IR 05000077/1993002
| ML20058L473 | |
| Person / Time | |
|---|---|
| Site: | 05000077 |
| Issue date: | 12/01/1993 |
| From: | Dragoun T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20058L472 | List: |
| References | |
| 50-077-93-02, 50-77-93-2, NUDOCS 9312170005 | |
| Download: ML20058L473 (3) | |
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U. S. NUCLEAR REGULATORY COMhilSSION I
REGION I
l Report Nos. 50-77/93-02 Docket Nos. 50-77 License Nos. R-31 Licensee:
The Catholic University of America 620 hiichican Avenue. N.E.
Mshincton. D. C. 20064 Facility Name: AGN 201 Nuclear Research Reactor Inspection at: The Catholic University of America. Washincton. D. C.
Inspection Conducted: November 4 and 5.1993 Inspector:
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Thomas F. I)lagoun, Project Scientist Date Effluents Radiation Protection Section (ERPS)
Approved By:
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/>M'MJ Acting Chief, ERPS, I*Icilities bat'e Radiological Safety and Safeguards Branch, Division of Radiation Safety and Safeguards Areas Insoected:
equipment.
Status of reactor decommissioning, facility staffing, and radiation survey Results: No safety concerns or violations were identified. The target dates specified in the Decommissioning Plan have not been met. The licensee will submit a revised schedule to the NRC by November 30,1993.
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9312170005 931208 PDR ADOCK 05000077 L
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DETATIE 1.0 Individuals Contacted
- S. Keimig, Director of Environmental Safety
- D. Luster, Radiation Safety Officer and Reactor Administrator M. Saba, Health Physicist I
- Attended the Exit Interview on November 5,1993 2.0 Status of Decommissionine Since the last inspection, all extraneous material in the reactor roora has been removed. The graphite reflector was pulled from the core tank and placed on the
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floor along with the lead shielding from inside the tank. The core tank and associated systems remain intact. The Reactor Administrator stated that the reactor fuel elements were verified to be secured in the two facility safes during the turnover from the previous Administrator in August 1993. However, the safes were jammed and could not be opened during this inspection. The inspector re-emphasized the NRC concern that was raised during previous inspections regarding the lack of progress on the return of the fuel to the Department of Energy (DOE). The Administrator stated that he was aware of the issues that needed to be resolved with DOE and would give these matters prompt attention.
Section 2.0 of the Decommissioning Plan states that the project would be completed 12 months after the Plan was approved by the NRC Approval was granted in September 1992, therefore decommissioning should be completed by September 1993.
This goal was not met. The Administrator stated that a revisal schedule will be submitted to the NRC by November 30,1993. The target date for completion will be J
in the Spring of 1994. The inspector stated that a projected completion date was
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necessary so that the NRC could schedule a confirmatory survey by a contractor.
This matter will be reviewed in a future inspection (50-77/93-02-01).
j 2.1 Staffine The current Administrator has been in place for about one month. The previous Administrator retired on schedule in August and was unavailable. The current Administrator's background and experience were reviewed and found to be very well suited to the current activities. He was recently involved in the decommissioning of a fuel fabrication facility and was aware of the steps necessary to complete the research reactor decommissioning. The qualified Health Physicist named in the Decommissioning Plan remains on staff. The Director of the Environmental Health and Safety Department stated that other departmental personnel could be made available to assist the new Administrator. Within the scope of this review, the inspector determined that staffing was adequate to complete the decommissionin.. _.
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2.2 Radiation Surver Equipment l
f The previous NRC inspection determined that some of the licensee's laboratory and
i portable radiation survey equipment was not operable or out of calibration. The
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j licensee was not able to complete a final radiation survey.' The Reactor Administrator's previous employer (decommissioned fuel fabrication facility) has ~
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donated a large quantity of high quality laboratory and portable survey equipment to i
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the University. This included two Tennelec gas flow proportional counters with l
automatic planchet feed and three Ludlu'm portable micro-R meters.which are needed
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for the final radiation survey. The inspector verified that this. equipment was on site.-
l Most of the equipment remains in the shipping boxes. The licensee stated that a.
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priority effort will be made to install and operationally check the equipment. This -
l matter will be reviewed in a future inspection.
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2.3 Exit Interview j
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The inspector met with the licensee representatives indicated in' Section 1.0 on -
November 5,1993, and summarized the scope and findings of this inspection. The
licensee acknowledged the inspection fmdmgs.-
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