IR 05000241/1982001
| ML20062J677 | |
| Person / Time | |
|---|---|
| Site: | 05000241 |
| Issue date: | 07/13/1982 |
| From: | Albright R, Barr K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20062J646 | List: |
| References | |
| 50-241-82-01, 50-241-82-1, NUDOCS 8208160437 | |
| Download: ML20062J677 (3) | |
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TAR RfGog UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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t Report No. 50-241/82-01
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i Licensee: Mississippi State University Mississippi State, MS 39762
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Facility Name:
Homogeneous Reactor Facility e
Docket No. 50-241 l
License No. CPPR-91 Inspection at Mississippi State University site near Starkville, MS.
Inspector:
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7- /3-82.
R. H. Albrig Date Signed K. P arNtTon" Chief 7'atef3 8&
Approved by:
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lgned Technical Inspection Branch
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Division of Engineering and Technical Programs SUMMARY
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Inspection on June 21-22, 1982 Areas Inspected
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This routine, announced inspection involved six inspector-hours on site.
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purpose of the inspection was to ensure that no residual contamination remained i
after the disposal of the contaminated reactor components.
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PDR ADOCK 05000 l
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REPORT DETAILS I
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1.
Persons Contacted j
i Licensee Employees
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Dr. C. T. Carley, Head of Department of Mechanical and Nuclear Engineerina
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- Dr. J. I. Paulk, Associate Dean
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- D. T. Simpson, Assistant Professor
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- Attended exit interview i
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Exit Interview
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The inspection scope and findings were summarized on June 22, 1982, with
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those persons indicated in paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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4.
Unresolved Items Unresolved items were not identified during this inspection.
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5.
Transportation of Radioactive Materials
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The licensee shipped five known radioactive reactor components to the f
Barnwell Waste Management Facility in December 1981.
Disposal of these
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components was authorized by the NRC. The inspector reviewed the documenta-
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tion for this shipment and found no discrepancies.
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6.
Independent Survey of Storage Area
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The inspector conducted an independent radiation survey of the reactor
component parts.which had not been shipped for disposal as radioactive
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waste. A micro - R meter was used for this survey. The survey results are
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listed in Table 1.
Two crates were opened in order to perform a smear survey, however, the potentially contaminated portions of the equipment were
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bagged in plastic.
The licensee will open the bags during their final
survey.
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TABLE 1 Independent Survey Measurements
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Results Component Smear Direct Radiation (alpha and beta)
(micro-R/hr)
Contamination 2 Detectors less than 50 (on contact)
1000 DPM/100cm2 on outside of bagging 2 Control less than 20 (on contact)
Rods 1000 DPM/100cm2 on outside of bagging Graphite Bricks less than 20 (on contact)
1000 DPM/100cm2 Off-Gas Holding Tank 5 (on contact)
This survey indicated measurements above background which may be a result of low level residual contamination above the limits stated in Regulatory Guide 1.86 or activation of these components. A licensee representative stated that these components were not surveyed because they were never uncrated after receipt from North Carolina State University in 1966. Only components received as radioactive material were disposed of as radioactive waste.
The inspector verified that posting and marking of radioactive materials was conducted in accordance with 10 CFR 20. The reactor component storage area was still locked and posted as a radioactive materials area.
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Spot checks of the floor using an RM-14 with a pancake type probe indicated
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no residual contamination.
A licensee representative stated that the
remaining reactor components will be surveyed to determine if the components will be controlled as radioactive materials or released for unrestricted use. All crates and plastic bagging will be opened in order to perform the smear survey. In order to be released, component loose surface contamina-tion levels will meet the requirements of Regulatory Guide 1.86 and direct
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radiation measurements at one meter from each component will be less than 5 micro-R/hr above background.
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