ML20083D884

Annual Rept for Ohio State Univ Research Reactor,Jul 1990 to June 1991

ML20083D884
Person / Time
Site:	Ohio State University
Issue date:	09/26/1991
From:	Redmond R OHIO STATE UNIV., COLUMBUS, OH
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9110020009
Download: ML20083D884 (11)

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THE Engineering taperiment station 142 Hitchcock Hall 2070 Neil Avenue O"]'",

Coltimbus, OH 43210-1275 O'

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]w riione 614 292 241 UNIVERSfrY September 26, 1991 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, Sincer91y,

/?AA'at Robert F. Redmond Director RFR/s enclosure c: Nuclear Regulatory Commission (w/ enc.)

Theodore S. Michaels-(w/ enc.)

9110020009 910926 PDR ADOCK 05000150 R PDR College of Engineering

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l Introduction l

( As stated in The Ohio State Univoralty Research Reactor Technical l

Specifications, Section 6.6.1 Operat ing Report s, an annual report shall be j

made to the NRC by September 30 of each year. This report is to include the j followfug seven sectiona.

(1) A narrative summary of operating experience (including experiments performed) and of changes in facility design,

-performance characteristics, and operating procedures related to i reactor safety occurring during the reporting period. I (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 inspections. 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. i I

(5) A summary of changes to the facility ter procedures, which affect reactor safety, and performance of t u ts or experiments carried out under the conditions of Section 50.59 of 10CRF50.

i (6) A nummary of the nature and umuunt of radioactive gaseous, j t

liquid, and solid effluents released or discharged to the j environs beyond the offeetive control of the 1icensee as  !

measured or calculated at or prior to the point of such release j or discharge. l

-(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 ar e all for the period July

1. 1990 through June 30, 1991 except as noted for exposure records.

l (1) A. Experiments Performed The staff of The OSU Rese; ' Reactor are generally involved la four types-of experiments a, che Nuclear Reactor Laboratory.

i included are jntroductions to nuclear resenrch, neutron j activation unalysis, material irradiations, and classes that I measure various reactor parameters. Additionally, this year we completed preparation of HEU fuel for shipment, shipped 5 fuel eleuents, and began installation of the heat removal system for 500 KW operation.

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1. Typically when we introduce students, faculty, or'other >

experimenters to nuclear research we do the following:

a; Discuss nuclear renetions.and rudlological safety, bi Operate the reactor.'at 10KW. "

c.'llave the individuals observe control room operations and

d. Complete a tour and demonstration of irradiation techniques.

2. Neutron activation analysis experiments are routinely completed for students ranging from high schcol to graduate school. The facilities-normally utilized are the

" rabbit" (pneumatic tube) and the "CIF" (Central Irradiat ton 1:acility). The majority of the NAA work is

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- biological samples. Irradiations _ar;e typically no longer than eight. hours.

l" 3.-Material-frradiations, other than for NAA, are in four basic areas Isotope production detector, electronic 3

. component, and fiber optle testing; boron neutron capture

-therapy-(11NCT); and irradiation of biological samplea~lsotope production is extremely limited. Only one

-irradiation.(specifically for isotope production) was completed in the last-year. Detector and electronic component testing is done more routinely. - This-testing is usually completed-in the thermal column, or one of the beam ports,while'ftsalon chamber testing is in the Central

-Irradiation Facility. The reactor thermal column 18 also utilized for other UNCT studies. Typically it is.the location for blood samples to determine their baron contentfand for-the evaluation of Cr-39 plastic plates.

We also: completed a few-othhr hiological. sample ,

irradiations for research projects but currently are not approved to do any-animal irradiationa.

-4.LVarlous.nuc] ear. engineering or physies elasses throughout Ohlo utilize the reactor for the following basic experiments:

ai Approach to critical (using banked control rods rather than fuel' loading) b.~ Control rod calibration by rod drop;-positive

.perlod, and'auberitleal multIplicatlan

c. Measurement of the Reactor Transfer-function

d. Vold-coefficient measurements and

e. Radiological-surveys.

5. The conversion to LEU fuel was completed in the Pall and L Winter.of 1988/80 Since.that time we have been working

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towards the shipment- of our 11EU fuel to D.O.E To better l utilize the existing-shipping cask (BMI-1) we decided to p

! .- trim the foot and_ ball-from each fuel element. This-j' enables shipment;of 24 elements .instead of only 12 at one time. The element trimming operations were completed in l1 i:

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.1 August 1990- , Five 1(Ehtly-irradiated elements were' shipped to D.O.E. on 1/29/91_in G M Drums. The remaining

-f elements are in storage pending availability for the BMI-l cusk.

-0 On November 14, 1990 the OSURR i.icense was. amended to allow 500 KW operation. InstallatJon of_the in-pool portion of the heat removal system was completed.in June.

V 1990.

