ML20235D060
| ML20235D060 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/30/1988 |
| From: | Anderson T, Dodd B, Higginbotham J Oregon State University, CORVALLIS, OR |
| To: | |
| Shared Package | |
| ML20235D043 | List: |
| References | |
| NUDOCS 8902170240 | |
| Download: ML20235D060 (178) | |
Text
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q ANNX RE?21 ~, .
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- REGOTSTATE 31VE3SI"Y ;
RADIA" ION lEX"ER AXD "RIGA REAC"0R II 1,1987 -
JUNE 30,1988
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', L .4 -' ,' Annual Report ;
7 .j of the !
Oregon State University Radiation. Center
, and i
! !TRIGA Reacter ;
a
, July 1,k987-June 30,1988:
!. .l To satisfy'the requirements of: 1 1
A. U.S, Nuclear Regulatory Commission, License No. R-106 (Docket No. 50-243),. 1 Technical Specification 6.7(e).
B. Task-Order No. 3, under Subcontract No. C84-110499 (DE-AC07-76ER01953)~ "
for University P.eactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc.
, .C. Oregon,Departaent of Energy, ODOE Rule No.30-010.
Written by:
T. V. Anderson, Reactor Supervisor B..Dodd,. Reactor Administrator J. F. Higginbotham, Senior Health Physicist D S. Pratt, Health Physicist i
A. G. Johnson, Director i
Submitted by:
A. G. Johnson Director, Radiation Center 3 4
Radiation Center Oregon State University -
Corvallis, Oregon 97331-5903 Telephone: (503) 754-2341 l
l December 28, 1988 J
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Annual Report of the - 1
. ' Oregon State University _
q Radiation Center and TRIGA Reactor. m a
1 Table of Contents j l
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Page
-PART I -'0VERVIEW~ ,
A. ' Acknowledgements................................................. 1-1 B. Executive Summary................................................ I-2 C.- Introduction.... ............................................... I-5 D. Overview of the Radiation
. Center.................................. 1-6 l E. Summary.of OSTR Environmental and Radiation Protection .]
Data............................................................ I-9 l
'1. Liquid Effluents Released................................... I-9 =!
- 2. Airborne Effluents Released................................. I-10 1
- 3. Solid Waste Released......,................................. 1-10 j
- 4. Radiation Exposure Received by Personnel.................... 1 f
- 5. Number of. Routine Onsite and Offsite Monitoring l Measurements and Samples.................................... I-12 F. History......................................................... 1-13 PART II - PEOPLE j A. Faculty......................................................... 11-1
- 5. Visiting Scientists and Special Trainees. . . . . . . . . . . . . . . . . . . . . . . . 11-3 C. OSU G ra d u a te S tu d en t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-4 D. Business, Administrative and Clerical Staff..................... II-5 E. Reactor Operaticas Staff............................ ............ II-5 F. . Radiation Protection Staff...................................... II-5
-l G. Sci enti fi c Su pport Sta f f. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . II-6 H. OSU Radiation Safety Of fice Staff. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-6
- 1. Committees....................................................... IT-7
- 1. Reactor Operations Committee................................ II-7 1
- 2. Radiation Safety Committee.................................. II-7
- 3. Radiation Center Safety Committee............................ II-7 l
1
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1 1
Page l PART III - FACILITIES A. Research Reactor................................................ III-1 1
- 1. Description........................... ...................... III-1 )
- 2. Utilization................................................. III-5 l
- a. Instruction.............................................. III-5 l
- b. Research.............. ................................. III-9 B. Analytical Equipment............................................ III-11
- 1. De s c r i p t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-11 ,
- 2. Utilization................................................. III-11 )
C. Radioisotope Irradiation Sources................................ III-15 l
- 1. Description................................................. III-15 l
- 2. ti t i l i z a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . III-15 1 D. X-Ray Machine............. ..................................... III-18 l
- 1. Description................................................. III-18 l
- 2. Uti11zation................................................. 111-18 l E. Instructional Laboratories and Classrooms....................... III-19 !
- 1. Description................................ ................ III-19
- 2. Utilization................................................. III-20 Instrument Repair and Calibration Facility......................
F. III-22 l
- 1. Description................................................. III-22 !
?. Utilization................ ................................ 111-22 G. Libraries....................................................... III-23
- 1. Description.......................................... ...... III-23
- 2. Utilization................................................. III-24 PART IV - REACTOR A. Operating Statistics...... ..................................... IV-1 B. Experiments Performed........................................... IV-10 C. Un pl a n n e d S h u tdown s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-13 D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments, and Tests Performed Pursuarit to 1 10 CFR 50.59.... ............ ..........................,....... Iva15
- 1. 10 CFR 50.59 Changes to the Reactor Facility................ IV-15 2, 10 CFR 50.59 Changes to Reactor Procedures.................. IV-17 1
- 3. 10 CFR 50. 59 Changes to Reactor Experiments . . . . . . . .. . . . . . . . . IV-18 !
E. Surveillance and Maintenance..........................v......... IV-22 }
- 1. Non-Routine Maintenance..................................... IV-23
- 2. Routine Surveillance 4rd Maintenance. . . . . . . . . . . . . . . . . . . . . . . IV-23 F. Reportable Occurrences... ..................................... IV-23 L l
l t
3 i
! 1
3 1
O. Page PART V - PROTECTION A '. Introduction.................................................... V-1 B. Environmental Releases.. ....................................... V-3
- 1. Liqui d Ef fl uent s - Rel eased. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _V-3.
- 2. Ai rbo rne E f fl uen ts Re l eased . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-3
- 3. Solid Waste Released........................................ V-6 C. Personnel Doses................................................. V-8 D. Facility Survey. Data............................................ V 11 1
-1. Area Radiation Dosimeter.s................................... -V-11: l
- 2. Routine Radiation and Contamination Surveys................. V-15 j E. Environmental Survey Data....................... ............... .V-17 j 1.1 Gamma Radiation Monitoring.................................. V-17 l
- 2. Soil, Water, and Vegetation Surveys.......................... V-23 e F. Radioactive Material Shipments.................................. V-28 G. R e fe re n c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-31 PART VI - WORK- ]
A. S u mma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. VI-1 ,
B. Teaching......................................................... VI-1 q C, Rtsearch and Service............................................ :VI j
- 1. Neutron Activation Analysis................................. VI-24 {
- 2. Forensic Studies............................................ VI-25
- 3. Irradiat1ons................................................ 'VI-25
- 4. Radiological Emergency Response Services.................... VI-25
- 5. Training and Instruction..................................,. VI-26
- 6. Radiation Protection Services............................... .VI-28'
- 7. Radiological Instrument Repair and Calibration.............. VI-29
- 8. Consultation................................................ VI-30 PART VII - WORDS y
A. Publications in Print......................................... . VII-1 B. Theses........................................................... VII C. Reports Submitted for Publication.............................., VII-8 D. Documents in Preparation........................................ VII-10
- 1. Publications................................................ VII-10
- 2. Theses...................................................... VII-11 E. Presentations................................................... VII-12 F. Public Relations..................................,............. VII-15 i
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_ _ ___J
j B
LIST OF TABLES L
Table Title _Page i III.A.1 Courses Using the 0STR...................................... III III.A.2 OSTR Teaching Hours......................................... III-8 1 .i
)
' III.A.3' OSTR-Research Hours......................................... 121-10 !
s III.B.1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, Alpha...................................... 4 ....... III-12
!!I.B.2 Radiation Center Liquid Scintillation Counting Systems....,. 111-13 III.B.3 Radiation Center Proportional Counting Systems............... III-14' III.C.1 Cobalt-60 Irradiator Use.................................... III-17 III.E.1 Student Enrollment in Nuclear Engineering and Nuclear Science Courses Which Are Taught at the Radiation Center.... III-21 IV.A.1 OSTR' Operating Statistics (Using the FLIP Fuel Core) for the 10-Year Period August 1976 - June 1986.................. IV-2
'IV.A.2 OSTR Operating Statistics (Using the FLIP Fuel Core) for the Period July 1986 - June 1988. . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-3 IV.A.3 OSTR Operating Statistics with the Original (20% Enriched)
Stand a rd TRI GA Fuel Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-4 IV.A.4 Present OSTR Operating Statistics.............. ............ IV-5 !
IV.A.5 OSTR Use Time in Terms of Operational Functions............. IV-6 IV.A.6- OSTR Use Time in Terms of Specific Use Categories. . . . . . . . . . . IV-7 IV.A.7 OSTR Muitiple Use Time...................................... IV-8 IV.B.1 Use of OSTR Reactor Experiments............................. IV-12 IV.C.1 Unplanned Shutdowns (Scrams)..................... .......... IV-14 V.A.1 Radiation Protection Requirements and Frequencies........... V-2 V.B.1 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer for the year July 1, 1987 through June 30, 1988....... V-4 V.B.2 Monthly Summary of Gaseous Effluent Releases for the Year July 1, 1987 through June 30, 1988.......................... V-5
r l
LIST OF TABLES (Continued)
Table Title P}gg -
V.B.3 Annual Summary of Solid Waste Generated and Transferred for the Year July 1, 1987 through June 30, 1988............. V-7 l
V.C.1 Annual Summary of Personnel Radiation Doses Received for the Year July 1,1987 through June 30, 1988................. V-10 V.D.1 Tctal Dose Equivalent Recorded on Area Dosimeters Located i Within the TRIGA Reactor Facility for the Year July 1, 1987 i through June 30, 1988....................................... V-13 V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located l Within the Radiation Center for the Year July 1,1987 l through June 30, 1988....................................... V-14 t V.D.3 Annual Summary of Radiation Levels and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys for the Year July 1, 1987 through June 30, 1988....................................... V-16 V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence for the Year July 1, 1987 through June 30, 1988............. V-20 V.E.2 Totai Dose Equivalent at the Uff-Site Gamma Radiation Monitoring Stations for the Year July 1, 1987 through June 30, 1988............................................... V-24 V.E.3 Annual Average Concentration of the Total Net Beta Radio-activity (Minus 3 H) for Environmental Soil, Water, and Vegetation Samples for the Year July 1,1987 through June 30, 1988............................................... V-26 V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water and Vegetation Samples for the Year July 1, 1987 through June 30, 1988....................................... V-27 V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 for the Year July 1, 1987 through June 30, 1988..................... 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, 1987 through June 30, 1988............................................... 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 Radiction Center............................................ VI-5
LIST OF TABLES (Continued)
Table Tit 1e- Page VI.C.3' Listing of Major Research and Service Projects. Performed
.at the Radiation Center and Their Funding Agencies.......... VI-8 VI.C.4 Summary of the Types of Radiological Instrumentation Cali-brated to_ Support the OSU TRIGA Reactor and the Radiation Center...................................................... VI-31 VI.C.5 Sunsnary of Radiological Instrumentation Calibrated to Suppo rt Othe r Agenci es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-32 VII.F.1 Summary of Visitors.to the Radiation Center for the period July 1, 1987 through June 30, 1988............,...... VII -l
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'l I
LIST OF FIGURES Figure . Title Pm i I.D.1' Floor Plan of the Radiation Center............................ I-8 III.A.1 Cutaway View of Standard TRIGA Mark II Core Arrangement....... III-2 III.A.2- Horizontal Section of TRIGA Mark II Reactor. . . . . . . . . . . . . . . . . . . III-3 III.A.3 Vertical Section of TRIGA Mark II Reactor..................... III-4 III.C.1 Cobalt-60 Irradiator (Vertical Section)....................... III-16 IV.A.1 OSTR Annual Energy Production Vs. Time (Annual Reporting Period)....................................................... IV-9
-IV.E.1 Monthly Surveillance and Maintenance (Sample Form)............ IV-24 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form). . . . . . . . . . IV-25 IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form)........ IV-26 IV.E.4 Annual Surveillance and Maintenance (Sample Form)............. IV-28 V.D.1 TRIGA Facility and Radiation Center Area Dosimeter Location...................................................... V V.E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence............................... V-19 V.E.2 Monitoring Stations for the OSU TRIGA Reactor for the Year July 1 1987 through June 30, 1988............................ V-21 l
t i, ;
4 PART I 1
OVERVIEW -
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PART I OVERVIEW A. : Acknowledgements The staff of the OSU Radiation Center and TRIGA Reactor would like to offer their appreciation to the many organizations and individuals who have contributed to the information and events contained in this report. To the University administration who has consistently supported our program; to those, both internally and externally, who have 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 have 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; and to the OSU Department of Printing, who con-sistently produce a quality product; we most earnestly say thank you.
I As a final note of gratitude, the staff would like to recognize the talents and the tolerance, especially the tolerance, of our secretarial staff, who have performed admirably during the preparat.an of this report.
i 3
I-2 B. Executive Summary For the first time, an executive summary has been incorporated l
l into our annual report. The summary highlights Radiation Center activ-ities and accomplishments and describes major changes which have occur-red during the past year. We hope you will find it helpful.
One of the biggest changes this year is the report :tself. Our annual report has undergone a major revision in terms of scope and format, and now includes information about ?,he entire Radiation Center rather than concentrating mainly on the reactor. However, our report still includes all inforstion needed by the various agencies who require an annual report dealing with the OSU TRIGA redctor.
We are again very happy t0 report that the Radiation Center and !
reactor exper;enced a year in which there was increased u";e and funding.
In fact, the 1987-88 interval was the busiest and most product'ive year for quite some time. However, before we review our achievements, we would like to express our appreciation to the university's adminis- !
tration for their financial and adminfitrative support and encourage-ment. We are also most grateful to the U.S. Department cf Energy for their support through the reactor sharing program, and we would like to say thank you to the many other organizations who funded re-search and technical services conducted by the Center. The resources obtained through these channels created educational opportunities which allowed many students and new researchers to use the unique facilities present at the OSU Radiation Center.
As indicated, academic activity at the Radiation 'anter and reactor reached new neights during the current reporting period. For example, the reactor was utilized 91% of the available 45-hour work week, and the total reactor use hours increased 23%. As a result, we occasionally were required to operate beyond our normal one-shift schedule and compensated for this by performing evertime reactor runs. We view this as a prelude to the establishment of a formal second-shift operation.
In the teaching area, the Radiation Center accommodated 26 OSU classes from 10 different academic departments, and reactor operating hours equivalent to approximately 30% of the normal academic year were used to directly support such classes. There was also over a
1 I-3 65% increase in the number of student projects at mmodated at the Center, and a 54% increase in the number of reacto hours devoted to these projects. When the preceding instructional hours are combined with a significantly increased number of ' operating hours for academic revaarch we show a 66% overall increase in the. number of reactor hours devoted to teaching and research.
Other use indicators also reflect the busy year experienced by t'ne Radiati6n Center and reactor. For example, we had a 146% increase in the (1 umber of operating hours when the reactor had multiple users, and on eight different occasions we had six users at one time. We also ended the year with a 92% increase in the number of other uni-versities using the Center, a 78% increase in the number of state, federal, and other organizations usi6g the facility, an 85% increase ir the number of research and service projects performed, and a 12-fold increase in the number of times these research und service projects were repeated. We are particularly pleased with these h$olts because we were able to measurably increase our assistance to the OSU community while concurrently expanding our research and service interactions f with other universities in the Oregon State System of Higher Education ,
(OSSHE), with a number of state and federal agencies, and with colleagues at otiler universities across the nation. We also feel encouraged by these results because, from our perspective, they are a good indication of the fact that the OSU Radiation Center is continuing to grow in terms of national recognition.
In the area of research support and new technical programs, the Radiation Center made 84 shipments of radioisotopes to users outside the Radiation Center, and significantly increased 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 received a large increase in the number of requests for gamma irradiations using the cobalt-60 irradiator. By the end of the reporting period we had accumulated a total of '2,278 hours0.00322 days <br />0.0772 hours <br />4.596561e-4 weeks <br />1.05779e-4 months <br /> for various irradiations (a six-fold increase in use)..
i I-4 The Radiation Center continued to be a popular place to visit, particularly for high schools, community colleges and' interested cit-izens. We again hosted over 800 visitors during the course of the year.
Scholarly publications involving a major contribution by the Radiation Center increased 100%, and we recorded nearly. a four-fold increase in presentations at professional meetings where the Center was instrumental in developing 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 99 total articles generated during the reporting period which' involved a significant contribution by the Radiation Center.
To manage the increased overall use of the Rsdiation Center and its facilities, our recently implemented " project" system continued to develop as a means of accounting, scheduling and recording facility use. The coming year will see further changes in this system to meet the recordkeeping requirements of the new annual report format.
We also feel that it is iniportant to note that there were no items of regulatory noncompliance, no reportable occurrences, and no emergencies or security events relating to the Radiation Center during this reporting period. In addition, all of the increased use of the Radiaticn Center and 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 can be operated safely and within the international goal of keeping personnel doses and releases of radionuclides as low as reasonably achievable (ALARA).
