IR 05000077/1993001
| ML20045E783 | |
| Person / Time | |
|---|---|
| Site: | 05000077, 07000190 |
| Issue date: | 06/24/1993 |
| From: | Bores R, Dragoun T, Ratta A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20045E776 | List: |
| References | |
| 50-077-93-01, 50-77-93-1, 70-0190-93-01, 70-190-93-1, NUDOCS 9307060038 | |
| Download: ML20045E783 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION i
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REGION I
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Report Nos. 50-77/93-01 and 70-190/93-01 Docket Nos. 50-77 and 70-190 License Nos. R-31 and SNM-164-Licensee:
The Catholic University of America 620 Michigan Avenue. N.E.
Washincton. D. C. 2@fM
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Facility Name: AGN 201 Nuclear Research Reactor Inspection at: Thp Catholic University of America. Washington. D.- C.
Inspection Conducted: June 8 and 9.1993
/!93 Inspectors:
oun Thomas P. Dttagdun, Project Scientist Date Effluents Radiation Protection Section (ERPS)
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Anhur.Della Ratta, Physical Security date'
l Inspector, Safeguards Section
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/3 Approved By:
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l l'R'obert J. Uptp's, Chief, ERPS, Facilities Date
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RadiologicaVSafety and Safeguards Branch, Division of Radiation Safety and Safeguards L
Areas Insoccted: Status of reactor decommissioning and the special nuclear material safeguards program.
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Erstlig No safety concerns or violations were identified.
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DETAILS 1.0 Individuals Contacted
- Sister R.'Donley, Executive Vice President H. Crannell, Chairman, Radiation Safety Committee T. Francois, Campus Police Officer C. Goldston, Director of Public Safety
- W. Keene, Radiation Safety Officer and Reactor Administrator
- S. Keimig, Director of Environmental Safety M. Saba, Health Physics Technician
- Attended the Exit Interview on June 9,1993 2.0 Status of Decommissionine 2.1 Physical Status The inspector toured the reactor room with the Reactor Administrator. The core remains stored in the safe. The inspector requested the licensee to demonstrate compliance with Section 5.0 of the Decommissioning Plan (DPlan) which requires the fuel to be stored such that k n be maintained less than 0.8. The licensee stated that only half the fuel disks are stored together on a shelf. According to manufacturers data, this configuration and the absence of a reflector or moderator satisfies the criterion. The licensee had not
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completed arrangements to return the fuel to the Department of Energy and was uncertain as to when these arrangements would be finalized. The inspector stated that the NRC is concerned about the lack of progress in this matter.
Some non-reactor related equipment that had been stored in the reactor room was cleared but a few extraneous items remained to be removed. The reactor tank and reactor room were intact. The graphite reflector was in place except for small pieces chipped out for gamma spectroscopic analysis. The lead shield bricks were removed from the tank and stacked nearby.
2.2 Staffine
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The Reactor Administrator, who had been in the position for many years and authored the DPlan, will retire on August 31,1993. He indicated that he would not be available to assist with the decommissioning after that date. Due to the uncertainties with disposing of the fuel and possible delays conducting the termination radiation survey, the inspector discussed these matters with the Chairman of the Radiation Safety Committee (RSC). The Chairman stated that he would become familiar with the detailed status of the decommissioning to ensure continuity with the change of personnel. In addition, the Executive Vice President stated that every effort will be made to have the replacement
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on board by August 1 to allow adequate time for an effective turnover, Several qualified candidates have been identified to fill the position.
The inspector interviewed the health physics technician who will assist in the decommissioning in accordance with Section 1.7 of the DPlan. The individual was knowledgeable and adequately experienced.
2.3 Isrmination Radiation Survey The standard one-meter-square survey grids had been marked on the reactor room floors,
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walls, and ceilings, including the reactor pit area and surface of the reactor tank. The licensee stated that smears had been taken of all areas except the ceiling and light fixtures. However, the smears had not been counted. The inspector toured the health physics laboratory area and determined that the licensee has a windowless gas flow proportional counter available to count the smears for alpha and beta contamination. The equipment was not operating because the electronic interface circuitry was in process of being replaced with a locally designed and built unit. This unit was in the breadboard stage. A doped germanium gamma spectroscopy system was available for qualitative gamma analyses of smears.
