ML20092M830

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Oh State University Research Reactor Annual Rept for FY94/95
ML20092M830
Person / Time
Site: Ohio State University
Issue date: 06/30/1995
From: Cruz J
OHIO STATE UNIV., COLUMBUS, OH
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510040116
Download: ML20092M830 (12)


Text

V T 11 E Engineedng Experiment Station 167 Hitchcock Hall j

,,- 2070 Neil Avenue  ;

Columbus, OH 432101275 Phone 614-292-4903 FAX # 614-292-9021 UNIVERSITY September 26,1995 Document Control Desk Nuclear Regulatory Commission Washington,DC 20555

Dear Sir:

Please find enclosed the annual report for The Ohio State University Research Reactor, Docket No. 50-150. This report is being submitted as required by our Technical Specifications, Section 6.6.1. If you have questions on the content of this report, please contact Mr. Richard Myser, Associate Director of the Nuclear Reactor Laboratory.

Sincerely yours, Jose B. Cruz, Jr.

Dean i JBC:krh c: Nuclear Regulatory Commission Region III (w/ene.)

Theodore S. Michaels (w/ enc.)

l Don W. Miller (w/ enc.)

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THE OHIO STATE UNIVERSITY RESEARCH REACTOR ANNUAL REPORT FOR FY 94/95 8

SEPTEMBER 26,1995 I

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l Intre, duction As stated in The Ohio State University Research Reactor Technical Specifications, Section 6.6.1 Operating Reports, an annual report shall be made to the NRC by September 30 of each year. This report is to include the following seven sections.

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1. A narrative summary of operating experience (including experiments performed) and <

of changes in facility design, performance characteristics, and operating procedures related to reactor safety occurring during the reporting period.

2.- A tabulation showing the energy generated by the reactor (in Kilowatt hours) and the number of hours the reactor was in use.

3. The results of safety-related maintenance and inspection. The reasons for corrective maintenance of safety-related items shall be included.
4. A table of unscheduled shutdowns and inadvertent scrams, including their reasons and the corrective actions taken.
5. A summary of changes to the facility or procedures, which affect reactor safety, and performance of tests or experiments carned out under the conditions of sections 50.59 of 10CRF50.  !

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6. A summary of the nature and amount of radioactive gaseous, liquids, and solid effluents released or discharged to the environs beyond the effective control of the licensee as measured or calculated at or prior to the point of such release or discharge.
7. A summary of radiation exposures received by facility personnel and visitors, including the dates and times of significant exposures. .

These seven sections are discussed below. These are all for the period July 1,1994 through June  ;

30,1995 except as noted for exposure records.
1. A. Experiments Performed

. The staff of The OSU Research Reactor are generally involved in four types of experiments at the Nuclear Reactor Laboratory. Included are introductions to nuclear research, neutron

activation analysis, material irradiations, and classes that measure various reactor parameters. Typically when we introduce students, faculty or other experimenters to
nuclear research, we do the following
a. Discuss nuclear reactions and radiological safety.
b. Operate the reactor at 10kW-100kW
c. Have the individuals observe control room operations.
d. Complete a tour and demonstrate irradiation techniques.

i Neutron activation analysis experiments are routinely completed for students ranging from l high school to graduate school. The facilities noimally utilized are the " rabbit" (pneumatic

- tube) and the "CIF" (CentralIrradiation Facility). The majority of the NAA work is l- geological samples. Irradiations are typically no longer than'six hours.

l Material irradiations, other than for NAA, are in four basic areas: isotope production, detector, electronic component and fiber optic testing; boron neutron capture therapy 1 l (BNCT); and irradiation of biological samples. Isotope production is extremely limited.

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i Detector and electronic component testing is done routinely. This testing is usually  :

completed in the thermal column, or one of the beam ports, while fission chamber testing is  ;

in the Central Irradiation Facility. The reactor thermal column is also utilized for other '

BNCT studies. Typically it is the location for cell samples to determine their boron  :

content.  !

i Various nuclear engineering or physics classes throughout Ohio utilize the reactor for the following basic experiments:

a. Approach to critical (using banked control rods rather than fuelloading).
b. Control rod calibration by rod drop, positive period, and subcritical multiplication.
c. Measurement of the Reactor Transfer function.
d. Void coefficient measurements.
e. Radiological surveys.