This reporting period saw the first full year of the new Radiation Center Director, the arrival of a new Senior Health Physicist, and the subsequent completion of the Radiation Center's reorganization and management plan. We believe that these staffing changes have resulted in the structuring of a strong group of personnel capable of meeting the challenges of increased demands and facility use.
We are looking forward to another good year.
I
I-5 C. p troduction The annual report for the OSU TRIGA Reactor has been extensively revised .
and expanded this year. In particular, the report now includes infor-mation relating to-the entire Radiation. Center rather than just the reactor. However, the information is presented in such a menner that data on the reactor may be examined separately if desired. It should q 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.3 in Part IV of this report, or to the 19'/6-77 annual report if a more comprehensive
~ review is needed.
l In addition to providing general information about the activities of the Radiation Centeri 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 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 alrecdy. familiar with the Radiation Center's operation.
I l
1
I-6 D. Overview of the Radiation Center The Radiation Center is an extremely unique facility which serves the entire OSU Campus, all other institutions within the Oregon State System of Higner Education, and many other colleges and universities throughnut 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 assistanea to Oregon industry. In addition, the Radiation Center provides purelanent office and laboratory space for the OSU Department of Nuclear Engineering, the OSU Radiation Safety program, 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 United States. See Figure'I.D.1.
located in the Radiation Center are major items of specialized equipment and unique teaching and research facilities, including a 1RIGA Mark 11 research nuclear reactor; a cobalt-60 gamma irradiator; a 300 kVp X-ray generator; a number of state-of-the-art computer-based gama radiation spectrometers and associated germanium detectorst a neutron radiography facility capable of taking still or very high speed radio-graphs; and a variety of instruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with up-to-date instrumentation and related equipment for performing neutron activativn analysis and radiotracer studies; laboratories for animal and plant experiments involving radio- ;
activity; an instrument cal';bration facility for radiation protection l instrumentation; and facilities for packaging radioactive materials for shipment to national and international destinations.
The Radiation Center staff regularly provides direct support and assis- l tance to OSU teaching and research programs. Areas of expertise commonly l l
involved in such efforts include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, neutron radiography, radiation effects on biolog1 cal systems, radiation dosimetry, production
-4 . , :. I-7 of short-lived radioisotopes, radiation shielding, nuclear instrumen-
. tation, emergency response, transportation of. radioactive materials, instrument calibratio", radiation health physics, ' radioactive waste disposal, and other related areas.
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 prograns, and professional consultation associated with the feasibility, design, safety, and execution of experiments using radiation and radioactive materials.
I
Figure I.'D.1 I-8 Floor Plan of the Radiation Center THino FLoon SEcoHo FLoon F1ast FLoon g [-g- }
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I l I-9 1 E, Sunnary of OSTR Environmental and Radiation Protecti,on Data ] Year July 1, 1987
, 1. Liquid Effluents Released (See Table V..B.1)- Through June 30, 1988 'l l a. Total estimated quantity of radioactivity released (to the.s6nitary sewer)(in curies)(1) 5.86 x 10-5 I I
- b. Detectable radionuclides in the liquid waste 3H, 60 Co'- !
l
- c. Estimated average concentration of released radioactive material at the point of release !
(its microcuries per cabic centimeter) 7.11 x 10-6 {
- d. Percent of applicable MPC for released liquid radioactive material at the point 0.24%(2) of release (%) 0.01%(3)
- e. Total volume of liquid effluent released. i including diluent, which W
contribution (in galloris)99gtained an 05TR 2176 ' I i (1) The OSU operational policy is to subtract only detector background l from our water analysis data and not background radioactivity in the Corvallis city water. i (2) Based on values listed in 10 CFR 20, Appendix B, Table 2, Column 2. , 1 (3) Based on values listed in 10 CFR 20, Appendix B Table 1, Column 2, applicable to sewer disposal. (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. i
I-10 l' Year July 1, 1987
- 2. Airborne Effluents Released (See Table V.8.2) Through June 30, 1988
- a. Total estimated quantity of radioactivity '
- released (in curies) 6.3
- b. Det.w;cble radionuclides in the gaseous waste',ll 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-11ggs greater ther, 8 days (in curies)W None Year July 1, 1987
- 3. SolidWas,teReleased(S_eeTable1,B.,3,1 Through_ June 30, 1988
- a. Total acount of solid waste packaged and disposed of (in cubic feet) 19.0 Detectable radionuclides in the solid waste 24sa, 46sc. 51ce, f h.
54m , 58co, 59p,
]
60cm 753 ,, 82Br. 110 mag, 124sb, 131g, 141Ce 154Eu ,
- c. lotal radioactivity in the solid waste (in curies) 5.5 x 10-4 l
(1) Routine gama spectroscopy analysis of the gaseous radiohetivity in the stack discharge indicated that it was virtually all argon-41. (2) Evaluation of the detectable particulate radioactivity in the stack f discharge con 7f rmed its origin at naturally occurring radon daughter products, predominant?y lead-214 and bismuth-214, which are not asso-ciated with reactor operations.
- - l
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l' i
- 4. : Radiatien Exposure Received,by Persomiel' Year' July 1,~1987
']
(in mrem)_.(fee Teble V.C.1) ul Through June 30 1988' 1 1 (( [.y a; Facility Operating-Personnel ! c 1) Average'Whole body. 39 'l (. ~2) Average extremities 77 l" 3) Maximum whole body 340 i
- 4) Maximum extremities 460 1
- b. Key Facility Research Personnel
- 1) 1 Average wh61e body <1
- 2) - Average extremities 0 3)- Maximum whole body 15 i
'4) Maximum , extremities 0 l
- c. Physical Plant Maintenance Personnel i
- 1) Average whole body <1 2)' Maximum tehole' body- 8
{
- d. Laboratory Class Students i) Average whole body. 0
- 2) Average extremities 4 1
- 3) Maximum whole body. 0 (
- 4) Maximum extremities 70 j
- e. Camp'us Police and Security Personnel
- 1) Average whole body 0
- 2) Maximum. extremities 0
]
- f. Vitjtors
- 1) Average whole body (1
- 2) Maximum whole body 9' )
J (1) "0" indicates that each of the beta-gamma dosimetarr during the report-ing period itera less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the neutron dosimeters were less than the vendor's threshold of 30 mrem, as applicable. l 1
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' 5. Number of Routine Onsite and Offsite Year July 1,'1987 .j Monitoring Mea;urements and Samples _. Throuah June 30, 1988 j
- a. Facility Survey Data
- 1) Area. Radiation Dosimeters (See Table V.D.1) a) 'B?ta-gamma dosimeter. measurements 148 b) Neutron dosimeter measurements 48
- 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 Detectior. Co.' TLD monitors .72
-- Monthly R/hr measurements 108
-- Integrating ion chamber measurements 216 b) Offsite monitoring
-- OSU TLD monitors 226
-- Radiation Detection Co. TLD monitors 104
- Monthly pR/hr measurements 252 :)
-- Integrating ion chamber measurements 156
- 2) Soil, Water and Vegetation Surveys (See Table V.E.3) <
a) Soil samples 16 . i b) Water samples 13 c) Vegetation samples 56 l l l I I l' l
e , 1. s,
'o p.?.3 -
' F. . History A brief chronology of the key 1 dates sHd events in the history of the-
' OSU Radiatien Center and the TRIGA reactor is given below:-
l 1 June 1964 Completion of the first phase of the Radiation Center consisting of 32,397., square feet of offhe .and labora-tory space. July 1564 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. This reactor was initially. housed in the l 1 Mechanical Engineering Department.and had gone critical 'l in January of 1959. Oct. 1966 Completion of the second phase of the Radiation Center consisting of 9,956 square feet of space fer the TRIGA reactor and associated laboratories and offices. March 1967 Initial criticality of the Oregon State TRIGA Reactor (OSTR). The reactor was licensed to opert.te at a maximum steady. state power level of 250 kW, and was fueled with 20% enriched fuel. August 1969. OSTR if tensed to operate at a maximum steady state power of 1 MW, but could do so only for short periods < l 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 inergy Facility Siting Council.
Sept. 1972 OSTR area fence installed.
-Dec. 1974 AGN401 reactor permanently shut down.
March 1976 Completion of 1660 square feet of additional space to accommodate the rapidly expanding nuclear engineer- ; ing program. July 1976 OSTR refueled with 70% enriched FLIP fuel.
o . l I-14 l 1 i July 1977 Completion of a second 1600 square feet of space j to bring the Radiation Center complex to its current ] I. total of 45,553 square feet. Jan. 1980 Major upgrade of the electronics in the OSTR control console, i July 1980 AGN-201 reactor decommissioned and space released for unrestricted use. Julie 1982 Shipment of the original 20% anriched OSTR fuel to I Westinghouse Hanford Corporation. I 1 j 1
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PART II PEOPLE 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 lists the makeup of the committees involving Center personnel. It should be noted that this section on personnel does not include all of the faculty and students who used the Radiation Center for their teaching and research. 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 Minney, Stephen E. Associate Professer of Nuclear Engineering Chairm % OSTR Reactor Operations Committee I
*Conrady, Michael R.
Research Assistant i Neutron Activation Analysis Speai611st Daniels, Malcolm , Professor of Chemistry )
*Dodd, Brian Reactor Administrator Associate Professor of Nuclear Engineering
*Goiightly, Vivian H.
Research Assistant , Radiation P;'otection Technologist
- Reactor users for research and/or teaching. )
c"' a ' f{ 4 gy < t , , .
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.hi Hart, Lucas P: !
.Research Associate, Chemistry
'f ~ ., m
- 3. l*Higginbotham, Jack F.
Senior Health Ph .ist
- Assistant Professor of Nuclear. Engineering 'q i .- *Hughes, Scott lS. ) '
Research Associate, Chemistry 1
.Klein, Andrew C.
. 'l L
Assistant Professor of' Nuclear
- Engineering
' *Loveland, Walter D.
Professor of Chemistry - l
'MacVicar,' Robert
)q President Emeritus, OSU
*Pastorek,. Christine 4 L Instructor.of Chemistry.
Popovich, Milosh.' Vice President Emeritus 050
*Pratt, David S. <1 j _
Research Assistant Il Health Physicist' Reyes,' Jose N.
-Assistant Professor of Nuclear Engineering
*Ringle, Jo'hn C.
Professor of Nuclear. Er.gineering ! Associate Dean of the Graduate School, OSU l
- Robinson, Alan H. f Head, Department of Nuclear Engineering .i Professor of Nuclear' Engineering ;
*Schmitt, Roman A. /
Professor of Chemistry lJ
- Walker, Robert J. !
Research Assistant j Neutron Activation Analysis Specialist Wang, Chih H. Professor Emeritus, OSU ] J
)
- Woods, W. Kelley Professor of Nuclear Engineering i1 I
- Reactor users for research and/or teaching. =
1 1 1
..- - .A
1 II-3 '! j. I B. Visiting Scientists and Special Trainees j Advisor or Research Name Field (Affiliation) Program Director Groening, Hugo Nuclear Chemistry W. D. Loveland 4 (Argentina) f
- Gross, Kim Reactor Operator Trainee B. Dodd
*Hou,Bijun Radiation Health A. G. Johnson !
(People's Republic of China) l Hu, Dingguo Radiation Chemistry M. Daniels 1 (Peoph 's Republic of China) , I
*Jin, Guang '/u Neutron Activation Analysis R. A. Schmitt ]
(People's Republic of China) j i Long, Zhenjie Nuclear Engineering A. H. Robinson (People's Republic of China)
*Miah, Md. R3hez Uddin Neutron Activation Analysis R. A. Schmitt '
(Intetnationti Atomic Energy Agency--Bangladesh)
*Pablo, Samuel Reactor Safety B. Dodd l (International Atomic Energy Agency--The Philippines)
Wang, Rushan Data Analysis-Chemistry W. D. Loveland (People's Republic of China) i Xu, Zhenyuan Data Analysit-Chemistr.i W. D. Loveland (People's Republic of China) l 4 1 1
- Reactor users for research and/or teaching. l
)
l 1 l
II-4 i C. OSU Graduate Students Degree Name Program Field Advisor j Abdelhai Mohamed I. PhD Nuclear Engr. B. Dodd 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, Bilgees PhD Nuclear Engr. S. E. Binney
*Bakir, Alla J. MS Nuclear Engr. S. E. Binney Bostick, Kent MS 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 I., Snee
*Feeley, Todd C. MS Geology A. L. Grunder Fu, Yingxian MS Chemistry M. Daniels Gedeon, Steve MS Nuclear Engr. A. H. Robinson
- Hill, Brittain E. PhD Geology E. M. Taylor !
- Ivy, Susan MS Geology R. A. Schmitt Jordheim, Daniel P. MS Nuclear Engr. S. E. Binney King, John MS Nuclear Er.gr. 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 .
*Marso, Jeffrey N. MS Geology E. M. Taylor 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 l 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 i
- Reactor users for research and/or teaching. f I
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- D. Business, Administrative and Clerical Staff j ij Di rector.' A. G. Johnson f
' Business Manager S. K. Tschannen '
, . Administrative Assistant E. C. Flickinger
- Clerical Assistants P. A Cunningham J. R. Smith Accounting Clerk I S. C. Campbell Custodian M. L. Benad
' Administrative Assistant i
.NuclearEngineering)
( D. L. Cramer- l 4 Clerical Specialist (Nuclear Engineering) R. A. Keen ! E. Reactor Operations Staff l Principle Security Officer A. G. Johnson Reactor Administrator, Senior a Reactor Operator B. Dodd
. Reactor Supervisor, Senior 3 Reactor Operator T. V. Anderson "
Senior Reactor Operators S. E. Binney j J. F. Higginbotham i Reactor Operator A. D. Hall T F. Radiation Protection Staff Senior Health Physicist J. F. Higginbotham Health Physicist- D. S. Pratt Radiation Protection Technologist V. H. Golightly Health Physics Monitors (Students) W. Cox D. Harlan ; R. Hughes S. LaBuy W. McClatchey A. Scarbrough 0 i I. i
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' f L Scier.tific Support Staff ' -l D' ' Senior' NeutronA ctivation Analyst- ,R.:A. Schmitt-
- Neutron ActivatWn' Analysis ,-
.L -1 Specialists M. R.;Conrady'- 1 R. J. Wal ker-J-
Neutron' Activation Analysis. ..
. Technicians(Students); J. Curless ,
j
'T. Feeley 'l S.ilvy . "i R. Kennedy; J, Marso R. Reed-S. Yesilyurt:
.H. L. Busby
' Scientific. Instrument Technicians.
D.-K. Woodrow a
?
H. OSU Radiation Safety Office Staff . l Title Name Radiation Safety Officer G. A. Little Radiation Specialists R. H. Farm 6r j '] R. C. Wallace H K. C. Tompkins
-]
' Secretaries- M. A. Goode- ,
K. L.' Miller ,
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, I. Commiittees
- 1. Reactor Operations Comittee Name Affilia' tion .
S. E. Binney, Chairman Nuclear Engineering T..V.' Anderson Radiation Center B. Dodd. Radiation Center and Nuclear. Engineering J. F. Higginbotham Radiation Center and Nuclear-Engineering A. G. Johnson Radiation Center and Nuclear Engineering J. C. Ringle Nuclear Engineering and Graduate School A. H.' Robinson iluclear Engineering R. A. Schmitt Chmistry and Radiation Center S. A. Stone College of Engineering; Dean's Office W.'H. Warnes Mechanical Engineering
- 2. Radiation Safety Committee (OSU)
Name, A,ffiliation D. W. Barnes. Chairman Biochemistry, Biophysics G. S. Beaudreau Agricultural Chemistry . i L. E. Coate V. P. for Finance and Administration l i.' B. Dodd Radiation Center and Nuclear Engineering ; A. G. Johnson Radiation Center and Nuclear Engineering l G..A. Little, Secretary & RSO Radiation Safety Office ! T. F. Murray Pharmacy }
.C. J. Rivin. . Botany B. B. Smith Veterinary Medicine
,. J. B. Zaerr Forest Science ;
- 3. Radiation Center Safety Comittee d
Name Affiliation i L W. D. Loveland, Chemistry J Chairman _ T. V. Anderson Radiation Center I l S. E. Binney Nuclear Engineering l H. L. Busby R diation Center l
.H. R. Conrady Radiation Center l A. G. Johnson Radiation Center and Nuclear Engineering )
S. K. Tschannen Radiation Center i l r l l l ( l
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m [ PART III FACli.ITIES A. Research Reactor
- 1. Description H 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, end the tank is surrounded by a concreto monolith which acts as a radiation shield and structural support. See Figures III. A.1, III. A.2 and III. A.3.
