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Annual Rept of Oregon State Univ Radiation Ctr & Triga Reactor Jul 1988 - June 1989.
	ML20012A090
Person / Time
Site:	Oregon State University
Issue date:	06/30/1989
From:	Anderson T, Dodd B, Higginbotham J; Oregon State University, CORVALLIS, OR
To:	;
Shared Package
ML20012A086	List: ML20012A085; ML20012A090;
References
	NUDOCS 9003080266
	Download: ML20012A090 (193)
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, ss D Annual Report of the Oregon State University

o Radiation Center

and TRIGA Reactor o July 1,1988 - June 30,1989 To satisfy the requirements of:

A. U.S. Nuclear Regulatory Commission. License No. R-106 (Docket No. 50-243),

Technical Specification 6.7(e).

B. Task Order No. 3. under Subcontract No. C84-110499 (DE-AC07-76ER01953) for University Reactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc.

C. Oregon Department of Energy, ODOE Rule No.30-010.

e Written by:

1

T. V. Anderson, Reactor Supervisor B. Dodd, Reactor Administrator J. F. Higginbotham, Senior Health Physicist D. S. Pratt. Health Physicist A. G. Johnson, Director 1

Submitted by:

A. G. Johnson Director, Radiation Center l

l Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (503) 737-2341 a

January 1990 L

L !

l I

i u

I Annual Report of the L. !

4 J, Oregon State University Radiation Center and TRIGA Reactor l

!. l 1

o Table of Contents l 1

I

.Pa3L! !

i PART I - DVERVIEW 1,

A. Ac knowl e dgeme n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 B. E xe c u t i ve S umma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 C. Introduction.................................................... 1-5 '

' D. Ove rvi ew of the Radi ati on Cente r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 E. Summary of OSTR Environmental and Radiation Protection i Data............................................................ 1-9

1. Liquid Effluents Released................................... 1-9

2. Airborne Effluents Released................................. 1-10 i

3. Solid Waste Released........................................ 1-10

4. Radiation Exposure Received by Personne1.................... 1-11 !

5. Number of Routine Onsite and Offsite Monitoring t Measurements and Samples.................................... 1-12

, 1-13 F. History.........................................................

l e PART II - PEOPLE I

A. Faculty......................................................... 11-1 B. Visiting-Scientists and Special Trainees........................ 11-4 :

C. OSU Graduate Students........................................... 11-5 D. Business Administrative and Clerical Staff..................... 11-6 ,

E. Reactor Operations Staff........................................ II-6 ;

F. Radi ati on P ro t ec ti on Sta f f. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-6 G. Scientific Support Staff........................................ Il-7 ;

H. OSU Radiation Safety Office Staff............................... 11-7 II-8

1. Committees......................................................

1. . Reactor Operation.e Committee................................ 11-8 l: 2. Radiation Safety Committee.................................. II-8 ,

3. Radiation Center Safety Committee........................... II-8 l .

i l

l

T 0

Page PART III - FACILITIES

'O A. Research Reactor................................................ 111-1

1. Description.....................................:........... 111-1

2. Ut111 ration................................................. III-5 o a. Instruction............................................. 111-6

b. Research................................................ III-9 B. Analytical Equipment............................................ 111-11

1. Description................................................. !!!-11

2. Utilization................................................. III-11 C. Radioisotope Irradiation Sources................................ 111-15 i

1. Description................................................. III-15

2. Utilization................................................. 111-15

D. X-Ray Machine................................................... 111-18

1. Description................................................. !!!-18

2. Ut111 ration................................................. III-18 E. Instructional Laboratories and Classrooms....................... 111-19 4

1. Description................................................. III-19

2. Utilization................................................. 111-20 F. Instrument Repair and Calibration Facility...................... 111-22

1. Description................................................. 111-22

2. Utilization................................................. 111-22 G. Libraries....................................................... III-23

1. Description................................................. 111-23

2. Ut111zation................................................. III-24 0

PART IV - REACTOR A. Operating Statistics............................................ IV-1 B. Experiments Performed........................................... IV-10 C. Un pl a n ne d S hu t d own s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-12 D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59.......... IV-14

1. 10 CFR 50.59 Changes to the Reactor Facility................ IV-14

2. 10 CFR 50.59 Changes to Reactor Procedures.................. IV-29 3, 10 CFR 50. 59 Changes to Reactor Experiments. . . . . . . . . . . . . . . . . IV-33 E. Surveillance and Maintenance.................................... IV-35

1. Non-Routine Maintenance..................................... IV-35

2. Routine Surveillance and Maintenance........................ IV-36 F. Reportable Occurrences.......................................... IV-36 l

l 2

o

F L

L I. .

Page PART V - PROTECTION

-o V-1 A. Introduction....................................................

B. En vi ronmenta l Rel e a se s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3

1. Liquid Effluents Released................................... V-3

'o 2. Ai rborne Ef fl uents Rele ased. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3

3. Solid Waste Released........................................ V-6 C. Personnel Doses................................................. V-B D. Facility Survey Data............................................ V-11

1. Area Radiation Dosimeters................................... V-11

2. Routine Radiation and Contamination Surveys. . . . . . . . . . . . . . . . . V-15 T. E nvi ronme ntal Su rvey Da ta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-17

1. Gamma Radiation Monitoring.................................. V-17

2. Soil Water, and Vegetation Surveys......................... V-24 F. Radioactive Material Sh1pmentr................................... V-28 G. References...................................................... V-31 PART VI - WORK A. Summary......................................................... VI-1 B. Teaching........................................................ VI-1

, C. Research and Service............................................ VI-1

1. Neutron Activation Analysis................................. VI-26

2. Forensic Studies............................................ VI-27

3. Irradiations................................................ VI-27

4. Radiological Emergency Response Services.................... VI-27 5.- Training and Instruction.................................... VI-28

6. Radiation Protection Services............................... VI-29 ,

7. Radiological Instrument Repair and Calibration. . . . . . . . . . . . . . VI-30

8. Consultation................................................ VI-31 PART VII - WORDS A. P u bl i c a ti on s i n P ri n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII-l

'B. Theses.......................................................... Vll-8 C. Reports Submitted for Publication............................... Vll-9 D. Documents in Preparation........................................ Vll-11

1. Publications................................................ Vll-11

2. Theses...................................................... Vll-12 E. Presentations................................................... Vll-13 F. Public Relations................................................ Vll-16 9

. i

1

> LIST OF TABLES Title Page Table Courses Using the 0STR...................................... 111 7 III.A.1 OSTR Teaching Hours......................................... 111-8 111.A.2 111-10 III.A.3 OST R Re s e a rc h Hou r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Radiation Center Spectrometry Systems: Gamma Low Energy Ill.B.1 111-12 Photon, A1pha...............................................

Radiation Center Liquid Scintillation Counting Systems...... 111-13 Ill.B.2 Radiation Center Proportional Counting Systems.............. 111-14 Ill B.3 Cobalt-60 Irradiator 111-17 Ill.C.1 Use....................................

Ill.E.1 Student Enrollment in Nuclear Engineering and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center........................................ 111-21 IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) for the 10-Year Period August 1976 - June 1986. . . . . . . . . . . . . . . . . . IV-2 .

j IV.A.2 OSTR Operating Statistics with the Original (20% Enriched)

Standard TRIGA Fuel Core.................................... IV-4 Present OSTR Operating Statistics........................... IV-5 IV.A.3 OSTR Use Time in Terms of Operational Functions. . . . . . . . . . . . . IV-6 IV.A.4 OSTR Use Time in Terms of Specific Use Categories. . . . . . . . . . . IV-7 IV.A.5 IV.A 6 OSTR Multiple Use Time...................................... IV-8 i

Use of OSTR Reactor Experiments. . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-11 IV.B.1 Unplanned Reactor Shutdowns (Scrams)...................,.... IV-13 IV.C.1 Radiation Protection Requirements and Frequencies........... V-2

.V.A.1 V.B.1 Monthly Sunnery of Liquid Effluent Releases to the Sanitary Sewer for the year July 1, 1988 through June 30, 1989....... V-4 o-V.B.2 Monthly Summary of Gaseous Effluent Releases for the Year July 1, 1988 through June 30, 1989.......................... V-5 o

4 a -----------------------_.-- ___,,,, ,,

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- x

?

LIST OF TABLES (Cont W ed) o Table ~ Title P_ age

'l

.V.B.3 Annual Summary of Solid Waste Generated and Transferred N; for. the Year July 1,1988 through June 30, 1989............. V-7 V.C.I. Annual Summary of Personnel Radiation Doses Received for the Year July 1, 1988 through June'30, 1989................. V-10' l a V.D.) Total Dose Equivalent Recorded on Area Dosimeters Located -

A Within the TRIGA Reactor Facility for the Year July 1, 1988 y through June- 30, 1989....................................... V-13 V.D.2 ~ Total Dose Equivalent Recorded on Area Dosimeters Located.

Within the Radiation Center for the Year July 1,1988

~

through June 30,-1989....................................... V-14 V.D.3 ' Annual Summary of Radiation Levels-and Contamination Levels Observed Within the Reactor Facility and Radiation W.ter During Routine Radiation Surveys for the Year July 1, 1988 '

' through June 30, 1989....................................... V-16 V.E.1 Total Dose Equivalent'at the TRIGA Reactor Facility Fence l'

< for the Year July 1, 1988 through June 30, 1989............. V-20 n- 'V.E.2 ' Total Dose Equivaler.t at the Off-Site Gama Radiation lionitoring Stations for the Year July 1,1988 through

- June 30, 1989............................................... V V.E.3 Annual i.verage Concentration of the Total Net Beta Radio-activity (Minus 3 H) for Environmental Soil, Water, and Vegetation Samples for'the Year July 1, 1988 through June 30,'1989............................................... V-26 V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water and Vegetation Samples for the Year July 1, 1988 through June 30, 1989....................................... V-27 V.F.1 Annual Summary of' Radioactive Material ' Shipments Originating

. From the TRIGA Reactor Facility's NRC License R-106 for the L' Year July 1,1988 through June 30, 1989..................... V-29' V.F.2- Annual Summary of Radioactive Material Shipments Originating

? From the Radiation Center's State of Oregon License ORE-0005-3 for the Year July 1,1988 through 2*-. June 30, 1989............................................... V-30 VI.C.1 Institutions and Agencies Which Utilized the Radiation

, Center...................................................... VI-3 VI.C.2 Graduate Student Thesis Research Which Utilized the Radiation Center............................................ VI-6 h

