IR 05000083/1975002
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IE Report Nos. 50-83/75-2, 70-462/75-1
70-49/75-1 and 70-1068/75-2 DETAILS Prepared by:
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J. W. Hodges,. Safeguards Auditor
'Datd Materials and Plant Protection Branch Dates of Inspection: March 24-26,1975
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Reviewed by:
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W.'B.
Kenna, Chief Date Materials and Plant Protection Branch 1.
Individuals Contacted
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Don G. Pri:e - Head, Radiation Control Department Dr. N. J. Diaz - Reactor Supervisor, Nuclear Engineering Sciences 2.
General The inspection was conducted to determine the University of Florida's conformance to materials protection requirements contained in Title 10, Code of Federal Regulations, Part 70, "Special Nuclear Materials," and specific requirements contained in licenses R-56, SNM-50, SNM-452, and SNM-1050.
The licensee's material protection controls were reviewed by an audit of records, review of procedures, observations by the inspector, and interviews with appropriate personnel.
3.
Inventory The inventory of SNM at the University was located in the Nuclear Sciences Center and in the Field Research Building and consisted of the following:
Nuclear Sciences Center
Stored in various laboratories:
Misc. quartz tubes coated with enriched uranium, foils, etc.
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(216 gms U-235)
4 PuBe neutron sources (205 gms Pu)
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4 fission chambers (containing less than 1 gm U-235)
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0.360 gms U-233.
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kg L
8204210599 811110
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POLLOCKSI-399 PDR
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IE Rpt. Nos. 50-83/75-2, 70-462/75-1 70-49/75-1 and 70-1068/75-2-2-UFTR (University of Florida Training Reactor)
18 fuel plates and two containers of fuel samples,
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- 8 fuel platesj
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22 fuel plates,
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(3337 gms U-235)
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1 PuBe neutron source on top of reactor tank (15 gms Pu)
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- 1 fission chamber in reactor (1 gm U-235)
Field Research Bldg.
5400 SPERT fuel pins containing 187.9 Kgs. of U-235 at an enrich-
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ment of 4.8%, storedl ~~
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These pins are
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encapsulated in stainless steel rods 3-1/2 feet long by 1/2 inch diameter.
2 PuBe neutron sources (31 gms. Pu)
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Procedures Written material control and accounting procedures are required by 10 CFR 70.51c.
The licensee has prepared and maintains written procedures as required.
The licensee is execpt from 570.58, "Funda-mental Nuclear Material Controls," under the exclusion provisions of 570.58 (a).
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Reactor Thermal Output The methods employed for the determination of UFTR thermal output are considered acceptable for a facility of this size.
Negligible heat is produced by the University of Florida SPERT assembly and measure-ments of thermal output are not required.
6.
Nuclear Material Depletion and Production The licensee uses a depletion factor and thermal output to determine fuel depiction.
Depletion has been very small to date (2 gms for this inspection period; about 4 gms since Mcy 1970).
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IE Rpt. Nos. 50-83/75-2, 70-462/75-1 70-49/75-1 and 70-1068 /75-2-3-7.
Internal Control Procedures and practices for the internal control of SNM are deemed to be adequate considering the size and type of facility.
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Records and Reporta Receipts and shipments of SNM for the inspection period were verified by examination of the NRC-741's on file and a determination made that the licensees'NRC-742 " Material Status Report," issued for the periods under inspection, are correct and are in agreement with internal records.
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