The reactor is licensed 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. The OSTR has a number of different irradiation facilities including. a pneumatic transfer tube, a. rotating rack, a thermal column, four beam ports, and sample-holding (dummy) fuel elements for special in-core irradiations. The pneumatic transfer facility enables samples to be inserted 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 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 1 irradiation.
III-2 CONTROL RODS CENTRAL PE RI M E NTA L THERW LIZING g 3, ,,.
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III-5 The reactor's thermal column consists of a large stack of graphite blocks which slow down neutrons from the reactor core in ordei to. increase thermal neutron activation of samples. Graphite blocks are removed from the-thermal column to enable scmples 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 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 large neutron fluxes, especially fluxes involving higher energy neutrons, then such samples may be inserted into a dummy fuel element. This device will then be placed into one of the core's inner grid positions normally occupied by a fuel element.
- 2. Utilization l
The two main uses of the OSTR are instruction and research. During ' this reporting period, the reactor was in use an average of 41 hours during a typical 45-hour work week. Hence, the reactor was used approximately 91% of the available time.
- 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 I ' l demonstrations and instructional experiments can be performed j using the OSTR which cannot be carried out with a commercial ) 1 power reactor. Shorter-term demonstration experiments are I
.III-6
(. also' performed for many undergraduate students in physics, chemistry and biology classes, as well as for asitors from other universities and-colleges, from high schools and from , public groups. I The second instructional application of the OSTR involves education of reactor operators, operations managers, and radi- .i ation health physicists. The OSTR is in a unique position ! to provide su:h 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.C.5 of this report. During this reporting period the OSTR accourodated 26 OSU academic classes and 2 reactor operator training programs. In addition, portions of classes from other Oregon universities 1 were also supported by the OSTR. The OSU teaching programs utilized 359 hours of reactor time. Tables III.A.1 and III.A.2 as well as Table III.E.1 provide detailed information on the use of the OSTR for instruction and training. i f
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'111-7 ' ,
1 Table III.A.1' Courses Using the OS1R- l 1 j Course No. Course Name
, NE 101 Nuclear Engineering Critntation' q NE 102- ' Nuclear Er.gineering Orientation, NE'203- Nuclear Radiation Detection and Measurement NE 4084 Field Practices in Radiation Protection (undergraduate).-
NE 40 Projects (Nuclear Engineering) ,
' NE 441- Nuclear Reactor Experiments '(
lNE 461' Radiation Protecticn Engineering ' NE 503 Thesis (Nucletr Engineering) , CH 106- -General Chemistry Laboratory -
-CH 107 General Chemistry Laboratory CH 206H Chemistry Honors i CH 207' General Chemistry Laboratcry-CH 419 Radioactive Tracer Methods 7 CH 503 Thesis (Chemistry) '
CH 505 Reading and Conference CH 528 Activation Analysis
~GS'405A Field Practir es in Radiation Protection-(undergraduate)
.GS 505A Field Practices in Radiation Protection (graduate)
G 503 Thesis (Geology) l G. 582 Isotope Geochemistry OC 503 Thesis (Oceanography) PH 503 Thesis (Physics) ! BMC 366A Broadcast Media Communication - Television Production WR 327 Technical Report Writing H 344 Man, Health and the Environment ! J 434 Journalism - Advanced Photography .i o .3 New Student Programs
. . 4
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.b i
. . Table III.A.2 l
~l OSTR. Teaching. Hours i Annual Cumulative .
Values for Values for; . 1 Jul. 87. 1- AUG -76 1 c, ; Description Through Through . I 30 JUN 88 30 JUN 88. (hours). (hours) - 1 Departmental '235 .2405 Nuclear _ Engineering ~117 Chemistry. 62 General Science (Radip on Health) 56 Geologyi{J 4cernographyll) Physicsul Special Classe 1 and Proje~tsc 2L 124 329 Total Teaching Hours (3,4,5) 359 , 2734 (1) Uce hours by these departments are not shown under " Teaching Hours." but are reflected under Thesis Research, both funded and anfended.
'(2) ' A variety. of educational classes were conducted which involved one-
.tima meetirgs for orientation or support' purposes. These included:
high school science c'insses, journalism or broadcast media c' lasses',
.new student programs support reactor operator orientation and train-3 ing, community college classos and other state university classes.
(3) See Table III.E.1 for classes and s'tudent enrollment. ,
- (4) See also Table IV. A.6 for a summary of all reactor use categories. 1 (5) Total teaching hours reflect all time the reactor was in use for j teaching, and because of this the total hours it.6'ude time the reactor !
itself may not actually have been in operation. , i l I i { E____ _ _ _ .
112-9 l I
- b. Research 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 l experimental technique requiring reactor use is neutron acti- l vation arialysis (NAA). Thir, is a particularly sensitive method l 1 of elemental analysis which is described in more detail in Part VI.C.I. Part III.B provides a listing of equipment used I in NAA at the Radiation Center. The OSTRi s irradiation facilities provide a wide range of neutron flux levels and ne; tron flux qualities, which are suf> ficient to meet the needs of most researchers. This is true not only for NAA, but also for other experimental techniques q such as fission track dating of geological and anthropological materials. During this r(porting period, the OSTR accommodated 91 funded research projects which utilized 1009 hours of reactor time, and 19 unfunded research projects which utilized 88 hours of reactor time. Details of the reactor's use snacifically for research are given in Table III. A.3. ArJditional information regarding reactor use for research, thesis and service can be found in Tables VI.C.1 through VI.C.3. In these tables GSTR use is indicated with an asterisk. 1 1 l h i 1 i i l i I _o
!!!-10 )'
i Table III.A.3 l OSTR Research Hours Annual Cumulative , Values Values for for Types of Research 1 JUL 87 1 AUG 76 ' Through Through 30 JUN 88 l 30 JUN 88 (hours) (hours) j OSU Research 370 5396 Off-Campus Research 727 2118 Total Research Hours (1)(2) 1097 7513 l (1) Total research hours statistics: (a) 92%(1009 hours) of the total research hours were user-funded by federal, state, or other organizations. (b) 8% (88 hours) of the total research hours were user-unfunded studies in stipport of graduate thesis research or other academic investigations. Reactor costs for this research were absorbed (funded) by the OSU Radia-tion Center. (2) OSTR operating hours in support of OSU teaching and research programs equal the hours the OSTR operated for off-campus research projects. Of the off-campus research hours OSTR recorded, nearly 14% (approximately 100 hours) were in direct suppcet of research being conducted at the University of Oregon and Portland State University, t l
)
f 1 1 III-11 l l I l B. Analytical Equipment
\
l 1. Description l The Radiation Centei has e great variety of radiation counting r equipment. 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 provide a brief listing of typical laboratory counting equipment present at the Center. Much additional equipment for use in the { classroom, and an extensive inventory of portable counting instru-mentation are also available.
- 2. IJtilization Radiation Center counting equipment receives intensive use due to both teaching and research applications. In addition, service projects also use these 'eystems and the combined use often results in 24-hour pe day schedules for many of the counting instruments.
Use of Center counting squipment extends beyond that located at 1 the Center as represented by two single channel analyzers on loan for the past few years to OSU researchers 1." the Departments of Pharmaceutical Chemistry and Fisheries and Wildlife. l l l l l
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4
' Radiation Center Spectrometry: Systems: I u
. Gamma, Low Energy Photon, Alpha ,- l i ~
Re?. Effic.- 1 Room ' System- .(%) , ,
-- < 3, B100 Adcam 1, Sk Ortec,.0rtec HP Ge 26.B'
~ B100 Adcam 2, 8k'Ortec, PGT Gefli)' 13.0 , :
A B100L Adcam 3, 8k Ortec, Canberra Ge(Li) ,
.19.4 .l
- B100 Adcam 4, 8k Ortec, PGT Ge(L1) 13.2 '
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C126- Ace 1. 4k Ortec, NaI(T1).3x3 N/A , , C123 Ace 2, 4k Ortec, PGT Ge(Li) 18.7 q
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C126- 2 K, N060, NaI(T1) 3x3 N/A-L A138 H.P. Scaler, NaI(TI) 2x2 N/A A146 ~ ' Ace, 4k Ortec, Ortec HP Ge 30.0 A146: Ace,.4k Ortec, Ortec Ge(Li) 27.0 C134- Ace, 4k Ortec, Ortec HP Ge 32.0 C134 4x4 k ND Micro MCA, PST Ge(Li) 16.2'
,1 C134 4x4kNDMicrohCA,PGTGe(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 Alpho N/A Spectrometer
+,.
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- 0126 Seckman, Betamata l
C126 Bec,kman, Betarcate B136 Beckman, LS 7600
.I B136 Searle
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I I i l 1 i
U ' _ 111_14 l l l 1 Table III.B.3 ! Rad 5ation Center Proportional Counting Systems _. ._ _._. _ l l Room System C126 NMC 1. PCS C126 NMC 2, PCS C126 NMC 3, PC5 A138 NMC, PCC-11T and DS 2 l A138 NMC Auto Counting System w/ IBM XT l l l t l 1 h N i h..-_ __m _ - -- --w -
L ' j
]
112-15 s l 1 C. Radioisotope Irradiation Sources. j
, l
- 1. Description-11 1
The Radiation Center is ~ equipped with a cobalt-60 gamma . irradiation. I
- l. facility which is capable of delivering high. doses of gamma radia-
' tion to a.wi(le variety of materials. Typically, the-irradiator.
c j
-is used by researchers wishing to perform mutation and other b.io-- .
logical. effects studies, studies in the area of radiation' chemistry,: f I dosimeter testing, sterilization of food materials, soils, sediments .) and other media. gamma radiation damage studies, and other such 1 applications. In addition to the cobalt-60 irradiator,.the Center. j is also equipped with a variety of smaller cobalt 60, cesium-137 .
]
radium-226, plutonium-beryllium, and other isotopic sealed sources . 4 of various curie levels which are available for use as irradiation-j 3 sources.
- 2. Utilizatio_n !
During this reporting period there were two large projects using the cobal'c-60 irradiator. One involved the irradiation of mice as part of an immuno-toxicological study of dioxins, and the other involved the testing of thermoluminescent dosimeters. However, examples of other samples irradiated include fish lymphocyte cells ; i and pumpkins seeds. In addition, the Center resumed use of the irradiator for long irradiations associated with the sterilization of soil and other materials. Data on use of the irradiator for-this reporting period are given in Table III.C.1, I i i _o
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- l. .
.III-17
'(s I:
Table III.C.1 Cobalt-60 Irradiator Use
.l Purpose of Dose itange Number of Use Time Irradiation Samples (rads) Irradiations (hours) i Sterilizatioil Soil 5 x 106 '4 2260.3 2.7 $
Botanie,t Pumpkin' 104 -'2x104 3 Studies Seeds ln
..- l Biological Mice, fish 2x102 - 2x103 45 7.6 1 Studies "iymphocyte cells
.I Dosimeter TLDs 30 - 103 18 7.2 Analysis .
/- _._ lq TOTALS 70 2277.8 I
l 1 1 l i I l 1 l l 1 l j I I- i
III-18 D. X-Ray Machine ! L Description A General Electric Maxitron 300 kVp X-Ray generator is 16cated in the Radiation Center. This device is situated in a shielded room which is large enough to accommodate a wide variet:. ' exper-(mehts. The machirie is capable of operating at 300 kVp and 20 . mA, and devices for calibrating the beam intensity are available. ,
- 2. t, U_tilization ..
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 chec,ks required - for such a facility, i 1 i l I I J . _ _ . J
.{
i III-19 E. InstructignaljaboratoriesandClassrooms q
- 1. Description The Radiation Cewter is equipped with a number of specialized laboratories designed to accommodate classes offered by variour.
OSU academic departmene or off-tampus groups which involve the [ use of radioactive materials. I Facilities available at the Center include an instructional laboratory f especially equipped for radiochemistry and two nuclear instruments-tion 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 computer rooms equippad with microcomputers and terminals which are linked to other computers, both on and f off campus. In addition to these dedicated instructional laboratories, many other research laboratories and facilities are regularly used for teaching. In particular, classas are routinely given access to appropriate state-of-the-art analytical equipment located in othet Center laboratories. A number of classes also regularly use the reactor and the reactor bay as an integral part of their instructional coursework., i l There are two relatively largo classroones in the Radiation Center which are capable of holding about 35 students each. In addition, there are two smaller conference rooms suitable for graduate c1essas and thesis examinations. As a service to the student body, the Radiation Center also provides a student study room /lotnge as well as an office area for the stuaent chapter of the American ! Nuclear Society, f
)
1 _ _ w
111-20 4
- 2. Utflizet?q Al'I of the instructional laboratories and classrooms are used extensively during the academic year. A listing of most of the courses accommodated at the Radiation M ter along with their enro11 cents during this reparting period are given in Table III.E.1.
Table III.A.1 gives a complete listing of all 26 classes accom- i modated by the Center during the reporting period. l l I t j i i r 1 I i
L III-21 L Table Jil.E.1 I" Student Enrollment in Nuclear bgineedng and Huclear Science Courses ; l' Which Are Taught at the Radiatien Center l J
. 1 Number of ' Students I
. Fall Winter Spring. J
. Course Credit Course Title 1987 1988 1988 4 l
l l Nuclear ' Engineering Courses
*NE 101 2 Nuclear En inoering Orientation 24 -- --
*NE 102 2 Nuclear En ineerin Orient 3 tion -- 17 -
NE 103 3 Intro. 10 lear En ineering & Comp. -- -- IR NE 201 -3 Nuclear Energy Fundamentals 28 -- -- NE 202 3 Nuclear Radiation a flatter -- 25 --
*NE 203 3 Nuclear Radiation Detection 5 Measurement -- -- 22 NE 405 2 Reading 6 Conference -- -- i'
**NE 405A 1-3 RL"/ Field Practice Radiation Health 2 1 5
,NE 405B 2 RE/ Radiation Health -- --
2
*NE 406 1-6 ?rojects -- -- --
NE 406D 1-5 Individual Design Project 3 7 4 NE 407 1 Seminar -- 13 11 -;' NE 415 4 Principles Radiation Safety 18 -- -- NE 417 4 Huclear Reactor Power Generation -- 14 +- NE 419 4 Nuclear Reactor Theorf -- -- 15
.NE 421 3 Nuclear Reactor Ar.alysis & Computation 17 -- --
t NE 422 3 Nuclear Reactor Anal sis & Computation - 16 -- NE 423 3 Nuclear Reactor Anal sls & Computation -- -- 15 NE 430 3 Nuclear Fuel Cycle -- 16 -- NE 431 3 Reactor Thernal Hydraulics 17 -- -- 1 NE 432 2 Reactor Oesfgn 13 -- -- \ NE 433 . 3 Reactor Design -- 11 -- NC 434X 3 Relear Reactor Design -- - 9 f
**NE 451 3 Guclear Reactor Experira m -- - 15 d
**NE 461 3 Radiation Protectio; cnginesring --
21 --
)
NE 465 3 Nuclear Rules & Regulations -- -- 24 NE 501 1-15 Research 1 i 1
'**NE 503 1-15 Thesis 14 15 14 NF 505 1-15 Reading & Conference -- -- 1
'NE 506 1-15 Projects 1 -- --
NE 507 1 Semin6r -- 2 3 NE 511 3 Neutron Trant, port Theory < - - 5 --
'lE 512 3 Advanced Nuclear Reactor Theory -- --
5 NE 532 3 Advanced Nuclear Reactor Design 4 -- -- NE 533 3 Advanced Nuclear Reactos Design -- 4 -- NE 534X 3 Advanced Nuclear Reactor Design -- -- 1 NE 542 3 t,dvanced Thermal Hydraulics -- -- 13 NE 581 3 Special Topics 2 -- -- NE 5835 3 Special Topicushielding 7 -- -- i4E 583W 3 Special Topics / Waste Mant.nement 8 -- -- Chemistry Courses
*CH 106 5 General Chemistry 50 -- -- ,
*CH 107 2 General Chemistry Lab 60 -- --
*Cli 206H 5 Chemistry Honors. -- --
12
*CH 207 2 General Chemistry Lab 4 - --
*t;H 419 4 Radioactive Tracer Methods 17 -- --
*CH 503 1-15 Thesis (Chemistry) 5 5 5
*CH 505 1-15 Reading & Conference (Cheristry) -- 5 5 CH 507D 1 Seminar Nuclear Radiation -- 2 --
*CH 528 4 Activation Analysis -- 5 --
Other Courses
* / 2 Field Practices in Radiation Protection --
1 1
**G 503 1-15 Thesis (Geology) 7 7 7
**G 582 3 Geochronology and Isotope Geochemistry ) -- --
j
**0C 503 1-15 Thesis Oceano aphy) 1 1 1
**PH S03 Thesis Physic 2 2 2
*0STR used occasionally for demonstration ond/pr experiments
**0STR used heavily I
i
I III-22 ] F. Instrtment Repair and Calibration Facility J
?