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PART I J. OVERVIEW A. Acknowledgements During the 1988-89 reporting period, many individuals and organizations helped the Radiation Center succeed. In recognition of this, the-staff of the OSU Radiation Center and TRIGA Reactor would like to offer their appreciation to all of those who contributed to the in-formation and events contained in this report. To the University
-administration who consistently supported our program; to those who
. provided our funding, particularly the state of Oregon and the U.S.
Department of Energy; to our regulators; to the researchers, the students and others who used our facilities and services; to the OSU Physical Plant, who patiently provided invaluable assistance through their engineering, maintenance, and other _ supporting programs; to the OSU Police and Security who are always there when we need them; and to the OSU Department of Printing, who consistently produce a quality a
product; we most earnestly say thank you.
As a final note of gratitude, the staff would like to highlight the talents and the tolerance, especially the tolerance, of our secretarial
. staff, who performed admirably during the preparation (and many revisions) of this report.
O
1-2 B. Executive Summarv
+
The OSU Radiation Center is very pleased to report the completion of another busy and successful year-a year in which there was an increase in both facility use O-and funding from outside sources. However, before we summarize our achievements, we would like to express our appreciation to everyone who contributed to our growth, in particular, we wish to thank the university's administration for their financial and administrative support and encouragement. We are also most grateful to the U.S.
Department of Energy for their valuable support through the reactor sharing program, and we would like to extend our gratitude to the many other organizations who funded research and technical services conducted by the Center. The resources obtained through these channels continued to create opportunities for numerous students and new researchers to use the unique facilities present at the Radiation Center.
Academic activity at the Radiation Center and reactor remained very high during
,- the current reporting period. For example, the reactor showed a 4% increase in total hours at full power and continued to be in use 90% of the available 45 hour5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months work week. This is about the maximum possible use for a one shift operation. As a result, we occasionally were required to operate beyond our normal schedule and accomplished this by performing overtime reactor runs, in the teaching area, the Radiation Center accommodated 53 OSU classes from a number of different academic departments. About one-half of these classes used the reactor and about 25% of the reactor's total operating hours were in direct support of such classes.
Student projects for instruction and research continued to keep our program busy, and the number of student projects accommodated at the Center remained approximately equal to last year's all time high. Additionally, the number of reactor ~
hours devoted to OSU research increased 4%, the number of funded research hours using the reactor increased approximately 10%, and the total number of reactor hours
, devoted to supporting all research increased slightly over 7%.
Other use indicators also reflect the busy year experienced by the Radiation Center and reactor. For example, we had a 13% increase in the number of operating hours when the reactor had multiple users, and 24% of the total operating hours involved more than one user. The multiple use mode, which is an important way to increase the efficiency of reactor use, was much more predominate during the current
1-3 L
reporting period, and on several occasions we had as many as seven users at one time. This is a new record for our program. We also ended the year with a 10%
increase in the number of other universities using the Center, a 6% increase in the number of research and service projects performed, and a 51% increase in the number of faculty using our facilities. We are particularly pleased with the preceding results because we were able to measurably increase our assistance to the OSU community while concurrently expanding our research and service interactions with other universities in the Oregon State System of Higher Education (OSSHE), with a number of state and federal agencies, and with colleagues at other universities across the nation. We also continue to feel encouraged by these results because, from our perspective, they are a good indication of the fact that the OSU Raoiation Center is continuing to grow in terms of regional and national recognition, in the area of research support and new technical programs, the Radiation Center made 79 shipments of radioisotopes to users outside the facility, and had a 4-fold increase in the size of our program for calibrating portable radiation monitoring instruments. Enlargement of this program directly benefitted OSU and other State System schools, in addition to helping several agencies of the state of Oregon and several federal organizations. The staff also continued to receive a significant increase in the number of requests for gamma irradiations using the cobalt-60 irradiator. By the end of the reporting period we showed a 26% increase over last year in the number of irradiations performed using the cobalt 60 irradiation facility.
The Radiation Center also continued to be a popular place to visit, particularly for high schools, community colleges, and interested citizens. We again hosted over 800 visitors during the course of the year.
Scholarly publications involving a contribution by the Radiation Center increased 10%, and there were 29 presentations at professional meetings where the Center supported the development of the research data being reported. Considering the publications currently in print, those presently submitted for publication, and those in the final stages of preparation, there have been 109 total articles generated during the 1988-89 reporting period which involved a contribution by the Radiation Center.
Within the current reporting interval, the Center built and installed a new cad-mium lined, in core irradiation facility for the reactor. We also hosted the 1988 annual meeting of the National Organization of Test, Research and Training Reactors and the 1989 American Nuclear Society Western Regional Student Paper Conference. To
1-4 manage the increased overall use of the Radiation Center and its facilities, our project system continued to work well as a means of accounting, scheduling, and recording facility use.
As a final note, we feel that it is very important to point out that there were no L ltems of regulatory noncompliance and no emergencies or security events relating to the Radiation Center during this reporting period. Furthermore, all of the increased use of the Radiation Center arid reactor was accomplished with no increase in personnel radiation exposure or any impact on the environment. The comprehensive radiation protection program at the Radiation Center once again showed that the Center and the reactor car' be operated safely and within the international goal of keeping personnel doses and releases of radionuclides as low as reasonably achiev-able (ALARA).
t o
h 0
1 C.. Introduction
The current annual report of the Oregon State University Radiation Center and TRIGA Reactor follows the expanded format introduced for ,
9 the first time last year. In particular, the report includes information relating to the entire Radiation Center rather than just the reactor.
However, the information is still presented in such a manner that - .
data on the reactor may be examined separately if desired. It should be noted that reactor operating data in this report relate only to the FLIP-fueled core. For a summary. of data on the reactor's original 20% enriched' core the reader is referred to Table'IV. A.2 in Part IV-of this report, or-to the 1976-77 annual report if a more comprehensive review is needed.
In addition to providing general information about the activities of the Radiation Center, this report is designed to meet the reporting requirements of the U.S.-Nuclear Regulatory Commission, the U.S.
Department of Energy, and the Oregon Department of Energy. Because_ ,
Y- of this, the report is divided into several distinct parts so that
.the reader may easily-find the sections of interest. An executive ;
summary is also included for those already familiar with the Radiation Center's operation.
L 1
1.
l l
I 9-p
I-6:
~
' D. -Overview of' the Radiation Center
.m The Radiation Center is an extremely unique facility which serves i the entire OSU Campus, all'.other institutions within the Oregon State System of Higher Education, and many other colleges and universities throughout-the nation. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law; enforcement, energy, health, and-environmental quality, and renders-assistance to Oregon industry. In addition, the Radiation i Center provides permanent office and laboratory space for the OSU !
Department of Nuclear Engineering, the OSU _ Radiation Safety program, the. Institute of Nuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, and geo- and cosmochemistry _
programs. There is no other university facility with the combined capabilities of the OSU Radiation Center in the western half of the q United States. See-Figure I.D.1.
-i j Located in the Radiation Center are major items of specialized equipment '
and unique teaching and research facilities. These include a TRIGA Mark 11 research nuclear reactor; a cobalt-60 gamma irradiator; a 300 kVp X-ray generai.or; a number of state-of-the-art computer-based
> gamma radiation spectrometers and associated germanium detectors; j a neutron radiography facility capable of taking still or very high i speed radiographs; and a-variety of instruments for radiation measure-ments' and monitoring. Specialized facilities for radiation work include teaching and research laboratories 'with up-to-date instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laboratories for animal and plant experiments +
involving radioactivity; an instrument facility for repair and calibration-of_ radiation protection instrumentation; and facilities for packaging radioactive materials for shipment to national and international destinations.
The Radiation Center staff regularly provides direct support and assis-tance to OSU teaching and research programs. Areas of expertise commonly involved in such efforts include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, neutron radiography, radiation effects on biological systems, radiation dosimetry, production l
4 1-7; of short-lived radioisotopes, radiation shielding, nuclear instrumen-tation, emergency response, transportation of radioactive materials, instrument calibration, radiation _ health physics, radioactive waste disposal, and other related areas.
.O
-In addition to formal academic and research. support, the Center's staff provides a wide variety of other services including public tours and public instructional programs, and professional consultation associated with the feasibility, design, safety, and execution of experiments using radiation and radioactive-materials.
I
-9
1 4
J Figure 1.D.1 _ _ _ .
I-8 _
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E I-9 4 U
?
Sunnary of OSTR Environmental and Radiation Protectibn Data
~
E. ! o- t
.. Year July 1, 1988 *
1. Liquid Effluents Released (See Table V.B.1)' Through June 30, 1989-
,' a. Total estimated quantity of radioactivity released (to the sanitary 3 ewer)(in curies)(1) 8.53 x 10-4'
b. Detectable radionuclides in the liquid waste 3g, 60C0-

c. Estimated average concentration _ of released
'*" radioactive material at the point of release (in microcuries per cubic centimeter) 3.00 x 10-5
d. Percent'of applicable.MPC for released ,
liquid radioactive material at the point 1.0%(2) I of release (%) 0.03%(3)
e. Total volume of-liquid effluent released.
' including diluent, which contained an OSTR contribution (in' gallons)(4) 7542 -o l >+
(1) The OSU operational policy is to subtract only detector background from our water analysis data and not background radioactivity in the Corvallis city water. (2) Based on values listed in 10 CFR 20, Appendix B Table 2, Column 2. (3) Based on values-listed in 10 CFR 20, Appendix B, Table 1, Column 2, applicable to sewer disposal. > n, (4) Total volume of effluent plus diluent does not take into consideration the additional mixing with the over 7,500,000 gallons per year of liquids and sewage normally discharged by the Radiation Center complex . into the same sanitary sewer system. f
~
li L I-10 Year July 1, 1988
2. Airborne Effluents Released-(See Table V.B.2) Through June- 30, 1989 4

a. Total estimated quantity of radioactivity released ~ (in curies)~ 6.3

b. Detectable radionuclides in the gaseous
'wastell) 41A r (Tg = 1.83 hr)-
c .- Estimated average atmospheric diluted concentration of argon-41 at.the point
- of release (in microcuries per cubic centimeter) 4.0 x 10-8
d. Percent of applicable MPC for diluted concentration of-argon-41 at the point of release (%) 1.0

e. -Total _ estimated release _of radioactivity in particulate form with half-l greaterthan8 days (incuries)jygs \U None ;
Year July 1,1988
.3. - Solid Waste Released (See Table V.B.3) Through June 30, 1989 - a. Total amount of solid waste packaged and disposed of (in cubic feet) 21.0-
b. Detectable radionuclides in the solid waste 3H , 46se, 51C r. ,
54Mn, 58Co. 59pe- j 60C0, 75$ ,, 82Br. 124Sb, kJ2Te, 141Ce, 144Ce, 152E u, 154Eu
c. Total radioactivity in the solid waste (in curies) 5.2 x 10-5 i
$ (1) Routine gamma spectroscopy analysis of the gaseous radioactivity ,
in the stack discharge indicated that it was virtually all argon-41. (2) Evaluation of the detectable particulate radioactivity in the stack
. discharge confirmed its origin as naturally occurring radon daughter 4 products, predominantly lead-214 and bismuth-214, which are not asso-ciated with reactor operations.
l l ii
'h -1 11 m
4. Radiation Exposure Received,by Personnel ' Year Wy 1,' 1988 (in mrem) (See Table V.C.1) W Through .b 7e 30,1989 -
a Facility Operating Personnel 9 1 ' Average whole body 12 2 Average extremities 72
-3 Maximum whole body -80 4): Maximum extremities 500-e b. Key Facility Research Personnel ..1)- Average whole body 0
2) Average extremities 5

3) Maximum whole body. 0

4) Maximum extremities 40 3 i

c. Physical Plant Maintenance Personnel

1) Average whole body <1-

2) Maximum whole body 8

d. Laboratory Class Students 4.

1) Average whole body 0-2)-~ Average extremities 7 J- 3) Maximum whole body 0 [
4)' Maximum extremities 100-e.. Campus Police and Security Personnel
1) Average whole body 0 !

