ML20078C151
| ML20078C151 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/30/1994 |
| From: | Anderson T, Conrady M, Dodd B Oregon State University, CORVALLIS, OR |
| To: | |
| Shared Package | |
| ML20078C149 | List: |
| References | |
| NUDOCS 9410280127 | |
| Download: ML20078C151 (218) | |
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-[ ...l, r ANNUAL 1 REPORT .
E LOFJTHE J . OREGONTSTATERUNIVER$1TY f . 1 i I RADIATIONQCENTER .- - L 1_ LAND ' $ll TRIGA REAGTOR! ' l
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1 E Annu 1 R: port cf tha Oregon State University Radiation Center and TRIGA Reactor July 1,1993 - June 30,1994 To satisfy the requirements of: A. U.S. Nuclear Regulatory Commission, License No. R-106 (Docket No. 50-243), Technical Specification 6.7(e). B. Task Order No. 3, under Subcontract No. C84-110499 (DE-AC07-76ERO1953) for University Reactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc. C. Oregon Department of Energy, ODOE Rule No. 30-010. I Edited by: B. Dodd, Reactor Administrator With contributions from: T. V. Anderson, Reactor Supervisor M. R. Conrady, Neutron Activation Analysis Specialist S. M. Cordell, Radiation Protection Technologist D. L. Cramer, Office Coordinator D. K. Dalton, Administrative Assistant I A. D. Hall, Reactor Operator l J. F. Higginbotham, Senior Health Physicist A. G. Johnson, Director C. L. Phillips, Office Specialist D. S. Pratt, Health Physicist J. R. Smith, Office Specialist I S. P. Smith, Scientific Instrument Technician M. J. Streck, Neutron Activation Analysis Specialist E. G. Torne, Neutron Activation Analysis Specialist i l Submitted by: A. G. Johnson ; Director, Radiation Center l I Radiation Center l Oregon State University I Corvallis, Oregon 97331-5903 Telephone: (503) 737-2341 Fax: (503) 737-0480 I October 1994 I
I A mual Report of the I Oregon State University Radiatior, Center and TRIGA Reactor I Table of Contents I Paoe PART I - OVERVIEW A. Acknowledgements . . . .. ....... ............ ............1-1 B. Executive Summary . . . . . . . ..................................1-2 I C. D. E. Introduction . . ....... ... .. ........ ... Overview of the Radiation Center ............................. Summary of OSTR Environmental and Radiation Protection Data ...........1-9
...................l-5
. . . 1-6
- 1. Liquid Effluents Released .... .......... ........... . . . . . . 1-9
- 2. Airborne Effluents Released ... ......... ..................1-10
- 3. Solid Waste Released . ............... .................. 1-10
- 4. Radiation Exposure Received by Personnel . . . . . . . . . . . . . . . . . . . . . 1-11
- 5. Number of Routine Onsite and Offsite Monitoring Measurements and Samples . . . . . . . ...... ....... . .. ...............l-12 F. History . ..... ...... . .. . . .. . ......... . . . . . . 1- 13 i
PART ll - PEOPLE A. Fa c ulty . . . . . . . . . . . . . . . . . . . . . . ........... .............. . 11- 1 B. Visiting Scientists and Special Trainees . .... ...................... 11- 6 C. OSU Graduate Students . . . . . . . . .. ...... ..... ... ... .. ... 11- 7 D. Business, Administrative and Clerical Staff . . . . . . . . . . . . . . . . . . . . . . . . . 11-8 E. Reactor Operations Staff . ...... ... ......... ................ll-8 F. Radiation Protection Staff . . . . .. .. .. ... ...............11-8 G. Scientific Support Staff . ...... .. . .. . ... ....... . . . . . . . 11-9 H. OSU Radiation Safety Office Staff . . . . .... .... ..... ............ Il 9
- 1. Committees . .............. .. .... ...... ....... ....... 11- 9
- 1. Reactor Operations Committee . . . . . . . . . .................. .. 11- 9
- 2. Radiation Safety Committee ....... .. ........... . . . . ... 11- 1 0 I 3.
4. Radiation Center Safety Committee . . .. .......... ..... ... Radiation Center TOM Teams ..... .. . . ...... ....... 11- 1 0 ll-10 I I I I
U PART 111 - FACILITIES A. Research Reactor . . . . . . . . . . . ....... ........................Ill-1
- 1. D e s c rip ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ill-1
- 2. Utilization . . . . . . ......................................111-5
- a. Instruction ....... ....... .......................111-6
- b. Research . . . . . . . ......... .................... . . . Ill-6 B. Analytical Equipment ............... ................. . . . . 111-11
- 1. Description . . . . . . . . . . . . . .... .... ............... . . 111- 1 1
- 2. Utilization . . . . . . . . . . . .. ........................... 111- 1 1 C. Radioisotope Irradiation Sources . . . ............... .... . . . 111- 1 6
- 1. Description . . . . . . . . . . ........ .. .................... 111- 1 6
- 2. Utilization . . . . . . . . . . . . . ... .... ........... . . . . . . 111-16 D. X-Ray Machine ..... ................ . . . . . . . . . . . . . . . . . . . 111- 21
- 1. Description . . . . . . . . .......................... . . . . . 111-21
- 2. Utilization . . . . . . .............. ...... ..... . . . . . . . . . . lll-21 E. Laboratories and Classrooms . . . .. ........ . . .. . . . . . . . . . . . 111-2 2
- 1. Description . . . . . .... .... . . ............. . . . . 111-22
- 2. Utilization . . . . . . . . ... ........ ......... ... . . . . 111- 2 3 g F. Instrument Repair and Calibration Facility . . . . . .......... . . . . . . . 111-27 E
- 1. Description . . . . ... . ....... . . . ......... . . . . . . . Ill-27
- 2. Utilization . . . . .... .......... ....... ..... ... ... . lll-27 g G. Libraries . . ..... .. .... ... .. .... .... .... . . 111- 2 8 E
- 1. Description . ........ . ............ . . . . . . . . . . . . . 111-2 8
- 2. Utilization . . . .. ... . .. . .. .... ........... . . . . . . 111-29 PART IV - REACTOR A. Operating Statistics . . . . . . . . ............ .. .............IV-1 I
B. Experiments Performed . .. .. ... ..... ......................IV-10
- 1. Approved Experiments . .... .... .. . . .... . . . . . . . . . . . I V- 1 0
- 2. Inactive Experiments . ... .... ..... ..... . ..... . IV-12 C. Unplanned Shutdowns . . . ....... .... .. ........... . . . . . . . IV-14 D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 .......... . . . IV-16
- 1. 10 CFR 50.59 Changes to the Reactor Facility . . . . . . . . . ....... . IV-16
- 2. 10 CFR 50.59 Changes to Reactor Procedures . .. ........ . . . IV-16
- 3. 10 CFR 50.59 Changes to Reactor Experiments . . . . . . . . . . . . . . . . . . IV-26 E. Surveillance and Maintenance . . . . . . . . . . . ........ .... . .... .IV-28
- 1. Non-Routine Maintenance .......... . . . . . . . . . . . . . . . . . . . . . I V- 2 8 E
- 2. Routine Surveillance and Maintenance . . . . . . ............... . IV-28 5 F. Reportable Occurrences . . . . . . ........ ............ . . . . . . . IV-2 8 I
I
.I 1
Paae PART V - PROTECTION A. Introduction . . . .................................. . . . . . . . . . V- 1 B. Environmental Releases ........ .............. . .............. V-3
- 1. Liquid Effluents Released ............................... . . V-3
- 2. Airborne Effluents Released ........ ........................ V-6
- 3. Solid Waste Rele a s ed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-6 C. Personnel Doses ............... .. ... ......... ............ V-9 D. Fa cility Survey Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... V-12
- 1. Area Radiation Dosimeters ........................... . . . . V- 12
- 2. Routine Radiation and Contamination Surveys . . . . . . . . . . . . . . . . . . . V- 1 7 E. Environmental Survey Data . . . . ... . ..... ................V-19
- 1. Gamma Radiation Monitoring ............... ........ . . . . V-19
- 2. Soil, Water, and Vegetation Surveys . . ................... . V-2 5 F. Radioactive Material Shipments . ................ . . .... .. V-29 G. References ............ .. . ..... ............... ... V-33 PART VI - WORK A. Summary ...... .. .... ..................... ...... . . VI-1 B. Teaching ........ ...... .. ... ........... . . . . . . . . . VI- 1 C. Research and Service . .. ................... ................VI-1
- 1. Neutron Activation Analysis . ... .......... ...............VI-30
- 2. Forensic Studies .... .. . ......... .. ..... . ....... VI-31
- 3. Irradiations .. . .. .... ..... ....... . . . . ... VI-31
- 4. Radiological Emergency Response Services . ........ . . . . . . . . . . VI-31
- 5. Training and Instruction .... . . .. ....... ........... .. VI-32 I 6.
7. Radiation Protection Services .. ... . .......... . RadiologicalInstrument Repair and Calibration ... ... VI-33 VI-34
- 8. Consultation . . . . . . .... . .......... . . . . . . . . . . VI-3 5 PART Vil - WORDS A. Publications in Print ... . .. ........... . . . ..... ..... . Vll-1 B. Theses .. ... ..... ...... ...... .......... . . . . . . Vil-11 C. Reports Submitted for Publication . . . . .. .... ................ Vli-12 D. Documents in Preparation . . . .... . ....... ...... .. . Vll-14
- 1. Publications . . . . . . ... . ... .. . . .... . . . . . . . . Vll-14 I E.
F.
- 2. Theses Presentations Public Relations
. . . . . . Vll-16
...............Vll-17
. . . . . . . Vil-2 5 I
LIST OF TABLES Table Title Pace Ill. A.1 OSU Courses Using the OSTR . . . . . . . . . . . . . . . . . . . . . . . . . . . 111-7 Ill. A.2 OSTR Teaching Hours .... ........................... lll-8 Ill. A.3 OSTR Research Hours .......... . ........... . . . . . Ill-10 lil.B.1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, Alpha . . . . . . . . . ................. ...... . . . Ill-12 111.B.2 Radiation Center Liquid Scintillation Counting Systems . . . . . . . . . Ill-13 Ill.B.3 Radiation Center Proportional Counting Systems . . . . . . . . . . .. 111- 1 4 Ill.B.4 Thermoluminescent Dosimeter Systems . .. .......... , lll-15 Ill.C.1 Budd S Co Irradiator Use . . ......... ... . . . . . . . . . . . . . 111- 1 9 lil.C.2 Gammacell 220 6 Co Irradiator Use . . . . . . . . . . . . . . . . . . . . . 111 - 2 0 lil.E.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics g and Nuclear Science Courses Which Are Taught or Partially Taught 5 at the Radiation Center . . ................ .......... . lll-24 IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) . .........IV-2 l l IV.A.2 OSTR Operating Statistics with the Original (20% Enriched) l Standard TRIGA Fuel Core ... ... .... .... . ........IV-5 IV.A.3 Present OSTR Operating Statistics . . . . . .. ................IV-6 IV.A.4 OSTR Use Time in Terms of Specific Use Categories . . . . . . . . . . . . IV-7 I IV.A.5 OSTR Multiple Use Time . . . . . . . . .... ..................IV-8 IV.B.1 Use of OSTR Reactor Experiments . . ..... .. ..... .... . IV-11 1 i IV.C.1 Unplanned Reactor Shutdowns and Scrams .. ..... . . . . . . . I V- 1 5 V.A.1 Radiation Protection Program Requirements and Frequencies ...... V-2 V.B.1.a Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer . .. ..... .. .. ........... . . . . . . . . . . . . . . V-4 V.B.1.b Annual Summary of Liquid Waste Generated and Transferred . . . . . . V-5 I I
LIST OF TABLES (Continued) Table Title Pace V.B.2 Monthly Summary of Gaseous Effluent Releases . . . . . . . . . . . . . . . V-7 V.B.3 Annual Summary of Solid Waste Generated and Transferred . . . . . . . . . . . ............. ...... . . . . . . . V- 8 V.C.1 Annual Summary of Personnel Radiation Doses Received . . . . . . . V- 1 1 V.D.1 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility . . ............. . . . . . . . V- 1 4 I V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center ............ ......... .... V-15 V.D.3 Annual Summary of Radiation Levels and Contamination Levels Observed Within the Reactor Facility and I'adiation Center During Routine Radiation Surveys . ............ ... . . V-18 V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence ..... V-21 V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations ......... .. ........... ..... ... V-24 V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus 3H) for Environmental Soil, Water, and Vegetation Samples . . . , ........ .. ........ . ... ........ V-27 V 8~ 4
. Average LLD Concentration and Range of LLD Values for Soil, I Water and Vegetation Samples . . . . . . . . . . . . . . . . .. .. . . V-28 l
V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 .. .. . . V-30 l V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License i ORE-0005-3 ... ........ ... ........ . . .. V-31 l V.F.3 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 . . . . . . . . . . . . V-3 2 1 VI.C.1 Institutions and Agencies Which Utilized the Radiation Center . .. . . .... .... .... .. .. . . . . . . . . VI-3 VI.C.2 Graduate Student Research Which Utilized the Radiation Center ... .. . . . .. . . ..... . . VI.7 I I
E us LIST OF TABLES (Continued) Table Title Pace VI.C.3 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies . . . . . VI-14 VI.C.4 Summary of the Types of Radiolc3i calInstrumentation Calibrated to Support the OSU TRIGA Reactor and the Radiation Center ....................................IV-36 VI.C.5 Summary of RadiologicalInstrumentation Calibrated to Support Other OSU Departments and Other Agencies . . . . . . . . . . . . . . . . VI-37 VI.C.6 Summary of Radiological Instrument Repair Activities for Non-Radiation Center Departments and Agencies ........ . . . . VI-3 8 Vll.F.1 Summary of Visitors to the Radiation Center . . . . . . ......... Vll-26 I I I I I I I. I-
I LIST OF FIGURES Fioure Title Pace Floor Plan of the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 I.D.1 fil. A.1 Cutaway View of Standard TRIGA Mark ll Core Arrangement . . . . . 111-2 Ill.A.2 Horizontal Section of TRIGA Mark 11 Reactor . . . . . . . . . . . . . . . . . 111-3 Ill.A.3 Vertical Section of TRIGA Mark 11 Reactor . . . . . . . . . . . . . .. . . lll-4 Ill.C.1 Budd8Co Irradiator (Vertical Section) . . . . . . . . . . . . . . . . . . . . 111- 1 7 Ill.C.2 Gammacell 220 6 Co Irradiator ........................ . 111- 1 8 IV.A.1 OSTR Annual Energy Production vs. Time (Annual Reporting Period) . . . . . ...... .. ..... .. .. .........IV-9 IV.E.1 Monthly Surveillance and Maintenance (Sample Form) . . . . . . . . . IV-2 9 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form) . . . . . . . . . IV-30 IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form) . . . . . . IV-32 IV.E.4 Annual Surveillance and Maintenance (Sample Form) . . . . . . . . . . IV-3 4 V.D.1 TRIGA Facility and Radiation Center Area Dosimeter Locations . . ...... ........... ........... . . . . . V- 13 V. E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence . . . . . . . . . . . . . . . . . . . V- 2 0 V.E.2 Monitoring Stations for the OSU TRIGA Reactor . . . . . . . . . . . . . . V-23 l l l l l 1 1 l I l l l i
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I I PARTI OVERVIEW A. Acknowledaements During this reporting period, many individuals and organizations helped the Radiation Center succeed. In recognition of this, the staff of the OSU Radiation Center and TRIGA Reactor would like to extend their appreciation to all of those who contributed to the information and events contained in this report. To the University administration who consistently supported our prograrr; to those who provided our funding, particularly the state of Oregon and the U.S. Dep.irtment of Energy; to our regulators; to the research-ers, the students and others who used the Radiation Center; to OSU Facilities Services, who patiently provided invaluable assistance through their engineering, maintenance, and other supporting programs; to OSU Security Services and the University Police, who were always there when we needed them; and to the OSU Department of Printing and Mailing, who consistently provided a quality service; we most earnestly say thank you. In a special note of gratitude, the staff would also like to highlight the talents and the tolerance of our secretarial personnel, particularly Jennie Smith, who performed admirably during the preparation of this report. I I