- 1. Description The Radiatio.1 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, pamma and neutron radiation, and encompresses both j high range instruments for measuring intense radiation fields ] and low range instruments used to measure environmental levels j of rad'ioactivity. The Center's instrument calibration capability l is described more completely in Section VI.C.7 of thfs report. )
- 2. Utilization {
The Center's instrument repair and calibration facility is used regulat?y thrcugh each year and is absolutely essential to the continued operaticn of the many different programs carried aut at the Center. In addition, the absence of any comparable facility in the state of Oregon is leading to a greatly expanded calibration program for the Center, including calibration of essentially all radiation detection instruments on the OSU campus, plus instruments from Oregon Health Sciences University, the Oregan Health Division's Radiation Control Section, the U.S. Environmental Protection Agency, the U.S. Bureau of Mines, and others. Additional information l regarding instrument repair and calibration efforts, and the growth of this activity s g1ven in Tables VI.C.4 and VI.C.5. l l l l l
-A
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1 '
' ' 112-23 i
] ?
J LG. Libraries j f 1, -Description- i
,; )
n ~ The Radiation Center nas libraries containing significant collections
. 'j of-texts, research-reports, and videotapes relating to nuclear da
' science land engineering, and radiation protection. j
.I 1
-The Radiation' Center is also a regular recipient of publications i 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 j documentation in the nuclear field. In addition,.the Center has.
a collection of over 50 sets of nuclear power reactor safety analy-sis and environmental reports specifically prepared by utilities for their facilities.
.1 The Center maintains an up-to-date set of reports of such organiza-tions as the International Commission on Radiological Protection, the National Council on Radiation Protection and Measurements,- l and the International Commission.on Radiological Units, and also keeps sets of the current U.S. Codie of Federal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation and other appropriate federal and state regulatory agencies. '
i The Radiation Center videot&pe library has over one hundred tapes' , i on nuclear ergiceerNg, radiation protection and radiological j emergency response. In addition, the Radiation Center uses video- 1 tapes for most of the technical orien'tations 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 ard the assistance [ of the OSU Communications Media Center. i
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\ :q . 111-24
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C 1-w ~ 2. Utilization. , I
.f Radiation Center' libraries are.used.mainly for reference on an- ,
l h,' as-needed basis; however..they receive extensive use during the' academic year. In addition, the orientation videotapes are usad. ) intensively during the beginning _of each term, and perio'dically , f
' tj u therenfter. \
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I PART IV REACTOR - A. Operating Statistics For the current reporting period, the operating statistics for the OSTR showed an increase in each of the major categories when compared
=to the previous period. -Operating data by individual category are given in Tables IV. A.1 and IV. A.2, and in Figure IV.A.1. Table IV.A.3 is included for reference and summarizes the operating statistics !
for the original 20% enriched fuel. I The thermal energy generated in the reactor during this reporting ! period was 41.7 MWD. The cumulative thermal energy generated by the FLIP core now totals 401.5 MWD from August 1, 1976 through June 30, j 1988. Reactor use time averaged approximately 91% of the normal nine-hour, five-day per week schedule. Tables IV.A.3 through IV. A.6 detail the operating statistics applicable to this reporting period. Excess reactivity increased approximately 604 during the current re-porting period. This change was caused by several facters including:
- 1. Removal of the cadmium-lined pneumatic transfer facility (increased
. reactivity).
- 2. Removal of the water container in beam port #4 which had been used to increase the flux in beam port #3 (increased reactivity). l
- 3. Removal of two deformed fuel elements (decreased reactivity).
- 4. Fuel burnup (decreased reactivity).
- 5. Consumption of the erbium burnable poison in the fuel (increased reactivity).
i J
4 5 _ 8 h 8 4 5 g _ L uN oU 8 6 9 9 4 0 7 _ U 0 4 3 4 0 0 J hrJ 2 9 9 4 1 1- T 0 . 3 e - r o c 3 4 8 h 8 3 3 l g e L uN 5 3 9 9 9 0 9 u U oU 0 4 3 4 2 6 f J rJ 2 9 9 4 h 1 P 1 T 0 I 3 L F w e 2 3 n 8 h 8 8 6 g a L uN 5 1 8 8 0 0 6 U oU 9 3 3 4 9 9 h J rJ 0 9 8 3 t h 1 i 1 T 0 w 3 r
) o t
e c r 2 a o6 1 8 e C 8 8 h 6 4 r 9 gN l 1 L 2 9 1 2 3 1 3 e e U uU 9 9 4 5 7 0 u e J oJ 1 9 9 4 h F n r 1 t u 1 h 0 P J T 3 l I e L - u F f 6 e e7 0 1 r h 9 8 h 8 9 5 t 1 g y L uE 5 5 1 2 8 0 8 l 1 gt U oU 5 0 4 5 9 4 e n s J rJ 2 0 9 3 t i u h 1 1 e A. s g 1 T 0 l p V 3 U u m I ( A o e sd c l c o 0 o b i i 9 h 8 t a t r 7 g 8 8 T s e uN r i P t a r "t J oU rJ 5 7 1 7 3 2 9 2 2 5 0 2 7 d e t a h 8 5 5 3 r S e 1 T 0 o Y 3 g - n i n0 i 1 t h a e 8 9 t rh 7 h 7 n et g 6 4 o p L u N m O r U oU 8 5 0 3 8 2 9 o J rJ 5 5 1 1 1 2 e R f h 4 2 2 3 n T 1 T 0 o S 3 O r o f 7 8 6 7 h 7 7 g 6 9 9 L uN 1 U oU 9 6 0 5 1 0 5 J rJ 1 9 2 2 8 7 , h 8 4 4 3 6 1 T 0 2 3 y l u J
)
1 n 6 h ( o 7 g 7 u 7 5 1 9 4 1 5 4 n G o N 7 5 1 2 0 8 4 w U r U 8 4 4 o A h d T J t 1 u 0 h 3 s L s
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e o) u y U lF uAd t l r Hl o a u F e I q c a o a H D 0 F1 sv e a n rC gc 5 ( ft o fR e o o i f P it ni t t t t 3 2 t ar onm ee o n r t I ti a a e rmR ro e a L ar w w s sw ee ei h r F rc a a m ro bl r bt T e p e( p g e g e r a o uP mEo u ma u )' O O M M G H N N 1 ( i1l Ifl
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( 3 f U oU 5 0 4 5 8 2 7 J rJ 3 0 9 - 3 e h 1 1 n 1 T 0 o 3 t u b 7 d 6 h 8 ) e 8 g 4 9 l d uN i d L 2 3 1 1 0 7 a oU 7 9 4 5 8 O 8 U J rJ 1 9 9 3 e h 1 r 1 T 0 e 3 w s t
- n a d) i s e t s r
d e- dt m a s e ) ld( as e D u r s s lW ed re l e o) u y U l M uAd ru e . l r Hl o a u F e I q a o gc a H D 0 F1 sv e l n rC 5 ( ft o fR e o o ni t t 3 t ar onm o u i f P it t t 2 ee n f t I ti ar a a e rmR ro a r L F rc w a w a s m sw ro ee bl r ei bt N o e e( g e g a r uP mEo ma p p e o u u ) O O M M G H N N 1 (
o ri 6 h7 o c h rT 7 g 7 r o RuL ) o f oU 4 3 3 9 0 5 0 7 9 f : P 1 - 0 1 3 he A hrJ ( 1 5 2 2 2 h tt 3 t no 1 T6 2 n oN o m m e . 5 6 e ne 7 h7 5 n or g 3 o o R uR - r rc P oA 4 8 7 1 - 0 2 7 3 o A rM 9 0 1 2 6 5 4 o fl h 7 4 4 3 f e e 1 T1 6u 3 1 7f r 7 9 o 9 1P C 1 I 5 ,L l 4 n7 , 6F e 7 g 5 9 1 1 2 u 4 3 8 F R uR oA - e yl i P 3 1 3 6 - 1 2 6 3 n A hrM l J'u% A 6 2 1 1 9 9 8 u u G 5 3 2 3 1 J r 1 T1 I R 3 n nee wa T w wny d o o r 3 4 d da3 h7 3 c 7 g 4 9 7 t th d 9 9 5 u n RuR P oA 5 2 9 h . hi ut0 a 5 3 7 - 0 2 sg sws t A hrM 0 3 1 1 0 3 0 r i S 7 3 2 4 1 ri rr 1 T1
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cc rsp o t tl oie a 9 h7 0 na fhr t 6 g 5 5 1 ei T S 0 7 2 e LuR ) mt ei h t h g U rM 2 oA ( 7 8 5 7 9 0 3 1 9 l n n: t n J h 6 3 5 2 1 9 9 ei oe i 5 1 3 2 mt n t 1 T1 0s oi a 3 r 7a eN e ( n e p s o g O 7r .n 8 9 6 a r)a R 6 h6 7 7 6 9e omh g 1 y f ec T 4 2 3 t S L oU uN - 3
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( ii wpat rrd oue ye - cee pr d t r _ - t r t o5 u s nsu ad t e s d ) d i ds e eic hu n 7. J-ah r u s r s e s W l e ed at rs s wh c To sd0y Dc l k l) l i l i o u y U l lW ud re u r rdyu l r H) o a u0 uM FA I u P o o(lJ ane l H D U F5 F q t : t n nEr ga 5 2 1 fs fe f ce cWom o aM o o nc t t 3 t( t( ot e oR o at _ i%C ii t t 2 a a nr eo e sr t0 tt a a r r r o rn r RN R1if _ a2 r ai rr w w a a s m se rwuo se rw emC be bi eo b e _ er ec g g a uo ml o mt m ) ) po p( e e r oP oP uEt ua u 1 2 0f O M M G H H N N N ( ( _ l. il Il >! e
IV-5' u Table IV. A.4 Present OSTR Operating Statistics Annual Values Cumulative Values Operational Data for for for 1 JUL 87 1 AUG.76 FLIP Core Through Through 30 JUN 88 30 JUN 88
- 1. MWH of energy producec' 1,001 9,633
- 2. MWD of energy produced 41.7 401.5
- 3. Grams 2350 used 52.3 504.1
- 4. Number of fuel elements added to or removed from
(-) the core -2(1) 85 + 3 FFCR(2)
- 5. Number of pulses 37 1,130
- 6. Hours reactor critical 1,352 12.976
- 7. Hours at full power (1 MW) 987 9.337
- 8. Number of startup and shutdown checks 258 3,013
- 9. Number of irradiatjgg requests processed \01 373 4,710
- 10. Number of samples irradiated 3,569 55,938 (1) Two fuel elements were removed due to cladding deformation.
(2) Fuel Follower Control Rod. (3) Each irradiation request caula authorize from 1 to 120 samples. The number of samples per irradiation request averaged 9.5 during the current reporting period, i -__d _ _ ___
IV-6 y Table'IV.A.5 OSTR yse Time in Ters: of Operational Functions I Annual Values Cumulative Values-for for 1 JUL 87 1 AUG 76 Through Through 30 JUN 88 30 JUN 88 0STR Operational Function (hours) (hours) 1 Chetkout, core. excess 4,425 and shutdown 385 Reactor in use(l) 2,384 17,697
,-s -
Totici reactor use time 2,769 22,122 (1) Thic < function includes preclude time, multiple reactor experiment time, and the time the reactor is in.use for teaching but not neces-sarily operating. (Preclude time is the time the reat+or is not availeble for regular use due to performance of surveit '.ance and saaintenance items, such as fuel olement inspections, transient rod lubrication, control rod calibration, as tample loading and unloading time.) power calibration, as well i 1 l A- - - - - - - - - - , - - - - - - - - - _ _ - - - -- -
IV-7 Table IV.A.6 OSTR Use Time in Terms of Specific Use Categories Annual Values Cumulative Values for for OSTR Use Category 1 JUL 87 1 AUG 76 Through Through 30 JUN 88 30 JUN 88 (hours) (hours) ; Teaching (d9pgrtmental and others)U1 359 2,734 OSU research(2) 370 5,396 Off-campus research(2) 727 2,118 Forensic services 15 143(3) Reactor preclude time 899 7,408 Facility time (4) 388 4,144 Visitor demonstration (5) 11 121 1 Total reactor use time 2,769 22,064 (1) See Tables III.A.2 and III.E.1 for teaching statistics. ' (2) See Table III. A.3 for research statistics. (3) Prior to the 1981-1982 reporting period, forensic services were grouped under another use category. Since then, this service has been a 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 open-house (demonstration) events. The remainder of the visitors viewed the reactor during times when the reactor was being operated for regularly scheduled research and teaching. l
IV-8 Tatsle IV.A.7 OSTR Multiple Use Time (3) Annual Values Cumulative ~Yalues for. for Number of Users 1 JUL 87 1 AUG 76 Through Through 30 JUN 88 30 JUN 88 (hours) (hours) Two '138 1,000 Three 58 200 Four 43 77 Five 4 4 Six 8 8 ,
> Total multiple use time 251(2) 1,289(3)
(1) Multiple use time is that time when two or more irrad% tion requests are being concurrently fulfilled by operation of the reactor. (2)- This represents 19% of the. total hours the reactor was critical during this reporting period. (3) This represents 10% of the total hours the reactor was critical since startup with FLIP fuel in August of 1976. i
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^ * ' ' * ' cc N"* N M CJ 03 CO 03 CO 03 Coa) b *T-*'+'~'~' 1 N I f,.. .. $, ds,d .E E..E. A.4 4 4. .d,,a d @ @ th tb O @ tn th @ Ch +. _ . . . - - . 4, ) .d l y gy. --------- m-- --e . n , ,. , .,. -4 . .,... . . 6 1 i j - , . . .L..g _p .. .- . . . @ e .. .,5- g .. o. . . p, . - . . e . . a . 7,... . . . . . . . ,.(... 44 . ;.. ,7_ L., . ;_{ }1+.. ... ,. .. - u-, - n , O O o e @ ##3 W m o g i N - 1 CMW i _ ~ - - _ _ _ - _ _ _ _ _ __ _ l IV-10 B. Experiments Performed l During this reporting period there were 12 approved reactor experiments { available for use in reactor related programs. In February 1988, three exotriments (B-3, B-11, and B-12) were revised and one experiment (B-8) was deleted. The revisions are described in detail in section IV.D.3. For completeness, the following listing of reactor experiments by title includes both the old and new titles where they are different. Missing numbers signify reactor experiments which are in the inactive file and are not currently being used. \ A-1 Normal TRIGA Operation (No Sample Irradiation). B-3 1rradf ation of Materials in Assorted Matrices for Elements H to Bi inclusive, Plus Natural Th and U for Neutron Activation 2 Analysis. B-3 (Revised) Irradiation of Materials in the Standard OSTR 1rra-diation Facilities. Bo8 Isotope Production for Elements 1 Through 83 (H Through Bi) Excluding Cd. (Deleted in February 1938.) B-11 Nuclear Reaction Studies Using the Irradiation of Stable Elements to Produce Any Nuclide Farmed During the Neutron Irradiation of Natural Uraniu'n. B-11 (Revised) Irradiation of Materials Involving Specific Quantities of Uranium and Thorium in the Standard OSTR Irradiation Facilities. B-12 Exploratory Experiments to Investigate the TRICA's Capability to Achieve Certain Experimental Goals. (If the TRIGA can achieve the desired goals, a regular experiment is established,) B-12 (Revised) Exploratory Experiments. 8-21 Beam Port No. 3 Neutron Radiography Facility; Amendment No.1 to B-21; Neutron Holography. B-23 Studies using TRIGA Thermal Column. B-24 General Neutron Radiography. B-25 Neutron Flux Monitors. l IV-11 l i 8 29 Reactivity Worth of Fuel. B-30 NAA of Jet Diesel, cod Furnace Fuels. l B-31 TRIGA Flux Mapping. Of the approved experiments on the active list, ten were used during the reporting period. A tabulation of information relating to reactor cxperiment use is given in Table IV.B.1, .and includes a listing of the expertoents which were used, how oft 2n each was used, and the general purpose of the use. Footnote (2) to Table IV B.1 gives abbre-viated titles. Presently, 25 experiments are in the inactive file and could be reapproved for use if needed. I i l l l t I l i q, IV Table IV.B.1 Use of OSTR Reactor Experiments (l) ,9 lifetor Experi gt .. Facil(i,ty Number C Research
- Teaching Forensic . Time 31' , TOTAL A-1 11 40 0 106 157 B-3 145 21 3 0 170 B-8 24 9 0- 0 33 ,
B-11 6 0' 'O O 6 B-12 2 0 0- 0 2 B-21 1 0 0 0 1 P,- 23 0 2 0 0 2 B-24 0 0 0 0 0 J B-25 0 1 0 0 1 ! B-29 1 0 0 0 1 TOTAL 191 73 3 106 373 4 (1) This table displays the number of times reactor experiments were used for a particular purpose. ! (2) The following tabulation gives the reactor experiment number and its corresponding abbreviated title: A-1 Normal TRIGA Operation B-3 Irradiation of Materials in OSTR Facilities B-8 Isotope Production B-11 Irradiation of Materials Involving Uranium and Thorium B-12 Exploratory Experiments B-21 Beam Port #3 Neutron Radiography Facility B-23 Studies Using TRIGA Thermal Column B-24 General Neutron Radiography B-25 Neutron Flux Monitors B-09 Reactivity Worth of Fuel (3) See Table IV.A.6, footnote (4). 1 IV-13 l f i C. Ifnplanned Shutdowns There were seven unplanned shutdowns (scrams) during the current report-ing period. Table IV.C.1 contair s a tabulation of the unplanned shutdowns [ which occurred during regular reactor operations. I i l 1 r IV-14 Table IV.C.1 Unplanned Shutdowns (Scrams) Number of Type of Scram Occurrences Cause of Scram Safety Channel 3 Spuricus scram rignals. . No cause or reason could be deterfdned. These did not involve actual overpower situations. l Safety Channel 1 A Nuclear Engineering class was conducting f reactor behavior experiments. Reactivity ; was inserted as part of a square wave opera-tion to full power which resulted in the scram set point on tSe safety channel being re. ached. 9 Power Channel 1 The scram set point on the % power channel was reached when the reactor was approaching < full power with a full complement of samples l in the rotating rack. The flux perturbation caused by the full rack of samples resulted in lower readings on the linear and safc.ty { channels relative to the reading on the % 1 power channel, i Period 1 A Nuclear Engineering class was conducting a rod calibration experiment. A student operator insarted too much reactivity during l a rod pull and caused a low power, period ; scram. Manual 1 A leaking air hose supplying the ventilation ; system damper motor ccused the vant dampers to sag partly closed. The reactor building differential air pressure started to depart from normal conditions; therefore, the reactor operator scrammed the reactor. The damper air supply system was subsequently repaired. ! 1 . I l l - = - .1 IV-15i u i 4 i D. ,Cjhances to the OSTR Facility._ to Reactor Prr.edures o and to Reactor j ) ' Experiments, and Tgsts Performed Pursuant to 10 CFR 50.59 j The information contained in this section.of the report provides a summary of any changes and any tests perftJrmed during the reporting 'j L period under the provisions of 10 UR 50,53 , For each item listed, we have incheded a brief descriptiet) of the action taken and a summary 1 of the applicable safety evaluation. f
- 1. 10 CFR 50.59 Changes to the Reactor Facility l Thers were two changes.to Ltd reactor facility which were reviewed and performed under the provisions of 10 CFR 50.59 during the reporting perio11.
