IR 05000186/1985004

Matl Control & Accounting Insp Rept 50-186/85-04 on 850304- 07.No Noncompliance Noted.Major Areas Inspected:Facility Organization & Operation,Measurement & Statistical Control & Storage & Internal Control

ML20215J151
Person / Time
Site:	University of Missouri-Columbia
Issue date:	03/26/1985
From:	Creed J, Pirtle G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20215J138	List: IA-86-421, Ack Receipt of Informing NRC of Steps Taken to Correct Noncompliance Noted in IR 05000186/1975003 IR 05000186/1976001 IR 05000186/1977007 IR 05000186/1978004 IR 05000186/1979001 IR 05000186/1980003 IR 05000186/1981002 IR 05000186/1983001 IR 05000186/1985003 IR 05000186/1985004 ML20215J136 ML20215J159 ML20215J183 ML20215J188 ML20215J201 ML20215J210 ML20215J230 ML20215J237 ML20215J240 ML20215J243 ML20215J248 ML20215J262 ML20215J265 ML20215J332
References
FOIA-86-421 50-186-85-04-01, 50-186-85-4-1, NUDOCS 8610240325
Download: ML20215J151 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-186/85004(DRSS)

Docket No. 50-186 License No. R-103 Safeguards Group II Licensee: University of Missouri Columbia, MO 65201 Facility Name: Research Reactor Facility Inspection At: ' Columbia, MO Inspection Conducted: March 4'-7, 1985 Date of Last Material Control and Accounting Inspection: July 13-15, 1983 Type of Inspection: Unannounced Material Control and Accounting Inspector: So ud .hM L. P tMl e m d &t985 Date Physical Security Inspector Approved By: M (J/ R. Crsed, Chief Date Physical Security Section Inspection Summary Inspection on March 4-7, 1985 (Report No. 50-186/85004(DRSS))

Areas Inspected: Facility organization and operation; measurement and statistical control; shipping'and receiving; storage and internal control; inventory; and records and report The inspection involved nine inspector-hours by one NRC inspecto Results: The licensee was found to be in compliance with NRC requirements in the areas inspecte .

(Details - PART 2.790(d) INFORMATION)

I B610240325 861010 hNI 6-421 PDR 10tCFR 2.790(d) INFO

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DETAILS Key Persons Contacted

• D r. R. Brugger, Director, University of Missouri (Columbia) Research Reactor (MURR)

• Dr. D. Alger, Associate Director, MURR

• Dr. A. Bolon, Chairman of MURR Reactor Advisory Committee (University of Missouri (Rolla) Nuclear Engineering facility)

• C. McKibben, Reactor Manager, MURR

• R. Hultech, Reactor Physicist, HURR

• Denotes those persons present at the exit meetin . Entrance and Exit Interviews (MC 30703)

The inspector met with the licensee representatives denoted in Paragraph 1 above at the conclusion of the inspection on March 7, 1985. The inspector described the scope of the inspection (Inspection Procedure No. 85102) and

stated that no violations were noted during the inspectio The inspector did note two observations of an administrative' nature which the licensee agreed to address. The observations pertained to

(1) four Westinghouse fission chambers, each containing approximately one gram of U-235, need to be added to the monthly and semiannual SNM physical inventory forms; and (2) the SNM custodian procedure needed to be clari-fied to clearly define " bimonthly visual inspection" requirements for fuel elements in the SNM vaul Additional information concerning the two observations are identified in Section 7 of this repor . Facility Organization and Operations The inspector confirmed that the Reactor Manager is responsible for day-to-day control of SNM at the Missouri University Research Reactor The Reactor Physicist was designated by a letter dated

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(MURR).

November 26, 1984 as the SNM custodian for the MURR. Detailed respon-sibilities for the SNM custodian were contained in the licensee's SNM

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Control and Accounting Procedure Manual, dated November 12, 1981. A l' review of the manual showed that the guidance was adequate to enable the licensee to comply with 10 CFR 70.51(c) requirements. The licensee also possessed the current copy of NUREG (BR-0006, Revision 2, " Instructions for Completing Nuclear Material Transaction Reports" effective March 1,

- 198 . Measurements and Statistical Controls The licensee utilizes the following method to calculate rates of consumption to compute uranium burnup:

U-235 Burnup: 1.26 gram / MWD U Burnup: 1.06 gram / MWD

.pART-2.790(dh fliFOTJ ATI0ft;a

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Thermal output is reported in megawatt days (MWD) and summed and tabulated after each refueling. This output is figured for each assembl Reactor power is determined by calorimetric heat balances. Primary indication is through an automatic reactor power calculator. The accuracy of the auto-matic power calculator is checked daily by hand calculating using process instrumentation. During periods of reactor operation, the calorimetric power is recorded hourly on tree process data sheet, which is maintained in the Reactor Operations Offic In addition to'the process data sheet, a MWD log of reactor operations is maintained. Once the total reactor power (MWD) is determined, the output for each assembly is figured based on uniform core load and the calculation noted abov The licensee's uranium burnup calculations for the inspection period were in agreement with NRC 742's that were reviewed by the inspector. NRC forms 741's and 742's were prepared for calculated uranium burnup on a