l I-2 me B. Executive Summary The purpose of the executive summary is to provide a brief snapshot of the work of the Radiation Center over the past year. One of the ways of doing this is to compare some of the indicator statistics given in the many tables in this report. Clearly the health of the reactor operation is of vital importance to the Center. Itis pleasing to see that while stdl meeting the needs of OSU academic classes, we have been able to increase OSU research use hours by 18% and the use hours of off-campus researchers by almost 150%. This attests to the increasing regional, national and international reputation of the OSU TRIGA Reactor (OSTR). Sadly, it may also be some reflection of the fact that the number of research reactors in the country continues to decline. In these times of increasingly tight budgetary constraints, it is noteworthy and encouraging that funded research hours were up by 110% over last year. Not only are research use hours up, but multiple user hours have increased. The time when we had two simultaneous users was up 140% and three users was up 80%. This indicates a deliberate attempt to maximize reactor availability and increase efficiency of use. During this reporting period, the we were the subject of a comprehensive inspection by the Nuclear Regulatory Commission (NRC) which covered such topics as: reactor operations, nuclear material control and accountability, radiation protection, emergency preparedness and physical security, in the exit interview the inspectors were very complimentary, particularly on the quality of our procedures, records, key control and our implementation of the new radiation protection regulations. In summary, we can say that the reactor operation program is very healthy. The S Co gamma irradiators are another significant facet of the Radiation Centel's operation. The use of these f acilities tends to vary a little more than the reactor and is l much more dependent on the types of research being performed on campus. This year the use of the lower radiation level Budd irradiator decreased, which may be an indication that it is time to begin thinking of recharging it with new sources. The Budd started with 3,000 Ci, and is now down to about 50 Ci of radioactivity. On the other E hand, the number of hours the Gammacellirradiator was used jumped up by a f actor of nearly 2.5. This clearly indicates a high level of demand and need for OSU to maintain high dose rate gamma irradiation capability. I l
I-3 Other numericalindications of the increased level of productivity last year are shown by the number of off-site shipments of samples irradiated in the reactor which increased to 77 (up by 75%), and the number of publications resulting from use of the Radiation Center's facilities which increased to 111 (up by 39%). The Radiation Center is now maintaining and calibrating almost all of the portable radiological monitoring instruments for OSU, and many instruments for the institutions of the Oregon State System of Higher Education, State of Oregon agencies, and several federal agencies located in Oregon. This represents about 440 instruments. It is gratifying to note, however, that the number of instrument repairs has begun to decrease. We believe that this is due to the increased level of care that Radiation Center-calibrated instruments now receive. I No discussion of the Radiation Center statistics would be complete without a mention of the fact that we hosted 1267 visitors during the 1993-1994 year. While this total is down a little on last year's record high, the actual number of tours conducted was up by over 40%. We believe that tours are an important part of the Center's educational mission, as well as part of being a good neighbor. I Apart from the numbers, the past year was characterized by two significant regulatory issues which affected the Radiation Center. The first was the implementation of a requirement to pay a $62,100 licensing fee to the USNRC. After a major expenditure of time and effort, OSU and other university research reactor f acilities were successful I in petitioning the NRC to restore the generic exemption from annual fees for non-profit educationalinstitutions. OSU played a leading role in persuading them to reverse their I previous decision. The second significant regulatory event this year was the January 1, 1994 implementation of the completely revised radiation protection regulations given in 10 CFR 20. This necessitated a very complete and careful review of the whole health physics program to determine the changes needed and the best way to make the modifications. The Radiation Center's health physics group are to be complimented on a difficult task well done. I
I-4 ,, Work conthued this year on the analysis necessary to prepare an application to the USNRP ',or authorization to convert the OSTR from high-enriched uranium fuel to low-enriched uranium fuel. It was analysis by the Radiation Center which brought to light potential problems with the proposed composition of low-enriched fuel and paved the way for solutions suitable for all TRIGA reactors undergoing conversion. The OSTR is currently scheduled for refuelling in 1997; however, progress on this project will be somewhat dependent on funding and a variety of other factors, many of which are outside the control of the Radiation Center's staff. The APEX f acility successfully completed shakedown tests and began matrix testing for I Westinghouse Electric Corp. during this reporting year. While this facility is not run by the Radiation Center staff, many of them have made significant contributions in a support role to its success and are deserving of congratulations. Many people play a part in the successful operation of a facility such as the OSU Radiation Center. Some of these are highlighted in the acknowledgements section; to all of them we say thank you. On a final note, as we do each year, we like to point out that there were no regulatory citations and no emergencies or security events relating to the Radiation Center during this reporting period. Furthermore, all of the increased use of the Radiation Center 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). I I I ~ I I 1
~
1-5 C. Introduction The current annual report of the Oregon State University Radiation Center and TRIGA Reactor follows the usual format by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the reactor may be examined separately if desired. It should be noted that all annual data given in this report cover the period from July 1,1993 through June 30,1994. Cumulative reactor operating data in this report relate only to the FLIP-fueled core. This covers the period from August 1,1976 through June 30, 1994. For a summary of data on the reactor's original 20% enriched core the reader is referred to Table IV.A.2 in Part IV of this report, or to the 1976-77 annual report if a more comprehensive review is needed. In addition to providing general information about the activities of the Radiation Center, this report is designed to meet the reporting requirements of the U.S. Nuclear Regulatory Commission, the U.S. Department of Energy, and the Oregon Department of Energy. Because of this, the report is divided into several distinct parts so that the reader may easily find the sections of interest. I I l; l I I l I . I I
I l-6 D. Overview of the Radiation Center ' The Radiation Center is a unique facility which serves the entire OSU Campus, all other institutions within the Oregon State System of Higher Education, and many other colleges and universities throughout the nation. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law l enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry. In addition, the Radiation Center provides permanent office and I laboratory space for the OSU Department of Nuclear Engineering, the OSU Radiation Safety program, the institute of Nuclear Science and Engineering, and for the OSU l 1 nuclear chemistry, radiation chemistry, and geo- and cosmochemistry programs. There j is no other university f acility with the combined capabilities of the OSU Radiation Center in the western half of the United States. Located in the Radiation Center are major items of specialized equipment and unique I. teaching and research facilities. Figure I.D.1 shows the layout of these facilities at the Radiation Center. They include a TRIGA Mark ll research nuclear reactor; two cobalt-60 gamma irradiators; a 300 kVp X-ray generator; a number of state-of-the art computer-- based gamma radiation spectrometers and associated germanium detectors; a neutron radiography facility capable of taking still or very high speed radiographs; and a variety of instruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with up-to-date instrumenta-tion and related equipment for performing neutron activation analysis and radiotracer studies; laboratories for animal and plant experiments involving radioactivity; a facility for repair and calibration of radiation protection instrumentation; and facilities for packaging radioactive materials for shipment to national and international destinations. A recent major addition to the Radiation Center is the one-quarter scale thermal hydraulic advanced plant experimental (APEX) test f acility for the Westinghouse AP600 reactor design. The AP600 is a next-generation nuclear reactor design which incorporates many passive safety features as well as considerably simplified plant systems and equipment. APEX operates at pressures of up to 400 psia and tempera-tures up to 450 F using electrical heaters instead of nuclear fuel. All major components of the AP600 are included in APEX and all systems are appropriately scaled to enable the experimental measurements to be used for safety evaluations and licensing of the I
E i E l-7 i i i full scale plant. This world-class facility meets exacting quality assurance criteria to provide assurance of safety as well as validity of the test results. The Radiation Center staff regularly provides direct support and assistance to OSU teaching and research programs. Areas of expertise commonly involved in such efforts include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, neutron radiography, radiation effects on biological systems, radiation dosimetry, production of short-lived radioisotopes, radiation shielding, nuclear instrumentation, emergency response, transportation of radioactive materials, instrument calibration, radiation health physics, radioactive waste disposal, and other related areas. I In addition to formal academic and research support, the Center's staff provides a wide l variety of other services including public tours and public instructional programs, and j professional consultation associated with the feasibility, design, safety, and execution ; of experiments using radiation and radioactive materials. I I I : I I I I
I8 l Figure I.D.1 Floor Plan of the Radiation Center : l
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l l-9 E. Summary of OSTR Environmental and Radiation Protection Data
- 1. Liauid Effluents Released (See Table V.B.1)
- a. Total estimated quantity of radioactivity released (to the sanitary sewer)on2) <4.12 x 104 Curies' )
- b. Detectable radionuclides in the liquid waste None
- c. Estimated average concentration of released radioactive material at the point of release < 4.00 x 10 4 Ci/cc'3'
- d. Percent of applicable MPC for released liquid radioactive material at the point of release'* Not applicable
- e. Total volume of liquid effluent released, including diluent
- 2724 gallons (1) OSTR contribution OS gallons (1) OSU has implemented a policy to reduce the absolute minimum radioactive wastes disposed to the sanitary sewer.
(2) The OSU operational policy is to subtract only detector background from our water analysis data and not background radioactivity in the Corvallis city water. (3) This is the lower limit of detection at the 95% confidence level. I (4) Based on values listed in 10 CFR 20, Appendix B to 20.1-20.601 in effect until 12/31/93. There were no liquid effluent releases to the sanitary sewer after that date in which 10 CFR 20, Appendix B to 20.1001-20.2401 was in effect. (5) 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. (6) OSTR contribution does not include the volume of liquid effluent from the infrequently used reactor bay sink. I
i E! l-10 g!
- 2. Airborne Effluents Released (See Table V.B.2)
- a. Total estimated quantity of radioactivity released 3.64 Curies
- b. Detectable radionuclides in the gaseous waste m Ar (TS = 1.83 hr)
- c. Estimated average atmospheric diluted concentration of argon-41 at the point of release 2.4 x 10 8 Ci/ml
- d. Percent of applicable MPC for diluted concentration of argon-41 at the point of release 0.6 %
- e. Total estimated release of radioactivity in particulate form with half-lives greater than 8 daysc2' None
- 3. Solid Waste Released (See Table V.B.3)
- a. Total amount of solid waste packaged and disposed of 49.5 ft
- b. Detectable radionuclides in the solid waste C,
- K, '8Sc, 5'Cr, 5dMn, 58Co, 5'Fe, 8 Co, 65Zn, 75Se, 85Zr, 1243g 12 s S b, ' 'Ba, '37Cs,
'"Ce, 52Eu,15'Eu
- c. Total radioactivity in the solid waste 6.2 x 10 Curies I
I (1) Routine gamma spectroscopy analysis of the gaseous radioactivity in the stack discharge indicated that it was virtually all argon-41. (2) Evaluation of the detectable particulate radioactivity in the stack discharge confirmed its origin as naturally occurring radon daughter products, predominantly lead-214 and bismuth-214, which are not associated with reactor operations. m
I-11
- 4. Radiation Exoosure Received by Personnel (See Table V.C.1)"'
- a. Facility Operating Personnel (mrem)
(1) Average whole body 25 (2) Average extremities 48 (3) Maximum whole body 230 (4) Maximum extremities 230
- b. Key Facility Research Personnel (1) Average whole body 0 (2) Average extremities 11 (3) Maximum whole body 0 (4) Maximum extremities 120
- c. Physical Plant Maintenance Personnel I (1)
(2) Average whole body Maximum whole body
<1 10
- d. Laboratory Class Students (1) Average whole body 0 (2) Average extremities O (3) Maximum whole body 0 (4) Maximum extremities O
- e. Campus Police and Security Personnel (1) Average whole body 0 (2) Maximum whole body O
- f. Visitors (1) Average whole body <1 (2) Maximum whole body 9 l
I (1) "O" 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 neutron dosimeters was less than the vendor's threshold of 30 mrem, as applicable. I
E l-12 Ul 1
- 5. Number of Routine Onsite and Offsite Monitorina Measurements and Samoles
- a. Facility Survey Data E E,
(1) Area Radiation Dosimeters (See Table V.D.1) (a) Beta-gamma dosimeter measurements 136 (b) Neutron dosimeter measurements 48 (2) Radiation and Contamination Survey Measurements (See Table V.D.3) ~ 6000
- b. Environmental Survey Data (1) Gamma Radiation Monitoring (See Tables V.E.1 and V.E.2)
(a) Onsite monitoring
-- OSU TLD monitors 108
-- Radiation Detection Co. TLD monitors 72
-- Monthly R/hr measurements 108 (b) Offsite monitoring
-- OSU TLD monitors 264
-- Radiation Detection Co. TLD monitors 104
-- Monthly R/hr measurements 252 (2) Soit, Water and Vegetation Surveys .