2) Maximum extremities 0
'l t
f. Visitors j

1) Average whole body <1

2) Maximum whole body 5
-i .i -1 l
e (1) "0" indicates that each of the beta-gamma dosimeters during the report-ing period was less than the vendor's gamma dose reporting threshold of -10 mrem or that each of the neutron dosimeters was less than the vendor's threshold of 30 mrem, as applicable, i 1 4
4 1-12. Year July 1, 1988:
5. Number of Routine Onsite and Offsite Monitorin'a Measurements and Samples Through June 30,~ 1989
~ - a. Facility Survey Data a 1) Area Radiation Dosimeters (See' Table V.D.1)-
a) - Beta-gamma dosimeter measurements 136 48 b) Neutron dosimeter measurements - ,. 2) Radiation and Contamination Survey-Measurements-(See Table V.D.3) s6000 b '. Environmental Survey Data
1) Gamma-Radiation Monitoring (See Tables V.E.1 and V.E.2) a): Onsite monitoring
-- OSU -TLD monitors- 108 -- Radiation Detection'Co. TLD monitors 72 --- Monthly pR/hr measurements 108 b) Offsite monitoring -- OSU TLD monitors 264 -- Radiation Detection Co. TLD monitors 104 -- Monthly pR/hr measurements 252-
2) Soil, Water and Vegetation Surveys (See Table V.E.3) a) . Soil samples 16 b) Water samples 16 c) Vegetation samples 56 a
.D' e
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!-13 F. History
_ A brief chronology of the key dates and events-in the history of the OSU Radiation Center and the TRIGA reactor is given below: is Jun'e_1964 _ Completion of the first phase of the Radiation Center, consisting of 32,397 square feet of office and laboratory space. July-1964 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. This reactor was initially housed in the Mechanical Engineering Department and first went critical _in' January of 1959. Oct. 1966 Completion of the second phase of the Radiation Center, consisting of 9,956 square feet of space for the TRIGA reactor and associated laboratories and offices.. March 1967 Initial criticality of the Oregon State TRIGA Reactor j (OSTR) . The reactor was licensed to operate at a
- maximum steady state power level of 250 kW, and was fueled with 20% enriched fuel.
August 1969 OSTR licensed to operate-at a maximum steady state power of 1 MW, but could do so only for short periods of time due to lack of cooling capacity. June 1971 OSTR cooling capacity upgraded- to allow continuous { operation at 1 MW.
- April 1972 OSTR Site Certificate issued by the Oregon Energy ;
Facility Siting Council. Sept. 1972 OSTR area fence installed. Dec. 1974 AGN-201 reactor permanently shut down.
~. *: March 1976 Completion of 1600 square feet of additional space to accommodate the rapidly expanding nuclear engineering program.
July 1976 OSTR refueled with 70% enriched FLIP fuel.
;;7 1-14 July 1977. Completion of a second 1600 square feet of space ' to bring the Radiation Center complex to its current total of 45,553 square feet.
a' Jan. 1980 Major upgrade of the electronics in the OSTR control console. July 1980 AGN-201 reactor decommissioned and space released-
, for unrestricted use. - June 1982 Shipment of the original 20% enriched OSTR fuel to Westinghouse Hanford Corporation.
Dec., 1988 AGN-201 components transferred to Idaho State University for use in their AGN-201 reactor program. 9-id - T lm'
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a PART 11 o PEOPLE 4- -This part contains a listing of all people who were residents of the Radiation-Center or who worked a significant amount of time at the Center during this reporting period. Sections A, B and C list the academic staff, trainees and students, while sections D through G give the Radiation Center's operating
staff. Section H shows the OSU Radiation Safety Office staff and section I provides the composition of committees involving Center personnel.
It should be'noted that not all of the faculty and students who used the , Radiation Center for their teaching and research are listed in this part. Summary information on these people is given in Table VI.C.1, and individual names and projects are listed in Tables VI.C.2 and VI.C,3.
+ A. Faculty
Johnson, Arthur G.
Director, OSU Radiation Center Director, OSU Institute of Nuclear Science and Engineering
-Professor of Nuclear Engineering and Radiation Health *Binney, Stephen E.
Associate Professor of Nuclear Engineering Chairman, OSTR Reactor Operations Committee
*Conrady, Michael R.
Research. Assistant Neutron Activation Analysis Specialist
*Cordell, Sharon M.
Research Assistant
' Radiation Protection Technologist Daniels, Malcolm Professor of Chemistry ' *Dodd, Brian e Reactor Administrator Professor of Nuclear Engineering
Reactor users for research and/or teaching.
4 11 2: e 4
*Golightly, 'Vivian H. -Research Assistant Radiation-Protection Technologist Hart, Lucas'P.--
Research Associate, Chemistry' : j_ Higginbotham, Jack F. Senior Health Physicist , Assistant Professor of Nuclear Engineering '
*Hughes, Scott S.
Research Associate, Chemistry Klein, Andrew C. Assistant Professor of Nuclear' Engineering
*Loveland, Walter _ D.
Professor of Chemistry
'MacVicar, Robert l President Emeritus, OSU }
l. J. - Maki, Leonard M. -t Professor of Nuclear Engineering (Visiting)
*Pastorek, Christine Instructor of Chemistry Popovich, Milosh ,
Vice President Emeritus, OSU
*Pratt, David S. 3 <- Research Assistant-Health Physicist Reyes, Jose _N.
Assistant Professor of Nuclear Engineering
*Ringle,fdohn C.
Professor of Nuclear Engineering > Associate Dean of-the Graduate School, OSU
' *Robinson,. Alan H.
Head, Department of Nuclear Engineering P~ Professor of Nuclear Engineering
r. '
y *Schmitt, Roman A. L Professor of Chemistry l
Reactor users for research and/or teaching.
y;, , u, F 11-3
;a ;\ -;
Walker,: Robert J.
J/ Research~ Assistant'
#E Neutron' Activation. Analysis Specialist-
@' c,1 . Wang Chih'H. 49-Professor Emeritus,- 0SU - v
-
Woods W.'Kelley 4 Professor of Nuclear _ Engineering Ii
L,: 4 l'
f l e, -
l '. , t. .. ! I o ! 4 y k -l ow-1 ?'* - i,
Reactor users for research and/or teaching, i s
' kt :
, 4 II-4 ;B. Visiting Scientists and_ Special Trainees Advisor or Research Field (Affiliation) Program Director Name BergstrBm.. Magnus Nuclear Chemistry W. D. Loveland-l=
(Sweden) W. D. Loveland '< Groening, Hugo. . Nuclear Chemistry (Argentina) a
*Hou,Bijun Radiation Health. A.'G. Johnson (People's. Republic of China) *Jin, Guang Yu Neutron Activation Analysis R. A. Schmitt (People's Republic of China) *Jin, Yuequn Neutron Activation Analysis R. A. Schmitt '
(People's Republic of. China) i Long,~Zhenjie Nuclear Engineering A. H. Robinson (People's' Republic of China) . i i Rahman, Mofizur Nuclear Engineering A. H. Robinson [ ' (Bangladesh) 3 Wang, Rushan Data Analysis-Chemistry W. D. Loveland
.X (People's Republic of China) .
! *Yokoyama,- Akihiko Nuclear Chemistry W. D. Loveland (Japan) i-l l-l L I .. ~ . L.
D-IReactor users for research and/or teaching.
l. i
11-5 i C.. OSU Graduate Students
Degree Name Program Field Advisor os Abdelhai, Mohamed I. PhD Nuclear Engr. B. Dodd Al-Baroudi, Honan PhD Nuclear Engr. A. C. Klein Almarshad, Abdullah PhD Nuclear Engr. A. C. Klein Almasoumi, Abdullah PhD Nuclear Engr. S. E. Binney Anand,Ajay. PhD Nuclear Engr. A. C. Klein
.-. Azim, Bilqees PhD Nuclear Engr. S. E. Binney Bukar, Kyari A. MS Nuclear Engr. S. E. Binney *Casey, Coreen PhD Chemistry W. D. Loveland Cho, Byung-Oh MS Nuclear Engr. A. H. Robinson *Curless, John M. MS Geology C. W. Field *Davidson, Gary F. PhD Geology L. Snee Eicnenberg, Thomas.W. MS Nuclear Engr. J. N. Reyes *Feeley, Todd C. MS Geology A. L. Grunder Fu, Yingxian MS Chemistry M.- Daniels Gedeon, Steve MS Nuclear Engr. A. H. Robinson s
Greek, Kevin PhD Nuclear Engr. A; H. Robinson Greene, Kenneth PhD Nuclear Engr. A. H. Robinson Hicks, Thomas MS Radiation Health B. Dodd

Hill, Brittain E. PhD Geology E. M. Taylor
*1vy, Susan MS Geology R. A. Schmitt Jordheim, Daniel P. MS Nuclear Engr. S. E. Binney-o: King, John MS Nuclear Engr. A. C. Klein Lafi, Abd.Y. PhD Nuclear Engr. A. C. Klein Lee, Chungchan PhD Nuclear Engr. A. H. Robinson. '*Liu,.Yung-Gang PhD Chemistry R. A. Schmitt Marks, Tim MS Nuclear Engr. A. C. Klein *Marso, Jeffrey N. MS Geology E. M. Taylor Pauley, Keith MS Nuclear Engr. J. N. Reyes Pawlowski, Ronald MS Nuclear Engr. A. C. Klein ' *Pratt, David MS Radiation Health A. G. Johnson Richardson, Alan D. PhD Chemistry M. Daniels Saleh, Hassan PhD Nuclear Engr. S. E. Binney Samuels', Jeffery PhD Nuclear Engr. A. H. Robinson *Schilk, Alan J. PhD Chemistry R. A. Schmitt Van Winkle, James A. MS Nuclear Engr. A. C. Klein
Walker, Robert J . PhD Geology C. W; Field
*Yesilyurt, Suleyman MS Geology C. W. Field *Yousef, Samir MS Radiation Health J. F. Higginbotham 'Zahm, Lance MS Nuclear Engr A. C. Klein
Reactor users for research and/or teaching.
'II-6 c..
14 '
- D. Business, Administrative and Clerical Staff Director .
A. G. Johnson Business Manager M. L. Whitney C. A. Barber
. Administrative-Assistant E. C. Flickinger Clerical Assistants- P. A. Cunningham J. R. Smith C. L. Hatcher-England K
i Custodian- M. L. Benad .
' Administrative Assistant (Nuclear Engineering) 'D. L. Cramer Clerical Specialist (Nuclear Engineering) R. A. Keen i L-l E. Reactor Operations Staff ~
i l ' !- Principle Security Officer A. G. Johnson Reactor Administrator, Senior Reactor Operator B. Dodd Reactor Supervisor, Senior Reactor Operator T. V. Anderson Senior Reactor Operators- S. E. Binney.
. J. F. Higginbotham ,
Reactor Operator A. D. Hall ; F. Radiation Protection Staff I Senior Health' Physicist J. F. Higginbotham Health Physicist D. S. Pratt Radiation Protection Technologist V.- H. Golightly S. M. Cordell Health Physics Monitors (Students)- W. Cox S. LaBuy N. Moreno =r K. Richardson i' E. Rockett J. Starr ,
, 5-e:
L r
=-
e. r.f:) t: , " , , 11 7: L , 4: ; p - 2
' i
s. . - 6. Scientific Support Staff I.Q ' -
Senior Neutron Activation Analysti R. A. Schmitt Neutron. Activation Analysis 7 , Specialists M. R. Conrady a is- - R. J. Walker ,
. Neutron Activation Analysis '
i:- Technicians (Students) T. Berkman s J. Curless
T. Feeley Jo - , T. Harris ,
J. Marso- . A. Mathis
L. Ovey T.. Poet D. Zook _
r Scientific Instrument Technicians H. L.-Busby
. D. K. Woodrow l
H. - OSU Radiation Safety Office Staff h*' ' Title Name-t n . Radiation Safety Officer- G. A'. Little
-l l- W Radiation Specialists- R. H. Farmer R.'~C. Wallace ~~
l K. C. Tompkins t
. D. L. Harlan ^!
c l-I- Secretaries ' K. L. Miller ., i f
. -I 'h ) .V ,,1 s.
l,: l .I 4 - - - , - -
i p: II-8 - I. Committees- , l*! 1. Reactor Operations Committee Name Affiliation , i . 1 S. E. Binney, Chairman Nuclear Engineering . D. L. Amort Electrical and Computer Engineering
~ .T. V.. Anderson Radiation.. Cente r s .
B. Dodd . .
-Radiation Center and Nuclear Engineering.
4 J. F. Higginbotham- Radiation Center and Nuclear.. Engineering: L A. G. Johnson Radiation Center ana Nuclear Engineering .; l" J. C. Ringle-Nuclear Engineering and Graduate School- '. A. H. Robinson Nuclear Engineering . R. A.'Schmitt Chemistry and Radiation Center ' S. A. Stone College of- Engineering, Dean's Office ,
~W. H. Warnes Mechanical Engineering 1 . ~ 2. Radiation Safety Committee (OSU)
Affiliation Name' ,
* .T. F. Murray, Chairman Pharmacy L. E. Coate V. P. for Finance and Administration' ; 'B. Dodd -Radiation Center and: Nuclear Engineering.
. J. F. Higginbotham- Radiation Center and Nuclear Engineering-A. G. Johnson Radiation Center and. Nuclear Engineering-G. A..Littla retary & RS0 Radiation Safety.0ffice
'G. F.~Rohr9 Agricultural' Chemistry C. J. Rivir, Botany C.-B. Schrec- Fisheries arid Wildlife ' -~J. B.-Zaerr Forest Science
3. Radiation Center Safety Committee j =Name Affiliation
~W. D. Loveland, Chemistry Chairman . T. V.' Anderson Radiation Center S. E. Binney Nuclear Engineering H. L. Busby Radiation Center.
M..R. Conrady Radiation Center-A. G. Johnson Radiation Center and Nuclear Engineering ?*- -M. L. Whitney Radiation Center
- e '.
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i U i PART III i lo FACILITIES 1 1
, i ;, A. Research Reactor ,
1. Description l The Oregon State University TRIGA Reactor (OSTR) is a water-cooled,
- swimming pool type of research reactor which uses uranium / zirconium hydride fuel elements in a circular grid array. The reactor core is surrounded by a ring of graphite which serves to reflect neutrons back into the core. The core is situated near the bottom of a 22 foot deep water-filled tank, and the tank is surrounded by ;
a concrete bioshield which acts as a radiation shield and structural support. See Figures III.A.I. III.A.2 and III.A.3. g The reactor is lir.ensed by the U.S. Nuclear Regulatory Commission ; to operate at a maximum steady state power of 1 MW and can also , be pulsed up to a peak power of about 3000 MW. e i The OSTR has a number of different irradiation facilities including q a pneumatic transfer tube, a rotating rack, a thermal column, four beam ports, two sample-holding (dummy) fuel elements for special in-core irradiations, and a cadmium-lined in-core irradi-ation tube for experiments requiring a high energy neutron flux. , i The pneumatic transfer facility enables samples to be inserted L and removed from the core in a few seconds. Consequently, this . facility is normally used for neutron activation analysis involving !' short-lived radionuclides. On the other hand, the rotating rack i is used for much longer irradiation of samples (e.g., hours). The
rotating rack consists of a circular array of 40 tubular positions, ,
each of which can hold two sample tubes. The rotation of the , rack ensures that each sample will receive the same amount of o- irradiation.
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2s FT. a lse. Fig. III.A.3 Vertical Section of TRIGA Mark II Reactor t b l __________- . - .._.. -_ . . - .. .. .. . - . , . . . , . . - . - . - . . . . ~ . . . . - . . . . ~ . - . , - . , , . - . . - - . - - , . . - , . - . _ .
F I III-5 g The reactor's thermal column consists of a large stack of graphite
blocks which slow down neutrons from the reactor core in order to increase thermal neutron activation of samples. Graphite blocks i
i. are removed from the thermal column to enable samples to be posi-
tioned inside for irradiation.
The beam ports are tubular penetrations in the reactor's main [ concrete shield which enable neutron and gamma radiation to stream i from the core when a beam port's shield plugs are removed. Two of the OSTR's beam ports are permanently configured for neutron radiography while the other two may be used for a variety of ex-
! periments.
If samples to be irradiated require a large neutron fluence, especially from higher energy neutrons, then such samples may be inserted i L* into a dummy fuel element. This device will then be placed into one of the core's inner grid positions which would normally be occupied by a fuel element. The cadmium-lined in-core irradiation tube enables samples to be irradiated in a high flux region near the center of the core. The cadmium lining in the facility eliminates thermal neutrons , and thus permits sample exposure to epithermal neutrons only. The cadmium-lined end of this air-filled aluminum irradiation tube is inserted into an inner grid position of the reactor core , which would normally be occupied by a fuel element.
. 2. Utilization The two main uses of the OSTR are instruction and research. During .c this reporting period, the reactor was in use an average of 40 l* hours during a typical 45-hour work week. Hence, the reactor was used approximately 90% of the available time. ,
e l l
r 111-6 r l. ,~ ,
a. Instruction
Instructional use of the reactor is twofold. First, it is used significantly for classes in nuclear engineering, radiation protection, and chemistry at both the graduate and undergraduate

levels to demonstrate numerous principles which have been pre-sented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many

demonstrations and instructional experiments can be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experiments are also performed for many undergraduate students in physics, chemistry and biology classes, as well as for visitors from other universities and colleges, from high schools and from public groups.