- a. Addition of Coilthread Inserts to the Thermal Column Graphite Stfingers ,
(1) Bescripticn 'f The thermal colusn graphite stringers were designed to be removed by screwing an extraction tool into a threac'ed hole and pulling out the stringer. Because graphite j is relatively _ soft, the threads in the stringers had been stripped over the years by repeated use of the ex- . traction tool. In order to remove a stringer from the thermal column..the extraction tool had to be wedged into the elongated and deformed hole and the stringer gently wcrked out. In order to facilitate removal of the strirgers and to prevent further deterioration of' the holes, it was decided to drill and retap the graphite, f and then screw in metal coilthread inserts. These inserts are manufactured in three diffprent materials: stainless steel, inconel, and bronze. After a safety evaluation and revilaw by the Reactor Operations Committee, bronze coilthreads were chos6n and inserted. i - - - - - . _ ~ - _ - - - - _ _ - . _ _ . _ - _ _ _ - - ~ L, ; o ,, - ,4 1 1 i-1 l lAe , , , IVi16- 4 1 (1 m 1 , a 1 q s . (2) _ Safety EYaluation O > The' coilthread inserts have greatly facilitated the removal ,; ' of the graphite thermal column stringers. They have'also l f:t 'i L L , -prevented any further erosion'of.the graphite holes.and hence l l reduced the potential for activated graphite contamination- ~ i ( on the reactor bay floor. Therefore, the. inserts have enhanced I safety. The handling of the graphite stringers in the' thermal. l column isinormally dictated by the gamma dose rates from ! the reactor core. This mecns that before insertion or removal of stringers the reactor typically has to'be shut down.long enough to allow the radioactivity in the fuel'to decay to. j acceptable levels. This length of; time-(t' ypically over a - weekend) is sufficiently long to ensure that the Cu-64 in - a the bronze inserts has decayed. Therefore, there is no sig-nificant: increase in hand exposure due to the'use of these .[ inserts. Indeed, the total doses to the hand may'be reduced because of the fact that the stringers can now be removed ' more rapidly.
- b. Addf tion of a New Air Flow Meter to the Stack Monitoring System (1) Description 1 The air flow meter which was originally supplied with the .,
OSTR stack monitor is located after the particulate ar.d gas ] monitoring chambers, but before the air pump. The OSTR staff suspected that the air-flow rate being Indicated by the orig-inal flow meter might not always be an accurate reflection of the air flow rate through the sampling line from the stack due to the fact that there could be small air leaks into the systm at gaskets and hose fittings. Clearly, it is- f important that the actual air flow rate through the sampling line be known and maintained at the proper rate in order to ensure that the sampling is isokinetic. Therefore, the ) staff decided to install an additional air flew meter immedi-ately upstream of the stack monitor which will indicate the actual air flow rate through-the sampling line. __ _ _ ___ _ ____. _ _ _ __] XV-17 (2) Safety Evaluation The addition of this extra air flow yneter enhances safety i by ensuring that there is isokinetic sampling of the reactor stack sffluent. This in turn will ensure an accurate collec-tion and assessment of any airborne particulate in the stack effluent stream. The second (original) air flow meter down- } stream of the monitoring chambers will continue to be used and will further enhance safety by giving an indication of any significant air leaks into the monitoring system. 2, 10 CFR 50.59 Changes to Reactor Procedures There was one change to reactor procedures which was reviewed and approved under 10 CFR 50.59 during the reporting period.
- a. Revision of the General Limitations on Experiments (1) Description J
The sample encapsulation requirements which are specified in the General Limitations on Experiments in OSTR Operating Procedure (OSTROP) 18 were revised. The overall format of the limitations document was also changed in an effort to clarify the currently approved methods of encapsulation and other limitations. This resulted in two sections dealing with encapsulation. The first section gives a table of the methods for sample encapsulation which have been found by testing and experience to be satisfactory. The second section presents the way in which other, non-specified methods of encapsulation may be approved. (2) Safety Evaluation All of the methods of encapsulation listed in the tablo in the General Limitations on Experiments are ones which have been: a) tested ano shown to be satisfactory, or b) previously reviewed and approved for use by the Reactor Supervisor and ,g ' u:, R ,','<a..< . ]J > cv . L, EM ' w, e IV-18. ..o , 497 7 , t [' , the-SeniorHealthlPhysicist. As a result; the current changes j merely involved writing down already approved encapsulation methods and rewriting existing material in a manner which , . l would.make it clearer. .This in turn will enhanceLsafety, '{ as encapsulation requirethents and other 1Mitations on experi-ments will -be more understandable and thus introduce less chance for error. {
- 3. *10 CFR 50.59 Changes to Reactor'Experirrents There were three changes to reactor experiments which were made during' this reporting' period. -
~
- a. Combination of Experiments B-3 and B-8 into a Revised Version fl of Experiment-B-3, ,.
(1) ' Description i- The 'old reactor experiments B-3 and .B-8 were essentially j identical except for the stated purpose of the irradiation.. Experiment B-3 was used for neutron activation analysis, and B-8 was.used for radioisotope production. After a review of'all of the reactor experiments it was recognized that these two experiments contained a great deal of duplication. 'i In. addition, it was also recognized that they did not specif-ically address irradiations in all of'the OSTR's available facilities. Therefore, it was decidert to combine the two experiments into a new B-3 which would allow irradiation s of a wide variety of sample materials'in any of the'0STR irradiation facilities without specifically mentioning the purpose of the irradiation. (2) Safety Evaluation ] Experiments B-3 and B-8 had been used safely for about 20 years. The new B-3 retained most of the original text, but eliminated duplication and references to the purpose of the l irradiation. These deletions in no way reduced the safety i 1 IV-19 l l of the revised experiment, because no safety requirements l were eliminated, and the reason why samples are being irradi-ated has no bearing on reactor and radiation safety. All ! of the original, as well as several additional experimental ll controls, are contained in the revised experiment description. The deletion of certain details relating to small cadmium covers in no way reduces safety because tests and the repeated use of such covers over 20 years of operation have shown that for all facilities (except for the sampleholding dunany element, which still requires an analysis) there is a negli-gible effect on reactivity. 1
- b. Revisien of Experiment B-11 j f
(1) Description The original B-11 experiment was written for a specific appli-cation involving the irradiation of natural uranium for nuclear I structure and recction studies. The experiment description { i included a number of very specific details with respect to the hn Ith physics aspects of the experiment. It was, there-fore, decided to rewrite B-11 to make it more general so that it could be used to accommodate irradiation of materials j containing small quantitites of uranium and/or thorium in f any of the standard OSTR irradiation facilities. The new j B-11 is complementary to the revised B-3. l i i (2) Safety Evaluation ( The health physics precautions and details in the previous l B-11 experiment are not incioded in the new B-11 because ) l they are now in a nember of standard Radiation Center docu- ! l 1 ments. The procedures in these documents are at least as j { stringent as those in the old B-11 and hence there is no j reduction in the 16 vel of safety as a result of this change. ) l The safety evaluation of experiment 8-3 is applicable to f i I i _ . - - . - - - - __- _ -- _ . _ _ - _ ___ J 1 , ~ 1 s I ' r i 'L IV-20 , , 4 L: h o this experiment because most of the standard paragraphs' with respect-to limitations are the same. The details of the safety analysis calculations which determined the limits. L in the-new B-11 experiment are included as Attachnent A to ! the experiment. There are two main considerations which < c. p limit the quantities of uranium and thorium which may be irradiated. These'are: a) the total radioactivity of iodine L isotopes 131 through 135, and b)'the heat generation from k the fission process. During' the isnalysis it was determined that the most limiting of these was the fission heat produc-tion and the resulting temperature rise. fi L From actual. experiments.it war, determined that polyethylene vials remain intact at 110 C and begin to nelt at 130'C with , l complete melting occurring at 150*C, In addition, it is known that the temperature in the OUTR rotating rack can reach 70 C. Therefore, the maximum quantity of uranium or thorium allowed in tamples encapsulated in polyethylene was limited to that which would result in a temperature rise ; I of 30 C using the' conservative assumptions outlined-in Attach-ment A to the experiment. '( Experiments with sealed quartz vials in aluminum TRIGA tubes showed no change in their condition even when heated up to ] 600'C. The melting point of aluminum is 660*C. Therefore, the maximum quantity of uranium or thorium allcwed in samples q encapsulated in quartz, which in turn is placed in aluminum tubes.was limited to that which would result in a temperature rise of 500 C using the assumptions outlined in Attachment A to the experiment. All of the assumptions used in the calculation of iodine inventory and fission heating are conservative, and it is l expected that actual inventories and temperature rises will ' j be much less than those calculated. l l l u_=___._______.___________ . _ _ _j r y' > < < . ,i 2 .\ l1 c- , . o , , . .. .. + ) IV-21 jy < s . [ r- + c. Revision.of; Experiment 0-12 l\ (1) Description ~ Experiment.B-12 was revised to make it consistent with the 'other general reactor experiments. Most of the changes merely ' , involved a change of wording to incorporate many of the stan-dard paragraphs used in the B-3 revision. The specific con- 'dttion' requiring approval. of exploratory programs t'y the Reactor Supervisor, tne Senior Health Physicist and the Chair. man'oftheReactorOperationscommittee(kOC)wasdeleted because of its inconsistency with other current procedures.- (2) Safety Esaluation Most of the wording changes were minor hnd did nbt change q the intent of the experiment. Other ch.snges' involved the , incorporation of many'of the standard paragraphs used in the revised B-3, and therefore the favorable safety Evaluation-for that experiment is'also applicable here., The deletion j of the con.iition requiring approval of exploratory programs m .bv the' Reactor Supervisor, the Senior Health Physicist and i the Chairman of the ROC will in no way reduce sefety because the experiment will either be one which meets all. of the~- 1 old requirete :s listed in the experiment, or it will have ! 'to be spec 16'?.y approved by the full ROC In addition, the Reactor Supervisor and the Seni n Health Physicist still j must approve any Irradiation Request submitted under this l - experiment, and therefore these individuals are not removed ,4 from the approval p'athway for experiments pe-formed under j the provisions of experiments B-12. , i l l l 4 t Y ' .IV-22 2 ,. lei Surveillance and Maintenance c ,
- 1. Non-Routine Maintenance 22 SEP 87 The moving-filter paper drive-motor was replaced on the stack ironitor.
15 0CT 87 Silicon sealer was put around the top of.the reactor tank flenge where it meets the concrete slab on-the top of the reactor to uinimize the probability of moisture getting between the tank and the concrete. 5 NOV 87 A new fission chamber was installed for the wide-range log-linear nuclear instrumentation. 14 DEC 37 Two in-r. ore fuel elements with deformed cladding were discovered and removed. 15 DEC 87 The in-core portion of the cadmium-lined pneumatic transfer facility termintis was removed from the reactor core. 11 JAN 88 Selected fuel el ment worths were measured. q 1 25 #N 88 Heliccil inserts were installed in the five therinal .! calymn graphite stringers. 18 FEB 38 The. fuel e~lement handling tool was shipped to the manufacturer for repairs. 29 FEB 8J The safety channel uncompensated ion chamber was re-plac'ad t,ecause the chamber in use did nct respond properly during a startup check. 4 APR 88 The f an bearings were replaced on cooling tower #2. 4 APR 88 An auxiliarv air flow gauge was instr.11ed on the stack monitor. 4 APR E3 The water cantainer was re%ved from beam port #4. 14 APR 88 The voltage regulator was replaced on the reactor top continuous air monitor. 7 JUN 88 The bearings were replaced on the primary coolant pump, and the 1Lbrication system for the primary pump bearings was changed from grease to oil. 27 JUN BS The safety channel sensitivity was adjusted by chsnging a circuit resistor. Ib23
- 2. Routine _ Surveillance and Mair.tenance The OSTR has an extensive routine surveillance and maintenance (S&M) program. Examples of typica) S&M checklists are presented in Figures IV E.1 through IV.E.4. Items marked with an asterisk
(*) are required by the OSTR Technical Specifications. f i
- 7. Reportable Occurrences _ ,
{ In a letter to the USNRC dated May 17, 1988, the OSU Radiation Center i reported an event involving OSTR procedures for checking the continuity and scram capabi';ity of percent power circuits. . Based on the nature of the event, it was not clear whether or not a formal report needed j to be filed, however, a report was submitted by OSU in order te maintain open communications with the NRC on such matters. l 4 l t / \ l l- , f l ..- .IV-24
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angNQ i&Tj .@Q lll.' n. yN;w;;'L $g h;y W:hl:- - WWQ:y . A O , ;W c.: QAQ f.f,.p:y&nnw$f..;i.;- ;.a: :v 4 Q f Q Q.. Q 1 t,1 w pl. l A +' Q4h k j h y Q py ! $Q}g}gggl&w&a Q .g.,y.G gRy& i. a &v . . .s3 ; q p$ ex< A qwan-w w ;r Mwg w.~.n.n e s w e s nu g.vg sm / w k m . . . a,/nan f , ... . . . wy .w ,.a ., I qq. gyQin gga g ,y g m . ,y ow awn%~ g 4. > r c . .. a., . c.4 ,[,jf ! v adT ,M rg[ _ $ D mM. [ , ,W $ _ $ j ;ffg$ k , e e n ,Ca <( n: {f . g - W; j , g.y. a n-y; ,~ 'n J . a 3 g 7 y p . l l PART V PROTECTION f l A. Introduction l This section of the report deals with the radiation protection program at the-0SU Radiation Center. The purpose of this program is to ensure the safe use of radiation and radioactive materials in the Center's teaching, research, and service activities, and in-a similar manner to ensure the fulfillment of all regulatory requirements of the state of Oregon, the U.S. Nuclear Regulatory Comission, and other regulatory agencies. The comprehensive nature of the program is shown in Table V.A.1, which lists the program's major radiation protection requirements and the performance frequency for each item. i The radiation protection program is implemented by a staff. consisting of a Senior Health Physicist, a Health Physicist, a Radiation Protection Technologist, and one to five part-time Radiation Protection Technicians (see Part II.F). Assistance is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director. The data contained in the follouing sections have been prepared to comply with the current requirements of Nuclear Regulatory Commission (NRC) Facility License No. R-106 (Docket No. 50-243) and the Technical Specifications contained in that license. The material has also been prepared in compliance with Oregon Department of Energy Rule No. 345-1 30-010, which requires an annual report of environmental effects due ] to research reactor operations. A summary of required data for the j OSTR is provided in Part I.E for quick reference., ) Within the scope of Oregon State University's radiation protection program, it is standard operating policy to maintain all releases of radioactivity to the unrestricted environment and all exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable" (ALARA). I I V-2 l Table V.A.1 Radiation Protection Requirements and Frequencies FREQUENCY RADIATION PROTECTION REQUIREMENT Daily / Weekly / Monthly Routine area' radiation / contamination monitoring. Wrekly Gamma spectroscopy of the (OSTR) continuous air monitor particulate filter. Monthly Routine response checks of radiation monitoring instruments. Monitor radiation levels (pR/hr) and read integrating dosimeters at the environ-mental monitoring stations. Collect and analyze 1RIGA primary, secondary, and make-up water. Exchange personnel dosimeters and inside area monitoring dosimeters and review exposure reports. Laboratory inspections. Emergency and safety equipment checks. Neutron generator and tritium assembly contamination survey. Calculate previous month's gaseous waste discharge. As Required Process and record solid and liquid waste discharges. Prepare and record radioactive material shipments. Survey and record incoming radioactive material receipts. Monitor and record special radiation surveys. , Perform thyroid and urinalysis bioassays. Conduct orientation and training. Issue radiation work permits and provide health physics coverage for maintenance operations. Quarterly Prepare, exchange and process environmental TLD packs. Collect and process environmental soil, water and vegetation samples. Orientation for classes using radioactive materials. Collect and analyze sample from reactor ventilation effluent line. Simi-Annual Leak test and inventory sealed sources. Floor survey of corridors and the reactor bay. Calibrate portable radiation monitoring instruments and personnel pocket ion chambers. Inventory and inspect Radiation Center equipment located at the Student Health Center. Corvallis fire Department Haz/ Mat van, and Good Samaritan Hospital. Annual Calibrate environmental integrating ion chambers. Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, water monitor, and air samplers. Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA filters as necessary. Inventory and inspect Radiation Center emergency equipment. Facility radiation survey of the cobalt-60 irradiator and X-ray machine. Personnel dosimeter training. V-3 +, B. Environmental Releases ] The annual reporting requirements in the OSTR Technical Specifications include the neac" for 'a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee, as measured at, or prior to, the point of-such release or discharge." The liquid and gaseous effluents released, and the solid waste generated and transferred are discussed briefly below. These effluents are also summarized in detail in the designated tables.