(See Table V.E.3) (a) Soil samples 16 (b) Water samples 12 (c) Vegetation samples 56 I I
l-13 F. Histon A brief chronology of the key dates and events in the history of the OSU Radiation Center and the TRIGA reactor is given below: June 1964 Completion of the first phase of the Radiation Center, consisting of 32,397 square feet of office and laboratory space. July 1964 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. This reactor was initially housed in the Mechanical Engineering Department and first went critical in January of 1959. Oct.1966 Completion of the second phase of the Radiation Center, consisting of 9,956 square feet of space for the TRIGA reactor and associated laboratories and offices. March 1967 initial criticality of the Oregon State TRIGA Reactor (OSTR). The reactor was licensed to operate at a maximum steady state power level of 250 kW, and was fueled with 20% enriched fuel. Oct.1967 Formal dedication of the Radiation Center. August 1969 OSTR licensed to operate at a maximum steady state power of 1 MW, but could do so only for short periods of time due to lack of cooling capacity. June 1971 OSTR cooling capacity upgraded to allow continuous operation at 1 MW. April 1972 OSTR Site Certificate issued by the Oregon Energy Facility Siting Council. Sept.1972 OSTR area fence installed. Dec.1974 AGN-201 reactor permanently shut down. March 1976 Completion of 1600 square feet of additional space to accommodate the rapidly expanding nuclear engineering program. July 1976 OSTR refueled with 70% enriched FLIP fuel. July 1977 Completion of a second 1600 square feet of space to bring the Radiation Center complex to its current total of 45,553 square feet. I I
E l-14 O Jan.1980 Major upgrade of the electronics in the OSTR control console. July 1980 AGN-201 reactor decommissioned and space released for unrestricted use. June 1982 Shipment of the original 20% enriched OSTR fuel to Westinghouse Hanford Corporation. Dec.1988 AGN-201 components transferred to Idaho State University for use in their AGN-201 reactor program. Dec.1989 OSTR licensed power increased to 1.1 MW. June 1990 Installation of a 7000 Ci 8 Co Gammacellirradiator. March 1992 25th anniversary of the OSTR initial criticality. Nov.1992 Start of APEX plant construction. May 1994 Completion of APEX acceptance tests. August 1994 APEX inauguration ceremony. 1 I I
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i
I I PARTll 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 provides the composition of committees involving Center personnel. It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed in this part. Summary information on the number of
.P people involved is given in Table VI.C.1, while 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 Al-Baroudi, Homam M. Research Assistant Nuclear Engineering
- Albertson, Barry D.
Professor, School of Medicine, Division of Endocrinology, Diabetes and Clinical Nutrition Oregon Health Sciences University, Portland, OR Baxter, Clarence J. Research Assistant APEX Instrument and Controls Technician Nuclear Engineering Bilich, Dan K. I Research Assistant College of Veterinary Medicine
- Reactor users for research and/or teaching.
I
E ll-2 U
- Binney, Stephen E.
Professor of Nuclear Engineering Chairman, OSTR Reactor Operations Committee "Conard, Bobbi, L. Senior Research Assistant Oceanic and Atmospheric Sciences "Conrady, Michael R. Research Assistant Neutron Activation Analysis Specialist
- Cordell, Sharon M.
Research Assistant Radiation Protection Technologist (through 3/30/94) Craig, A. Morrie Professor, College of Veterinary Medicine Daniels, Malcolm Professor of Chemistry
- Dodd, Brian Reactor Administrator Professor of Nuclear Engineering Groome, John T.
Research Assistant APEX Facility Operations Manager Nuclear Engineering Hart, Lucas P. Research Associate Chemistry Haytas, John J. Research Assistant ( APEX Facility Operator l Nuclear Engineering
- Higginbotham, Jack F.
l Senior Health Physicist 1 Associate Professor of Nuclear Engineering Hovermale, Jeannette T. Research Assistant
- College of Veterinary Medicine l
l l 1
- Reactor users for research and/or teaching.
I
ll-3 King, John B. Instructor of Nuclear Engineering Klein, Andrew C. Associate Professor of Nuclear Engineering
- Kulas, Mary M.
Assistant Professor of Nuclear Engineering Lafi, Abd Y. Research Associate APEX RELAP Analysis Support Nuclear Engineering
- Liu, Yun-Gang Research Associate Chemistry
*Loveland, Walter D.
Professor of Chemistry MacVicar, Robert President Emeritus, OSU I *Martsolf, Steven W. Research Assistant Nuclear Engineering Meggs, Deanna Research Assistant Radiation Center
- Meredith, Charlotte C.
Research Assistant Oceanic and Atmospheric Sciences
*Millan, Monica Visiting Researcher Oregon Health Sciences University, Portland, OR Miller, Michael D.
Research Assistant APEX Facility Operator Nuclear Engineering I
- Reactor users for research and/or teaching.
E 11- 4 0
'Mumford, Margaret Research Assistant Oceanic and Atmospheric Sciences
*Pastorek, Christine Instructor of Chemistry Popovich, Milosh Vice President Emeritus, OSU
- Pratt, David S.
Research Assistant Health Physicist Reyes, Jos6 N. APEX Principal Investigator Associate Professor of Nuclear Engineering
'Ringle, John C.
Professor of Nuclear Engineering Associate Dean of the Graduate School, OSU Robinson, Alan H. Head, Department of Nuclear Engineering Professor of Nuclear Engineering l
'Schmidt, Stephen W.
Research Assistant l Oregon Health Sciences University, Portland, Oregon
*Schmitt, Roman A.
Professor Emeritus, Chemistry i i Sparrow, Margaret l Senior Research Assistant Oceanic and Atmospheric Sciences Srivastava, Alok Research Associate Chemistry l
- Streck, Martin J.
! Research Assistant Radiation Center Geochemist 1 I l
- Reactor users for research and/or teaching.
I
11- 5
*Tharakan, Binesh Research Assistant Radiation Protection Technologist (from 4/1/94) l
- Thompson, David E. !
Research Assistant I Oregon Health Sciences University, Portland, Oregon "Torne, Erwin G. Research Assistant Radiation Center Geochemist Wachenheim, Daniel E. Research Associate College of Veterinary Medicine Wang, Chih H. Director Emeritus, Radiation Center Professor Emeritus, Nuclear Engineering, OSU Willis, David L. Professor Emeritus General Science, OSU Young, Roy A. Professor Emeritus, OSU Yundt, Michael S. Research Assistant APEX Calibration Technician Nuclear Engineering I i I I l I
' Reactor users for research and/or teaching.
I !
- - _ - - _ _ - - _ _ _ _ _ _ _ - _ _l
O 11- 6 E B. Visitina Scientists and Special Trainees Advisor or Research Name Field (Affiliation) Proaram Director Altschul, Brett D. Saturday Academy Mentorship W. D. Loveland g Program, Sprague High School I (Salem, Oregon) Andersson, Mia T. Royal Institute of Technology W. D. Loveland Chemistry (Sweden) Behkami, Aziz N. Visiting Scientist W. D. Loveland I Chemistry (Iran) Ham, Neal Saturday Academy Mentorship W. D. Loveland Program, Pasco High School (Pasco, Washington)
- Liedtke, James D. Visiting Associate Professor A. G. Johnson (Portland Community College)
I I I I I
- Reactor users for research and/or teaching.
I w
11- 7 I C. OSU Graduate Students I l Degree l Name Proaram Field Advisor i Abdul-Hamid, Shahab A. MS Nuclear Engr. A. C. Klein l Al-Hussan, Khalid A. PhD Nuclear Engr. A. C. Klein l Al-Kheliewi, Abdullah S. PhD Nuclear Engr. A. C. Klein l Ala, Abbas PhD Nuclear Engr. S. E. Binney ! I Bahmaid, Mohammad R. I MS Radiation Health J. F. Higginbotham
*Bae, Jung Soo MS Radiation Health J. F. Higginbotham Betts, Curt M. MS, PhD Nuclear Engr. M. M. Kulas '
I *Brockington, Melinda Cantaloub, Michael
- Day, Travis D.
MS MS PhD Oc. & Atm. Sci. Nuclear Engr. Chemistry R. W. Collier J. N. Reyes W. D. Loveland Dickinson, Jeffrey W. A. C. Klein I Dominick, Jared L. Dunn, John R. MS MS PhD Nuclear Engr. Radiation Health Chemistry B.Dodd W. D. Loveland
*Eversmeyer, Bruce MS Chem. Ocean. R. W. Collier I *Fitz, Christopher K.
Franz, Scott C. MS MS, PhD Radiation Health Nuclear Engr. B. Dodd J. N. Reyes Fu, Yingxian PhD Chemistry M. Daniels I Fundak, Robert Gulshan-Ara, Zubaida MS MS, PhD Nuclear Engr. Nuclear Engr. A. C. Klein A. C. Klein
' Hamoudi, Ali K. MS Radiation Health J. F. Higginbotham I Hekkala, Darin
- Johnson, Jennifer E.
MS MS Radiation Health Radiation Health B.Dodd S. E. Binney "Kellar, Marvin MS Radiation Health B.Dodd Lee, Hsing H. PhD Nuclear Engr. A. C. Klein Lee, Taejin PhD Civil Engineering A. M. Craig Lotrario, Joseph MS Environmental Engr. A. M. Craig Ma, Chang Chun PhD Nuclear Engr. J. N. Reyes
- Martin-Bandin, Fernando MS Radiation Health J. F. Higginbotham "Merritt, Patrick A. MS Nuclear Engr. A. C. Klein Nasir, Adil MS Chem. Engr. J. McGuire Pagh, Richard T. MS Nuclear Engr. M. M. Kulas Pimental, David A. MS Nuclear Engr. J. N. Reyes Potter, Nathan K. MS Radiation Health B.Dodd Richardson, Kira L. MS Radiation Health S. E. Binney
" Shepherd, Stephen H. PhD Nuclear Engr. J. C. Ringle Siadal, Jeremy C.
I Stevens, Owen L. Stewart, Donald N. MS MS MS Radiation Health Nuclear Engr. Radiation Health S. E. Binney J. N. Reyes B.Dodd "Streck, M. PhD Geosciences A. Grunder
*Torne, E. MS Geosciences C. Field "Vostmyer, Chris MS Radiation Health S. E. Binney Wang, Yi MS Nuclear Engr. J. N. Reyes Will, Yvonne PhD Biochemistry A. M. Craig l Wu, Re.apo MS Radiation Health B.Dodd l Zhou, Liansheng MS Nuclear Engr. M. M. Kulas i Zyromski, Kristiana E.
PhD Chemistry W. D. Loveland
' Reactor users for research and/or teaching.
11- 8 O D. Business, Administrative and Clerical Staff Director, Radiation Center . ....... ..................... A. G. Johnson Business Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. C. Campbell Administrative Assistant .. . ......................... . D. K. Dalton Office Specialists . . . . . . . . . .......... . . . . . . . . . . . . . . . . . C. L. Phillips J. R. Smith Custodian . . . ...... ... .... .... . . . . . . . . . . . . . . . . . . E. Cim bri Office Coordinator (Nuclear Engineering) . .. . .... . ........... . D. L. Cramer Word Processing Technician (Nuclear Engineering) . . .... .........................R.A. Keen Word Processing Technician (APEX - Nuclear Engineering) . . . . . . . . . . . . . . . . . . . . . . . . . . T. L. Cul ver E. Reactor Operations Staff Principal Security Officer .. .... . ....... .... . . A. G. Johnson Reactor Administrator, Senior Reactor Operator ........ .. ...... . B.Dodd l Reactor Supervisor, Senior Reactor Operator ..... .. .... .. T. V. Anderson 5 Senior Reactor Operators ..... ... .......... . .... . . . . S. E. Binney A. D. Hall E J. F. Higginbotham E S. P. Smith Reactor Operator (Student) . ......... .. .. .... ......... . J. S. Bae - F. Radiation Protection Staff Senior Health Physicist . . . . . . . . . . . . . . . . . . . . . . . . . . . . J. F. Higginbotham Health Physicist . . . . . . ........... . ... .. .. . . . . D. S. Pratt Radiation Protection Technologist .... ....... (through 3/30/94) S. M. Cordell (from 4/1/94) B. Tharakan Health Physics Monitors (Students) . . .... .. .......... M. Cunningham D. Fisher D. Hummell J. Johnson G. Paek D. Sillonis O. Stevens I
11- 9 G. Scientific Support Staff Senior Neutron Activation Analyst . . . . . . . . . . . . . . . . . . . . . . . . . R. A. Schmitt Neutron Activation Analysis Specialist . . . . . . . . . . . . . . . . . . . . . . M. R. Conrady Geochemists . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . M . J. Stre c k E. G. Torne I Neutron Activation Analysis Technicians (Students) ... .. .... J. Johnson D. Maher F. Martin-Bandin I C. Payne 1.Ryu C. Schneider J. Templeton L.Zhang Scientific Instrument Technician . . . . . . ............. .. .... S. P. Smith Nuclear Instrumentation Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J. Bae H. OSU Radiation Safeti Office Staff Radiation Safety Officer ... ..... .. .. . .. . ... ... R. H. Farmer Radiation Specialists . . ... ............ ....... . . . . . . . D. L. Harlan E. F. Forrer I Secretary . ... Student Technicians
. . .. . .... ... . . . . . . K. L. Miller
. . . . . . . . . . . A. Arevalo J. Dominick W. Dunham I R. Miller S. Naguib S. Smith G. Wade
- 1. Committees
- 1. Reactor Operations Committee Name Affiliation S. E. Binney, Chair ...... ... .... . . . . . . . . . . . . Nuclear Engineering D. L. Amort . .... . .. .... . . Electrical and Computer Engineering T. V. Andersor. . ...... . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center I B. Dodd .... . ... . ... ...