The second instructional application of the OSTR involves education of reactor operators, operations managers, and radi-ation health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactor and in associated labora-tories. The many types of educational programs that the Radi-ation Center provides are more fully described in Part VI (section VI.C.5) of this report.
During this reporting period the OSTR accommodated 20 different OSU academic classes. In addition, portions of classes from other Oregon universities were also supported by the OSTR. The OSU teaching programs utilized 260 hours of reactor time. -i Tables Ill. A.1 and Ill. A.2 as well as Table III.E.1 provide detailed information on the use of the OSTR for instruction
) and training.
' III-7 r
Table III.A.1 Courses ilsing the OSTR Lo to. _ Course No. Course Name i l- NE 101 Nuclear Engineering Orientation NE 102 Nuclear Engineering Orientation NE 203 Nuclear Radiation Detection and Measurement
! NE-405A Field Practices in Radiation Protection (Undergraduate)
L NE 406 Projects (Nuclear Engineering) NE 441 Nuclear Reactor Experiments NE 461 Radiation Protection Engineering NE 503 Thesis (Nuclear Engineering) NE 505A Field Practices in Radiation Protection (Graduate) CH 106 General Chemistry Laboratory CH 107 General Chemistry Laboratory CH'206H, Chemistry Honors CH 207 General Chemistry Laboratory CH 419 Radioactive Tracer Methods
-'- CH 461- Experimental Chemistry 11 CH 503 Thesis (Chemistry)
FST 423 Food Analysis G 503 Thesis (Geology) OC 503 Thesis (Oceanography) PH 503 . Thesis (Physics) g. l '. 1
III-8 k' .
Table III. A.2 i J OSTR Teaching Hours i a o Annual Cumulative I
! Values for Values for 1 JUL 88 1 AUG 76 ,
Description Through Through l J' 30 JUN 89- 30 JUN 89 ; (hours) (hours) ! Departmental 231 2636 Nuclear Engineering 202 Chemistry. 25 ! 4 : Food Sc'iggce 1 GeologyW 1 Oceanogreghy(l) _; Physics \li i , c' I Special Classes and Projects \2 ) 29 358 2 l Total Teaching Hours (3,4,5) 260 2994 l (1) Use hours by these departments are not shown under " Teaching Hours," but are reflected under Thesis Research, both funded and unfunded, t (2) A variety of educational classes were conducted which involved one-time meetings for orientation or support purposes. These included: , high school science classes, new student programs support, reactor operator orientation and training, community college classes and classes from other universities. (3) See Table III.E.1 for classes and student enrollment.
. (4) See Table IV.A 5 for a summary of all reactor use categories. ,
(5) Total teaching hours reflect all time the reactor was in use for teaching, and b .cause of this the total hours include time the reactor
itself may not actually have been in operation.
e-1
i 111-9 l
b. Research
-o The OSTR is an extremely unique and valuable tool for a wide variety of research applications, and serves as an excellent source of neutrons and/or gamma radiation. The most popular ,
o experimental technique requiring reactor use is neutron acti- ! vation analysis (NAA). This is a particularly sensitive method - of elemental analysis which is described in more detail in 3 Part VI (section VI.C.1). Part 111.8 provides a listing of , equipment used in NAA at the Radiation Center, i The OSTR's irradiation facilities provide a wide range of ; neutron flux levels and neutron flux qualities, which are sufficient to meet the needs of most researchers. This is l true not only for NAA, but also for other experimental tech- [ niques such as fission track dating of geological and anthro-
. pological materials.
l t During this reporting period, the OSTR acconnodated 81 funded research projects which utilized 1106 hours of reactor time, and 10 unfunded research projects which utilized 71 hours of reactor time. Details of the reactor's use specifically for research are given in Table Ill.A 3. Additional information regarding reactor use for research, thesis and service can j be found in Tables VI.C.1 through VI.C.3. In these tables l l OSTR use is indicated with an asterisk. l-e. 4 e
n__ 111-10 Table ll1.A.3
.c ,
OSTR Research Hours 2 O-Annual Cumulative Values Values for for a Types of Research 1 JUL 88 1 AUG 76 Through Through 30 JUN 89 30 JUN 89 (hours) (hours) OSU Research 386 5782 Off-Campus Research 791 2909 Total Research Hours (l)(2) 1177 8691 ,
., (1) Total research hours statistics:
(a) 94% (1106 hours) of the total research hours were user-funded by federal state, or other organizations. (b) 6% (71 hours) of the total research hours were user-unfunded studies in support of graduate thesis research or other academic investigations. Reactor costs for this research were absorbed (funded) by the OSU Radia-tion Center. (2) 0STR operating hours in support of OSU teaching and research programs approximately equal the hours the OSTR operated for off-campus research projects. Of the off-campus research hours OSTR recorded, nearly 8% (approximately 60 hours) were in direct support of research being conducted at the University of Oregon and Portland State University. e t 4 i J
III-11 B. Analytical Equipment e' 1. Description The Radiation Center has a great variety of radiation detection
. instrumentation. Much of this equipment involves the latest in counting technology as represented by the twelve state-of-the-art gamma ray spectrometers with their associated computers and Ge(L1) ;
or intrinsic germanium detectors. Tables III.B.1 through III.B.3 a provide a brief listing of typical laboratory counting devices present at the Center. Much additional equipment for use in the , classroom, and an extensive inventory of portable radiation detection instrumentation are also available.
2. Utilization ,
Radiation Center nuclear instrumentation receives intensive use in both teaching and research applications. In addition, service ; projects also use these systems and the combined use often results l in 24-hour per day schedules for many of the analytical instruments. l Use of Radiation Center equipment extends beyond that located at the Center and instrumentation is commonly made available on a loan basis to OSU researchers in other departments. \* l l O' l l
c L III-12
' Table III.B.1 Radiation Center Spectrometry Systems:
i Gamma, low Energy Photon, Alpha L
Rel. Effic.
Room System (%) B100 Adcam 1, 8k Ortec, Ortec HP Ge 26.8 B100 Adcam 2, 8k Ortec, PGT Ge(L1) 13.0 f~ B100 Adcam 3, 8k Ortec, Canberra Ge(L1) 19.4 B100 Adcam 4, 8k Ortec, PGT Ge(L1) 13.2 C126 Ace 1, 4k Ortec, Nal(T1) 3x3 N/A C123 Ace 2, 4k Ortec, PGT Ge(L1) 18.7 C126 2 K ND60, Nal(T1) 3x3 N/A A138 H.P. Scaler, Nal(T1) 2x2 N/A A146 Ace, 4k Ortec, Ortec HP Ge 30.0 A146 Ace, 4k Ortec, Ortec Ge(L1) 27.0 C134 Ace, 4k Ortec, Ortec HP Ge 32.0 C134 4x4 k ND Micro MCA, PGT Ge(L1) 16.2 C134 4x4 k ND Micro MCA, PGT Ge(Li) 19.3 C134 4x4 k ND Micro MCA, PGT LEP N/A C134 4x4 k ND Micro MCA, Canberra LEP N/A C126 Ace 3, 4k Ortec, 576A Alpha N/A Spectrometer l. l l9 o L.
111-13 i Table III.B.2 Radiation Center Liquid Scintillation Counting Systems Room System C126 Beckman. Betamate C126 Beckman, Betamate C126 Beckman, Betamate C126 Beckman, Betamate B136 Beckman, LS 7500 B136 Searle O e 4 9' 4
111-14 l-jr Table Ill.B.3 Radiation Center Proportional Counting Systems f-
>c Room System 7
i C126 NMC 1, PC5
" C126 NMC 2. PCS e
C126 NMC 3. PCS A138 NMC, PCC-11T and DS 2 A138 NMC Auto Counting System w/ IBM XT 1 7 G 4
.4 9
i
'O
111-15 i: b
! C. Radioisotope' Irradiation Sources o 1. Description The Radiation Center is equipped with a cobalt-60 gamma irradiation To facility which is capable of delivering high doses of gamma radia- ** tion to a wide variety of materials. Typically, the irradiator is used by researchers wishing to perform mutation and other bio-g logical effects studies, studies in the area of radiation chemistry, L- dosimeter testing, sterilization of food materials, soils, sediments and other media, gamma radiation damage studies, and other such applications. In addition to the cobalt-60 irradiator, the Center is also equipped with a variety of smaller cobalt-60, cesium-137, radium-226, plutonium-beryllium, and other isotopic sealed sources of various curie levels which are available for use as irradiation sources.
2. Utilization During this reporting period there was a diverse group of projects
[ using the cobalt-60 irradiator. These projects _ included the irradi-ation of mice as part of an immuno-toxicological study of dioxins. l l the irradiation of fish lymphocyte cells, pumpkin seeds, pinto beans, onion flowers, and algae. In addition, the irradiator was used for radiation dosimeter analysis, soil sterilization. l and materials evaluation. Data showing uses of the irradiator for this reporting period are given in Table III.C.1. 1
.e.
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III-17 ! i L I i Table III.C.1 I Cobalt-60 Irradiator Use fo
o-Purpose of Dose Range Number of Use Time