However, no suitable NIST traceable standards were available that would allow quantitative analyses. A state-of-the-art portable survey meter capable of detecting microR-per-hour measurements was available but the calibration had expired. Some additional analytical equipment was available in the nearby Vitreous State Laboratory which studies the glassification of radioactive waste. The licensee stated that the equipment needed to support the termination survey would be made available in the near future. For the interim, an adequate supply of portable survey meters were.
available to support decommissioning activities.
No radioactive contamination is expected to be found due to the type of the reactor and its operating history. The inspector stated the NRC will arrange a confirmatory survey by Oak Ridge Institute for Science and Education to verify the licensce's results.
2.4 Status of Previously Identified Items 2.4.1 (Closed) Violation (50-77/91-01-01): Failure to hold quarterly meetings of the RSC.
Records indicate that the meetings were regularly held during 1992 and 1993 with one meeting currently due. Licensee action described in a letter dated March 11,1991 is complete and satisfactory. This matter is closed.
2.4.2 (Closed) Violation (50-77/91-01-02): Failure to perform audits. A review of transactions of the RSC indicates that the audit was completed and reviewed. Licensee action.
described in a letter dated March 11,1991 is complete and satisfactory. This matter is closed.
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3.0 Material Control and Accountine Procram 3.1 Organization and Operation
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The inspection included discussions with licensee management and review of the licensee nuclear material control procedures that are documented in its Radiation Safety Manual i
dated October 30, 1990. Custody of the special nuclear material (SNM) and the management of the material control and accountability program were the responsibilities of the Director Radiation Safety.
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3.2 Shipplne and Receivine The inspector determined through a review of records that the licensee maintained procedures to assure that all nuclear material shipped and received was accounted for accurately. During the period under review, the licensee made one shipment of SNM,'
and received no shipments of SNM.
3.3 Storace and Internal Controls
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The inspector determined through observations and review of records that the licensee'
was maintaining a system of storage and internal controls that indicated the quantity, identity and current location of all SNM within the facility.
The licensee had 1 plutonium beryllium source,10 plutonium alpha sources,13 reactor control rods,11 reactor fuel discs, I special thermal element, and 1 fission plate from the reactor, stored in locked containers. The keys for these storage containers were kept locked within the access controlled area.
3.4 Inventory i
The inspector determined through a review of records that the licensee had conducted semi-annual physical inventories in conjunction with the submittal of DOE /NRC Form-742 and 742-C.
The licensee maintains the signed Form-742C as inventory documentation.
The inspector conducted a physical inventory of SNM at the facility on June 8,1993.
The inventory included SNM on both the R-31 and SNM-164 licensees. The inspector verified each item on the inventory and confirmed that all items were listed.
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3.5 B.etQtds and Reports The inspector reviewed the Material Status Reports, (DOFJNRC-742 and 742-C)
submitted for the period October 1,1989 through March 31, 1993, for both enriched uranium and plutonium to verify compliance with 10 CFR 70.53.
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Exhibit I of this report summarizes the licensee's nuclear material activity for the period October 1,1989 through March 31,1993.
These were no deficiencies identified in the licensee Material Control and Accounting Program.
4.0 Fixed Site Physical Protection Measures for SNM of Low Stratenic Sienificance The licensee's program for the physical protection of special nuclear material of low strategic significance was reviewed by the inspector for confoimance to the NRC-approved physical security plan. The inspector examined physical barriers, access controls, procedures, and key control, and observed a licensee test of alarm system features. The inspector found that the implementation of the licensee's program met the general performance requirements and objectives of the governing regulations.
5.0 Exit Interview The inspectors met with acensee management denoted in Section 1.0 at the conclusion of this inspection on June 9,1993. The scope and findings of the inspection were discussed at that time. The licensee acknowledged the inspection findings.
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EXHIl3IT I CATHOLIC UNIVERSITY Docket No. 50-77 License No. R-31 Docket No.70-190 License No.SNM-164 Material Balance for Period October 1.1989 - March 31.1993 Reportine Identification Symbol: ZDC Report Unit: grams Enriched Uranium Plutonium
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Element Isotope Element Isotope Beginning Inventory:
(October 1,1989)
3,525 701
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Additions:
Receipts:
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Material to Account For:
3.525 2,Q1
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Removals:
Shipments:
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Fission and Transmutation:
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Total Removals:
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Ending Inventory (March 31,1993)
3.525 201 ff
Material Accounted For:
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=One PuBe Source Serial No. M-968
59 Ten Alpha Sources
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- =Less than one gram
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