J. F. Higginbotham . . . A. G. Johnson ... Radiation Center and Nuclear Engineering Radiation Center and Nuclear Engineering Radiation Center and Nuclear Engineering J. C. Ringle . . . ... . .... .. Nuclear Engineering and Graduate School A. H. Robinson .... . ... ......... . . . . . . . . Nuclear Engineering R. A. Schmitt .. ....... ..... . . Chemistry and Radiation Center W. H. Warnes . . . . .. ..... . ... . Mechanical Engineering
E Il-10 0
- 2. Radiation Safety Committee (OSU)
Name Affiliation C. Rivin, Chair . . . . . . . . . . . . . . . . . . . . . . . . . Botany and Plant Pathology R. Farmer, Secretary & RSO . . . . . . . . . . . . . . . . . . Radiation Safety Office H. Carpenter . . . . .. ............... ....... Fisheries and Wildlife R. Collier . . . . . . . ................ Oceanic and Atmospheric Sciences T. Dreher ..... . .. ...... . . . . . . . . . . . . . . . Agricultural Chemistry J. Higginbotham ...... .... .. Radiation Center and Nuclear Engineering D. K e szie r . . . . . . . . . . . . . . . . . . . ........ ........... Chemistry P. McFadden . ............. ............. Biochemistry / Biophysics C. Schreck .. ...... ....... ............. Fisheries and Wildlife T. Wolpert .... .... .. ............ . Botany and Plant Pathology
- 3. Radiation Center Safety Committee Name Affiliation W. D. Loveland, Chair ... . ......... ................ Chemistry T. V. Anderson . . . . ........................... Radiation Center S. C. Campbell . ... ... ... . .. . . . . . . . . Radiation Center M. R. Conrady . . . . . . . . .... ........ .. . . . . . . . Radiation Center J. F. Higginbotham . . . . . . . .. Radiation Center and Nuclear Engineering A. G. Johnson . . . . ... . . . Radiation Center and Nuclear Engineering S. P. Smith . ............... .. ........... . Radiation Center
- 4. Radiation Center TOM Teams Team No.1 Affiliation B. Dodd, Team Leader . . . . . . .. Radiation Center and Nuclear Engineering T. V. Anderson .. . . ..... ... ..... ..... . Radiation Center S. C. Campbell .. .. .. . . . . . . . . . . . . . . . . . . . . . Radiation Center M. R. Conrady . . . . .. ......... . . . . . . . . . . . . . . . . Radiation Center D. S. Pratt . . . . . . . . . . . . .. . ......... . . . Radiation Center Team No. 2 S. Cordell, Team Leader . .... . .... . .. . . . . . Radiation Center B. Dodd, Facilitator .................. .. . . . . . . . Radiation Center A. Hall . . ............ ........... . . . . . . . . . . . Radiation Center J. Higginbotham .. ...... . .............. ... . Radiation Center I
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PART lli FACILITIES A. Research Reactor
- 1. Description The Oregon State University TRIGA Reactor (OSTR) is a water-cooled, swimming pool type of research reactor which uses uranium / zirconium hydride fuel elements in a circular grid array. The reactor core is surrounded by a ring of graphite which serves to reflect neutrons back into the core. The core is situated near the bottom of a 22-foot deep water-filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support. See Figures Ill. A.1, Ill.A.2 and lli.A.3.
The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at a maximum steady state power of 1.1 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, five sample-holding (dummy) fuel elements for speciat in-core irradiations, and a cadmium-lined in-core irradiation tube for experiments requiring a high energy neutron flux. 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 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 irradiation.
E lil-2 CONTROL RODS 1 C E NT R AL EX P E R IM E NTA L i THIMBLE THERMALIZING l COLU M N 1 y "' ROTARY
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111- 5 The reactor's thermal column consists of a large stack of graphite blocks which slow down neutrons from the reactor core in order to increase thermal neutron activation of samples. Graphite blocks are removed from the thermal column to enable samples to be positioned 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 experiments. If samples which are to be irradiated require a large neutron fluence, especially from higher energy neutrons, then such samples may be inserted into a dummy fuel element. This device will then be placed into one J the core's inner grid positions which would normally be occupied by a fuel element. The cadmium-lined in-core irradiation tube enables samples to be irradiated in a high flux region near the center of the core. The cadmium lining in the facility eliminates thermal neutrons and thus permits sample exposure to epithermal I neutrons only. The cadmium-lined end of this air-filled aluminum irradiation tube is inserted into an inner grid position of the reactor core which would normally be I occupied by a fuel element.
- 2. Utilization The two main uses of the OSTR are instruction and research. During this reporting I period, the reactor was in use an average of 39 hours during a typical 45-hour work week. Hence, the reactor was used approximately 87% of the available I time.
I I I .
O lil-6 E
- 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 presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstra-tions and instructional experiments can be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experiments are also performed for many undergraduate students in physics, chemistry and biology classes, as well as for visitors from other universities and colleges, from high schools and from public groups.
The second instructional application of the OSTR involves education of reactor operators, operations managers, and radiation health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiation Center provides are more fully described in Part VI (section VI.C.5) of this report. During this reporting period the OSTR accommodated 27 different OSU academic classes. In addition, portions of classes from other Oregon universities were also supported by the OSTR. The OSU teaching programs utilized 498 hours of reactor time. Tables Ill.A.1 and Ill.A.2 as well as Table Ill.E.1 provide detailed information on the use of the OSTR for instruction and training.
- b. Research The OSTR is a unique and valuable tool for a wide variety of research I applications, and serves as an excellent source of neutrons and/or gamma radiation. The most popular experimental technique requiring reactor use is 5
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I Table Ill.A.1 lil-7 OSU Courses Using the OSTR Course Number Course Name NE 111 Introduction to Nuclear Engineering NE 113 Introduction to Nuclear Engineering NE 233 Nuclear Radiation Detection and Instrumentation RHP 233 Nuclear Radiation Detection and Instrumentation NE 457 Nuclear Reactor Laboratory NE 479 Individual Design Projects (Nuclear Engineering) RHP 480 Field Practices in Radiation Protection (Undergraduate) NE 484 Applied Radiation Safety RHP 484 Applied Radiation Safety I NE 503 Thesis (Nuclear Engineering) RHP 503 Thesis (Radiation Health Physics) I NE 549 Selected Topics /Hanford's Radioactive Waste: Technical & Social Issues NE 580 Field Practices in Radiation Protection (Graduate) I RHP 580 Field Practices in Radiation Protection (Graduate) RHP 584 Applied Radiation Safety (Graduate) CH 219 General Chemistry Laboratory CH 222 General Chemistry for Science Majors CH 462 Experimental Chemistry ll CH 503 Thesis (Chemistry) CH 577 Experimental Nuclear Chemistry GEO 503 Thesis (Geosciences) H 441/541 Environmental Health OC 503 Thesis (Oceanography) I Asia University, America Office (OSU) Japanese Class Adventures in Learning Visiting Students Saturday Academy Visiting Students SMILE Program Teacher's Short Course I I
O lll-8 E Table Ill.A.2 OSTR Teaching Hours Cumulative Values Description Annual alues for FLIP Core (hours) (hours) Departmental 294 4,526 Nuclear Engineering 230 Chemistry 49 Geosciences"' Oceanic and Atmospheric Sciences") - Public Health 4 Asia University (OSU) 4 Adventures in Learning 3 Saturday Academy 2 SMILE Program 2 Special Classes and Projectsi2' 204 967 Total Teaching Hours' ^5) 498 5,493 I (1) Some use hours by these departments are not shown under " Teaching Hours," but are reflected under Thesis Research, both funded and unfunded. (2) A variety of educational classes were conducted which involved one-time meetings for orientation or support purposes. These included: high school science classes, new student programs support, reactor operator orientation and training, community college classes and classes from other universities. (3) See Table Ill.E.1 for classes and student enrollment. (4) See Table IV.A.5 for a summary of all reactor use categories. (5) Total teaching hours reflect all time the reactor was in use for teaching, and because of this the total hours include time the reactor itself may not actually have been in operation. I 1 E
111- 9 neutron activation analysis (NAA). This is a particularly sensitive method of elemental analysis which is described in more detail in Part VI (section j VI.C.1 ). Part 111.8 provides a listing of equipment used in NAA at the j Radiation Center. ! l l The OSTR's irradiation facilities provide a wide range of neutron flux levels and neutron flux qualities, which are sufficient to meet the needs of most researchers. This is trJe not only for NAA, but also for other experimental techniques such as fission track dating of geological and anthropological materials. I During this reporting period, the OSTR accommodated 111 funded research projects which utilized 1,513 hours of reactor time, and 14 unfunded research projects which utilized 57 hours of reactor time. Details of the reactor's use specifically for research are given in Table Ill.A.3. Additional information regarding reactor use for research, thesis and service can be found in Tables VI.C.1 through VI.C.3. In these tables OSTR use is indicated with an asterisk. I I I I I I
E_ 111- 1 0 C Table Ill.A.3 OSTR Research Hours Cumulative Values Annual Values for FLIP Core Types of Research
. (hours)- . (hours)
OSU Research 296 7,276 I Off-Campus Research 1,274 7,037 Total Research Hours on2) 1,570 14,313 (1) Total research hours statistics: (a) 96% (1,513 hours) of the total research hours were user-funded by federal, g stats, or other organizations. m (b) 4% (57 hours) of the total research hours were i'ser-unfunded studies in support of graduate thesis research or other academic investigations. Reactor costs for this research were absorbed (funded) by the OSU Radiation Center. (2) OSTR use hours in support of OSU teaching and research programs equal approximately 39% of the hours the OSTR operated for off-campus research projects. Of the off-campus research iaurs OSTR recorded, approximately 11 hours were in direct support of research being conducted at the University of Oregon. Another 25 hours supported research being conducted at the Oregon Graduate Institute and Willamette University. I I I I s
=
111- 1 1 B. Analytical Eauipment
- 1. Descriotion The Radiation Center has a great variety of radiation detection instru nentation.
Much of this equipment involves the latest in counting technology as reoresented by the state-of-the-art gamma ray spectrometers with their associated c imputers and Ge(Li) or intrinsic germanium detectors. Tables Ill.B.1 through lil.B.4 provide I a brief listing of typical laboratory counting devices present at the Center. Much additional equipment for use in the classroom, and an extensive inventory of I portable radiation detection instrumentation are also available.
- 2. Utilization Radiation Center nuclear instrumentation receives intensive use in both teaching and research applications. In addition, service projects also use these systems and the combined use often results in 24-hour per day schedules for many of the analytical instruments. Use of Radiation Center equipment extends beyond that located at the Center and instrumentation is commonly made available on a loan basis to OSU researchers in other departments.
4 i
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l I 1 i l l l l
E Ill-12 U Table lil.B.1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, Alpha Rel. Effic. Room System (%) 8100 Adcam 1,8k Ortec, Ortec HP Ge 26.8 B100 Adcam 2,8k Ortec, Ortec HP Ge 38.1 B100 Adcam 3, 8k Ortec, Canberra Ge(Li) 16.6 B100 Adcam 4,8k Ortec, Ortec HP Ge 28.8 D102 Adcam 5, 8k Ortec, PGT Ge(Li) 12.1 C120 Ace 1,4k Ortec, Nal(TI) 3x3 N/A C123 Ace 2,4k Ortec, PGT Ge(Li) 18.7 A138 H.P. Scaler, Nal(TI) 2x2 N/A A146 Ace,4k Ortec, Ortec HP Ge 30.0 A146 Ace,4k Ortec, Ortec Ge(Li) 27.0 C134 Adcam MCA, PGT Ge(Li) 16.2 C134 Adcam MCA, PGT Ge(Li) 19.3 C134 Adcam MCA, PGT LEP N/A C134 Adcam MCA, Ortec LEP N/A C120 Ace 3,4k Ortec,576A Alpha Spectrometer N/A l l I l 1 I I l I i
111- 1 3 l Table Ill.B.2 I Radiation Center Liquid Scintillation Counting Systems ! l
' Room . System C120 Beckman, Betamate C120 Beckman, Betamate C120 Beckman, Betamate C120 Beckman, Betamate B136 Beckman, LS 6500 B136 Beckman, LS 7500 e
I i l l I , I l l l
O 111- 1 4 E Table Ill.B.3 Radiation Center Proportional Counting Systems Room _ System C120 NMC 1, PC5 I C120 NMC 2, PC5 C120 NMC 3, PC5 A138 NMC, PCC-11T and DS 2 A138 Tennelec Auto Counting System w/ IBM PC E a
lil-15 Table Ill.B.4 Thermoluminescent Dosimeter Systems I Room System C120 Teledyne TLD 7300 C120 Teledyne TLD 7300 C120 Teledyne TLD 7300 C120 Teledyne TLD 7300 B124 Harshaw Model 2000 A132 Harshaw Model 2000 I I I l I , I 1 l l
u ill-16 E C. Radioisotone Irradiation Sources
- 1. Description The Radiation Center is equipped with two S Co irradiation facilities: an older Budd irradiator and a Gammacell 220 irradiator. These two irradiators complement each other and are capable of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.