Irradiations (hours)
Irradiat16n Samples (rads) Sterilization Soil 5 x 106 1 744 t Botanical Onion flowers. 104 - 2x104 14 477.9 Studies pumpkin seeds, pinto beans, ' algae culture Biological Mice, fish 4.5x102 - 6x103 62 20.1 Studies lymphocyte
cells o Dosimeter TLDs 37 - 2x103 4 1.3 Analysis i
Materials Wood. PVC. 3x102 - 1x106 7 269.6 Evaluation copper wire TOTALS 88 1512.9 I t,. I 2 e-
c , t-111-18 r O. X-Ray Machine
1. Description A General Electric Maxitron 300 kVp X-Ray generator is located I in the Radiation Center. This device is situated in a shielded so room which is large enough to accommodate a wide variety of experi- .
ments. The machine is capable of operating at 300 kVp and 20 o mA, and devices for calibrating the beam intensity are available. .
! 2. Utilization ,
The X-Ray machine continued to be used as a radiation source where , students could perform state-required radiation surveys of a fixed X-Ray machine installation and carry out other safety checks required for such a facility, e
'O F
F 9 i I i lh 4 l 4 1 l l: . 1
W I11-19 ; E f
'E. Instructional Laboratories and Classrooms o 1. Description The Radiation Center is equipped with a number of different radio- ' + active materials laboratories designed to accommodate classes '* offered by various OSU academic departments or off-campus groups.
Instructional facilities available at the Center include a laboratory
-e s especially equipped for teaching radiochemistry and two nuclear t-instrumentation teaching laboratories equipped with modular sets of counting equipment which can be configured to accommodate a ;
variety of experiments involving the measurement of many types of radiation. The Center also has two student computer rooms - equipped with microcomputers and terminals which are linked to other computers, both on and off campus.
In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equipment
,o; are regularly used for teaching, in particular, classes are routinely given-access to appropriate state-of-the-art gamma spectroscopy equipment located in Center laboratories. A number of classes also regularly use the reactor and the reactor bay as an integral i part of their instructional coursework.
There are two classrooms in the Radiation Center which are capable of holding about 35 students each, in addition, there are two smaller conference rooms suitable for graduate classes and thesis ; examinations. As a service to the student body, the Radiation- ; 4 ' Center also provides a student study room / lounge as well as an L office area for the student chapter of the American Nuclear Society. , \o. p t l' l l v.
111-20 l
2. Utilization
!.. All of the. instructional laboratories and classrooms are used extensively during the academic year. For example, a listing of 53 courses accommodated at the-Radiation Center during this
o g reporting period along with their enrollments are given in Table
; III.E.1. Table Ill.A.1 gives a separate listing of the 20 classes specifically accomodated by the reactor during the reporting 5 period.
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!!!-21 i Table !!!.E.1 ' $tudent Enrollment in Nuclear Engineering and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center o
Number of $tudents
Fall Winter Spring Course Credit Course Title 1988 1988 1989 1 F
Nuclear Engineering Courses
'* *NE 101 2 Nuclear En ineerin Orientation 25 -- --
I
*NE 102 2 Nuclear En ineerin Orientation -- 16 --
NE 103 3 Intro. Nu lear En ineering & Comp. -- -- 13 , NE 201- 3 Nuclier Energy Fundamentals 17 -- -- NE 202 3 Nuclear Radiation & Matter -- 14 -- i
*NE 203 3 Nuclear Radiation Detection & Measurement -- -- 13 'e' . NE 405 2 Reading & Conference -- 2 -- *NE 405A 1- 3 R&C/ Field Practice Radiation Health -- 2 1 *NE 406 1-6 Projects -- -- 1 NE 406D 1-6 Individual Design Project 2 6 4 NE 407 1 Seminar 4 11 7 NE 415 4 Principles Radiation Safety 23 -- --
NE 417 4 Nuclear Reactor Power Generation -- 13 -- NE 419 4 Nuclear Reactor Theory -- -- 16 NE 421 3 Nuclear Reactor Analysis & Computation 13 -- -- NE 422 3 Nuclear Reactor Analysis & Computation -- 11 -- NE 423 3 Nuclear Reactor Analysis & Computation -- -- 12 l NE 430 3 Nuclear Fuel Cycle 13 16 -- NE 431 3 Reactor Therinal Hydraulics 16 -- -- i NE 432 3 Nuclear Reactor Design 14 -- -- ; NE 433 3 Nuclear Reactor Design -- 13 -- NE 434 3 Nuclear Reactor Desi n -- -- 13
**NE 441 3 Nuclear Engineering xperiments -- -- 13 **NE 461 3 Radiation Protection Engineering -- 17 --
NE 465 3 Nuclear Rules & Regulations -- -- 14 . NE 501 1-15 Research 1 1 1 5
**NE 503 1-15 Thesis 12 14 13 o NE 505 1-15 Reading & Conference -- 1 -- *NE 505A 1-3 > R&C/ Field Practice Radiation Health -- -- 1 NE 506 1-15 Projects 2 1 2 NE 507 1 Seminar 2 3 2 NE 513 3 Advanced Nuclear Reactor Theory -- -- 7 i NE 522 3 Nuclear Reactor Safety Problems -- -- 11 NE $32 3 Advanced Nuclear Reactor Design 1 -- -- .
NE $33 3 Advanced Nuclear Reactor Design -- 1 -- NE $34 3 Advanced Nuclear Reactor Design -- -- 2 NE $81N 3 $T/ Advanced Numerical Techniques 1 -- -- NE 583F 3 ST/ Fusion Techniques 6 -- -- 9 -- -- NE 583M 3 ST/MCNP Monte Carlo Calculations NE 583T 3 ST/ Application of Nuclear Techniques -.- 4 -- t Chemistry Courses
*+CH 106 5 General Chemistry 15 -- -- *CH 107~ 2 General Chemistry Lab $0 -- -- *CH 206H 5 Chemistry Honors -- -- 13 i *CH 207 2 General Chemistry Lab 4 -- --
ia **CH 419 4 Radioactive Tracer Methods 14 -- l *CH 461 2 Experimental Chemistry 2 -- --
*CH 503 1-15 Thesis (Chemistry) 3 3 3
l. CH 505 1-15 Reading & Conference (Chemistry) -- 2 --
" Other Courses CrS 503 1-15 Thesis Crop Science) 3 1 0 l **G 503 1-15 Thesis Geology) 3 3 3 l **0C 503 1-15 Thesis Oceanography) 1 1 1 **PH 503 1-15 Thesis Physics) 1 1 1 *FST 423 5 Food Analysis -- 20 -- ~ '051R used occasionally for demonstration and/or experiments , **0STR used heavily + Class held Summer Term 1988
~
F, L
; 111-22 l-h F. Instrument Repair and Calibration Facility
1. Description The Radiation Center has a facility for the repair and calibration
- of essentially all types of radiation monitoring instrumentation.
This includes instruments for the detection and measurement of alpha, beta, gamma and neutron radiation, and encompasses both high range instruments for measuring intense radiation fields and low range instruments used to measure environmental levels of radioactivity. The Center's instrument calibration capability is described more completely in Section VI.C.7 of this report.
2. Utilization The Center's instrument repair and calibration facility is used regularly throughout each year and is absolutely essential to the continued operation of the many different programs carried e
out at the Center. In addition, the absence of any comparable facility in the state of Oregon is leading to a greatly expanded
instrument calibration program for the Center, including calibration of essentially all radiation detection instruments used on the OSU campus, plus instruments from Oregon Health Sciences University, the Oregon Health Division's Radiation Control Section, the U.S.
Environmental Protection Agency, the U.S. Bureau of Mines, and others. Additional information regarding instrument repair and calibration efforts, and the growth of this activity is given in Tables VI.C.4 and VI.C.S. Iy 1 4 l l' P
hr 111-23 G. Libraries ,
;y~ 1. Description 1 !
The Radiation Center has libraries containing significant collections ;
. .: of texts, research reports, and videotapes relating to nuclear :
o science, nuclear engineering, and radiation protection. i The Radiation Center is also a regular recipient of a great variety of publications from commercial publishers in the nuclear field, from many of the professional nuclear societies, from the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission and other federal agencies. Therefore, Center libraries maintain } a current collection of leading research and regulatory documentation in the nuclear area. In addition, the Center has a collection . of over 50 sets of nuclear power reactor safety analysis and environ-mental reports specifically prepared by utilities for their facilities. ; The Center maintains an up-to-date set of reports from such organi- . rations as the International C.ommission on Radiological Protection, the National Council on Radiation Protection and Measurements. l and the International Commission on Radiological Units. Sets of the current U.S. Code of Federal Regulations for the U.S. Nuclear t Regulatory Commission, the U.S. Department of Transportation and other appropriate federal agencies, plus regulations of various state regulatory agencies are also available at the Center. The Radiation Center videotape library has over one hundred tapes on nuclear engineering, radiation protection and radiological
, emergency response. In addition, the Radiation Center uses video-tapes for most of the technical orientations which are required for personnel working with radiation and radioactive materials.
These tapes are produced, recorded and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communications Media Center.
W- , 1 0 , i ' !!! 4 AJ
'2 . Utilization
[g i Radiation Center;1ibraries are used mainly'to provide reference material on an-as-needed basis; however, they receive extensive
c ;- ~ use during the academic year. In addition. the orientation video--
d= tapes ~are used intensively during the beginning of each term, and: periodically thereafter.- g: h" 4
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i PART IV k REACTOR l l
A.. Operating Statistics . i
*: For the current reporting period,' the operating statistics for the ;
OSTR showed modest increases.in most of the major categories when' j compared to the previous period. Operating data by individual category o ' are given in Table IV.A.1 and annual energy production is plotted in Figure-IV.A.I. Table IV.A.2 is -included mainly for. reference and summarizes the operating statistics for the original 20% enriched-fuel. , The ' thermal energy generated in the reactor during this reporting _ period was 42.7 megawatt days- (HWD). The cumulative thermal energy
-generated by the FLIP core now totals 444.2 MWD from August ~1, 1976 through June 30, 1989. Reactor use time averaged approximately 90%
of the normal nine'-hour, five-day per week schedule. Tables.IV.A.3
.- through IV.A 6 detail the operating statistics apclicable to this !
reporting. period. Excess _ reactivity increased approximately 18c' during the current re- + porting period. This change was caused by three factors: 4
1. Consumption of the erbium burnable poison in the fuel (increased reactivity).
2.- Fuel element movements to even out core burnup (increased reactivity).
3. Fuel burnup (decreased reactivity).
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Table IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) for the 10-Year Period August 1976 - June 1986 1 JUL 77 1 JUL 78 1 JUL 79- 1 JUL 80 1 JUL 81 1 JUL 82 1 JUL 83 1 JUL 84 1 JUL 85" Operational Data 1 AUG 76 Through Through 'Through Through Through' Through Through Through Throtrgh for Through 30 JUN 78 30 JUN 79 30 JUN 80 30 JUN 81 30 JUN 82 30 JUN 83 30 JUN 84 30 JUN 85 30 JUN 86 FLIP Core 30 JUN 77(1) 458 875 1255- 1192 1095 1205 1208 .1470 Operating Hours 875 819 (critical) 496 255 571 1005 999 931 943 946 1042 Meg watt Hours 451 19 20.6 10.6 23.8 41.9 41.6 38.8 39.3 39.4 43.4-Megawatt Days 13.4 29.8 52.5 52.4 48.6 49.3 49.5 54.5 Grams 235U Used 24 25.9 552- 998 973 890 929 904 1024 Hours at Full (01 481. 218 Power (1 MW) 0 0 1 0 0 0 0 Number of Fuel 85 0 2 Elements Added or Removed (-) 372 348 438 396 _469 407 403 Number of Irradt- 44 375 329 ation Requests (1) The reactor was shutdown on July 26, 1976 for one month in order to completely refuel the reactor with a new FLIP fuel o-t.
~
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7 i Table'IV.A.I.(continued) OSTR Operating Statistics (Using the FLIP Fuel Core) for the Period July 1986 - June 1989 Operational Data 1 JUL 86. 1 JUL 87 1 JUL 88 1 JUL 89 .1 JUL 90 1 JUL 91 1 WL 92 - 1 JUL 93 1 JUL 94 1 JUL 95 for Through Through Through Through Through Through 'Through Through Through Through FLIP Core 30 JUN 87 .30 JUN 88 30 JUN 89 30 JUN 90 30 JUN 91 30 JUN 92 30 JUN 93 30 JUN 94 30 JUN 95 30 JUN 96 Operating Hours 1172 1352 1170 (critical) Megawatt Hours 993 1001 1025 Megawatt Days 41.4 41.7 42.7 Grams 235U tsed 51.9 52.3 53.6 Hours at Ful1 980 987- 1021 Power (1 MW) Number of Fuel 0(I) -2(2) 0-Elements Added or Removed (-) Number of Irradi- 387 373 290 ation Requests l l (1) No fuel elements were added, but one fueled follower control rod was replaced. l (2) Two fuel elements were removed due to cladding deformation. e t,a3 I I
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. .,; .1.z ' 6.- o g .. s Table IV.A.2 OSTR Operating Statistics with the Original (20% Enriched) Standard TRIGA Fuel Core 1 JUL 68 1 JUL 69 1 APR 70 1 APR 71 1 APR 72- 1 APR 73 1 APR 74 1 APR 75 1 APR 76 Operational Data 8 MAR 67 Through Through Through Through TOTAL: . MR 67 :
for 20% Enriched Through Through Through Through Through Through 30 JUN 69 31 MAR 70 31 MAR 71 31 MAR 72 31 MAR 73 31 MAR 74 31 mR 75 31 MR 76 26 JUL 76 Through JUL 76 Core 30 JUN 68 (1) (2) (3) (4) Operating Hours 6903 567 855 598 954.. 705 %3 794 353 (critical) 904 610 1 138.05 223.77' 195.11 497.82 335.94 321.45 408 213 2553 Megawatt Hours 117.24 102.47 4.88 4.27 5.75 9.3 8.1 20.74 13.99 13.39 17 9 .106.4 Megawatt Days 5.36 7.21 11.7 10.2 26.031 17.57 16.81 21.35 '10.7 133 Grams 235U Used 6.13 ,; l Hours at Full -- -- -- -- 856 Power (250 kW) 429 369 58 -- -- --
}
Hours at Full 200 291 460 205 1700
-- 20 23 100 401 Power (1 MW) --
Number of Fuel 2 2 .0 94 70 2 13 1 1 1 2 Elements Added to Core (Initial) Number of Irradi- . 550 452 396 357 217 4100 ation Requests 429 . 433 391 528 347 102 98 I
! 249 109 183 43 39 1560 'I Number of Pulses 202 236 299 l I (1) Reactor went critical on March 8, 1967 (70 element core; 250 kW). (3) Reactor shut down June 1,1971 for one month for cooling system -
Note: This period length is 1.33 years as initial criticality upgrading. occurred in March of 1967. (2) Reactor shut down August 22, 1969 for one month for upgrading to (4) Reactor shut down July 26. 1976 for one month for refueling 1 MW (did not upgrade cooling system). Note: This period length reactor with a new full FLIP fuel core. Note: This period is only 0.75 years as there was a change in the reporting period length is 0.33 years. from July-June to April-March. E i _ _ _ _ _ _ _ _ - _ _ _ - . =-- _+ .
L IV-5 L' N .
c: Table IV. A'.3 e
Present OSTR Operating Statistics Lo. ! o. Annual Values Cumulative Values Operational Data for for for 1 JUL 88 1 AUG 76
FLIP Core Through Through '
30 JUN 89 30 JUN 89. t MWH of energy produced 1,025 10,658 1.
-2. NWD of energy produced 42.7 444.2 -
3. Grams 2350 used 53.6 557.7

4. Number of fuel elements ,'
added to or removed from 0 85 + 3 FFCR(1) . (-) the core Number of pulses 18 1,148 5. Hours reactor critical 1,170 14,146
~
e 6. Hours at full power ('1 MW) 1,021 10,358 7.
8. -Number of startup and 252 3,265 shutdown checks