The reactor utilization for July 1,1994 through June 30,1995 is summarized in the following quarterly reports.

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Reactor Utilization Report

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July 1. September 30,1994

' Activity Hours ,

NS 744 Labs 58.0-ME 564 Experiment 1.5 Reuter-Stokes DetectorTesting 19.0

, Tours 2.0 Fiber Optics Testing 29.0 DSS Experiments 15.5 Maintenance and Calibrations 16.0 Neutron Activation Analysis 9.0 1- Aux. Irradiation I acility 10.0 160.0 Co.60 Irradiator Utilization July 1. September 30,1994 Activity Hours l EPRI Fiber Optics (2 tests) 6 l Chem. Eng. (Soil Samples) 3 l LakeShore (Elec. Components) 0.05 9.05 l l

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? . Utilization Report for the OSU-NRL f Oct. 1 - Dec. 31, 1994 Reactor

. Activity Ecurs Reuter-Stokes Fission Chambers 21 DSS Experiments 29.5 NE 766 8 M 7 Fiber Optics Expet.iments 22 >

t Auxiliary Irradiation Facility Measurements 34 l

Requalification and Training 7 and Reactor Effluent Monitor Cal.

Radiation Effects of Thermoelectric 88.5 Materials (Bi, Sb) (Te, Se)

NAA of Au in feathers for OSU Zoology 4.5 NAA of geological samples for 14 University of Memphis NAA of environmental samples for 2.5 Wittenberg University ,

NAA of rock samples for Wright State 3.0 University

' Production of Rh Isotopes for 4.0 Cleveland Clinic Production of Na-24 for Miami University 3.0 248 Co-60 Irradiator Activity Ecurs Sterilization of colostrum samples 3 for Vet. Hospital Lakeshore Cryotronics 2 Reuter-Stokes Fission Chambers- 3 8

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.c ,  ; Utilization Report for the OSU-NRL Jan.1 - Mar. 31,1995 Reactor Activity Hours Reuter-Stokes Fission Chambers 32 DSS Experiments 2 NE 766 2 F.O. Experiments 5 Tours 8 Hf Production for Miami U. 7 NAA for W.S.U. 15 J

Rh Production for Cleveland Clinic 1 NAA of Environmental Samples for Wittenburg U. 8 Approach to Critical for Kenyan Co'lege 2 Approach to Critical for U.C. 7 Radiation effects on BI, Sb, Te, Se in Thermcelectric Devices 160 Total 249 Co - 60 Irradiator i

Activity Hours I l

Reuter Stokes Fission Chambers 7 l Science Fair Projects 4 Sterilization of Plastic 3 EPRII 25 Total y

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Utilization Report )

for the OSU-NRL  !

April 1 - June 30, 1995 )

Reactor Activity Hours Reuter Stokes Fission Chambers 51 Radiation Effects on Thermoelectric Materials - Hi-ZTech. 47 Production of Rh-188 for Cleveland Clinic 7 EPRI - Fiber Optics 2 Neutron Damage of Laser Components - AFIT 4 Au in Feathers - OSU Zoology 2 Terra Community College - Approach to Critical 7 Activation of Dosimeters - Piketon 7 NAA of Rcck Samples - U. of Memphis 9 AFIT - Approach to Critical and Control Rod Cal 6 U. of Cincinnati - Approach to Critical and Control Rod Cal 5 NE-505 - Approach to Critical 5 l

NE 720 - Dynamic Reactor Behavior 2 NE 744 - Health Physics, Approach to Critical, Control Rod Cal 12 Production of Hg-203 for NuCON 4 Production of Hf-181 for Miami U. 7 Fiber Optics Damage Studies for Scientific and Engineering Asse. 4 Tours for St. Charles H.S.; Sinclair C.C.; Central Ohio Tech College; Westerville South H.S. 8 Total 182 1

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Co-80 Irradiator

~ Activity ' Hours Reuter Stokes Fission Chambers 11 Terra Community College 300 ~

Plastic Sterilization 4 Tolal 315 ,

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, i 1.B. Changes in Facility Design 1

There were no facility design changes that n: quired a change to the Technical  !

Specifications.10CFR50.59 changes are described in section 5. A.

l 1.C. Changes in Performance Characteristics j There have been no changes in performance characteristics related to reactor safety in the last year.