Typically, the irradiators are used by researchers wishing to perform mutation and other biological effects studies, studies in the area of radiation chemistry, dosimeter testing, sterilization of food materials, soils, sediments and other media, gamma radiation damage studies, and other such applications. In addition to the S Co irradiator, the Center is also equipped with a variety of smaller S Co, '87Cs, 22sRa, plutonium-beryllium, and other isotopic sealed sources of various cur:e levels which are available for use as irradiation sources.
- 2. Utilization During this reporting period there was a diverse group of projects using the
- Co irradiators. These projects included the irradiation of a variety of biological cells as well as the irradiation of various seeds. In addition, the irradiators were used for radiation dosimeter analysis, sterilization of several media, and materials evaluation. Data showing uses of the Budd irradiator for this reporting period are given in Table Ill.C.1. Table Ill.C.2 provides use data for the Gammacell 220 irradiator.
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111- 1 9 Table Ill.C.1 Budd 5 Co Irradiator Use (60 Ci: 7/1/93) Purpose of ' Dose Range Number of ' Use Time Irradiation Samples - (rads) - Irradiations - (hours) . 1.0 x 10 2 i i g.ical Cells, mice to 9 23 Studies 2.6 x 10'
.O x 10 2 Dosimeter TLDs, other Analysis dosimeters 6.0 x 102 TOTALS -- --
12 24 I I I I I I
E lil-20 U I Table Ill.C.2 Gammacell 220 8 Co irradiator Use (4679 Ci: 7/1/93)
' Purpose of . Dose Range . Number of Use Time -
Irradiation Samples . (rads) Irradiations - (hours) . Talc, blood semm, wood, 1.7 x 10 8 Sterilization to 93 1,590 latex, diesel, soil, water 5.0 x 108 Wood, con- 5.0 x 10 5 Material to 5 3,071 Evaluation crete, plastic 1.0 x 108 2.5 x 10 3 Botanical Bean seeds to 5 2 Studies 8.0 x 10' Biological Spleen cells' Studies cells 3.0 x 10 21 <1 TOTALS --- -- 124 4,663 I I I I i
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111- 2 1 D. X-Ray Machine i
- 1. Description l A General Electric Maxitron 300 kVp X-ray generator is located in the Radiation
, Center. This device is situated in a shielded room which is large enough to accommodate a wide variety of experiments. The machine is capable of operating at 300 kVp and 20 mA, and devices for calibrating the beam intensity are l available. I 2. Utilization The X-ray machine continued to be used as a radiation source where students could perform state-required radiation surveys of a fixed X-ray machine installation ) and carry out other safety checks required for such a facility. In addition, the X-ray machine was used three times (0.8 hours) for checking X-ray instrument response. l l I I l
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fl 111- 2 2 E E. Laboratories and Classrooms
- 1. Description The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate classes offered by various OSU academic departments or off-campus groups.
Instructional facilities available at the Center include a laboratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with modular sets of countirig equipment which can be configured to accommodate a variety of experiments involving the measurement of many types of radiation. The Center also has three student computer rooms equipped with a large number of personal computers and engineering workstations. In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equipment are regularly used for teaching. In particular, classes are routinely given access to appropriate state-of-the-art gamma spectroscopy equipment located in Center laboratories. A number of classes also regularly use the reactor and the reactor bay as an integral part of their instructional coursework. There are two classrooms in the Radiation Center which are capable of holding I about 16 and 35 students. In addition, there are two smaller conference rooms ; and a library that are suitable for graduate classes and thesis examinations. As l a service to the student body, the Radiation Center also provides an office area for the student chapters of the American Nuclear Society and the Health Physics i Society. 1 This reporting period saw further developments in the Radiation Center's thermal hydraulics laboratory. This laboratory is being used by a member of the nuclear I engineering f aculty to accommodate a one-quarter scale model of the Westing- l house Electric Corporation AP600 reactor. The AP600 is a next-generation reactor I E w
lil-23 which features simplicity, passive safety and standardization in its design. Construction of the multi-million dollar advanced plant experimental (APEX) test f acility was completed and the initial test phase commenced during this reporting period. The fully scaled, integral model APEX facility uses electrical heating elements to simulate the fuel elements, operates at 450 F and 400 psia and responds at twice real time. It is the only facility of its type in the world and is being used by Westinghouse, the U.S. Nuclear Regulatory Commission and other organizations to test the safety systems and provide licensing data. APEX is owned by the U.S. Department of Energy, designed by Westinghouse, and operated by OSU. I 2. Utilization All of the laboratories and classrooms are used extensively during the academic year. For example, a listing of 71 courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table Ill.E.1. Table Ill.A.1 gives a separate listing of the 27 classes specifically accommodated by the reactor during the reporting period. I
E Ill-24 8 Table Ill.E.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students Course Credit Course Title Fall Winter Spring Summer 1993 1994 1994 1994 Nuclear Engineering Department Courses NE 111
- 3 Introduction to Nuclear Engineering 19 -- - -
NE 112 3 Introduction to Nuclear Engineering - 18 - - NE 113* 3 Introduction to Nuclear Engineering -- - 19 - NE 231 3 Nuclear & Radiation Physics 15 - - - RHP 231 3 Nuclear & Radiation Physics 2 - - - NE 232 3 Nuclear & Radiation Physics -- 12 - - RHP 232 3 Nuclear & Radiation Physics - 1 -- - NE 233' 3 Nuclear Radiation Detection & Instrumentation - - 11 - RHP 233' 3 Nuclear Radiation Detection & Instrumentation -- - 1 - NE 361 3 Nuclear Reactor Systems - - 11 - NE 381 3 Principles of Radiation Safety 13 - - - RHP 381 3 Principles of Radiation Safety 9 - - - RHP 405 1 16 Projects 1 - - - NE 406 1-16 Projects 2 -- 2 3 NE 407 1 Nuclear Engineering Seminar 17 18 17 - NE 410 1-12 Internship -- - - 1 NE 444 3 Nuclear Fuel Cycle -- 24 - - 3 RHP 444 3 Nuclear Fuel Cycle - 7 -- - l NE 454 3 Nuclear Reactor Analysis 13 - - - l NE 455 3 Nuclear Reactor Analysis - 13 - - NE 456 3 Nuclear Reactor Analysis - - 13 -- NE 457' 3 Nuclear Reactor Laboratory - - 13 - NE 467 4 Nuclear Reactor Thermal Hydraulics 15 - - - NE 471 3 Nuclear Power Systems Design 15 - - -- g NE 472 3 Nuclear Power Systems Design - 15 - - E I NE 473 3 Nuclear Reactor Design - - 15 -- l NE 479*
- 1-4 Individual Design Project 3 1 5 4 l RHP 480* 1-3 Field Practices in Radiation Protection 2 -
1 1 l NE 484*
- 3 Applied Radiation Safety -
10 -- - l RHP 484 *
- 3 Applied Radiation Safety -
7 - - NE 486 3 Radiation Dosimetry - - 10 - (HP 486 3 Radiation Dosimetry - - 6 - RHP 487 3 Radiation Biology - - 13 - NE 501 1-16 Research -- - 1 --
*0STR used occasionally for demonstration and/or experiments.
I
* *0STR used heavily.
i l l l 111- 2 5 ) i l Table Ill.E.1 (Continued) i I Number of Students i 1 Course Credit Course Title Fall Winter Spring ' Summer 1993 1994 1994 1994 I RHP 501 NE 503*
- 1-16 1-16 Research Thesis 3
5 1 3 1 2 1 RHP503** 1-16 Thesis 6 4 5 - NE 505 1-16 Reading & Conference 1 2 1 - RHP 505 1-15 Reading & Conference 1 - - 1 NE 506 1-16 Projects 1 - -- - NE 507 1 Seminar 4 5 1 -- RHP 510 1-12 Internship 1 1 1 - NE 535 3 Nuclear Radiation Shielding - 5 -- - l RHP 535 3 Nuclear Radiation Shielding -- 8 - - NE543 3 Radioactive Waste Management - - 5 - RHP 543 3 Radioactive Waste Management - -- 14 - NE544 3 Nuclear Fuel Cycle - 5 - - RHP544 3 Nuclear Fuel Cycle - 2 - - ST/Hanford's Radioactive Waste & lts impact on NE 549' 3 - - - 12 Oiegon: An Overview of Social & Technical issues NE 554 3 Advanced Nuclear Reactor Analysis 2 - - - NE 555 3 Advanced Nuclear P.eactor Analysis - 2 - - NE 556 3 Advanced Nuclear Reactor Analysis - - 1 - NE 568 3 Nuclear Reactor Safety 11 - - - RHP 580* 1-3 Field Practices in Radiation Protection 1 - 1 - RHP 584*
- 3 Applied Radiation Safety --
1 - -- NE 586 3 Advanced Radiation Dosimetry - - 2 - RHP 586 3 Advanced Radiation Dosimetry -- -- 2 - RHP 587 3 Advanced Radiation Biology - -- 10 - RHP 589T 3 ST/ Transportation of Radioactive Materials - 18 - - NE 601 1-16 Research 1 1 - - NE 603 1-16 Thesis (Nuclear Engineering) 6 5 4 1 NE 607 1 Nuclear Engineering Seminar - 1 - - NE 654 3 Neutron Transport Theory 6 - - - NE 667 3 Advanced Thermal Hydraulic- - 5 - - l I
*OSTR used occasionally for demonstration and/or expenments. * *0STR used heavity.
O4 111- 2 6 I Table Ill.E.1 (Continued) Number of Students Course Credit Course Title Fall Winter Spring Summer 1993 1994- 1994 1994 Chemistry Courses CH 219* 2 General Chemistry Lab 35 - - - CH 222* 5 General Chemistry (Science Majors) - 332 -- - CH 462* 3 Experimental Chemistry 11 Laboratory - 17 - - CH 503* 1-16 Thesis (Chemistry) 4 4 4 - CH 577*
- 4 Experimental Nuclear Chemistry - -
3 - Other Courses GEO 503* 1-16 Thesis (Geosciences) 2 2 2 - OC 503* 1-16 Thesis (Oceanography) 1 1 1 - I I' Il l l II I l
*OSTR used occasionally for demonstration and/or experiments. I * *OSTR used heavily. ll me
lll-27 F. Instrument Repair and Calibration Facility
- 1. Descriction The Radiation Center has a facility for the repair and calibration of essentially all types of radiation monitoring instrumentation. This includes instruments for the detection and measurement of alpha, beta, gamma and neutron radiation, and encompasses both high range instruments for measuring intense radiation fields and low range instruments used to measure environmental levels of radioactivity.
The Center's instrument calibration capability is described more completely in Section VI.C.7 of this report.
- 2. Utilization The Center's instrument repair and calibration facility is used regularly throughout each year and is absolutely essential to the continued operation of the many different programs carried out at the Center. In addition, the absence of any comparable f acility in the state has led to a greatly expanded instrument calibration program for the Center, including calibration of essentially all radiation detection instruments used by state and federal agencies in the state of Oregon. This includes instruments used on the OSU campus, plus instruments from the Oregon I Health Division's Rediation Control Section, the Oregon Department of Energy, the Oregon Public Utilities Commission, the Oregon Health Sciences University, the Oregon Occupational Health Laboratory, the U.S. Environmental Protection Agency, and the U.S. Department of Agriculture. Additionalinformation regarding instrument repair and calibration efforts, is given in Tables VI.C 4, VI.C.5, and VI.C.6.
I I I
O 111- 2 8 E G. Libraries
- 1. Description The Radiation Center has libraries containing significant collections of texts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection.
The Radiation Center is also a regular recipient of a great variety of publications from commercial publishers in the nuclear field, from many of the professional nuclear societies, from the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission and other federal agencies. Therefore, Center libraries maintain a current collection of leading research and regulatory documentation in the nuclear area. In addition, the Center has a collection over 50 sets of nuclear power reactor safety analysis and environmental reports specifically prepared by utilities for their facilities. The Center maintains an up-to-date set of reports from such organizations as the international Commission on Radiological Protection, the National Council on Radiation Protection and Measurements, and the International Commission on Radiological Units. Sets of the current U.S. Code of Federal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation and other appropriate federal agencies, plus regulations of various state regulatory agencies are also available at the Center. The Radiation Center videotape library has over one hundred tapes on nuclear I engineering, radiation protection and radiological emergency response, in addition, the Radiation Center uses videotapes for most of the technical orientations which are required for personnel working with radiation and radioactive materials. These tapes are produced, recorded and edited by Radiation Center staff, using the Center's videotape equipment and the f acilities of the OSU Communication Media Center. I E sa
ll!-29 I 2. Utilization Radiation Center libraries are used mainly to provide reference material on an I as-needed basis; however, they receive extensive use during the academic year. In addition, the orientation videotapes are used intensively during the beginning of each term, and periodically thereafter. I I I I I I
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PARTIV REACTOR A. Operatina Statistics For the current reporting period, the operating statistics for the OSTR made a significant increase as shown in this section. Operating data by individual category are given in Table IV.A.1 and annual energy production is plotted in Figure IV.A.1. Table IV.A.2 is included mainly for reference and summarizes the operating statistics for the original 20% enriched fuel. The thermal energy generated in the reactor during this reporting period was 46.7 megawatt days (MWD). The cumulative thermal energy generated by the FLIP core now totals 656.2 MWD from August 1,1976 through June 30,1994. Reactor use time averaged approximately 87% of the normal nine-hour, five-day per week schedule. Tables IV.A.3 through IV.A.5 detail the operating statistics applicable to this reporting period. No fuel elements were removed or added during the reporting period. The reactor core excess reactivity has increased slightly over this reporting period. This slight increase is due to the erbium poison being burned up at a faster rate than the fuel. I I I I I I I
Table IV.A.1 E OSTR Operating Statistics (Using the FLIP Fuel Core) h Operational . . Data August 1,1976 July 1,1977 July 1,1978 July 1,1979 July 1,1980 July 1,1981 July 1,1982 July 1,1983 for Through Through Through Through Through Through Through Through FLIP Core June 30,1977"' June 30,1978 June 30,1979 June 30,1980 June 30,1981 June 30,1982 June 30,1983 June 30,1984 Operating Hours 875 819 458 875 1255 1192 1095 1205 (critical) Megawatt 451 496 255 571 1005 999 931 943 Hours Megawatt 19.0 20.6 10.6 23.8 41.9 41.6 38.8 39.3 Days Grams 2"U Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 49.3 Hours at Full Power 401 481 218 552 998 973 890 929 (1 MW) Numbers of Fuel Elements 85 0 2 0 0 1 0 0 Added or Removed (-) Number of Irradiation 44 375 329 372 348 408 396 469 Requests (1) The reactor was shutdown on July 26,1976 for one month in order to completely refuel the reactor with a new FLIP fuel core. M M M M M M M m M mm
M M M M M M M M M M M M M Table IV.A.1 (continued) OSTR Operating Statistics (Using the FLIP Fuel Core) Op rational Data July 1,1984 July 1,1985 July 1,1986 July 1,1987 July 1, .1988 July 1,1989 ' July 1,1990 July 1,1991 ' for Through Through Through Through Through - Through Through Through
' FLIP Core June 30,1985 June 30,1986 June 30,1987 June 30,1988 June 30,1989 June 30,1990 June 30,1991 June 30,1992 Operating Hours 1205 1208 1172 1352 1170 1136 1094 1158 (critical)
Megawatt 946 1042 993 1001 1025 1013 928 1002 Hours Megawatt 39.4 43.4 41.4 41.7 42.7 42.2 38.6 41.8 Days Grams '"U 49.5 54.4 51.9 52.3 53.6 53.0 48.5 52.4 Used Hours at Full Power 904 1024 980 987 1021 1009 909 992 (1 MW) Numbers of Fuel Elements 0 0 0'" - 2 ' 2' O - 1, + 1 m 3m ein Added or Removed (-) Number of irradiation 407 403 387 373 290 301 286 297 Requests (1) No fuel elements were added, but one fueled follower control rod was replaced. (2) Two fuel elements were removed due to cladding deformation. (3) One fuel element removed due to cladding deformation and one new fuel element added. 5 (4) One fuel element removed for core excess adjustment. 6 l (5) No fuel elements were added, but the instrumented fuel element was replaced.
