concrete blocks with elevated gamma radiation levels. The exposure rate measurements at one meter could not be performed due to inaccessibility. VPI agreed to remove the blocks and perform additional surveys; then leave the blocks in a separated array to allow ORAU to survey the area at a later date. Additionally, a soil sample collected from the area had detectable radionuclide concentrations as follows: Co-60 (10.6 1 0.7 pCi/g),
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Mr. Hosey August 10, 1987 Co-57 (11.2 1 0.4 pCi/g), Eu-152 (30.7 1 1.6 pC1/g), and Eu-154 (23.3 0.8 pCi/g). The NRC has released other sites with Co-60 soil concentrations ranging from 8 to 10 pCi/g, based on a direct exposure pathway of 10 pR/h. ORAU recommends that further radiological characterization of the landfill be conducted at a later date.
If you have any questions or comments, please give me a call at (FTS) 626-0048 or commercial (615) 576-0048.
Sincerely, du
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Glenn L. Murphy, ssistant Manager Radiological Site Assessment Program GLM/sjf cc:
Mr.'B. Revson, NRC/ Region Il fr.D. Sly,NRC/16E i
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