9. . Number of irradiatjog 5,000 requests processedt2/ 290

10. Number of samples irradiated
~
3,177 59,115 (1) Fuel. Follower Control Rod. L. (2) Each irradiation request could authorize from 1 to 120 samples. 1 The number of samples per irradiation request averaged 11.0 during
.the current reporting period. ; g:
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Table IV. A.4 co . . i 0STR Use Time in Terms'of Operational Functions a l~' Annual Values Cumulative Values for for 1 JUL 88 1 AUG 76 Through .Through-30 JUN 89 30 JUN 89 4 '0STR.0perational Function (hours) (hours) Checkout, core excess 377 4,802 an'd shutdown-2,353 20,050-Reactor in use(l) 2,730 -24,852- ; Total reactor use time (1) 1This function. includes preclude time, multiple reactor experiment time, and the time the reactor is in use for teaching but not neces- 3 sarily ' operating. (Preclude time is the time the reactor is not available for regular use due to performance of surveillance and- . maintenance items, such as fuel element inspections, transient rod-lubrication, control rod calibration, power calibration, as well - as sample loading and unloading time.)'
)
l d
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j 1
e 1 IV : Table-IV.A.5 q y '0STR.Use Time in Terms of Specific Use Categories. 'l 9' Annual Values Cumulative Values o for- for' ; OSTR Use. Category 1 JUL 88 1 AUG 76 Through Through. 30 JUN 89 30 JUN 89 W (hours) (hours) .
-Teaching,(dpgqrtmental 260 2,994 and others)\ /
386 5,782 OSUresearch(2)- Off-campus research(2) 791 2,909 i Forensic services 11 154(3) Reactor preclude time 938 8,346. l%. Facility-- time (4) 328- 4,472 l.
# Visitordemonstration(5) 16 195(6) 2,730 24,852-Total reactor use time (1) See Tables III. A.2 and III.E.1 for teaching statistics. ;
(2) See' Table III.A.3 for research statistics. 0 (3) Prior to the 1981-1982 reporting period, forensic services were grouped ; under another use category. Since then, this service has been a r separate category and the cumulative hours have been compiled begin-ning with the 1981-1982 report.
* ' (4) The- time OSTR spent operating to meet NRC facility license requirements.
(5) This is the time that the reactor was used specifically for visitor y 'open-house (demonstration)~ events. The remainder of the visitors '
.o. ' viewed.the reactor during times when the reactor was being operated for regularly scheduled research and teaching.
(6) An error in the preparation of the 1984-1985 report resulted in the
- "' reporting of 101 hours of OSTR operations for visitor demonstration while the actual value.was 159 hours. The difference of 58 hours is added to this year's report to correct the total cumulative reactor use time value.
t
IV-8 .: Table IV.A.6 OSTR Multiple Use Time (l) 0-Annual Values- Cumulative Values for for:
' -Number of Users 1 JUL 88 1 AUG 76 Through Through 30 JUN 89 30 JUN 89 (hours) (hours) 155 1,155
'Two Three 78 278 25 102 Four 6 10 . . Five 15 23 Six 4 4 -,- Seven.
Total multiple 1,572(3) 283(2) (1) Multiple use time is that tine when two or more irradiation requests are being concur _rently fulfilled by operation of the reactor. (2) This represents 24% of the total hours the reactor was critical-during this reporting period. (3) This represents 11% of the total hours the' reactor was critical since startup with FLIP fuel in August of 1976. o
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-s > .' % Reporting Period _
O I 1976-77: 19.D MWD
~
t 1977-78: 20.6 MWD O ' 1978-79: 10.6 ftfD - O - 1979-8D: 23.8 MWD - 2 20 - 1980-81: 41.9 MWD -
. 1981-82: 41.6 MWD .
1982-83: 38.8 MWD I '1983-84: 39.3 MWD
~ ~
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1984-85: 39.4 MWD
'1985-86: 43.4 MWD -
L 1986-87: 41.4 1000 .- I. 1987-88: - 41.7 MWD -
- 1988-89: ~42.7 MWD .
O l l l l l l l 'l l '. l l l l~ "l. l 76-77 78 80-81 82-83 84-85 86-87 . 88-89 90-91
'77-78 79-80 81-82 83-84 85-86 '87-88 89-90 Time (Annual Reporting Period) 2-Figure IV.A~.1 OSTR Annual Energy Production Vs. Time (Annual Reporting Period) & - - - . . - - _ = - . . - _ - - - = -. .
-l IV-10 t B. Experiments Performed ' During the current. reporting period there were 11 approved reactor . .
experiments available for use in reactor related programs. The follow-Jo .ing' list of reactor experiments identifies the 11 approved experiments.
Missing numbe'rs signify reactor experiments. which are in the inactive file and are not currently being used.
g. A-1 Normal TRIGA Operation (No Sample Irradiation). . B-3 Irradiation of Materials in the Standard OSTR Irradiation ; Facilities.- B Irradiation of Materials involving Specific Quantities of ,i Uranium and Thorium in the Standard OSTR Irradiation Facilities. B-12 Exploratory Experiments. B Beam Port No. 3 Neutron Radiography Facility; Aniendment No. 1 ) to B-21; Neutron Holography. l B-23 Studies Using TRIGA Thermal Column. l l.. B-24 General Neutron Radiography. B-25 Neutron Flux Monitors. l L B-29 Reactivity Worth of Fuel. B-30 NAA of Jet, Diesel, and Furnace Fuels. B-31 TRIGA Flux Mapping. Of the approved experiments on the active list, five were used during . the reporting period. A tabulation of information relating to reactor experiment use is given in Table IV.B.1, and includes a listing of
~*
the' experiments which were used, how often each was used, and the general purpose of the use. Presently, 25 experiments are in the
*n inactive ~ file and could-be reapproved for use if needed.
O
h ( th , IV-11 Table IV.B.1 Use of OSTR Reactor Experiments (l) j n-
.q .
Reactor Experi gt Facil(ip 4 Number 'l Research Teaching Forensic Tine JJ TOTAL ~ [ A 0 33 0 81 114- , B 132 17 2 0 151 B-11 20 0 0 0 20 B-23 0 2 0 0 2 B-31 2 0 0 0 2 4 1 TOTAL 154 52 2 81 289 _ { (1) This table displays the number of times reactor experiments were .
~ -. used for;a'particular purpose.
(2)' The following tabulation gives the number of each reactor experiment used and its corresponding title: A-1 Normal TRIGA Operation B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities B-11' Irradiation of Materials Involving Specific Quantities of Uranium and Thorium in the Standard OSTR Irradiation Facilities B-23 Studies Using TRIGA Thermal Column B-31 TRIGA Flux Mapping
'(3) The time OSTR spent operating to meet NRC facility license requirements. '.1 ;
I g.'
;9- '.g.
~
lt n:. . 4 f
~IV-12 :l 3:=
g n
' } l A 'i !
r ,
'C. -Unplanned Shutdowns. # Le There'were ten unplanned reactor shutdowns (scrams) during'the current !
reporting period. Table IV.C.1 contains a summary' of the unplanned i
o:: shutdowns including'a brief description ~of the cause'of each.. ]
,s e
q. 'l l
r
)
1
,\
l
'l l
r e,
'h 1 -D .l )
i n l.. t l t
.6: ..,p.-
0.
s
. )
t' IV i Table IV.C.1 Unp'anned Reactor Shutdowns (Scrams) lC Number of Type of Scram Occurrences Cause of Shutdown ; Safety Channel 6 Spurious scram signals. No cause or reason could be determined at the time. (These
-did not involve actual overpower situations.)
Even though the safety channel ion chamber ~ . checked out good, it was decided to change the ion chamber. This action appears to have solved the problem.
% Fower Channel 1 Spurious scram signal. Apparent noise in the-mode switch caused this scram. Reactor was at 100 watts preparing for pulsing operation.
When the mode switch was turned, the scram occurred. Mariual 1 The linear channel (blue pen) on the console recorder was behaving abnormally. It was ; observed that the drive line from the bull wheel to the pen was frayed. The reactor was scrammed and the pen drive repaired. Manual 1 The reactor top Continuous Air Monitor (CAM) ' ceased operation (low flow alarm) and the i reactor was-scrammed manually. It.was deter-mined that the CAM blew a fuse. The fuse was replaced and reactor operation was resumed. Manual 1 This scram was unintentional. The reactor operator reached for a writing pen and acci-dentally hit the manual scram button. Reactor operation was resumed. a
~ - _ - _ . - _ - _ _ _ _ _ _ _ _ _ . _ _
IV-14 ,
]
D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor l
+ Experiments Performed Pursuant to 10 CFR 50.59 ,
1 The information contained in this section of the report provides a
.- -summary of the changes performed during the reporting period under 'o - the provisions of 10 CFR 50.59. For each item listed, we have included j a brief description of the action taken and a summary of the applicable ,
safety evaluation. Although it may not be specifically stated in each of_ the following safety evaluations, all actions taken under 10 CFR 50.59 were implemented only after it was established by the - OSTR Reactor Operations Committee (ROC) that the proposed activity ll did not require a change in the facility's Technical- Specifications 1 and did not introduce or create an unreviewed safety question as defined in 10 CFR 50.59(a)(2). ,
1. 10 CFR'50.59 Changes to the Reactor Facility The)e were eight changes to the reactor facility which were reviewed, approved, and performed under the provisions of 10 CFR 50.59 during the reporting period.
I
a. INSTALLATION OF A CADMIUM-LINED, IN-CORE, IRRADIATION TUBE (1) Description The reactor operations staff built and installed a cadmium-lined irradiation tube which can be permanently positioned in the reactor core. As shown in Figure IV.D.1, the faci'lity consists of an air-filled aluminum tube with
~
an offset bend, which is inserted into a convenient B-ring' s core grid position. The cadmium is approximately 0.025 ,
-inches thick and is permanently encased in aluminum inside and out. The tube is positively secured near the top I ,.j .to a steel beam (the center channel) which extends across '
the reactor tank, and is equipped with a cap on top to seal it during reactor operations. To eliminate any small pressure increases due to radiolytic gas production, p a suction is drawn on the irradiation tube by connecting j a line from the rotating rack vent system to a tee-section on the irradiation tube. , l
7 y. , LCAP :IV-15
-ISOLATION' ( 0-RINGS
(,.7 VALVE ~ . w
'l JTO. LAZY SUSAN' _;
VENT LINE. ( 2 C '; w i 3 :. o: , n" INNER AND OUTER TUBES
' y WELDED TOGETHER i
CADMlUM (0.020") o OUTER TUBE
. i ,
,W CADMIUM DISK (0.020")
i END PLUB AND LOCATING PIN .i Figure IV.D.1 Cadmium-Lined, in-Core Irradiation Tube
V; - .
~ IV-16 i m s
{
'NOTEi '0 STROP 10'was revised to' detail the procedures %" - for using the new irradiation facility, and experiment l .B-3 was modified to allow irradiations in the cadmium - ; ;3 , - lined tube to be performed under~ this experiment. .These W changes, which were also made under 10 CFR 50.59, are: j ;, discussed later in section D. !
( P (2) Safety Evaluation ;
t.
The safety considerations for this facility were very , similar to those previously evaluated for the cadmium-lined - pneumatic' transfer tube which was installed under ROC
. approval and then recently removed from the reactor core. ;
The reactivity changes were expected to be about the
< 'same, or slightly more negative because a similar amount j of' cadmium was used but this' facility.was placed in a' .; *- core location with a slightly higher flux. The cadmium- ,
lined tube was therefore estimated to be worth about- l t y -$2.20 and was expected to reduce the core excess from l
about $6.50 to about $4.30. As indicated earlier, the J
_,e tube was secured (bolted) to the' reactor facility:in such a manner that it could not be easily or unintentionally removed. This will prevent any sudden, unp.lanned addition of reactivity to the reactor. a l The tube was constructed in such a manner th'at'the cadmium [ was completely sealed within an inner and outer aluminum .l tube. Therefore, there will be no potential for cadmium W. contamination of the samples or the reactor. . The offset bend in the tube is similar to that of the b other in-core facilities and effectively eliminates radia-tion streaming from the tube.
't I 'h
p - ps 5 A IV-17
c. ,
I - - S -Theproceduresfforthefacilitystipulatethat,thetube's'- ,
, cap-is to be on.the top of the tube except when samples are being, inserted or reinoved and whenever the reactor is in operation. ~ Additionally, under normal circumstances,. ;
[ samples-will be removed from the tube only after the- , reactor has been shut down for a time period adequate
s. to ensure that the bulk of the argon-41 activity has 1 W
+. + ' . decayed (usually overnight). This will prevent any unnecessary t release of-argon-41 to the reactor bay. The tube could be unloaded after a shorter decay period with specific health physics approval and appropriate precautions, / but this option is no different than that currently employed with the rotating rack and therefore introduces no new ,
safety considerations. > The procedures and limitations for encapsulation and irradiation of samples using the in-core cadmium-lined RY
facility follow current requirements, particularly those in OSTROP 18. Therefore, no new or untried practices ,
l- were introduced relative to the actual use of the new ; facility. in order.to position the cadmium-lined end of the tube
into.the core's-B-ring, a fuel element must first be moved 'from grid location B1 to G6. The cadmium-lined y ,
tube'can then be inserted into the vacant B-ring position. The estimated' reactivity effect at each stage of the move was calculated and is given below: " La u
1. Removal of the element from B1 = -35&