Table IV.A.1 (continued) Q E OSTR Operating Statistics (Using the FLIP Fuel Core) Operational . Data July 1,1992 July 1,1993 July 1,1994 July 1,1995 July 1,1996 July 1,1997 July 1,1998 July 1,1999 > for Through Through Through Through Through Through Through ' Through FLIP Core June 30,1993 June 30,1994 June 30,1995 June 30,1996 June 30,1997 June 30,1998 June 30,1999 June 30, 2000 Operating Hours 1180 1248 (critical) Megawatt 1026 1122 Hours Megawatt 42.7 46.7 Days Grams U 53.6 58.6 Used Houts at Full Power 1000 1109 (1 MW) Numbers of Fuel Elements O O Added or Removed (-) Number of Irradiation 329 303 Requests EM m m_ _ _ _ _ _ - - _ _ _ _ _ m e e m gg
M M M Table IV.A.2 OSTR Operating Statistics with the Original (20% Enriched) Standard TRIGA Fuel Core Operational . . . TOTAL: Data Mar 8,67 Jul 1, 68 - Jul 1, 69 .Apr 1, 70 Apr 1, 71 Apr 1, 72 Apr 1, 73 Apr 1, 74 Apr 1, 75 : Apr 1, 76 for 20% Through Through Through Through Through Through Through Through Through Through -' March 67 Enriched Jun 30, 68 Jun 30,69 Mar 31, 70 Mar 31,71 Mar 31,72 Mar 31,73 Mar 31, 74 Mar 31, 75 Mar 31,76 -Jul 26, 76 Through Core (1) (2) (3) (4) - July 76 Operating Hours 904 610 567 855 598 954 705 563 794 353 6903 (critical) Megawatt 117.2 102.5 138.1 223.8 195.1 497.8 335.9 321.5 408.0 213.0 2553.0 Hours Megawatt 4.9 4.3 5.8 9.3 9.1 20.7 14.1 13.4 17.0 9.0 106.4 Days Grams '"U 6.1 5.4 7.2 11.7 10.2 26.0 17.6 16.8 21.4 10.7 133.0 Used i Hours at Full Power 429 369 58 --- - -- - -- -- - 856 f250 kW) Hours at Full Power -- -- 20 23 100 401 200 291 460 205 1700 (1 MW) Number of Fuel Elements 70 2 13 1 1 1 2 2 2 0 94 Added to (in:tial) Core Number of Irradiation 429 433 391 528 347 550 452 396 357 217 4100 Requests Number of 202 236 299 102 98 249 109 183 43 39 1560 Pulaes (1) Reactor went critical on March 8,1967 (70 element core; 250 kW). Note: This period length is 1.33 years as initial criticality occurred in March of 1967. (2) Reactor shut down August 22,1969 for one month for upgrading to 1 MW (did not upgrade cooling system). Note: This period length is only O.75 years as there was a change in the reporting period from July-June to April-March. (3) Reactor shut down June 1,1971 for one month for cooling system upgrading. (4) Reactor shut down July 26,1976 for one month for refueling reactor with a new full FLIP fuel core. Note: This period length is 0.33 years. E dn
IV-6 I Table IV. A.3 Present OSTR Operating Statistics Operational Data Cumulative Values for Annual Values for FLIP Cere FLIP Core MWH of energy produced 1,122 15,749 MWD of energy produced 46.7 656.2 l Grams 23sU used 58.6 823.8 Number of fuel elements added to (+) or removed from (-) the core O 82 + 3 FFCRM) Number of pulses 9 1,201 Hours reactor critical 1,248 19,962 Hours at full power (1 MW) 1,109 15,377 Number of startup and shutdown checks 254 4,534 Number of irradiation requests l processed (2) 303 6,516 i Number of samples irradiated 3,890 75,121 (1) Fuel Follower Control Rod. These numbers represent the core loading at the end ! of this reporting period. (2) Each irradiation request could authorize from 1 to 120 samples. The number of samples per irradiation request averaged 12.8 during the current reporting period. i I' I' I, Ii l 5
I IV-7 I t Table IV.A.4 I OSTR Use Time in Terms of Specific Use Categories OSTR Use Category - Annual . Values . Cumulative Values (hours) for FLIP Core { rs) Teaching (departmental and others)"' 498 5,493 OSU research(2) 296 7,276 I
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Off-campus research:2> t 1,274 7,037 Forensic services 16 P Reactor preclude time 176* 797 12,886 Facility time") 205 6,240 Visitor demonstration
- 8 279 L
Total reactor use time 3,094 39,387 p (1) L See Tables Ill.A.2 and Ill.E.1 for teaching statistics. (2) See Table Ill.A.3 for research statistics. (3) Prior to the 1981-1982 reporting period, forensic services were grouped under another r l use 1982 category report. and the cumulative hours have been compiled beginning with the 1981-i (4) The time OSTR spent operating to meet NRC facility license requirements. (5) This is the time that th:: (demonstration) events. The remainder of the visitors viewed the reactor dre uring times when the reactor was being operated for regularly scheduled research and tea .
IV-8 Table IV.A.5 OSTR Multiple Use Time") Cumulative Values Annual Values for FLIP Core Number of Users (hours) (hours) 2,119 305 Two 124 687 Three 29 230 Four 13 55 Five 0.5 31.5 Six 10 Seven 0 t 3,122.5 a) I 471 <2) Total multiple use time (1) Multiple use time is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor. (2) This represents 38% of the total hours the reactor was critical during this reporting period. (3) This represents 16% of the total hours the reactor was critical since startup with F fuelin August of 1976. I I I I I I I ll,
IV-7 j Table IV.A.4 OSTR Use Time in Terms of Specific Use Categories Cumulative Values OSTR Use Category Annual Values
- for FLIP Core thours)
(hours) Teaching (departmental and 498 5,493 others)M8 OSU research<2) 296 7,276 Off-campus research(2) I 1,274 7,037 Forensic services 16 176(3) Aeactor preclude time 797 12,886 Facility time (* 205 6,240 Visitor demonstration (5) 8 279 I Total reactor use time 3,094 39,387 (1) See Tables Ill.A.2 and Ill.E.1 for teaching statistics. (2) See Table ill.A.3 for research statistics. (3) Prior to the 1981-1982 reporting period, forensic services were grouped under another use category and the cumulative hours have been compiled beginning 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. I I
O IV-8 E Table iV.A.5 I OSTR Multiple Use Time"I Cumulative Values Number of Users Annual Values for FLIP Core (hours) (hours) Two 305 2,119 Three 124 687 Four 29 230 Five 13 55 Six 0.5 31.5 Seven 0 10 Total multiple use time 471 <2) 3,122.5(3) (1) Multiple use time is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor. (2) This represents 38% of the total hours the reactor was critical during this reporting period. (3) This represents 16% of the total hours the reactor was critical since startup with FLIP fuelin August of 1976. I I I I E
m m m m M 60 - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
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U 1976-77: 19.0 MWD C / 1977-78: 20.6 MWD a . 1978-79: 10.6 MWD y - 1979-80: 23.8 MWD 1980-81: 41.9 MWD g a 1981-82: 41.6 MWD tyi 1982-83: 38.8 MWD O 1983-84: 39.8 MWD . 2 20 "fg 1984-85: 39.4 MWD _ 1985-86: 43.4 MWD .
\ 1986-87: 41.4 MWD .
1987-88: 41.7 MWD
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1988-89: 42.7 MWD
- 1989-90: 42.2 MWD 1990-91: 38.6 MWD 1991-92: 41.8 MWD 1992-93: 42.7 MWD 1993-94: 46.7 MWD 0 t- -{ -- }-- -} ---- l- --{ ---t--f---} --l --- { [-- t- -- l - l l--i---{
92-93 76-77 78-79 80-81 82-83 84-85 86-87 88-89 90-91 77-78 79-80 81-82 83-84 85-86 87-88 89-90 91-92 93-94 Time (Annual Reporting Period) 7 6 Figure IV.A.1 OSTR Annual Energy Production Vs. Time (Annual Reporting Period)
l 0 IV-10 E B. Experiments Performed
- 1. Acoroved Experiments During the current reporting period there were eight approved reactor experiments available for use in reactor-related programs. The following list of reactor experiments identifies the eight approved experiments. Missing numbers signify reactor experiments which are in the inactive file and are not currently being used.
These are listed in the next section. A-1 Normal TRIGA Operation (No Sample Irradiation). B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities. l B-11 Irradiation of Materials involving Specific Quantities of Uranium and Thorium in the Standard OSTR frradiation Facilities. 1 B-12 Exploratory Experiments. B-23 Studies Using TRIGA Thermal Column. ll ; B-29 Reactivity Worth of Fuel. B-30 NAA of Jet, Diesel, and Furnace Fuels. B-31 TRIGA Flux Mapping. Of the approved experiments on the active list, four were used during the reporting period. A tabulation of information relating to reactor experiment use is given in Table IV.B.1, and includes a listing of the experiments which were used, how often each was used, and the general purpose of the use. I I E si
IV-11 Table IV.B.1 Use of OSTR Reactor Experiments ul Reactor Facility: Experiment Research Teaching Forensic Timem TOTAL Numbert2) A-1 N/A 37 0 50 87 B-3 143 21 7 N/A 171 B-11 33 0 0 N/A 33 B-23 12 O O N/A 12 TOTAL 188 58 7 50 303 (1) This table displays the number of times reactor cAperiments were used for a particular purpose. (2) The following tabulation gives the number of each reactor experiment used and its corresponding title: A-1 Normal TRIGA Operation B-3 Irradiation of Materials in the Standard OSTR trradiation Facilities B-11 Irradiation of Materials involving Specific Quantities of Uranium and Thorium in the Standard OSTR frradiation Facilities B-23 Studies Using the TRIGA Thermal Column (3) The time OSTR spent operating to meet NRC facility license requirements. I I , I l I 1 1
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IV-12
- 2. Inactive Experiments Presently, 29 experiments are in the inactive file. This consists of experiments which have been performed in the past and may be reactivated. Many of these experiments are now performed under the more general experiments listed in the previous section. The following list identifies these 29 inactive experiments.