1.D. Changes in Operating Procedures There were no changes in operating procedures related to reactor safety in the last year ( 10 CFR50.59 changes are described in section 5 B.).

2. A. Kilowatt-Hours of Operation - 160,255 i

' 2.B. Hours of Utilization - 839

3. Safety Related Maintenance Work was completed on the design, construction, and testing of magnet control amplifiers  !

in response to the March 8,1993 report. The amplifiers have been installed and are  !

functioning properly. l

4. Unscheduled Shutdowns From July 1,1994 to June 30,1995 there were a total of seven unplanned scrams. These i are summarized below.

Reason Corrective Action A. Manual Scram Switch Failed. (1) Repaired Switch i B. Instmmentation caused spurious None to date.

signal on period safety amplifier. (4)

(None in the last seven months)

C. Operator Error. (2) Discussion with Operators 1

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5. Changes in Facility Procedures and Performance of Tests or Experiments in l Accordance with 10CFR50.59 A. During the period July 1,1994 to June 30,1995 no OSURR Modification Requests were completed by the reactor staff and approved by the Reactor Operations Committee.

B. The following is a list of procedure changes made under 10CFR50.59 from July 1, 1994 to June 30,1995 in accordance with Administrative Procedure AP-05 entitled Format for Writing, Revising, and Approving Procedures.

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ProceduIe Procedure Description ROC Number Title ofChange Apm@Ag OM-10 Demineralizer Regeneration Deleted 8/l1/94 OM-14 Fuel Element Cutting Deleted 8/l1/94 RS-13 Scaled Source Wipe Minor Change 8/l1/94 OM-11 Magnet Assembly None Needed 8/l1/94 OM-02 Control Rod Inspections Minor Change 8/l1/94 OM-08 Reactor Logbook Records Minor Change 8/l1/94 RS-07 Direct Frisk Delete 8/l1/94 RS-04 Particulate AirSampling None Needed 12/14/94 RS-12 Decontamination None Needed 12/14/94 RS-05 Pool Water Radioactivity Minor Changes 12/14/94 S P-09 OSUPD Response None Needed 4/17/95 SP-11 Protection of SNM None Needed 4/17/95 SP-01 Authorized Access Minor Change 4/17/95 SP-02 Security Call List Minor Change 4/17/95 SP-07 Bomb Threat Minor Change 4/17/95 SP-08 Alarm Failure Guide Minor Change 4/17/95 SP-12 Fuel Shipment Communications Minor Change 4/17/95 SP-05 Alarm Test Minor Change 4/17/95 SP-06 Operation of Security System Minor Change 4/17/95 SP-03 Access Control Minor Change 4/17/95 SP-04 Security Orientation Minor Change 4/17/95 j SP-10 Key Control Minor Change 4/17/95 RS-17 Ar-41 Release Calculation Change 9/22/94 OM-15 Process System Checks Addition 9/22/94 AP-09 RO/SRO Requal Minor Change 9/22/94 IM-07 Rod Parameter Testing Minor Change 9/22/94 AP-06 Procedure Writing Addition 9/22/94

6. Radioactive Effluents A. Gaseous Effluent- The only effluent we measure is the release of Ar-41. For the period July 1 - Dec. 31,1994, Ar-41 releases measured 3.33% of the Annual Average Concentretion Limit. From Jan.1 - June 30,1995, releases measured 3.51% of the annual average concentration limit.

i B. Liquid Releases- The reactor pool was not drained during this reporting period. Hot sink releases are recorded and reported throt.gh the OSU Office of Radiation Safety.

Total releases during this reporting period were 0.33 Ci.

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s C. No releases of solid radioactive material were made to the uncontrolled environment.

7. Radiation Exposures Since the firm that maintains records for The Ohio State University keeps a year to date l record, it is easier to report this by the nearest completed calendar year. Therefore film l badge exposures in this report are for the period January 1,1994 to December 31,1994.

Five individuals were monitored as radiation workers for the entire year or a major part of it. These are tabulated below. They are consistent with the ALARA policy for The Ohio t State University and represent a small fraction of allowed limits. All doses are in millirem.

Individual Whole Body Right left Deep Shallow Finger Finger 1 50 50 90 100 2 170 170 450 450 3 240 240 790 1050 4 110 110 320 280 5 40 40 - -

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