11. Insertion of this element into G6 = +30c i.
iii. Insertion of the cedmium-lined tube into B1 = -$2.20 , iv. Overall reactivity change = -$2.25 l, n. I
h*p - R r
.IV-18 5
g , Core excess measurements:were made at each step of the , b tube insertion ~ procedure outlined above. The control l rods were recalibrated after the tube was-inserted and , y the core excess was remeasured.
c-

b. CHANGES TO THE CADMIUM-LINED, IN-CORE, IRRADIATION TUBE y (1). Description 3 o Following Reactor Operations Committee-approval of the j facility change regarding the cadmium-lined, in-core irradiation tube, the staff recommended two changes related >
to the irradiation tube. The first change-involved the.
method to be used for insertion and removal of the sample .
support seat and the outer container holding the encapsulated r sample (s) to be irradiated. This change was suggested . because after the'in-core irradiation facility was constructed. i'. it was discovered that the standard TRIGA tube. handling U device used to insert and remove TRIGA tubes for the r otating rack would also easily go down the new irradiation tube.provided the handling device's outside borated shield was removed. Therefore, instead.of-a previously proposed, less desirable method for sample handling it was now
~
L proposed that samples be placed in the cadmium-lined facility in aluminum TRIGA tubes modified to-have internal l L threads so that the containers could be inserted and l-removed using the standard TRIGA tube handling device (fishing pole and grapple) and standard procedures developed ~ for the rotating rack. Similarly, the-top of the sample r* support seat was modified by adding an aluminum TRIGA l tube cap so that this too could be easily inserted and
removed using the TRIGA tube handling device. ,
y The second change involved moving the location of the
. facility's air suction tube to the irradiator tube cap, rather than having a "T" in the tube itself. It was determined that this change would allow much more flexi-bility in the angular positioning of the air tube.
V w . 'IV-19 (2) ' Safety Evaluation ,
^
It was judged that the first change improved the operational safety of the facility. The basis for this was related ; Lo - to the fact that the previously planned use of wire and V 4 cord to position and support samples was deleted, and with this deletion went any potential for activation y of wire, risk of wire breakage, and risks associated > with handling wire or cord when removing samples from' , the tube.. Conversely,.-the new method for sample insertion and removal employs currently approved procedures which have been in practice at the OSTR for many years. The new design of the sample support-seat also enables the staff to easily remove the seat when not in use, thus-preventing unnecessary activation. r
# There are no unfavorable safety implications involved with the second change. A slight air suction will still e, .. be pulled on the tube when it is in the core. -Repositioning the air suction tube to the cap simply allows this tube <
to be oriented in different directions and- thus eliminates the inconvenience of having the tube.in the way of other work which could be going on in the immediate area.
c. REMOVAL 0F' AN EXPERIMENTAL WATER RADI0 ACTIVITY MONITOR (1) Description .
As part of a graduate research project conducted approxi-mately 8 years ago, an independent water monitoring loop was installed in the demineralizer circuit of the primary :
.w ater system. The water monitor did not perform satisfac-torily, and once the project was finished, the monitor was never used again. The reactor staff removed the l
water monitoring loop from the demineralizer circuit. Specifically, all of the piping and equipment between l'
g p , f L" IV n A valve DV 17-and'the tee-section where valve DV 22 was ,
6 - attached to the main water line for the demineralizer circuit was removed (see Figure IV.D.2). The' tee was plugged and valve DV.17 remained in the system as a sample
( collection valve. This change resulted in a revision ! of'0 STROP 7 to remove. all mention of this water monitoring l oop ~. [e;
; (2) Safety Evaluation ' There were no unfavorable safety implications associated with this facility' change as this loop was never used ,
to support reactor operations and the original-water monitoring system for the reactor always remained fully functional. Appropriate health physics precautions were taken during the removal of the equipment. No'significant contamination was found during removal due to the long elapsed time since the loop was used and because of the
. low radioactivity concentration in the reactor primary 4 water.
d. ADDITION OF.A PARTICULATE FILTER DOWNSTREAM OF THE DEMINERALIZER TANK (1) Description The reactor staff installed a particulate filter downstream ,
of the demineralizer tank in the reactor primary cooling ' water cleanup system. The new filter prevents resin fines .from being introduced into the primary water system.. - I The filter assembly is moun ad next to the east wall
*y of the heat exchanger room Jjacent to the demineralizer pump skid. The pipe and vt ving system (see Figure IV.D.3) is primarily 1" plastic pipe with three valves (two shutoff ~~
valves and a bypass valve), two pressure gauges (to measure the pressure drop across the filter) and a drainable housing for the 25 micron filter. The filter housing can be shielded by concrete blocks, if needed. 1 e
-.. .~ 'I 30 AMI (N A' REACTOR : BAY EAT EXCHANGER ROOM p ._sEco __. _Rv__ _ q -wnT l. Coouns l , sYsTEw . .:
PRD44RY WATER ~ PUMP ~ 490 GPM Pv3 -
)b' ' " EAT ERCHANGER . C,'
[ . 1P onAss py,
~ ow - TE C y {PYs- g t>wAv vgi e -c< :
eg
, ~sso ritt -' ove ggy, opu (3-wAY DEMRALIZER Dv5 VALW) GEER Time PUMP -to n N - - TEMPERATURE PRGIE .N DV4 ] CDetC1MiY CELL g
i OYME OV'e o m2
s. o ~so Psc Xav2 Y
. p xo 2, ..
PRES = ovi7X_ l PITTER I s- /. ATOR HOLES VENg 9q 151 ove <is Pss DFFUSER ' DV20 , Looe g
,588ACCESE REACTOR TANK NEMCUCT) ,
sUtK sw te T At* ovii
. Xave wwwn - +w .
- w DVt5 DW13 K, +
[* : m-DVf2 F1 m new are .. e As, si Fig. IV.D.2 Removal of an Experimental Water Radioactivity. Monitor .E~ from the Primary Water. Purification System . _;
- _. . .. - - . - - - - - - - - - - - - - - - -- - ~ = - - - - ------- - - -- - ~- -.
.- . ^ _ .. ' , __
_e .. i-
.s~ 6. e 4- - _
,- .. :3. *i.~--. . . . =a' - <-
SEWIEED FWt - 4 29 n988 et '. _7'
- REACTOR ' BAY. E AT. EXCHANGER ROOM ,
1 g _SEcoptwtY __ __ _ _7 i .T - l Cootmo -l 1- SYSTEM .. Tw ' PRN4BY WATER PUMP , ggg gpy pyy _gl f, V6 -----}' NC
EAT ENChA -
PV2 x .[. i' <>
@^" . PV7 - PWS W C l}wAY VAlvEl
, g - - =
' ~440 DY1 lpy, spy RL, ,
l {} WAY VALVEl DEM9ERAlf2ER Ov5 GEICER 7t2E PUMP ~ M . 1:4 ~ TEpfERATURE PRGE -
- x ___ ove coeutwwfY CEn ggy g,, ,_ _. __ y SusMetR v OV22 ~50 PS8G l
UT OV17. [ .. l FITTER 'l
" =ssac be, /,
HOLES VENQ x,21 OR l ' mf 15] Dwig <15P9G OlFFUSER DV20 , g DV6 l
$$N ACCES,S., : ;
l BULK 95ELO REACTOR Tate ( T f - X0V10 Dv9 X TANK
-= % Xoa Ymrg ^
F'" + caoutwv - M aEnatizEn +m ovis ovo DETER CER DW1T \ DV7
**':.1; }l wo .1 7kw D- ]e ~'d p/ ADDavio9) m,w see,r awar-. . ~
m Ar si Fig. IV.D.3 Addition of a Particulate Filter Downstream of the Demineralizer.- ? ., in the Primary Water Purification System M 'J
.-. ,. - , . -- .~ ~ , -, - _-.- - =. - --- -- - - - - - - -
e D' IV-23: iii s , (2) Safety Evaluation There are no unfavorable safety implications related
~
to the addition of this new filter. All of the materials
# used are of good quality, and the system passed all pre- # operational-tests. The new filter is essentially no~ _!
different than the existing particulate filter for the-g primary water which has been in successful operation since~the OSTR was built. Procedures used to change-the new filter cartridge are the same as those used for the current filter. The new filter contributes to increased safety by removing'any resin fines which might pass from the-deminera'lizer tank into the primary water system. ' t
e. REPLACEMENT OF THE WATER CONDUCTIVITY MONITORING SYSTEM ,
; (1) Description The reactor staff upgraded the reactor water conductivity monitoring system to a digital readout instrument with l
automatic temperature. compensation. : While the original conductivity monitoring system was still quite reliable, it had one disadvantage related
-to'the. fact that the " cat eye" indicating tube in the conductivity system had-to be changed periodically.-
These old-style " cat eye" electronic tubes were becoming increasingly expensive and could possibly become unavail- " able in a few years. In order to install the new system the following changes were made: [, 1. Two new signal cables were pulled from the heat exchanger room to the reactor console. The original-cable did not have enough wire pairs to accommodate the temperature compensating feature of the ner instrument. ; K >
o , 4 IV-24
11. New temperature compensating conductivity probes jo- were installed..
iii. Adapters were installed so that the new probes y would fit into the water system piping,
,e. iv. Modifications to the console side cabinet were made to physically accommodate the installation of the new digital. readout instrument, se ~
(2) Sa'fety Evaulation There is a great deal of historical data documenting the normal range of conductivity for the OSTR primary.
. water. - Any significant discrepancy observed between established values and results obtained with the new system could and would be immediately investigated using other conductivity instruments, p.
Failure of the new system also does not create any immediate
.- safety implications, since the conductivity of the reactor primary water changes very slowly with time, and thus allows plenty of time for detection of abnormalities and repair of conductivity equipment, in addition, the OSTR primary water is kept at an extremely low level of conductivity, which gives an even greater margin of protection.
Because this is new equipment, it is expected that the - potential for failure will actually decrease and that !!
. thils installation will provide more accurate conductivity f readings. Hence, the new device will actually increase. -]'
reliability and safety. Li.
r. .;
i !.e I i i
a: , q IV o
-f. : MONITORING OF REACTOR POWER AND FUEL TEMPERATURE WITH A CDAS jo DURING NON-PULSING OPERATIONS (1) Description t#[ On an as-needed basis, a computer-based data acquisition o system (CDAS) can-be connected to test terminals on the OSTR- console to rassively measure reactor power and fuel. -
temperature signals during non-pulsing operations. Termi- 5 k nals TP2 and TP3 would be used to measure fuel _ temperature = from the fuel thermocouple- amplifier board (card XA16) in the left-hand console drawer. These terminals were extended.to the rear of the console for easier and safer access. The LINEAR and LOG terminals already on the rear of the console would be used to measure the linear ; and log reactor power, respectively. . No active circuitry will exist between.the test terminals and the CDAS. l4 s
-(2)- Safety Evaluation
The referenced terminals are designed to be used as-indi-cated above; however, additional measures will be taken to ensure the safe use of the CDAS while measuring reactor- 1 power and fuel temperature during non-pulsing operations.
First, a 100-ohm resistor was permanently installed between console terminals TP3 and TP4 for the Nyt circuit, thus- .; ensuring proper connection of the CDAS or other external recording devices to these terminals. Second, the CDAS system will be operationally tested to assure its proper functioning before it is connected to the reactor console. ;
This will eliminate the possibility that the CDAS will be connected to the console with an improperly functioning l
,# or failed comporent. In addition, cables used to connect N: the CDAS to console terminals were labeled and color-coded to minimize the possibility of an incorrect connection.
. It is important to note, however, that an incorrect con-nection would create no safety problems and would not 1
lV-26 affect console electronics. The impact.would be an incor- '
rect result on the external. recording device. Furthermore, extending terminals TP2 and TP3 from the thermocouple 1
,. amplifier board-(card XA16)'to the rear of the reactor ,
a console will increase safety by making these terminals : more accessible, by eliminating.the need to directly access electronics in the left-hand drawer of the. console. and by making it easier to confirm that the connections .
. are correct.
t An evaluation of the worst-case failure of the CDAS while connected to the reactor console to record reactor power. and fuel temperature indicated that the consequences are no worse than those created by the failure of an existing console component in the same-circuit, and such ;
c. consequences would be immediately d,vious to the reactor -
operator so that appropriate action could be taken. i l s. A-new OSTROP 26'was written and approved. It details operating procedures for the CDAS when it is being used to measure reactor power level and fuel . temperature. 1
g. MONITORING 0F REACTOR PEAK POWER AND FUEL TEMPERATURE-'WITH
~A CDAS DURING PULSING OPERATIONS (1) Description The OSTR staff installed an operational amplifer inside the reactor console cabinet. The amplifier provides u.. a gain of=about 100 to amplify the peak power (Nvt) signal I
l taken from console terminals TP3 and TP4. Signal amplifi-
~ cation at these terminals is from about 60 mV to about 6 V. Although the amplifier circuit has been permanently installed inside the reactor console cabinet, it will * ' be connected to Nyt circuit terminals TP3 and TP4 only as needed during pulsing. Also, as needed during pulsing operations, a computer-based data acquisition system
m . IV-27 E' H (CDAS) will be connected to the output from the operational y amplifier to measure the peak reactor _ power during a o b
, pulse.
To measure fuel temperature during pulsing, the CDAS will also be connected-to fuel temperature output terminals jJ TP2 and TP3 on the back of the OSTR console in order
*: to pussively measure fuel _ temperature signals from the- . thermocouple' amplifier board (card XA16) in the left-hand = console drawer. -No active circuitry will exist between the fuel . temperature terminals and the CDAS.