A-2 Measurement of Reactor Power Level via Mn Activation. A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack. A-4 Neutron Flux Measurements in TRIGA. A-5 Copper Wire Irradiation. A-6 in-core Irradiation of LiF Crystals. A-7 investigation of TRIGA's Reactor Bath Water Temperature Coefficient and High Power Level Power Fluctuation. B-1 Activation Analysis of Stone Meteorites, Other Meteorites, and Terrestrial Rocks. B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column. B-4 Flux Mapping. B-5 in-core Irradiation of Foils for Neutron Spectral Measurements. B-6 Measurements of Neutron Spectra in External irradiation Facilities. B-7 Measurements of Gamma Doses in External Irradiation Facilities. B-8 lsotope Production. B-9 Neutron Radiography. B-10 Neutron Diffraction. B-13 This experiment number was changed to A-7. B-14 Detection of Chemically Bound Neutrons. B-15 This experiment number was changed to C-1. B-16 Production and Preparation of isp, I M u
m IV-13 B-17 Fission Fragment Gamma Ray Angular Correlaticns. B-18 A Study of Delayed Status (n, y) Produced Nuclei. B-19 Instrument Timing via Light Triggering. B-20 Sinusoidal Pile Oscillator. B-21 Beam Port #3 Neutron Radiography Facility. B-22 Water Flow Measurements Through TRIGA Core. > B-24 General Neutron Radiography. I B-25 Neutron Flux Monitors. B-26 Fast Neutron Spectrum Generator. B-27 Neutron Flux Determination Adjacent to the OSTR Core. B-28 Gamma Scan of Sodium (TED) Capsule. C-1 PuO2 Transient Experiment. I I I E
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El IV-14 g C. Unolanned Shutdowns There were five unplanned reactor scrams during the current reporting period. A scram occurs when the rods drop in as a result of an automatic trip or as a result of the operator pushing the manual trip button. Table IV.C.1 contains a summary of the unplanned scrams including a brief description of the cause of each. I I I I! l 1 I' I! 1 E! EE i i
IV-15 I Table IV.C.1 Unplanned Reactor Shutdowns and Scrams Number of Type of Event . Occurrences Cause of Event Chart recorder drive motor failure. Drive repaired and I Manual Scram 1 reactor operation resumed. Manual Scram 1 Failure of SHIM rod CONT /ON switch. Switch repaired. Scram Buss 1 Failure of the SHIM rod UP switch caused the scram Scram buss relay to drop out. Switch cleaned. Safety Channel 1 While balancirig rods at 1 MW with the SHDFE Power Scram configursier., the flux profile was tilted towards the safety channel detector. Slight, though normal, oscillations in the channel response caused a safety channel power scram at 106% of 1 MW. Operation resumed with less flux tilt. Safety Channel 1 Failure of low voltage power supply in safety channel Power Scram system. Power supply repaired. I I I I I
C IV-16 E D. Chances to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments f Performed Pursuant to 10 CFR 50.59 The information contained in this section of the report provides a summary of the changes performed during the reporting period under the provisions of 10 CFR 50.59. For each item listed, we have included a brief description of the action taken and a summary of the applicable safety evaluation. Although it may not be specifically stated in each of the following safety evaluations, all actions taken under 10 CFR 50.59 were implemented only after it was established by the OSTR Reactor Operations Committee (ROC) that the proposed activity did not require a change in the facility's Technical Specifications and did not introduce or create an unreviewed safety question as defined in 10 CFR 50.59(a)(2).
- 1. 10 CFR 50.59 Chanaes to the Reactor Facility There were no changes to the reactor facility during the reporting period.
- 2. 10 CFR 50.59 Chanaes to Reactor Procedures There were seven changes to reactor procedures which were reviewed, approvet', !
and performed under the provisions of 10 CFR 50.59 during the reporting period. I.
- a. REVISIONS TO THE RADIATION CENTER AND OSTR EMERGENCY l RESPONSE PLAN (1) Description gl 3l As a result of the annual review of the Radiation Center and OSTR j Emergency Response Plan, and also as a result of the annual emer0en-cy response drill, a number of changes were needed to the plan and its implementing procedures.
First, the closure of the Trojan Nuclear Power Plant necessitated the deletion of all references throughout the plan and procedures to Portland General Electric (PGE) and the potential use of the whole body radiation monitor at Trojan. Second, a reorganization of the univer-sity's administrative structure required changes in the titles of certain I: E
l IV-17 l positions, and a change in the organizational diagram. Third, the title l 4 given to the second person in the line of succession for the Emergency ) Director and the Public information Officer needed to be changed from l Senior Reactor Operator to Chairman of the Reactor Operations Committee because the Chairman decided not to renew his Senior Reactor Operator license. i I Other revisions involved updates on the Area Radiation Monitors (ARMS), changes in the allowed emergency exposure limits, the addition of new decontamination facilities at the Good Samaritan Hospital, as well as corrections of typographical or minor grammatical errors. (2) Safety Evaluation l The removal of PGE from the emergency response plan and implement-ing procedures was made because the Trojan f acility was closed down and whole body counting is no longer available. Whole body monitor-ing services are available from several commercial companies. For this reason, the removal of the PGE assistance was not regarded as a reduction in the effectiveness of the plan. 1 1 ! The reorganization of the university's administrative structure was the , I subject of a request to change the OSTR Technical Specifications l submitted to the USNRC on July 7,1993. The emergency plan changes ensure conformity to the proposed changes in the Technical I Specifications. 1 The change in the title of the person second in the line of succession for the Emergency Director and Public Information Officer does not have any negative safety implications, because while the title has changed, the person filling the position has not. The Senior Reactor Operator and the Chairman of the Reactor Operations Committee are ; one and the same. Furthermore, anyone qualified to serve as Chairman
R IV-18 E l of the Reactor Operations Committee is qualified to fill these positions l in the Emergency Response Plan. l 1 l The changes to the ARMS have been addressed in the 10 CFR 50.59 Safety Analysis numbered 92-9 and, therefore, the conforming changes to the emergency plan need not be evaluated further here. Revisions to EPA guidance on allowable emergency doses for various I situations prompted the reduction of the lifesaving dose from 75 rem to 25 rem and the non-lifesaving dose from 25 rem to 10 rem. Clearly, these reductions follow federal guidance and result in a potential cancer risk decrease and an overall increase in safety. Good Samaritan Hospital (GSH) has purchased a portable decontamina-tion table and a portable shower. This provides more flexibility as to where injured, contaminated patients wili be initially treated. The GSH Standard Operating Procedure relating to such emergencies has been revised and the changes to the OSTR Emergency Response Plan make allowance for use of these facilities. This change increases the effectiveness of the plan by providing flexibility to cope with a greater variety of situations. Typographical and grammatical changes increase the plan effective-ness by making it more accurate and easy to read.
- b. REVISIONS TO THE RADIATION CENTER AND OSTR EMERGENCY RESPONSE PLAN (1) Description A number of changes to the Emergency Response Plan were needed as a result of the revision of 10 CFR Part 20. The effective date for these revisions was January 1,1994, when the OSU Radiation Center implemented the revised 10 CFR Part 20. During the review of the I
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i i IV-19 i emergency plan, it was recognized that a number of other minor changes were also needed and, therefore, these changes were made I at the same time. All changes were made under the provisions of 10 CFR 50.54 (q) and do not reduce the emergency response effective-ness of the plan. 1 (2) Safety Evaluation Deletion of the paragraph in Section 3.1.4 relating to the Fire Depart-ment providing training for Radiation Center personnel reflects the f act that a formalization of this training in the emergency plan was no longer needed. Key Radiation Center personnel have been sufficiently trained so that they can provide instruction to other Center staff. The OSU Radiation Center maintains a close relationship with the Corvallis Fire Department with various informal training opportunities provided both by and for the Fire Department. Deletion of this paragraph does not reduce the effectiveness of Radiation Center staff response to fires. Deletion of Section 3.2.2 c) was made to avoid confusion with respect to who authorizes emergency doses in excess of the occupational limits. In several other places in the plan it stated that the Emergency Director would authorize such doses with the concurrence of the Campus Radiation Safety Officer, if available. This is the correct wording, since there will always be a person fulfilling the duties of the Emergency Director, whereas the Campus RSO may not always be I available. Changes to Sections 4.1, and 7.4.3, and Table 5.1 were made to delete reference to quarterly dose limits. With the revised Part 20 there are no quarterly limits. The new wording achieves the same result by using the phrase "any applicable occupational dose limit." This takes care of the total effective dose equivalent, shallow dose I I
E IV-20 5l l equivalent and eye dose equivalent limits, as well as allowing for other potential regulatory changes. Changes to emergency action levels for Class I and Class 11 emergen-cies were made to make allowance for the fact that the revised Part 20 does not deal with MPCs, but does use the concept of effective dose equivalent. There are two action levels in the existing plan which have MPC criteria as well as whole body dose equivalent criteria. It was redundant to have both the airborne concentration and whole body dose criteria since the internal and external hazard can now be combined by setting a total effective dose equivalent (TEDE) emergen-cy action level. Since the whole body weighting factor is unity, the appropriate TEDE action levels are the same numerically as the previous whole body dose values of 15 mrem and 75 mrem for Class I and Class 11 emergencies, respectively. A further change in the same emergency action levels involved replacing the words "at the site boundary" with "in the unrestricted area." Under most conditions involving a release of airborne radioac-tive material, the largest dose will not occur at the site boundary, but at some point further away. This is due to the closeness of the site boundary to the point of release. The revised action level statement is therofore more conservative than the old one. Most references to in-vivo whole body counting at the Trojan nuclear power plant were deleted during a previously approved change to the emergency plan. However, one reference which was overlooked was deleted. The previous evaluation applies. The changes from "MPC" to "DAC" in Secticas 7.1.2, 7.2.2, and 7.3.2 were appropriate because they occ':'in the context of stating that a certain value is a small fraction of the MPC (DAC). Clearly, changing from MPC to DAC does not change such statements at all. I i
I IV-21 The addition of the license or docket number on the information reported (Sections 7.2.1 and 7.3.1) makes it easier for the USNRC to find the re!evant file when they are notified. This may help them provide a quicker response, and therefore, may have a positive implication on safety. Deleting " Region V" from the phrase " Region V Regional Administra-i tor" in Section 10.3 does not have any safety implications, and it prepared the way for planned changes in the USNPC regional struc-ture. The representative emergency equipment inventories were updated.
- c. REVISION TO OSTROP 11.0 - FUEL ELEMENT HANDLING PROCEDURES (1) Description i
OSTROP 11 was changed in order to add a new category of fuel handling which may be authorized by the Reactor Supervisor. The pattern of use for the various reactor irradiation facilities has been ! changing. As part of this change, there has been a significantly greater demand for the sample-holding dummy fuel element (SHDFE) , and the cadmium-lined, in-core, irradiation tube (ClICIT). Because each of these is placed in the B1 grid position when !n use, the fuel element in this location has seen a great deal of handling in the last year or two. In fact, it was moved over 60 times in 1993. While this element did not show any observable signs of wear or damage, it , i seemed to be a good idea to distribute the wear and tear associated ; with being in grid position B1 among the other fuel elements. Since l the requirement for fairly frequent movement of the B1 element is likely to continue for the foreseeable future, the Reactor Supervisor needed the flexibility to exchange the element in the B1 grid position I
I EI IV-22 O l with an element in another pusition without requiring ROC approval each time. Therefore, item f. was added to OSTROP 11.A.1. as follows: I:
" f. The exchanging of the fuel element in core grid position B1 with I
an element elsewhere in the reactor core. If the difference in core excess as measured just before and just after exchanging the two elements is greater than 8 cents then the control rods will be recalibrated." (2) Safety Evaluation Occasional replacement of the fuel element in core grid position 81 with another element from the core reduces the amount of handling that any one element will have to undergo. This in turn reduces the wear and tear on fuel element cladding and helps to ensure long term cladding integrity. Therefore, this procedural change enhances safety. The rnaximum reactivity change resulting from the exchange of any two fuel elements in the reactor core depends on the difference in the individual element's worth due to burnup differentials. Since the reactivity change with burnup is small and varies slowly with time, it is estimated that replacing the B1 element with any other element in the core will give a maximum reactivity change of only a few cents. Measuring the core excess before and after the fuel element exchange provides an assessment of this reactivity change. The requirement to recalibrate the control rods if the difference in the core excess is significant ensures that Technical Specification 4.3.1.a is met. The value of 8 cents was chosen as being significant because the repeatability of any one control rod worth measurement is one or two cents and there are four control rods. Therefore, it is possible to n
IV-23 l l have up to about an 8 cent difference in measured core excess with no physical core changes, j 1 1
- d. MINOR REVISION TO OSTROP 18.0 (1) Description OSTROP 18.0 in section B.18.4.b. provides a list of personnel who must be present in the reactor facility at the start up of a new experiment. The purpose of the revision was to clarify the meaning of the words "in the reactor facility." Therefore, the sentence in this section was changed to read:
"b. At the start of a new experiment, the following personnel must be present in the reactor control room or near the experiment."
(2) Safety Evaluation The change clarified the intent of the previous wording by making it more precise. This in turn reduced the potential for misunderstanding and thereby increased safety. The intent of the sentence which was revised is to ensure that a person responsible for the new experiment, and knowledgeable about it, is readily available to the reactor opera-tions staff and the health physics staff should there be a need for a decision about the new experiment. The revised wording provides this assurance,
- e. REVISION TO OSTROP 26, PROCEDURES FOR THE CONNECTION OF EXTERNAL MONITORING AND RECORDING DEVICES (1) Description The purchase of a new analog to digital converter board for the Computer-based Data Acquisition System (CDAS) and its associated software necessitated changes to the text of OSTROP 26. These changes were minor in nature and involved running a commercial software package called "daqware" on the computer rather than the I
O IV-24 E program "V" required previously. In addition, there were minor editorial changes in OSTROP 26, and a new appendix was added which provides details on running daqware. The new software is much more user-friendly and useful for class applications. There were no changes in the manner in which the computer, converter board and console are attached, and r'o changes in how the computer receives data from the console. (2) Safety Evaluation Since the changes described above did not alter the manner in which the console and the computer were electrically connected, there were no negative safety implications associated with this procedural change.
- f. REVISION TO OSTROP 16, ANNUAL SURVEILLANCE AND MAINTENANCE PROCEDURES (1) Description OSTROP 16.20 requires the inspection of selected fuel elements on an annual basis to determine if they are still within specifications.
Because of its location in the B ring of the reactor grid, one of these elements turns out to be the instrumented fuel element. The reactor operations staff wanted to remove this element from the list of those requiring annual inspection because of the wear and tear on this element caused by its removal and insertion into the grid. To be more specific, the location of this element in grid position B4, means that the long connecting tube with the thermocouple leads in it has to be bent in order to remove and insert the element. It was feared that the required bending of the tube could ultimately damage the weld at the top of the instrumented fuel element, which would clearly be undesir-able and would not be offset by the benefits gained by annually removing this element from the core. a
IV-25 (2) Safety Evaluation The fuel elements which are designated for annual measurement are I those in the B ring and those around the transient rod. The purpose of the annual measurements is to provide assurance that there are no undesirable physical changes occurring in these more highly irradiated elements. History has shown that the fuel elements which may show changes first are those around the transient rod. Removing the instrumented element from the list of ten elements does not signifi-cantly reduce the probability of finding the start of any such changes because checking the specifications of the other nine elements provides a sufficient level of inspection. If deemed appropriate in the future, the instrumented element can always be checked with no procedural changes since the Reactor Supervisor already has the authority to remove a single fuel element, measure it and replace it in the same position. Further, because it now appears that the potential for damage to the instrumented element may be greater if it is repeatedly moved rather than being left in the B-ring, not measuring the instrumented element will increase reactor safety.