- 1. Liquid Effluents Released _
Whenever possible, liquid effluent is analyzed for radioactivity content at the time it is released to the collection point (a holdup tank). However, liquids are always analyzed for radioactivity before the holdup tank is discharged into the unrestricted area (the sanitary sewer system). For this reporting period, the Radiation Center and reactor made only two liquid effluent releases, both to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to these two releases are contained in Table V.B.1.
- 2. Airborne Effluents Released Airborne effluents are discussed in terms of the gaseous component and the part1culate component.
- a. Gaseous Effluents Gaseous effluents from the reactor facility are monitored by the reactor stcck effluent monitor. Monitoring is continuous l ('i.e., prior to, during, and after reactor operations). It l is normal for the reactor facility stack offluent monitor to begin operation as one of the first systems in the morninc and to cease operation as one of the last systems at the end of the day. AlI gaseous effluent data for this reporting period are summarized in Table V.B.2.
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- b. Particulate Effluents Particulate effluents from the reactor facility are also coni-tored by the reactor facility stack effluent monitor.
k' Evaluation of the detectable particulate radioactivity in the stack effluent confirmed its origin as naturally-occurring radon daughter products, within a range of approximately 1 x 10-9 pC1/cc to 3 x 10-11 uCi/cc. This par?.iculate radio-activity is predominantly lead-214 and bismuth-214, which is not associated with reactor operations. i There was no release of particulate effluents with a half-life { greater than 8 days and therefore the reporting of the average f concentration of radioactive particulate with half-lives j greater than eight days is not applicable. j
- 3. Solid Waste RelecLed Data for the radioactive material in the solid waste generated /
and transferred during this reporting period are summarized in Table V.B.3 for both the reactor facility and the Radiation Center. Solid radioactive waste is routinely transferred on::lte (within the Radiation Center building) to the OSU Radiation Safety Office. Until this waste is disposed of by the Radiation Safety Office, it is held along with other campus radioactive waste on the Uni-versityts state of Oregon radioactive materials license. Solid radioactive waste is disposed of by the University Radia-tion Safety Office by transfer to the University's radioactive waste disposal vendor, U.S. Ecology Company, for burial at their installation located near Richland, Washington. 1 } l 1 i V-7 ) Teble V.B.3 Annual Summary of Solid Waste Generated and Transferred l for the Year July 1, 1987 through June 30, 1988 q Volume of Total Quantity I Dates of f Solid Waste Detectable of Radioactivity Shipment to ! Origin of Packaged Radionuclides in Solid Waste U.S. Ecology i Solid WasW (Cubic Feet) in the Waste (Curies) Company 24-Sodium 46-Scandium 51-Chromium I 54-Manganese 58-Cobalt TRIGA 59-Iron ' Reactor 19 60-Cobalt 5.5 x 10-4 (1),(2) Facility 75-Selenium 82-Bromine 110m-Silver i 124-Antimony 131-' lodine 141-Cerium
- 154-Europium
? 46-Scandium Radiation 59-Iron Center 30 60-Cobalt 2.2 x 10-5 (1),(2) Laboratories 154-Europium 225-Radium 1 (1) .All Radiatior. Center and OSTR solid radioactive Waste is routinely transferred onsite (within the Radiation Center tsuilding) to the OSU Radiation Safety Office, where it is held on the University's State of Oregon radioactive materials license, along with other campus waste, prict to shipment to U.S. Ecology. (2) During the applicable reporting period, no shipacnts of solid radioactive waste were inade by the University's Radiation Safety Office to the U.S. Ecology Company. 3 _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ ~ _ - - - . . - - . - . _ _ _ . _ ~ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . _ - _ _ _ . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ - - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - - _ _ _ _ - - . - _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ r
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Vc8 i , C. Personnel Doses The OSTR annual reporting requirements include the need to present I a sumary of the radiation exposure received by facility personnel and visitors. For the purposes of this report the summm y has been expanded to include all Radiatioit Center personnel who may have received exposure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research per-sonnel, physical plant maintenance personnel, students in laboratory classes, security personnel, and visitors. Facility operating personnel include the reactor operations and health physics staff. The dosimeters used to monitor these individuals include monthly X-ray, beta, and gamma [Xs(G)] film badges, quarterly track-etch / albedo neutron dosimeters, either monthly or quarterly TLD (finger) extremity dosimeters, and pocket ion chambers. Key facility research personnel consist of Radiation Center staif, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or other research facilities present at the Centor. The individual dosimetry requirements for these per-sonnel will vary with the type of research being conducted, but will generally include a monthly or quarterly X8(G) film badge and TLD (finger) extremity dosimeters. If the possibility of neutron exposure exists, researchers are also monitored with a track-etch / albedo neutron dosimeter. Physical Plant maintenance personnel are normally issued a gamma sen-sitive pocket ion chamber as their basic monitoring device. A few Physical Plant personnel who routinely perform maintenance on mechanical or refrigeration equipment are issued a quarterly Xs(G) film badge and other dosimeters as appropriate for the work being performed. V-9 Students attending laboratory classes are issued quarterly Xs(G) film badges, TLD (finger) extremity dosimeters, and track-etch / albedo or l other neutron dosimeters, as appropriate. Students who attend a one time laboratory denionstration and do not handle radioactive materials are issued a gamma sensitive pocket ion chamber. OSU campus security and police personnel are issued a quarterly XB(G) film badge to be used during their patrols of the Radiation Center i and reactor facility. Visitorst depending on the locations visited, may be issued a gamma i sensitive pocket ion chamber. OSU Radiation Center policy does not normally allow people in the visitor category to become actively in- i volved in the use or handling of radioactive materials. ! An annual summary of the radiation doses received by each of the above six groups is shown in Table V.C.1. There were no personnel radiation exposures in excess of the limits in 10 CFR 20 during the reporting period. V-10 Table V.C.1 Annual Summary of Personnel Radiation Doses Received For the Year July 1, 1987 through June 30, 1988 E Average Annual Greatest Individual Total Person-mrem Dose (1) Dose (1) For the Group (1) l , l Whole Wholo Whole Personnel Group. Body Extremities Body Extremities Body Extremities (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) ~ 1 ! Facility Operating 39 77 340 460 705 1390 Personnel Key Facility Research <1 0 15 0 15 0 Personnel Physical Plant Maintenance <1 N/A 8 N/A 51 N/A Personnel Laboratory Class 0 4 0 70 0 210 . Students ! Campus Security and Police 0 N/A 0 N/A 0 N/A Personnel , Visitors <1 N/A 9 N/A 129 N/A 1 (1) "0" indicates that each of the beta-gamma dosimeters during the reporting period were less than the vendor't, gamma dose reporting threshold of 10 mrem or that each of the neutron dosimeters were less than the vendor's threshold of 30 :nrem, as applicable. "N/A" indicates that there was no extremity monitoring conducted or required for the group. l l l l l I l l 1 4 .+ I V-11 3 l J D X Facility. Survey Data The OSTR Technical Specifications require an annual summary of the q radiation levels and levels of contamination observed during routine surveys performed at the facility. However, the Center's comprehensive area radiation monitoring program encompasses the Radiation Center y as well as the OS'TR, and therefore monitoring results for both facil-ities are reported.
- 1. Area _ Radiation Dosim_eters j Area monitoring dosimeters capable of integrating the radiation .
dose are locgte:t et strategic positions throughout the reactor facility cnd Radiatior. Center. All of these dosimeters contain at least a standard personnel-type beta-gamma film pack. In addition, for key locations in the reactor facility and for certain Radiation Center laboratories a CR-39 plastic track-etch neutron detector has also been included in th9 monitoring package. Figure V.D.1 shows the locations of the dosimeters in the reactor building i and Radiation Center. The total dose equivalent recorded on the various reactor facility dosimeters ~is listed in Table Y.D.1 and the total dose equivalent recorded on the Radiation Center area dosimeters is listed in Teble V.D.2. Gqnerally, the cnaracters following the MRC (Monitor kadistion Center) designator show the roc i number or location. The highest r'ecorded dose equivalent was measured in B119A,-the shielded sealed source storage room (siut Cell), but even the level recorded at this location corresponds te an average dose rate of less than one millirem per hour. This room is occupied only briefly on ar. irregular basis whils, obtaining or returning sealed sources. l V-12 j l Figure V.D.1 1 TRIGA Facility and Radiation Center Area Dosimeter Locatiens l MRCTWM MRCTEN Reactor Facility 3rd Floor I l Reactor facility 2nd Floor " V y ECTTOP ' MCDE g D.MRCTW [ a 0104 Reactor ~ D104 Reactor f - Re c or I E e i V Bay '. = () Eay l j \! I 'i [ M CTSW MRCTSE d l 3 hC - l NtCD-200 h ;$ 30 MRCD-300d EE T :: E 8 == 1 j i HRCD-101 p
- a > == l 0204 . CZ : k -
- g d - . l 1,202 D200 -m lD106 F D10'2 D104 I - - >
l l D206 , ~"~A f . MRCB-I t91 A TmEit mg l D104 Reactor Bay - MRCBRR y ' y I i, " [B123 LC C1231 Reactor Facility 4th Floor E norin
- 12' l I MRG-119-1 7~~dingDock Toa u B119 f lB121 A C122 U l I
N Y N j 4,tRCB-12C 'RCC ,23SI D409 0400A f ~" E E l iA13 4 '-' ~ l L m)l} .sa - Y um , A130 Y 4132 NRCB-124-61 [ggi l MRCH24-N[ 0 22-3 A-, C MRCB. 4 AMRCB-1; 2-2 C121 , V ] 3CA-134- MRCB-114 , lB126A MRCC-124 E130 MRCA-126] j l C;24 A134 B114 _,,B1268 C-120 j , f es % l ; j q Y D E102
- l gggg l>MRCC-126" A136 B108 B128 C126
, A124 C120 1 ; E104 E124 ]$, 4tCC 1194 R106 l B130 C128 E122 l - - ~ - - " A140 E10i( 6tCB-13g A142 B132 ', C130 y -- t004 - l E10' --. I < < g g C118 CII'2A i. p A120C g I 4 A144 E302 B134 C132 P o *--- I e C11a, E112 E114 ; 'fA120{- A ECA-14N {k B-100-C114 , A120A _C134JbC108 L"3 l A116 - k A1 ,44 . . 6100 _ B.136. . m 4 % . - . _ _ 7. A . . ,_ 3 '3 gv A xs(c)rn. 8' 8 s u o m pa ).3 N g ! d XB(G) Film Plus j e = = = ac we S S o v v v *hg Track Etch Heutron ' j ! l l l l V-13 1 u i Tchle V.'0 1 I i Total Dose Eq~aivalent Recorded on .orea Dosimeters tocated .i Withir, the TRIGE Leactor Fad City for the Year 1 July 1, ISB7 through June 30, 1988 ] _. - = . Tott1 Recorded TRIGA Rcactor Dose Equivalent (1)(3) Monitor Facility location XB(G) NeutrorF I.D. (See Figure V.D.1) -(mrem) (mrem) { MRCTNE D104 Novth Dadge East Wall 0 0 J I HRCTSE D104 South Badge East Wall 0 0 MRCTSW D104 South Bad:e West W611 30 0 MRCTNW D104 North Badge West Wall 75 0 MRCTWN 0104 West Badge North Wall 0 0 MRCTEN D104 East Btdge North Wall 130 100(5) HECTES D104 East Badge South Wall 190 0 MRCTWS D104 West Badge South Wall 300 460(4) MRCTTOP D104 React 9r Top Badge 335 0 ) HRCTflXS C104A South Badge HX Room 305 0 MRCTHXW D104A West Badge HX Room , O G MRCD-302 D302 Reactor Control Room 155 0 MRCD-302A D302A Reactor Supervisor's Office 15 (2) N/A I (1) The total recorded dose equivalent values do not include natural background contribution and, except as noted, reflect the summation of the results of 12 J monthly beta-gamma dosimeters or four quarterly fast neutron dosimeters fcr each location. A total dose equivalent of "0" indicates that each of the beta-gamma dosimeters dJrtng the reporting period was less than the vendor's gamma dose. reporting threshold of 10 mrem or tha'c each of the fast neutron dosimeters was less than the vendor's threshold of 50 to 100 mrem, as applicable. "N/A" indicates that there was no neutron monitor at that location. (2) The total dose equivalent reflects the summation of four quarterly beta-gamms l dosimeters. (3) These dose equivalent values do not represent radiation exposure through an exterior wali directly into an unrestricted area. (4) This value was reported by our dosimetry r,gpfler, Radiation Detection Co., but is not supported by raoiation survey e asurements performed by our health physics staf f concurrert with the experiment. Based on Radiation Center neu-tron measurements and the duration of the experiment, the expected neutron dose , equivalent at this location is estimated to have an upper lim (t of 10 mrom. (5) There was no work involving neutron radiation near this dosimeter during the interval of time corresponding to the reported dose. In addition, monitor MRC?NE, j which is directly 8djacent to monitor MRCTEN, showed ne detectable neutron dose. I 3 R < Table V.D.2' .V-14f 4 s ET ctal' Dose Equivalent Recorded on Arca Dosimeters , l 0 Located Within the Radiation Center for the Year l , July 1, 1987 through Jdne 30, 1988 J - 1 L, Total Recorded- 1 ll Radiation Center DoseLEquiu lent (1) .]