(2): Safety Evaluation The referenced terminals are designed.to be used as indi-cated above; however, additional measures have been taken L' to ensure the safe use of the CDAS and amplifier during ' l pulsing operations. First, a 100-ohm resistor has been permanently installed between console Nyt terminals TP3- , and TP4, thus ensuring proper connection of the CDAS, the amplifier, or other external recording devices to these terminals. Permanently installing a 100-ohm resistor across terminals TP3 and TP4 increases the system's relia-bility by eliminating the need for a jumper cable across TP3 and TP4. Second, the amplifier and the CDAS system will be operationally tested to assure proper functioning before they are connected to the reactor console. This > will eliminate the possibility that these devices will
,: be connected to the console with an improperly functioning I or failed component, which will thereby eliminate the chance that a signal from the amplifier or CDAS will !
affect console electronics. In addition, cables used i to connect the amplifier to the console and the CDAS to the amplifier were labeled and color-coded to minimize the possibility of an incorrect connection, it is impor-tant to note, however, that an incorrect connection would 1 a-r--
~
{ gp
- ~ <D .I' W
IV-28: y r 0 c;; create no safety problems and would not affect console y -electronics. :The impact would be an incorrect result , on the external recording device. Furthermore', only- !
' cables from inputLchannels of the covered distribution board for the.CDAS will be present,=and;thus no output:
[ signal cables will be available for connection between- ' t'
.. the CDAS and the reactor console. .As an added feature..- *, protective diodes were added to the amplifier circuit. ,
to isolate the CDAS and the amplifier from the reactor ; console. This action will prevent the CDAS or amplifier from introducing a measurable charge to the Nyt circuit capacitor. An evaluation of the worst-case failure of the CDAS and 1 amplifier while connected to the reactor console to record i
'a
( ; peak pulse power and fuel temperature indicates that ; l; the. consequences are no worse than those created by the L failure of an existing console component in the same- , f circuit, and such consequences would be immediately obvious
.to the reactor operator so'that appropriate action could- ~
o be'taken. 4 In addition to the above safety considerations, fuel temperature monitoring during pulsing'is described and fully evaluated by the 10 CFR 50.59 evaluation' entitled
" Monitoring of Reactor Power and Fuel Temperature with a CDAS During Non-Pulsing Operations," (see section IV.D.1.f). i n
[ Operating procedures for the CDAS and amplifier when used during pulsing are included in the new OSTROP 26
* " Procedures for the Use of External Monitoring and Record- # ing Devices."
i
p,
Iy.29 1
h. INSTALLATION OF AN ~XTERIOR LIGHT ON THE EAST WALL OF THE REACTOR BUILDING L (1) Description l9 In order to provide additional lighting for the northern half of the Radiation Center's parking lot, and to simulta-i- neously enhance exterior lighting on the east side of
(- the reactor building, an exterior light was installed g at the north end of the east wall of the reactor building. Electrical power was supplied by extending a conduit from an interior east wall electrical outlet located ~ adjacent to the east fire exit door. (2) Safety Evaluation The conduit penetration in the east reactor bay wall,
g as described above, was filled with-an electrical conduit which.was oppropriately caulked inside and out to prevent air leakage. Therefore, this facility change does not affect the ability of the reactor building to maintain the originally designed contairment integrity, and does not alter the probability of minimal radiological releases as described in the facility SAR, Consequently, the changa introduces no increase in the probability.or conse-l- quenrei of occurrences evaluated in the facility SAR.
l_ Furthermore, no new types of occurrences are introduced [' 1 and no margin of safety is reduced by the proposed change.
2. 10 CFR 50.59 Changes to Reactor Procedures w
There were four changes to reactor procedures which were reviewed, approved, and performed under the provisions of 10 0FR 50.59 during
,- the reporting period.
IV-30
a. REVISION OF OSTROP 6 L (1) Description OSTROP 6.0 was modified to incorporate revisions necessi-
[_ tated by recent organizational and procedural changes. In particular, job descriptions were modified for the Radiation Center Director, the Reactor Administrator,
-, and most of the health physics group. The revised ROC i
charter was also incorporated into the procedure. In , addition, the access control procedure for the reactor [ bay was changed to incorporate the daytime use of signs , when the security alarms are set during the day. (2) Safety Evaluation : There are no unfavorable safety implications associated ,
, with the job description changes. All of the necessary ;
responsibilities are well-covered, and the organizational ! changes have already been approved by the NRC and incor-porated into the OSTR Technical Specifications. The , changes to the ROC charter were also previously approved ! by the R00, and these changes were merely being incorpo-rated into OSTROP 6.0. The slight change to the reactor bay access procedure will not affect the security plan i for the reactor. The change only affects those people ; with reactor bay keys and these people are the most respon-sible members of the Radiation Center security staff. Even if the procedure is not followed, security is not compromised, only an alarm is sounded unnecessarily. L l
b. REVISION OF THE EMERGENCY RESPONSE PLAN 3 (1) Description .
A number of changes to the OSTR emergency response plan o were made as a result of the annual review of the plan by the standing subcommittee of the ROC. This review was conducted on October 26, 1988. Most of the changes I d
IV-31 were required as a result of the revised Radiation Center
. organization recently approved by the NRC. Remaining changes were merely updates of such things as telephone numbers, first aid qualifications, etc.
(2) Safety Evaluation None of the changes involve revisions of the actual emergency response described in the plan. Instead, the changes simply update the plan to incorporate the current titles and organizational structure of the Radiation Center, and involve appropriate modifications to designated lines of succession in the emergency plan. As a result, none of the changes have any impact on safety. Changes to the plan were also reported to the USitRC under the provi-sions of 10 CFR 50.54(q).
c. REVISION OF OSTROP 10 (1) Description The reactor staff amended section 10.7 of OSTROP 10 to specify the procederes for moving the cadmium-lined in-core irradiation tube from its storage location in the S-rack to the in-core position, and for returning the tube to the storage location.
In addition to amending section 10.7, the staff changed the title of OSTROP 10 to " Operating Procedures for OSTR Irradiation Facilities." (2) Safety Evaluation The reactivity effects of inserting and removing the cadmiunrlined in-core irradiation tube have already been addressed in a previous 10 CFR 50.59 safety evaluation. The required use of a specific set of control rod calibra-tions depending on whether the tube is in or out of the i
r, I IV-32 h i , i ; core will ensure that accurate measurements of core excess j 0 ;. and shutdown margin are made. A 24 limit for comparing control rod worths is also included in revised section p 10.7 of OSTROP 10 because this is the estimated error. j g for a rod calibration. ; With respect to movement of the tube in the reactor tank, , k aluminum TRIGA tubes filled with lead shot will be placed inside the cadmium-lined in-core irradiation tube and the tube's top cap will be sealed to ensure that the tube is neutrally bouyant. Therefore, the impact of , accidentally releasing the tube will be minimal. In addition, the tube will not be over the core when it is passed under the center channel, and as a result there will be no possibility of dropping the tube on the core. 1
~$
l d. (ADDITIONAL) REVISIONS OF OSTROP 6.0 l4 (1) Description s Three (additional) amendments were made to OSTROP 6.0,
" Administrative and Personnel Procedures." The first amendment states that no external measuring or recording device will be connected to reactor measuring channels or safety channels without ROC approval of a 10 CFR 50.59 safety evaluation and any needed operating procedures.
' However, it was not intended that ROC approval be required l for normel use of standard diagnostic equipment by the Scientific Instrument Technician or a designated replace- l ment. A second amendment to OSTROP 6.0 states that when classes are in the reactor control room, the operator ; o- of record will not be the instructor of the class. Finally,
'O. a third amendment was added to ensure that any connection .,
of an external system to reactor measuring or safety (- channels will be checked by the Reactor Supervisor.
-m-__.a-- __m.__-.-_.m___.____..__-mm__ -
*f p
IV-33 Again, this requirement was not intended to apply to o the normal use of standard diagnostic equipment by the Scientific Instrument Technician or a designated replacement.
, (2) Safety Evaluation l
All of the three revisions were made to increase safety,
.J end therefore the safety implications are all positive.
The first amendment noted above will prevent the addition of systems which might affect the reactor measuring or safety channels. The second amendment will decrease l the possibility of the reactor operator being distracted l by also having to instruct a class. The third amendment U will help to ensure that any connections made to important console systems are made correctly.
;* 3. 10 CFR 50.59 Changes to Reactor Experiments There were three changes to reactor experiments which were reviewed, approved, and performed under the provisions of 10 CFR 50.59 during the reporting period,
a. REVISION OF OSTR EXPERIMENTS B-3 AND B-11 (1) Description ExpeH oents B-3 and B-11 were revised to add the new cadmium-lined in-core irradiation tube as one of the standard OSTR irradiation facilities.
. (2) Safety Evaluation The installation of the cadmium-lined tube in the core Lo provides a new standard irradiation facility. From an L' - operational and health physics standpoint, irradiation of samples in this facility is no different than irradi-o ating samples in cadmium cups in the (dummy) sample-holding fuel element, in the rotating rack or in the pneumatic l"
I m i
I IV-34 ll e , L transfer facility. In fact, using the new tube will , I6 enhance safety by reducing radiation doses associated ; i with the use and handling of cadmium cups, which will f not now be needed for many experiments. All irradiations ,
;c, will be controlled following the usual procedures associated l
with irradiation requests. i l* b. REVISION OF OSTR EXPERIMENT B-31 i (1) Description i Experiment B-31 was revised to expand the types of materials I- that can be activated in OSTR facilities for flux-mapping ' purposes. All OSTR irradiation facilities can be used ' including the reactor tank and associated in-core locations. since this was the original intent of Experiment B-31. t (2) Safety Evaluation l No reduction in safety effectiveness results from these minor revisions. Reactivity values and radioactivity limits have not changed. i
c. REVISION OF OSTR EXPERIMENTS B-3, B-11 AND B-12 (1) Description i Experiments B-3, B-11 and B-12 were revised to prohibit l
the irradiation of elemental mercury or substances where , mercury is a major constituent. . (2) Safety Evaluation The change increases safety by preventing the introduction of mercury into the reactor. Mercury reacts with aluminum and could therefore cause undesirable corrosion of reactor components, o 1
IV-35 E. Surveillance and Maintenance
. 1. . Non-Routine Maintenance 18 AUG 88 Replaced a pneumatic damper motor in the reactor building . ventilation system.
o 29 AUG 88 Replaced the carbon vanes in the pump for the stack radioactivity monitor. 16 SEP 88 Changed the ion chamber in the reactor safety channel. 12 DEC 88 Installed a 20 micron filter downstream of the reactor primary water demineralizer tank. 21 DEC 88 Repaired the low flow alann on the continuous air monitor. 3 JAN 89 Sent the fuel element handling tool back to the manu-facturer for repair. 6 JAN 89 Installed a new cranking battery for the emergency power generator.
- 25 JAN 89 Installed a new test potentiometer (on the console) for the safety channel. . 30 JAN 89 Removed an unused water radioactivity monitor from the reactor's primary water purification system.
6 FEB 89 Performed a movement cf fuel elements to even out burnup. 16 FEB 89 Replaced a diode in the reactor servo system to improve servo response. 27 FEB 89 Repaired a frozen pre-heat coil in the reactor building ventilation system. 17 MAR 89 Replaced two bearings in the reactc-r building ventila-tion supply fan.
.- 3 APR 89 Replaced bearings in the reactor primary water pump.
4 APR 89 Replaced bearings in the reactor primary water pump motor.
~ ,- 10 APR 89 Replaced bearings (again) in the reactor primary water pump.
10 APR 89 Replaced the GM tube in the stack monitor's particulate e channel. 25 APR 89 Replaced the pump motor on the continuous air monitor.
IV-36 27 APR 89 - Replaced the time delay reley' in the stack monitor. 4 MAY 89 Permanently installed a 100 ohm resistor across console
;o terminals TP3 and TP4 for the Nyt circuit.
12 JUN 89 Installed a new outside light on the northeast side
!* of the reactor building. '* Replaced the closed r,ircuit TV monitor for the control 13 JUN 89 room access door.
0
2. Routine Surveillance and Maintenance The OSTR has an extensive routine surveillance and maintenance (S&M) program. Examples of typical S&M checklists are presented in Figures IV.E.1 through IV.E.4. Items marked with an asterisk l
(*) are required by the OSTR Technical Specifications, i F. Reportable Occurrences 4
In a letter to the USNRC dated April 17, 1989, the OSU Radiation Center reported an event involving OSTR procedures for hooking up external -
monitoring equipment to the OSTR console. Based on the nature of l
'the event, more stringent procedures were implemented for the connection of any external measuring device to the reactor control console.
No citations were issued as a result of the report and a routine onsite , inspection by the USNRC. l 4 lo D-6
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