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' The reactor utilization for July 1. 1990 through June 30, 1991 la summarized in the following quarterly reports, Utilization iteport ~

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July 1 - September 30, 1990 ,

1 Deserintion- llours

-Production of an Erbium-169 8.0 i for Mossbauer studies of

' rare-earth copper oxide compounds (Dr. Ja, lieuctor Sharing)

Control Rod Calibration 2 fi . 5 for NE 744, delayed groups, ,

? noise analysis, Permi Age

-Irradiation of cell media- 5.0 in the thermal column to determine neutron irradiation i:

_ effects (Barth/Matalka)

Measurement of Transfer 11.5-Function-for NE 744-'

- Annual' Maintenance 8.0 including Meter Zero, Scram checks, and discriminator settings NAA.of rock samples for 7.0 trace: element content determinatir,n (Thomas ,

KSU Reactor Sharing)

Evaluation of Cr-39 1.0 Plastic Plates for NE 900 (Woollard/Illue) 3 1

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3 Descriptlon llourn

• Introduction to Radiation (L O .

Research for Ohio Teachers Energy Workshop, Nuclear Pharmacy, IIPS-Calibratlen of Gaseous 2.5 Eft'luent Monitor using ArJ(1 Trimming foot and ball 13.0 ,

off-fuel elements Testing of neuter-Stoken 27.5- i fission chambers NAA for' Cat Tissue for 6.0 Vet,~ Pathology .

(Dr. Hoj Ko) >

Full Irradiation f or 1,0

-Half-Life study-for Ni? : 041 ' ( Bl ue )

Total 12.3.0 0ctober 1 - December 31, 1990

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Descrlptton - llou rs 1 Spectrum Measurements 10.0 in DPt1 und CIF for NRL Testing of;Reuter-Stokes 40.25.

LPission Chambers by NHL l'rradiation of Samples in. 2.0 T.C. for NE Student for

. IlNCT :(J l ang/H1ue) g NAAlof Deer' Antler and 22.0 l

-Zebra Mussel for Muskingum ColIpce-(Baxter). .

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' Tours and Surveys for 12.5 UAllS , BYSP, ~ NE606, Capital U.ntversit y Irradiation for 1,0 Pharmacy 800 (Feller)

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NAA of Adhesives for 4.5

' NASA (Frasca) 4

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.; Deserlotion llours Evaluation of Fiber 17.25 Optics for EPRI (llutch/ Miller) i NAA of Foods & Diodes 7.0

-for Eastmoor ll.S, (Denn/Talnagi).

NAA of Coal Arh for 7.0

-AEP=(Talnagi)-

TotrI 139.5 January 1 March 31, 1993 Description , hours

' Evaluation of Faber Optics' 33,5 for EPRI (Ifatch/ Miller)~

iletermis.nllon' of tiranium in Ash - 5.0 i samples for=AEP (NRL)

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- Testing of IES Fission Chambers' 21,5

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-Maintenance. including Fuel & 21,5 Control Rod Inspections, Control Rod'& Power Calibrations Plux Perturbation.in the CIF. 1.0

- by NRI, Tours for- Sincinir Community Co]Inge, 7.5-Otterbein,:Phlo Dominican

Irradiation ~of Trans.istors for NASA 49.0 Irradiation of Detectors in-Ttermal 2.0-Column f6r RhCT (Gupt+./ Blue)

Irradiatl'on af Tissue sempies in 1.0

, . Thermal Columr-for DNCT (Tiang/D]ue)

Irradiation'of Cella in Therma] 4.5-

. Column for BRT (Matnika/Darth)

'Isot ope h odt.ction of Ar-41 for 3.0 Victoreen 4

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Deser lpt lost llot!rs NAA of Water Samples for 2.0 Eastmoor High School Approach to Critical and Control 13.0 Rod Calibrations for AFIT and University of Cincinnati Total 143.0 April 1 June 30, 1991 Description llours NAA of Cat Tissue 10.0 (Veterinary Patholoty)

DNCT (illue/Gupt n/Jiang) 2.5 Evaluation of R-S Fisalon Chambers 24,0 Tours for Capital University. 18.0 Sincluir Community College, South liigh School, lleery Middle School Evaluation of Fiber Optics for EPHI 28.0 (lla tch/ Mille r)

NE720 Dynamic Reactor Behavior 4.0 (M111er)

Irractint ten of Transitors for NASA 15.0 Approach to CrItIcai for Youngstown 8.0 State University and University of Cincinnut.1 Detector Positioning Tests f or llpgrade 2.0 Irradiation of Plastic for 5.0 Wittenburg University Total 122.5 D. Changes in Facilit y besinn There were tio f acility design changes that required changes to the SAR or Technical Specifications. 10CFRSO.59 changes are described in Section 5.A.

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~C. Changes-in Performance Characterlatics There have been'no changes in performance characteristics-related to' reactor safety.In'the last year, llowever, the _

Reactor St tif f had completed Technical Spect fIcat ion '

. modifications to allow.a power increase from 10 KW to 500 KW.

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These Specifications were approved by the Reactor Operations Committee and submitted to the-NRC on June 12, 1990. They were approved-by the NRC on November 14, 1990.

D. Changes = In Otwrat Ing Procedures

-There were no changes in operating procedures related to reactor safety in the last' year. 10CFRSO.59 changea are describen in Sect i on : ( 5 )ll.