- g. REVISION TO OSTROP 6, ADMINISTRATIVE AND PERSONNEL PROCEDURES (1) Description The purpose of this revision of OSTROP 6 was to clarify the wording relating to ROC review and approval of new reactor operators. The second sentence of 6.4.C.2.] was changed from:
" Initial review and approval of new personnel must be accomplished before the individual begins any supervisory or operational tasks."
to: I
n IV-26 E
" Initial review and approval of new personnel must be accomplished before an individual's initial license application is submitted to the USNRC."
(2) Safety Evaluation The intent of this section was to have the ROC review and approve new reactor operator personnel prior to their becoming NRC licensed reactor operators. It is clear that the most appropriate time to do this for new personnel is prior to the submission of their initial license application, since the Director of the Radiation Center signs the application statement saying that the person has been properly trained and is needed as a licensed operator. Since the proposed change does not alter the intent of the approval statement, but rather clarifies it, there are no adverse reactor safety implications associated with this change.
- 3. 10 CFR 50.59 Chanaes to Reactor Exoeriments There was one change to a reactor experiment during this reporting period,
- a. REVISION TO REACTOR EXPERIMENT B-12 (1) Description Reactor experiment B-12 was revised to restore the requirement for a one page written experiment description and the approval of proposed B-12 experiments by the Reactor Supervisor, the Senior Health Physicist and the Chairrnan of the ROC.
When reactor experiment B-12 was last revised to make it conform to the new format for all other reactor experiments, two significant aspects of the old B-12 were inadvertently omitted. Therefore, item (12) to B-12 was added to restore the requirement for a one page written experiment description and specific approvals as follows: l I I l l
'l 1
IV-27
"(12) For any new use of reactor experiment B-12, a one page written experiment description will accompany the irradia-tion request to enable the impact of the experiment to be evaluated. The experiment description will include an outline of the goals of the experiment, a brief description of the materials and apparatus to be used, where the experi-ment equipment will be placed, a calculation of any radioactivity to be formed, and an estimate of the reactivity effect of the experiment. The approval of the Reactor Supervisor, the Senior Health Physicist, and the Chairman of the Reactor Operations Committee must be obtained before performing any new experiment for the first time."
(2) Safety Evaluation As stated in the experiment description, reactor experiment B-12 was designed to be generalin nature with the purpose of accommodating exploratory programs. The experiment allows for a few trial runs to confirm that the OSTR can be used to achieve a certain objective. There are a number of constraints, detailed in B-12, which provide limits on the types of experiments that can be performed. Anything beyond these constraints requires specific approval of the full ROC. Providing the additional information required on the one-page written description, and having it evaluated by senior, knowledgeable staff minimizes the possibility of any unforeseen or unsafe event. There-fore, because the experiment change imposes additional review and approval requirements to B-12, safety is likely to be increased. I
E IV-28 U E. Surveillance and Maintenance
- 1. Non-Routine Maintenance Dec.7,1993 Replaced the regulating rod nixie tube position indicator.
Jan.3,1994 Removed the red lights and high radiation area signs on the reactor top. Jan.10,1994 Replaced the water temperature indicator selector switch. Jan.10,1994 Inspected beam ports 1 and 4 for dampness. They were dry. Jan.24,1994 Changed the resin for the primary cleanup system. Apr. 4,1994 Changed the B-1 position fuel element. May 17,1994 Replaced a section of the emergency generator's ex-haust line. May 17,1994 Replaced the motor bearings on the primary pump. June 13,1994 Repaired the percent power channel low voltage power supply. June 21,1994 Replaced the regulating rod motor with a spare. June 23,1994 Changed the stack monitor filter paper from HV70 to HVLB 5211.
- 2. Routine Surveillance and Maintenance I
The OSTR has an extensive routine surveillance and maintenance (S&M) program. Examples of typical S&M checklists are presented in Figures IV.E.1 through IV.E.4. Items marked with an asterisk (*) are required by the OSTR Technical Specifica-tions. F. Reportable Occurrences I There were no reportable occurrences during the reporting period. I a.
M M M M M M m M Figure IV.E.1 Monthly Surveillance and Maintenance (Sample Form) OSTROP 13 SURVEILLANCE & MAINTENANCE FOR THE MONTH OF TARGET DATE NOT TO DATE REMARKS & SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUND DATE BE EXCEEDED" COMPLETED INITIALS
- 1 FUNCTIONAL CHECK OF REACTOR WATER MAXIMUM up: inch..
LEVEL ALARMS AND GREEN LIGHT ALARM MOVEMENT DN: We 13(NCHES ggt]N LeoHT: 2 MEASUREMENT OF THE REACTOR PRIMARY MIN: 5 WATER pH MAX: 8.5 3 MEASUREMENT OF THE BULK SHIELD TANK MIN: 5 WATER pH MAX: 8.5 4 EMERGENCY POWER SYSTEM LtOUtD: -1* DN BATTERY CHECKS INVERTER S.G.: > 1.250 FUNCTIONAL CHECK
. >1. 50 GENERATOR VOLTS = 12.6V DC 5 EVACUATION HORN & P.A. EMERGENCY LtOUID: FULL SYSTEM BATTERY CHECKS S.G.: > 1.250 VOLTS a 12.6V DC CORR: NONE 6 INSPECTION OF THE BRUSHES ON THE CHANGE WHEN PNEUMATIC TRANSFER SYSTEM BLOWER 1/4* LEFT MOTOR 7 GREEN LIGHT BULB REPLACEMENT 75 WATT 8 CHANGE LAZY SUSAN FILTER FILTER CHANGED 9 LUBRfCATE THE TRIGA TUDE LOADING TOOL USE GUN O!L NEED OfL7 (REEL) 10 REACTOR TOP CAM Ott LEVEL CHECK OSTROP 13.10 NEED OIL 7 11 PROPANE TANK LIQUID LEVEL CHECK >50%
(% FULL) { *12 BULK WATER TEMPEV ~4 ALARM CHECK FUNCTIONAL l 13 PRIMARY PUMP BEARIN'S$ Oil LEVFL CHECK OSTROP 13.13 NEED Ott?
- License Requirement.
4 O
*
- Date not to be exceeded is only applicable to marked (*) items. It is equal to the date completed fast month plus six weeks. Rey, f f/92 l
i
Figure IV.E.2 R Quarterly Surveillance and Maintenance (Sample Form) h OSTROP 14 SURVEILLANCE & MAINTENANCE FOR THE Ot1ARTER, OF F / TARGET DATE NOT TO DATE REMARKS & SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUND DATE BE EXCEEDED *
- COMPLETED INITIALS
*1 REACTOR OPERATION COMMITTEE (ROC)
AUDIT OF REACTOR OPERATIONS FOR QUARTERLY
/ / OUARTER
- 2 OUARTERLY ROC MEETING OUARTERLY 3 FUEL ELEMENT RADIATION LEVEL a:23 R/hr @
MEASUREMENTS IN WATER 2' IN WATER 4 INSPECTION OF THE SOLENOtD VALVES IN FUNCTIONAL THE PNEUMATIC TRANSFER SYSTEM 5 PNEUMATIC TRANSFER SYSTEM LNSERTION s6 SECONDS TIME CHECK 6 ROTATING RACK CHECK FOR UNKNOWN RACK SHOULD SAMPLES BE EMPTY 7 FUNCTIONAL CHECK OF EMERGENCY LIGHTS FUNCTIONAL (SEE CHECKSHEET) 8 WATER MON! TOR ALARM CHECK FUNCTIONAL 9 STACK MONITOR CHECKS (Oil DRIVE MOTORS OILED MOTORS, H.V. READINGS) PART: 1150 V 150 VOLTS OAS: 900 V t 50 VOLTS 10 11 ARM SYSTEM ALARM CHECKS CHAN 1 2 3 4 6 e 7 8 9 to 11 12 AUD UGHT FUNCTIONAL PANEL ANN 12 OPERATOR LOG NAME al TIME bl OPERATING EXERCISE g console (RO) or as Rx. Sup. (SRO) b) Complete Operating Exercise
- License Requirement t Physical Security Plan Requirement
*
- Date not to be exceeded is only applicable to marked (*) items. It is equal to the date completed last quarter plus four months. Rev. f/93 EiM M M -
M M M M M
M M M M M M M M Figure IV.E.2 (Continued) Quarterly Surveillance and Maintenance (Sample Form) OSTROP 14 (CONTINUED) SURVEILLANCE & MAINTENANCE FOR THE QUARTER OF / / 19 TARGET DATE NOT TO DATE REMARKS & SURVEfLLANCE & MAINTENANCE TO BE PERFORMED LtMITS AS FOUND DATE BE EXCEEDED' COMPLETED INmALS 13 CHECK FILTER TAPE SPEED ON STACK 1 */HR
- O.2 MONITOR 14 INCORPORATE S0.59 & ROCAS INTO QUARTERLY DOCUMENTATION IS 16 FUNCTIONAL CHECK OF EVACUATION ALL FUNCTIONAL ALARMS
*17 SUBMISSION OF SAFEGUARDS LOG BY P.S.O. SUBMIT IF NEW FOR / / QUARTER ENTRIES 18 STACK MONITOR ALARM CIRCUti CHECKS ALARM ON CONTACT 19 ALARM TESTING OF VITAL AREA DOUBLE FUNCTIONAL DOORS
- License Requirement.
*
- Date not to be exceeded is only applicab!e to marked (*) items It is equal to the date completed last quarter plus four months.
k Oa Rev. 2/93
Figure IV.E.3 3 Semi-Annual Surveillance and Maintenance (Sample Form) d OSTROP 15 SEMI-ANNUAL SURVEILLANCE AND MAINTENANCE FOR DATE NOT TO DATE REMARKS & SURVE1LLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUND TARGET DATE BE EXCEEDED *
- COMPLETED INITIALS
*1 FUNCTIONAL NO WITHDRAW 31 CHECKS OF a) NEUTRON SOURCE COUNT RATE INTERLOCK #E*
- REACTOR INTERLOCKS b) TRANSIENT ROD AtR INTERLOCK NO PULSE b c) PULSE PROHIBIT ABOVE 1 kW 21kW c d) TWO ROD WITHDRAWAL PROHIGIT 1 Only d ,
e) PULSE MODE ROD MOVEMENT INTERLOCK NO MOVEMENT e f) MAXtMUM PULSE REACTIVITY INSERTION LIMIT s $2.50 t g) PULSE INTERLOCK ON RANGE SWITCH NO PULSE o
*2 SAFETY CIRCUIT PERIOD SCRAM m3 see TEST
'3 CONTROL TRANS SAFE SHIM REG ROD WITH-DRAWAL. a) SCRAM s2 sec a bER ON & b) WITHDRAWAL s50 see b R
TIMES c) INSERTION s50 sec c
*4 PULSE COMPARISON (PREVIOUS FULSE): PULSE 8
$ s20 % m,sE #
MW CHANGE uw
'C *C
*5 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST **wnns cose em noon _
m s secoseos ist noon _
*6 CAllBRATION OF THE FUEL ELEMENT TEMPERATURE CHANNEL *2*C
'7 MATERIALS BALANCE REPORT / FUEL MANAGEMENT REPORTS DONE/ APRIL 15 AFRIL 30
- EVEN BURNUP OCTOBER 15 OCTOBER 30
*8 CLEAN 1NG & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL 3-IN-1 or CLEANED _
BARREL GUN Oil O! LED
'9 LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 3-IN-1 or McLY Rof t _._
OUN Olt CLED 10 LUBRICAY!ON OF THE ROTATING RACK BEARINGS 10 W Oft OILED 11 CONSOLE CHECK LIST (OSTROP 15.11) 08 TROP 16.11 12 CONSTANT AfR MONITOR RECORDER MAtNTENANCE License Requirements.
** Date not to be exceeded is only applicable to marked (*) items. It is equal to the date last time plus 7 % months. Rev. If/92 EM M M M M M M ME
M M M M M M M M M M M . M Figure IV.E.3 (Continued) l Semi-Annual Surveillance and Maintenance (Sample Form) OSTROP 15 (continued) SEMI-ANNUAL SURVEILLANCE AND MAINTENANCE FOR DATE NOT TO DATE REMARKS & SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUND TARGET DATE BE EXCEEDED" COMPLETED INITIALS 13 14 STANDARD CONTROL ROD MOTOR CHECKS CILED 15 FLUKE FUEL TEMPERATURE INSTRUMENT *O* CELL CHECK TEST POSITION READ >900*C 16 ION CHAMBER RESISTANCE A. SAFETY CHANNEL NONE MEASUREMENTS WITH MEGGAR Unfo Only) INDUCED VOLTAGE 8. % POWER CHANNEL NONE Unfo Only) 17 FISSION CHAMBER RESISTANCE @ 100 V. I= AMPS NONE CALCULATION @ 900 V. I= AMPS Unto Only) Al = AMPS R.8 At V R- O 18 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS 03TROF 16.19 HIGH FULL GREEN LBOHT b (d
- License Requirements.
** Date not to be exceeded is only applicable to marked (*) items it is equal to the date last time plus 7 % months. Rev.If/92 W. m-m~_--- . __ -- _--.-.m. _-,--~m-------M --Am-A-___-_ -,-nw _--,,n----___-- __---- a
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PART V PROTECTION A. Introduction This section of the report deals with the radiation protection program at the OSU Radiation Center. The purpose of this program is to ensure the safe use of radiation and radioactive material 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 Commission, 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. The radiation protection program is implemented by a staff consisting of a Senior Health Physicist, a Health Physicist, a Radiation Protection Technologist, and several part-time Health}}