- - konitor Facility Location f5TGT L
-Neutron t -] I.D. (See Figure V.D 1) (mrom) (mrem) ) .MRCA-100 Receptionist's Office 0(2)- N/A MRCA-126 0 (2) puCoIrradiatorRoommpus RSO's Radioisotope Receiving Lab , N/A ~MRCCO-60 ' 100 (2) 1 'N/A-' ; MRC300XRAY ! X-Ray Console Foom O'(2). .N/A j MRCA-134-2 NAA:Research . 110-(2) N/A MRCA-146- Gamma Analyzer Roc'm (Storage Cave) 105 N/A- l" MRCB-100 Gaana A 185 N/A l HRCB-114 a' tab (ggyzerRoom(Stor-ageCave) ' 9.a Storage Facility) 1610 O' "NRCB-116-1 RS0's RAM Waste krocessing Facility 65 (2) N/A1 -i MRCB-116-2 R50's RAM Waste Facility Compactor Room 185 (2) N/A >j MRC-B-119 Sc'urce Storage Room 0(2) , N/A q-MRCB-119A Sealed Source Storage Room 3270 3850 0(2) MRCB-120 Instruent Calibration Facility N/A 'MRCB-122-2 Radioisotope Storage Hood. 980(2) N/A-MRCB-122-3 Radioisotope Retearch Laboratorj 0 (2) N/A f i4RCB-124-1 ' Radioisotope Research Laboratory (Hood) 50 (2) N/A ! HRCB-124-2 Radioisotope Research Laboratory 0 (2) N/A J MRCB-124-6 Radioisotope Research Laboratory 0 (2) N/A. MRCB-128 Instrument Repair Shop 0 (2) N/A , MRCB-132 Radioisotope Research Laboratory 130 (2) N/A i MRCC-100 Director's Office 0 (2) N/A ! MRCC-118 Radio-Chemistry Laboratory 0 (2) N/A MRCC-120 Student Counting Laboratory 0 (2) N/A MRCC-123N Gamma Analyzer Room (Storage Cave) 260 (2) N/A' MRCC-123S Gamma Analyzer Room 55(2) N/A MRCC-124 Studcat Computer Laboratory 0 (2) N/A MRCC-126 Student Counting Laboratory 0 (2) N/A MRCC-130 Radioisotope Labbratory 0 (2) N/A MRCC-134 Gamma Analyzer Boom (Storage Cave) 15 N/A MRCD-102 Pneumatic Transfer Terminal Leberatory 75 N/A MRCD-102-H 1st Floor Corridor 0 D102 0 0 M3CD-105-H 1st Floor Corridor 0 D106 145 N/A MRCD-200 Senior Health Physicist's Office 55 (2) N/A MRCD-204-H 2nd Floor Corridor 0 D204 0 0 MRCD-300 3rd Floor Conference Room . 0 120(3) HRCBRF Front Personnel Dosimetry Storage Rack 0 (2) N/A MRCBRR Rear Personnel Dosimetry Storage Rack 0 (2) N/A l - _ j (1) The total recorded cose equivalent values do not include natural background contribution and, except as noted, reflect the summation cf the results of 12 monthly beta-gamma dosimeters or four quarterly fast neutron dosimeters for enh location. A total dose equivalent of "0" indicates that each of the beta-gamma dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of.50 to 100 mrem, as applicable. "N/A" indicates that there was no neutron monitor at that location. (2) The total dose equivalent reflacts the summation of four quarterly beta-gamma dosimeters. (3) There was no work involving neutron radiation near this dosimeter at any time during the reporting period. In addition, Monitor MRC D-302 (Table V,0.1), , which is near nenitor MRC D-300, showed no neutron dose. 1 J V-IS,
- 2. Routine Radiation end Contamination Suryeys The Center's program for routine radiation and contamination surveys consists of d&ily, weekly and mor.thly inessurements throughout the TRIGA reactor facility'and Radiation Center- The frequency 4
arr ed o t a art ar 1 t o on e f tr ch indicate that'surveillar.ce over a specific area at a dcfined tre-quency is desirable. I The primary purpose of'the routine radiation and contamination 8 survey program is to assure regularly scheduled surveillance over selected work areas in th 'eactor facility and in the Radiation Cer3ter, in order to provide current ard characteristic data on the status of' radiological conditions. A second objective of the program is to assure frequent on-the-spot personal observations , (along with recorded data), which will provido advance warning , of needed corrections and thereby help to ensure the safe use and handling of radi6 tion sources and radioactive inatorials. A third objective, which is really derived from successful execution of the firrt two objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection programs are in line with.the goal of keeping 811 radiation doses to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA) The annual tummary of radiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.D.3. ; l l c , 1 l 1 V-16 Table V.D.3 Annual Surecry of Radiation Levels and Contaminatici, Leve'Is Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys for the Year July 1, 1987 through June 30, 1988 Contamination I WSole Body I Radiation Levels Levels (1) (mrem /hr) (dpm/100 cm2) Accessible Location Average Naximum Average Maxim'en (See Figure V.D.1) TR1G_A Reactor Facility: l Reactor Top (0104)- 1 125 (500 1786(2) I <500 Reactor 2nd Deck Area (0104) B 61 <500 l <1 100 <500 <500 ) General Reactor Room (0104) <500 <500 Beam Port Facilities (D104) <1 <$ 5 <500 Sample Handling Area (0104) <1 100 <500 Class Experiments (0104,0302) <1 2 <500 <500 Demineralized Tanb - Outside Shielding (0104A) <1 8 <500 <500 Particulate Filter-- <500 Outside Shielding (0104A) <1 1 <500 ; Radiation Center: NAA Counting Rooms (A146,B100,C134) <1 3 <500 <500 Health Physics Laboratory <1 <1 <500 <500 60(A138) C0 Irradiator Room (Al28) <1 3 <500 <500 Radiation Research Labs (8114,B122,8124,B132,C130) <1 8 <500 <600 Radioactive Source Storage j <1 22 <500 <S00 i (B119A) Student Chemistry Laboratory f <1 1 <500 <500 , (C118) l Student Countieg Laboratories (C120,C126) <1 1 <500 <500 Operations Counting Room <1 <1 <500 <500 (C123) Pneumatic Transfer Laboratory <1 4 <500 <500 (0102) l .I (1) <500 dpm/100 cm2 = Less than the lower limit of detection for the port 6ble survey instrument used. (2) The contamination shown for this location assumes 100% smearing efficiency and es immediately removed. As a result, the average contamination level at this location dy, ring the reporting period was, for all practical purposes, <500 dpm per 100 cmc . + T . ;c ' v .- , ,g i , y.17 L o , 1 .E. Environmental' Survey Data, i The' annual ~ reporting. requirements'of the OSTR: Technical Specifications include "an annual summary of environmental surveys performed outside the facility." l .l
- 1. ' Gasinma' Radiation Monitorina
- a. On-site Monitoring l
Monitors used in the on-site gamma environmental radiation 'I monitoring program at the Radiation Center consist of the reactor. facility stack effluent monitor described in sectf on - Y.B22 and nine environmental monitoring stations located on s -l the fence surrounding the reactor. facility (s'ee Figure V.E.1). . .? These stations consist of a standard metal mailbox attached { to the fence at a height of four feet. ]i l Each fence environmental statior, is equipped with an 030 supplied , ] and processed TLD area monitor (normally three Harshaw 7LiF l TL0b700 chips per monitof in a plastic " LEG 0" mount). These f monitors are exchanged and processed quarterly. The' total number of TLD samples for the reporting period was 108 (9 j stations x 3 chips per station per quarter x 4 quarters per l year). A summary of this TLD da ca is shown in Table V.E.1. ] l Each fence environmental station also utilized.a-CaSO4 TLD- '] monitoring packet supplied and processed by Radiation Detection Company (R.D. Co.), Sunnyvale, California. Each P..D. Co. j packet contained two CaSO4 TL0s and was P.xchanged quarterly { for a total of 72 samples during the reporting period (9 statfons f x 2 TLDs per station per quarter x 4 quarters per year). ) A summary of Radiatien Detection Company's TLD data is also - shown in Table V.E.1. i I, l 1 V-18 1 . Monthly measurements of the direct gama exposure rate, in -microroentgens per hour .(pR/hr), were also made at each fence l monitoring station. These measurements were made with an I Ebarline Instrument Company micro-R per hour survey meter containing a 1" x 1" Nal detector. t i 1 A total of 108 pR/hr measurements were taken (9 stations per mo1th x 12 months per year). The total calculated dose equivalent ' was determincd by averaging the 12 separate pR/hr measurements, inultiplying this average by 8760 hours per year, and then I by converting microroentgens to millirem. A summary of this data is shown in Table V.E.1. l In addition to the dosimeters previously mentioned, each fence environmental monitoring station also c0ntains, two, O to 200 l mil 11 roentgen, gamma-sensitive integrating ionization chambers {self-reading pocket dositaeter type). These ionization chambers are read every month, but are used only as backep monitors for each ttation. j l From Table V.E.1 we have concluded that the doses recorded , by the dosimeters on the TRIGA facility fence can be attributed to natural backgrou'1d radiation, whicn is about 110 mrem per . year for Oregon (Refs. 1, 2). j b, Off-site Monitoring The off-site g&iama environmental rediition monitoring program consists of cwenty monitoring stations surrounding the Radiation ) Center (see Figure V.E.2) and one station located 5 miles i to the south at the Corvallis Airport. Each off-site radiation monitoring stetion is equipped with an 05U supplied and processed TLD monitor. Each monitor con-sists of three (MRCTE-11 has sir) Harshaw 7 tiF TLD-700 chips in a plastic " LEG 0" mount. The mount is sealed it, a PVC tiabe 1 Figure V.E.1 Area Radiation Monitor Locations for the i TRIGA Reactor, and en the TRIGA Reactor Area Fence -) 1 N- 1 PERIMETER FENCE _ l \ _ j i : e e 1 ^ i i e MRC FE3 MRC FE2 ! 0FFICE - l l BUILDING S MRC FE4 MRC FE19 F <? . c 3 MRC TSE F-( MRCTNE e e R A DI ATION l '.l MR6 TEN g TRIGA 1 REACTOR- CENTER BAY BUILDIN G L i MRCTWN $ MRCTSW e e - j- /. HX $ MRC TNW MRC THXS e-g ROOM MRC THXW $ MRC FE5 ^ [ L10U1D gInp- R . A .WA ST E ~ HOLD UP TANK I l \ l MRC FE6 ' - l k- \ l l TRANSFORMER MRCFE99 l 5TA1l0N MRC FE7 MRC FE8 e e 0 50ft l l 4 V-20 o Table.V E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence for the Year July 1, 1987 through June 30, 1988 Total Calculated Dose Equivalent Fence Based on the Environmental Total Recorded Total Recorded Annual Average Monitoring Dose Equivalent -Dose Equivalent pR/hr Station Eased on R.D. Co. Based on OSU ' Exposure Rate (See TLDs (1) TLDs (2)(3) (3) ' Figure V.E.1) (mrem) (mrem) (mrem) 'MRCFE-1 79 91 1 8 83 2 17 > ! MRCFE-2 110 91 5 87 25 MRCFE-3 105 99 1 8 83 26 MRCFE-4 116 98 i 5 84133 MRCFE-5 101 96 2 3 73 1 26 MRCFE-6 103 91 7 85 39 , MRCFE-7 104 93 10 82 t 29 MRCFE-8 101 88 7 75026 MRCFE-9 102 94 t 10 74 22 (1) Radiation Detection Comptny R.D. Co. TLD totals include their annual natural background contribution of 90 mrem for the reporting period. Average Corvallis , area natural background using Radiation Detection Company TLDs totals 97 i mrem for the same period. (2) 050 fence totals include a measured natural background contribution of 90 1 3 mrem. (3) values represent the standard deviation of the total value at the 95% confidence level. I l j i 1 i l 1 l m____. - _ _ _ _ _ _ _ _ _ _ - V-21 Fiaure V.E.2 .Monitaring Stations for the 050'TRIGA Reactor , For the Year July 1,1987 through June 30. 1988 co ,a N , CC Q C. D' & m a W >=h a DCd3OhG u, :nr- m OUo n. d* C $ A [aq ; . 7t u , N ,0 $ .! . . l O O j /. g of . JL > i 'X 2 " j u orcure f ldlG~ k- J / 5". '" I _r gJ h 0y 2, .(t ,p Q(( = Wk&"YU$51NY A 0 "A bY% Jn S w @c ri g,j;e;g _ gen?@ u - -a. n . N N l w&,e ;. m8 g 3 gp ;; T sp/ [ hey.e g 4* s - - - 7- bFhk q ,
- m. e j
j ItYrs d, ; i l II i ?h g . L gos,,,,,,,,use eg...3, gj 4 y,,$t a,. 3g[ggw _- .. .Q _~ F. q p Il ue,,c,,, 3 9,b L'" i
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&!-@, oaerreenn nyaoe-wed tt 3 c.s i j 7 sp* k f.! Y " o 'i Forestry xtence to. fusnAh 3s O .n >..., usi .. ~ D e La h ***h'etera r w. .e uina e n. A. . . m a ,~ . i . 3. 1. .Mi.n 1 't. o House ))W%isl_A.dL..~{ m e b up- 1, ". W? N ft p L ,, s W l,,gn .*EN t ~ '#~' l.
- pryden ut E- seooder mue m 4Q FPhys. Ptent stee.,e g 8
-) g , u r% .? ,,%.,..f m . [.'Cvet AA rerch p' Gbp,?. .w ,. < ..h'h.{c,.iu.nreo.,t. 5~,- . ,. , .. .r, e to a,. i 3.. . . 3 N~ ,. '~ '- gn to loc.ted --- ~ ~ -* %** { r .,= "' u mn,..u.; ,f I l ""*"'" '""" b i . Wd -- r 8/('. g,7-cor..n i. . .n s .n e. o.i c,... iouth ef the e.41.tton center g 3 , 0 Q . -f 1,2 h 3._ p . .. . n. :. , .. a, ts .k ,, 5 sig t N Y l h b *i,}* m. D Q ;:$' .- h } Gama g Grass ,,, 5 Soil %RE * * - - , W Water ' 0 100 200 300 RW Rainwater L1 _ _ _ _ _.__. _ _ _ _ _ 1-22 l which is taped to the station's post about four feet above the ground. These monitors are exchanged and processed quar-terly, and the total number of TLD samples during the current 1 year reporting period was 226 (20 stations x 3 chips psr station per querter x 4 quarters per year plus 1 station x 6 chips per station per quarter x 4 quarters per year). A : sumr.ary of the OSU off-site TLD data is provided in Table V.E.2. - Thirteen of the off-site radiation monitoring stations also have a tMn weather-tight aiuminum box munted to the post at approximately four feet above the ground (these stations do not have an "L" at the end of the station identification number). The aluminun: box contains a packet wn.h two CaSO4 TLDs supplied and processed quarterly by the Raciation Detection Company. The total number of R.D. Co. TLD samples for the raporting period was 104 (13 stations x 2 TLDs per station l per quarter x 4 quarters per year). A summary of Radiation l Detection Company's TLD data for the of f-site monitoring sta- l tions is alsc given in Table V.E.2. l Each of the thirteen monitoring statioiis with an aluminum box alt,o contains two O to 200 milliroentgen, gamma-sensitive, integrating ionization chambers (seif-reading pocket dosimeter type). These ionization enambers are read every math and are used only as backup monitors for each station. Data from these devices are not included in this report. In a manner similar to that described for the on-site fence stations, monthly measurements of the direct gamma exposure rate in microroentgens per hour ( R/hr) ere cade at each of the twenty-one off-site radiation monitoring stations. As 1 noted before, these measurements are made with an Eberline Instrument Company micrc-R per hour survey meter containing a 1" x 1" Nal detector. A total of 252 pK/hr measurements were made during the reporting period (21 stations per month i l l _ _. _ ___ _-. _ _U V-23 1 x 12 months per. year). The total dose equivalent for each , j st: tion was determined by averaging the 12 separate pR/hr, j measurements, multiplying this average by 8760 heyrs' per ' year, l and then by converting microroentgens' to millirem. A sumnary of this data is given in Table V.E.2. ., After a review of the data in Table V.E.2, we have concluded that, like the dosimeters on the TRIGA facility fence, til of the dose.s recorded by the off-site dosimeters can be at-tributed to natural background radiation, whic~n is about 110 ] rtrem per year for Oregon (Refs. 1, 2).
- 2. Toil Water, and Vegetation Surveys The soil, water and vegetation . monitoring program consists of the collection and analysis of a limited number of samples in each category on a quarterly basis. The program monitors any possible radioactive material releases from either the TRIGA reactor facility or the OSU Radiation Center, and also helps indicate the general trend of the radioactivity concentration in each of the various substances sampled. See Figure V.E.2 for the locations of the sampling stations for grass (G), soil (S), water (W) and rainwater (RW) campies. Most locations are within a 1000 foot radies of reactor facility and the Radiation Center. In general, simples are collected over a local area having a radius of about ten feet at the positions indicated in Figure V E.2.