' six month basis (March and Saptember) of each year. The forms were filed in the required time peri'o . Shipping and Receiving

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The inspector reviewed the NRC forms 741s for 16 transactions since the previous inspection (July 1983). The transactions included ten receipts of SNM and six shipments of SNM. All NRC Forms 741, except one, appeared adequately documented and filed within the required time period (receipts i

within ten days of receiving the material; shipments - the day of shipment or the next working day). A NRC Form 741 for.a shipment of 21 grams of enriched U-235 from Los Alamos National Laboratory (DOE) was not receipted for within ten days due to shippers delay in mailing the NRC form 74 NRC Forms 741 for spent fuel shipments were properly marked as safeguards information in accordance with 10 CFR 73.21. The procedure for shipment and receipt of SNM appeared adequate. Shipments, receipts, and uranium burnup were annotated on appropriate NRC Forms 742 for the September 1983 to September 1984 time frame (two reporting periods).

a Storage and Internal Controls

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The licensee has established the following item contrcl areas for the physical and administrative control of SN Fuel storage vault Reactor Pool (Reactor and X, Y, and Z storage baskets) , Containment Building Laboratory Building

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The licensee's authorized possession by material type and license are as follows:

License Authorized Limit l

R-103 45 Kgs. U-235 80 grams (Pu/Be sources)

] 20 grams (Pu/Be sources)

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WPART 2.790(d).

INFORMATION.-h

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The licensee's actual possessions were within authorized limit Internal transfer of SNM between item control areas was accomplished only by the SNM Custodian's written authorizatio . Inventory The inspector confirmed that monthly inventories of SNM within the SNM storage vault were conducted and physical inventory of all SNM was

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conducted in March and September of each year. The inspector observed inventory procedures conducted by the SNM custodian. The following items were accounted for:

Item (s) Quantity

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General Electric Fission Chambers 4 :(serial No. verification)

Reuter Stokes Fission Cha'mbers 11 (serial No. verification)

Westinghouse Fission Chambers 4 (serial No. verification)

MURR fuel plate , 1:(piece count)

Atomic International fuel plate samples 4 (piece count)

Gulf Atomic fuel plate samples 21 (piece count)

Four bottles containing 2 fuel pellets each 8 (piece count)

Fuel plates 50 (piece count)

Pu filters' 2 (piece count)

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Additionally,[ forty-nineffuelelementswereaccountedfor.;Two' fuel elements (ME-137 and 140) were within the SNM storage vault and' accounted for by serial number. ,'Six fuelfelements were in t,he Y basket of the reactor pool and verified by piece count. ; Fifteen' fuel elements in the Z basket of the reactor pool were accounted for bi' piece count. CEighteen'

fuel elements not clearly visible within the Z basket and(eight! fuel elements within the reactor were accounted for by reviewing fuel sequence logs to confirm dates of fuel element placement in those locations and confirmation that they had not been moved. The refueling sequence for the current reactor core configuration (85-9) and the diagram for the current spent fuel pool configuration were also reviewe Movement of fuel elements are identified by refueling sequence and position and element number are confirmed and documented. Review of licensee records showed that all fuel elements within the spent fuel pool were irradiated to the self protecting level (> 100 R/hr). Monthly and semiannual SNM inventories conducted by the SNM custodian were reviewe Inspection results showed that monthly audits conducted by the licensee

- did not include by itemffour Westinghouse fission ~ chambers, even though, the audits did include the total number of grams for theffour,' chamber The inspector requested that the licensee identify each of these fission chambers individually instead of collectively on future audit The inspector also requested that a clarification be made to the licensee's SNM custodian procedure to clearly define " Bimonthly Visual Inspections" Bimonthly can be defined as twice a month or once every two months. The licensee is conducting these audits once a month. The licensee has agreed to take action to address the two concerns identified abov )T 4 y- m vy- awy- - -- .y - - - - - +,-<--.-----e . p-

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. Records and Reports The following records were reviewed by the inspecto Record Dates / Quantity Reviewed Monthly SNM Inventory _ Forms- November 1984 through January 1985-Semiannual SNM inventory Forms September 1983 through September 1984 Nuclear Material Transaction September 1983 through September 1984 Reports (NRC Form-741)

Fuel Element Megawatt Day Log January 1984 through February 1985 MURR Refueling Sequence Documents and Reactor Core / 13 Diagrams were reviewed for the period Spent Fuel Diagrams between October 22, 1984 and February 28, 198 Letter Designating SNM Custodian November 26, 1984 SNM Control Procedure Man'ual November 12, 1981

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