(2) A. Ellvwatt-llours of Operatir,a 2035 II. Ilours of Utilization - 518 (3) Safety llelated Maintenance

-Routine preventive maintenance and inspect ions by the_ reactor staf f

.and an-audit-by the Reactor Operations Committee did not reveal'uny reportable safety related iten. Ilowever, maintenance was required on one-system related to safety. It is listed below:

Corrective Reason for.

Maintenance- Maintenance

1. Pool. Top ARM Replaced

1. Would not calibrate (4) Unscheduled shutdowns From July 1, 1990 to June 30, 1991 thero wero.a total-of fivc

-unplanned scrams. One was from a loss of building power the remainder were instrument related. These are summarized below:

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Reason' Corrective Actinn _

a. Loss.of building power (1) n. None, spurinus l _b. Low counts on su channel (3)' b. Replaced Su Recorder tube

c. Period Recorder' Spike.(1) c. None, spurious scram I

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(5) Channes in Facility Procedures a and Performance of Tests or Experiments-

. in Accordance with 10CFR50.59 A..During the potiod July 1 1990 t o June 30, 1991 one t:5URH Modification Request was completed by the Reactor Staff and approved by the Reactor Operat lems Committee, it did not require license or technical specification changes or result in un unreviewed safety question per 10CPR50.59. The modification is described below.

1 New power lines were installed for the reactor process system pump and for control and justrument power.

11 The following is a . list of Procedure changen made under 10CFR50.59 from July 1, 1990 to June 30, 1991 in accordance with Administrative Procedure AP 05 Format for Writing, Revising, and Approving Procedures.

AMINISTRATIVE PROCEDURES (AP)

Procedure Procedure Latest Revision ROC

-Number Title Number Date Approval AP-01 Obtaining Use of the OSURR 3 11/01/90 11/08/90

-A?iO2- General Rules 3 11/01/90 11/08/90 AP 03 Filing Requests for Reactor 4 11/01/90 11/08/90 Operations AP-04 Approval of Requests for Reactor 1 11/01/90 11/08/90 Operatton ,

AP-05 SNM Inventory 2 11/01/90 11/08/90 AP-06 Format - for Writ ing, Revising 5 11/01/90 .11/08/90 and Approving Procedures AP-07 Review of Procedures- 6 7/05/89 11/08/90 AP 08 NRL Audit 1 11/01/90 11/08/90 AP-09 RO/SRO Requaljfication 5 11/01/90 11/08/90-

-AP Consolo Operating Experience 3 11/02/00 11/08/90 Record AP-11 Recsd Reeping 1 11/02/90 11/08/90 AP-13 Personnel Required for Reactor 2 11/02/90 11/08/90 Opera t. lon AP-14 OSURR Modification Requests 2 11/02/90 11/08/90 8

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C. No~ testis or-experiments were conducted under 10CFR50.SD from July 1.,.1990 to June 30, 1991.

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(6) RadIonetIve Effluents

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-A. Gaueous Effluent --The only effluent we measure is-the. release of Ar-41. During the period the maximum. production was

-calculated to be about 6.0% of MpC for the unrestricted aren, A new procedure to directly measure Ar 41 releases was Jmplemented titarting 0ctober 1, 1989.

The measured value for the period July 1, 1990 to June 30, 1991 was 0.0051% of MpC released to the unrestrleted aren.

B. Liquid Releases - The reactor pool was drained during this reporting period. Prior to draining the pool, the' water was analyzed for radienctivity. Two Isotopes were ident ified as being present in the water. These were Cs-137 and Na-24. Both were-below MpC for an unrest ricted area before their release.

C. Solid Releases - No relaases of solid radioactive materin] were made to the uncontrolled environment,  !

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.(7) A. Radiation Expoqures l Since the firm-that maintains records for The Ohio State l University keeps a yunr to date record it. la easier to repart i this by the nearent . cmpleted calendar year. Therefore film l badge exposures ~1n this report are for the porlod January I to December 31, 1990. Six individuals were monitored as radiatinn workers for the euttre year, one other for part of the year.

These are tabulated below. They;ure conulatent with the ALARA policy for Thej 0hla State (Jniverally and represent a small-fraction of the allowed-1imits.

Individual Whole Body (Walat ) -Right. Left Eye-Deep Shallow Finger Finger 'ic e p Shallow

1. C1nrk_ 10 .30 - - -

t iI.1 Davis- 60 60 40 -

IIIl. ' Hatch .40 40 50 100 - --

IV. Longenbaker 20 20 - "

'V. Myser- 200 200 860- DD0-VI. Ta1nagi 130 130 430- 640 - -

VII. Patire M M -

All' doses in millJrem, M. denotes less that minimum detectable level for l' monitoring devjce. - denotec no monitoring.

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F B. In addition to the above individuals, all visitors nnd experimenters are monit ored. These individuals are normally issued visitor or spare-film badges. Resulta of these exposures are tabulated below. They do not include = 20 mrem for the month of August when all badges were inadvertently exposed.

Visitors (30 badges) 8 -- M 2 - 20 mi.1]! rem Spares (13 badges) 13 - M i

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