There are a toth1 of 22 quarterly sampling locations; four soil locations, four water locations (when water is available), and fourteen vegetation locations. The total number of camples possible during the reporting period is 88 (16 soil samples,16 water samples, i and 56 vegetation samples). 1 The annual average concentration of total net beta radioactivity (minus tritium) for samples collected at each environmental soil, water, and vegetotion sampling location (sampling station) is I L a I [ - < L .)' , V-24 . ,u Table'V.E,2 O'. .. Total Dose Equivalent at the .- x Off-Site' Gamma Radiation Monitoring Stations , for the Year. July?l,1987 through June 30. 1988 1 ' i . Total [Calcu' lated T , 100se Eq'uivalent V O J.-Off-si ce v , Based 'on. the m Radiation I TotcLRecerded . Total Recorded Annual' Average; Monitoring Dose Equivalent Dose Equivalent- _pR/hr-Station (l') Based on R.D. Co. Based on OSU- Exposure Rate (See Figure .TLDs (2) TLDs (3)(4) (4) 'V.E.2) ~(mrem) (mrem) (mrem) NRCTE-2L ---- 82 1 6 59 1 15 MRCTE-3 107 96 i 9- 86 i 18 MRCTE-4' 100- 89 i 5 74120 MRCTE-5L --- 84 1 9 78 i .18 - MRCTE-6 307 95
- 9 83.1 18 MRCTE-7L --- 88 i 11 78118 88 i 18 MRCTE-8 113 93 i 9
'MRCTE-9 111 96 1 7 91 t'12-l I -MRCTE-10 96- 93 10- 65 t 19 Ll MRCTE-11 97- 91'i 13- -70 1 17-l MRCTE-12 108 101 i 15 89113 MRCTE-13L --- 92 1 6 80 i 19 MRCTE-14L --- 93 11 67 2 21 MRCTE-15 103 102 i 12 79
- 22 MRCTE-16L --- 92 1 13 80 1 8-NRCTE-17 100 72 i 12 70
- 24 MRCTE-18L --- 89
- 14 83 1 23-l MRCTL-19 111 92 i 14 87 1 20 MRCIE-20L --- 101 i~19 79113 MRCTE-21 85 72 1 4 54 29 MRCTE-22 90 83 i 8 57 1 17 (I) Monitoring stations coded with an "L" contained one standard ?SU TLD pack only.
. Stations not cooed with an "L" contained, in addition to the OSU TLD pack, one R.D. Co. TLD monitoring pack and- two, 0-200 nR, gamma pocket dosimeters. (2) Radiation Detection Company TLD totals include their annual natural background contribution of 96 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 97 mrem for the same period. (3) OSU off-site totals include a measured natural background contribution of 87 1 11 mrem. -(4) i values represent the standard deviation of the total value at the 95% confi-dence level. i J V-25 l listed in Table V.E.3. Calculation of the total net beta disinte-I gration rate incorporates subtraction of enly the counting system l background from the gross beta counting rate, followed by applica-( tion of an appropriate counting system efficiency. l The annual average concentrations were calculated using sample results which exceeded the lower limit of detection (LLD), except that sample results which were less than or equal to the LLO were I averaged in at the corresponding LLD concentration. Table V.E.4 gives the average LLD concentration and the range of LLD values l for each sample category for the current reporting period. , l As used in this report, the LLD has been defin,ed as the amount ] or concentration of radioactive material (in terms of uCi per j unit volume or unit mass) in a representative sample, which has ) a 95% probability of being detected. , Identification of specific radionuclides is not routinely carried l out as part of this monitoring program, but would be conducted if unusual radioactivity levels above natural background were detected. However, from Table V.E.3 it can be seen that the levels q of radioactivity detected were consistent with naturally occurring radioactivity and comparable to values reported in previous years. ) { i l 1 4 i l 1 i l 1 1 l l .\ . , ,1 q. , t ' V ,, cu - ,p , o . Table V.E.3 Annual Average Concentration of.the Total Net 8 eta Radioactivity (Minus 3g)- i " for Environmental Soil,. Water, and Vegetation Samples- .[ ' for the Year =(fuly 1,~ 1987 through June 30, 1988 bcc - ? Sample ! Location - Annual Average Concentration of '(See Figure Sample the Total Net Beta.(Minus 3) H Reporting 6 Y.E.2)' Type' Radioactivity (1) Units 1-W Water. 3.01'x 10-8
- 2.39 x 10-9 pCi/cc 4-W Water- 2.97. x 10-8
- 2.39 x 10-9 (2) pCi/cc 11-W Water 2.89 x 10-8
- 3.19 x 10-9 (3) pCi/cc-pCi/cc a "19-RW Rainwater 2.89 x 10-8 1 3.19 x 10-9 a
3-S Soil '3.28lx 10-5
- 3.21 x 10-5 pCi/ gram of dry soil 5-S Soil- 6.83 'x 10-5
- 5.02 x 10-5 pC1/ gram of dry soil 20-S Soil 5.43 x 10-5 3.7.01 x 10-5 pCi/ gram'of dry soil ,
21-S Soil 8.33 x 10-5 t 4 71 x 10-5 pCi/ gram of dry soil I o 2-G Grass 3.15 x 10'4 1 2.17 x 10-4 pC1/ gram of dry ash- ! 6-G Grass 3.07 x 10-4 1 3.22 x 10-4 pC1/ gram of dry ash 1 3.65 x 10-4 i 2.17 x 10-4 pC1/ gram of dry ash - ! :) 7-G 8-G ' Grass Grass 4.55 x 10-4 1 2.09 x 10-4 pCi/ gram of dry ash H i 9-G Grass 3.90 x 10-4 1.93 x 10-4 pC1/ gram of dry ash' I 10-G Grass .3.17 x 10-4 2.78 x 10-4 pCi/ gram of dry ash-12-G Grass 3.44 x 10-4
- 2.24 x 10-4 pCi/ gram of dry' ash 13-G Grass 2.99 x 10-4 1 2.99 x 10-4 Ci/ gram of dry. ash 14-G Grass 2.72 x 10-4 3.60 x 10-4 pCi/ gram of dry ash' 15-G Grass 2.44 x 10-4 1 2.08 x 10-4 pCi/ gram of dry ash' 16-G Grass 2.92 x 10-4
- 2.42 x 10-4 pCi/ gram of dry ash.
17-G Grass 3.09 x 10-4
- 2.94 x 10-4 pCi/ gram of dry ash' l 18-G Grass 3.34 x 10-4 2.82 x 10-4 pCi/ gram of dry ash 22-G Grass 3.49 x 10-4 1 2.90 x 10-4 pCi/ gram of dry ash (1) i values represent the standard deviation of the average value at the 95% confidence level.
(2) Results are based on two quarterly samples. The indicated collection point was dry during two collection periods. (3) Results are based on three quarterly samples. The indicated collection point was dry during one collection period. i { i i q =__ . . .. . . . . . . j V-27 I i Table V.E.4 Average LLD Concentration and Range of LLD Values for Soil,~ Water and Vegetation Samples for the Year l July 1, 1987 through June 30, 1988 i L Sample Average Range of Reporting l Type LLD Value LLD Values Units ; i Soil 1.33 x 10-5 1.25 x 10-5 to 1.41 x 10-5 pC1/cc Water 2.89 x 10-8 2.68 x 10-8 to 3.13 x 10-8 C1/ gram of dry soil Vegetation 2.61 x 10-5 2.20 x 10-5 to 3.01 x 10-5 pCi/ gram of dry ash i l ! \ 4 l 1 -i i r:. " .[ L, l ' - ' l: , L V-28 L. \' - Y i' , . ) F. Radioactive Material Shipments ] . l l -1. A summary of! the radioactive material . shipments orginating from ) the TRIGA reactor f$cility, NRC license R-106, is shown in Table V.F.1. . A similar sumirary for shipments originating _ from the Radi- .ation Center's state of Oregon radioactive materials license ]f L/ /-~ f ORE-0005-3 is shown in Table.V.F.2. ' ,j l a. l i 1 -l l .l i i q i ) i ) 1; i i V-29 Table V.F.1-Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 for the Year July 1, 1987 through June 30, 1988 Number of Shipments Total Type A Quantity Shipped To Activity Limited White Yellow Yellow (Curies) Quantity I II III Total \ OSU Physics Department Corvallis, Oregon 3.7 x 10-1 7 7 2 -- 16 OSU Oceanography Dept. Corvallis, Oregon 2.1 x 10-2 4 .. 6 -- 10 Univ. of Oregon Eugene, Oregon 1.3 x 10-2 4 -- 16 -- 20 ! j Portland State Univ. 1.6 x 10-2 7 -- 7 Portland, Oregon < - - -- Battelle Pacific NW Lab. 3.8 x 10-2 3 3 Richland, Washington o- -- -- Brigham Young Univ. Provo, Utah 5.0 x 10-5 4 __ __ -- 4 Lawrence Berkeley Lab. Berkeley, California 3.0 x 10-5 2 -- -- -- 1 Univ. Southern Cal., 8.1 x 10-6 2 Los Angeles, Calif. 2 -- -- -- General Atomic San Diego, California 1.6 x 10-7 1 -- -- -- 1 Univ. of Wyoming -- -- -- 1 Laramie, Wyoming 1.0 x 10-6 1 U.S. Geological Survey , Denver, Colorado 8.3 x 10-4 -- -- 1 -- 1 Rensselaer Poly. Inst. > 4 Troy, New York 2.2 x 10-4 4 -- -- -- 4.6 x 10-1 29 7 32 3 71 ! I TOTAL 5 l i V-30 Table 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, 1987 through June 30, 1988 Number of Shipments Total Type A Quantity Shipped To Activity Limited White Yellow ' Yellow (Curies) Quantity 1 II III Total OSU Oceanography Dept. Corvallis, Oregon .. 2 j 8.3 x 10-5 1 _. 1 Corvallis Fire Dept. (1) 6.0 x 10-3 2 -- 2 Corvallis, Oregon -- -- University of Oregon Eugene, Oregon 2.5 x 10-5 1 .. __ .. I Battelle Pacific NW Lab, 1.2 x 10-2 1 2 Richland, Washington .. -- 1 Lawrence Berkeley Lab. o- 1 Berkeley, California 1.0 x 10-7 1 -- -- University of ilt.ssouri Columbia, Missouri 2.0 x 10-6 2 -- -- -- 2 fermi Nat'l Accelerator Lab. ' Batavia, Illinois 5.0 x 10-9 1 -- -- -- 1 Harvard-Smithsonien Center for Astro-physics i Cambddge, Mass,. 8.4 x 10-8 1 -- -- -- I han Piank Institut fur Chemie Mainz, FRG 2.0 x 10-8 1 .. .. .. I ~ . __ 1.8 x 10-2 8 9 4 3 13 TOTALS - I j (1) Temporary shipment of training material to Corvallis Ff re Departmert under Oregon I State Health Division license ORE-0269-1. The radioactive material was returned to the Radiation Center's license ORE-0005-3. l 1 l V-31 G. _ References l 1. U.S. Environmental Protection Agency, " Estimates cf Ionizing Dadia-l tion Doses in the~ United States, 1960-2000," ORP/CSD 72-1, Office of Radiation Programs, Rockville, Meryland (1972).
- 2. U.S. Environmental Protection Agency " Radiological Quality of the Environment in the United States, 1977," EPA 520/1-77-009, Office of Radiation Programs; Washington, D.C. 20460 (1977).
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Ah-q '~ 4 .p. g-. ; \ p [k J l ank 4] hgg , _ . _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ m_ _ .J myy 77,47 y;g yy a ; e s: +4;g 'y y yr 4& U.% a py ; ' g o a :) . dy4 ', 4.d x .i! j.M y' J ' fy y };,, f . v' ' .1.g u y l ' "kj-Mif . I ; y'q ,g$ jhh g hj {]/Q w . i, 1 m$ ,g i , ,9 3 @ gW f.!g .pj l ?,- q$ .hj. ': L. yan m .a,, ig,(j;l 9: h n . j hM, j. < ;g ^.. i y,Og :4 h;g. ( j.g. ,jg i c; M c y4t J Mc 'p jffklhg,,jgg , 1 ,Myac lh,3 ^ ! $ p! ' .aJ J v dg n db-i d'N .aj$wl&w Q 4 ;r 5 yNW(o: . . .g g, , .;q qc. h , M#. h meg s m y y 4m 3 Jhyge l[]j ]f l jgk % [ , :q y , o , "- -m L 3 1a . ! PART VI ! l WORK q A. Summary ; The Radiation Center offers a large variety of resources for teaching, J research and-service related to radiation and radioactive materials. ') Some of these are discussed in detail in other parts of this report, j The purpose of this pr.rt it, to mnenerize the teaching, research and ) service efforts carried out during the current reporting period. ) J B. 3 aching Use of the R6diation Center and reactor to support OSUts academic programs is considered to be our most important responsibility. Imple- l mentation of this support occurs through direct involvement of the Center's.staft and facilities in ths teaching programs of various departments and through our participation in University research pro-grcms. For example, during the current reporting period the Radiation I Cent 6r accommodated 26 OSU academic classes involving 10 different academic departments, and conducted 2 reactor operator training pro- J g rams . In addition, portions of classes from other Oregon.universit-les were also support by the Radiation Center. The OSU teaching programs utilized 359 hours of reactor time, which equates to about 30% of the available teaching hours in a normal academic year. Tables III.A.1, III.A.2, and III.E.1 plus .section VI.F provide more detailed information on the use of the Radiation Center and reactor for instruction and training. C. Researc_h and Service Almost all Radiatioil Center research end service work is tracked by means of a project system. When a request for facility ute is received, a numbee is assigned to that project and a project sheet is generated. This sheet includes such information. as the project number, data about the person and institution recpesting the work, a description of the ! project, Radiation Center resources needed, estimated costs for the project, and the funding source. I i VI-2 l j Table VI.C.1 provides a summary of institutions and agencies which used the Radiation Center during this reporting period and includes , additional information about the number of acedemic personnel involved, ) the number of students involved and the number of uses logged for each organization. Details on graduate student thesis research which used the Radiation Center are given in Table VI.C.2. The major table in this section is Table VI.C.3. This table provides an essentially complete listing of the research and service projects carried out during tnis reporting period and lists information relating to the personnel and institution involved, the type of project, and thi funding agency. Projects which used the reactor are indicated by an astorisk. Due to the fact that the project system is relatively new, not all of the work done by the Radiation Center and it staff have been included as projects. However, much of this work is summarized in cther parts of this report. In addition to the listing of specific projects in Table VI.C.3. key technical areat representing major Radiation Center activities in rescarch and service have also been highlighted in this part. (See section VI.C.1 through VI.C.8, pages VI-24 through VI-30.) 1 i VI 1 Table VI.C.1 Institutions and Agencies Which Utilized the Radiation Center 1 Humber of Number of Number of Number of Faculty Students Uses of Institution' Projects . Involved Involved the facility *0regon State University 54 40 32 M0 f' *U.S. Bureau of Mines 1 0 0 1
- Albany Titanium 1 0 0 1
. *University of Oregon- 12 5 8 17 *Medford Water Commission 1 0 0 4 *0lackamas County Sheriff 1 0 0 2:
- Portland State University 4 2- 3 6
- Reed College 1 2 0 1 Scientific Resources Inc. 1 0 0 1
*N.W. Forensic Laboratory 1 0 0 1
- Columbia Gem House 1 0 0 5
- University of Washington 1 1 1- 1
'*Battelle Pacific N.W. Labs 4 1 1 6 '*Humbolt State University 1 1 0 1
- Boise State University 1 1 1 1
*U.S. Air Forr.a. McClellan AFB 1 0 0 1
- Lawrence Berkeley Laboratory 1 0 0 3
- Stanford University 1 1 1 1
- University of Soythern California 2 1 1 2
- W iversity of Wyoming 1 3 0 2
*Brigham Young University 1 1 0 4 *t',S. Geological Survey 1 0 0 1
- University of Alberta, Edmonton 1 1 0 1
$ University of Texas, Arlihgton 2 3 0 2
- Rice University 4 3 3 4
- South Dakota School of Mines and Technology 1 2 1 1
- Louisiana State University 2 1 1 2
- University of Tennessee 2 1 1 3
- University of South Carolina 1 2 1 1
*Clemr.on University 1 1 0 1 I - _ _
- Used the OSTR.
VI-4 Table VI.C.'1 (Continued) Number of Number of Number of 1 Number of Faculty Students Uses of ( Institution Prcjects Involved Involved the Facility l ' Western Carolina University 1 1 0 1
- North Carolina State University 2 2 1 2 ,
) 1 *Ashtabs12 Trading Company 1 0 0 1
- Sierra /Nord Rutile Company 1 0 0 1
- City College of New York 3 1 0 3 !
*Rensselaer Polytechnic Institute 1 1 1 6
- University of Rochester 1 1 0 1
*Carpco, Inc. 2 0 0 18 ' University of Rhode Island 1 1 1 1 *0xford University 1 1 1 9 j
- Geological Suney, Papua, New Guinea 1 1 0 1
- International Atomic Energy Agency 2 0 2 4 TOTI.LS 124 82 61 885 L
- Used the OSTR.
(1) This trble does not count community collega, high school, and elementary school classes which , came through for special tours. These are listed in the section on public relt. tion! (VII.F). , ; 1 j l l I 1
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