ML12306A510
| ML12306A510 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/30/2012 |
| From: | Reese S Oregon State University |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12306A510 (50) | |
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0 Submitted by:
0 ~Steve R. Reese, Director 0
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- Radiation Center 0
- Oregon State University Corvallis, Oregon 97331-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 To satisy the requirements of U.S. Nuclear OA. Regulatory Commission, License No. R-1 06 0 (Docket No. 50-243), Technical Specification 6.7(e).
0 B. Battelle Energy Alliance, LLC; Subcontract Award No. 00074510.
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0 ConltenIts 0 0
0 Part I-Overview 0 Executive Summary ..........
Introduction ............... 0 Overview of the Radiation Center. . . . . . . . . .. . . . . . . 5 0 Part Il-People 0
Radiation Center Staff ........ .6 0 Reactor Operations Committee .6 0 Professional & Research Faculty . *7 0 Part Ill-Facilities 0
Research Reactor ............ .8 0 Analytical Equipment ......... .9 0 Radioisotope Irradiation Sources . .9 Laboratories & Classrooms ..... .9 0
Instrument Repair & Calibration.. .10 0 Library ................... .10 0 Part IV-Reactor 0 Operating Statistics ............................. ...................
. .14 0 Experiments Performed ....................... .14 0 Unplanned Shutdowns ......................... . .................... .15 Changes Pursuant to 10 CFR 50.59 ...................... ................... .15 0 Surveillance & Maintenance .................... . .................... .15 0 Part V-Radiation Protection 0 Introduction ........................................................ .28 0 Environmental Releases ............................................... .28 Personnel Doses ...................................................... .29 0 Facility Survey Data .............................. .................... .30 0 Environmental Survey Data .............................................
Radioactive Material Shipments ..........................................
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References ......................................................... .31 0 0
Part VI-Work Sum m ary ................. .50 0
Teaching .................. .50 0 Research & Service ........... .50 0 Part VII-Words 0 Documents Published or Accepted. .................................... .74 0 Presentations ............... .................................... .78 0 Students .................. .83 0
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- Tables Table Title Page 111.1 Gam m acell 220 6"Co Irradiator Use ............................................ 11 111.2 Student Enrollment in Courses at the Radiation Center ............................... .. 12 IV.1 Present OSTR Operating Statistics . . . ............................................ 17 S IV.2 OSTR Use Time in Terms of Specific Use Categories .................................. .. 18 IV.3 OSTR Multiple Use Time ......................................................... 18 IV.4 Use of OSTR Reactor Experiments .................................................. 19 IV.5 Unplanned-Reactor Shutdowns and Scrams ........................................ 19 V.1 Radiation Protection Program Requirements and Frequencies .......................... .. 32 V.2 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer ...................... .33 V.3 Annual Summary of Liquid Waste Generated and Transferred ............................ 34 V.4 Monthly Summary of Gaseous Effluent Releases ..................................... 35 V.5 Annual Summary of Solid Waste Generated and Transferred ............................. 36
- V.6 Annual Summary of Personnel Radiation Doses Received .............................. 37 V.7 Total Dose Equivalent Recorded Within the TRIGA Reactor Facility ....................... .. 38 V.8 Total Dose Equivalent Recorded on Area Within the Radiation Center ....................... 39 V.9 Annual Summary of Radiation and Contamination Levels Within the Reactor ................. 41 V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence .............................. 42 V.1 1 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations ................. 43 V.12 Annual Average Concentration of theTotal Net Beta Radioactivity ......................... 44 V.13 Beta-Gamma Concentration and Range of LLD Values ................................. 45 V.14 Radioactive Material Shipments under NRC General License R-106 ....................... 46 V.15 Radioactive Material Shipments under Oregon License ORE 90005 ........................ 47 V.16 Radioactive Material Shipments Under NRC General License 10 CFR 110.23 ................. 48 VI.1 Institutions and Agencies Which Utilized the Radiation Center .......................... .. 53
- VI.2 Listing of Major Research & Service Projects Performed and Their Funding .................. 58 VI.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments ............ 72 VI.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies ............. 73 0
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- Figures
- Table Title Page I V.1 Monthly Surveillance and Maintenance (Sam ple Form) ....................................................................................... 20 IV.2 Quarterly Surveillance and M aintenance (Sam ple Form ) ........................................................................................ 21 IV.3 Sem i-Annual Surveillance and Maintenance (Sample Form) ............................................................................... 23 IV.4 Annual Surveillance and M aintenance (Sam ple Form ) ................................................................................................... 25 V.1 M onitoring Stations for the OSU TRIGA Reactor ..................................................................................................... 49 VI.1 Summary of the Types of Radiological Instrumentation Calibrated ................................................................. 72 0
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Executive Summary T1he Radiation Center web site provides an easy way for 0 The data from this reporting year shows that the use of the potential users to evaluate the Center's facilities and capabili-ties as well as to apply for a project and check use charges. The 0
Radiation Center and the Oregon State TRIGA reactor (OSTR) has continued to grow in many areas. address is: ht-tp://radiationcenter.oregonstare.edu.
The Radiation Center supported 58 different courses this year, mostly in the Department of Nuclear Engineering, Radia-0 tion Health Physics, Medical Physics, and Radiochemistry.
Introduction About 29% of these courses involved the OSTR. The number The current annual report of the Oregon State University of OSTR hours used for academic courses and training was Radiation Center and TRIGA Reactor follows the usual for-28, while 4,849 hours0.00983 days <br />0.236 hours <br />0.0014 weeks <br />3.230445e-4 months <br /> were used for research projects. Sixty- mat by including information relating to the entire Radiation five percent of the OSTR research hours were in support of Center rather than just the reactor. However, the information off-campus research projects, reflecting the use of the OSTR is still presented in such a manner that data on the reactor may 0
nationally and internationally. Radiation Center users pub-fished or submitted 83 articles this year, and made 83 presen-tations on work that involved the OSTR or Radiation Center. 0 The number of samples irradiated in the reactor during this reporting period was 3,584. Funded OSTR use hours com-prised 84% of the research use. 0 Personnel at the Radiation Center conducted 123 tours of the facility, accommodating 1,392 visitors. The visitors included 0 elementary, middle school, high school, and college students; relatives and friends; faculty; current and prospective clients; national laboratory and industrial scientists and engineers; and 0
state, federal and international officials. The Radiation Center is a significant positive attraction on campus because visitors 0 leave with a good impression of the facility and of Oregon State University.
The Radiation Center projects database continues to provide a useful way of tracking the many different aspects of work at the facility. The number of projects supported this year was 0 205. Reactor related projects comprised 68% of all projects.
The total research supported by the Radiation Center, as reported by our researchers, was $8,076,109. The actual total is likely considerably higher. This year the Radiation Center provided service to 73 different organizations/institutions, 32%
of which were from other states and 23% of which were from outside the U. S. and Canada. So while the Center's primary mission is local, it is also a facility with a national and interna- 0 tional clientele. 0 0
0 4 11-12 Annual Report 0 0
Overview 0
0 be examined separately, if desired. It should be noted that all for repair and calibration of radiation protection instrumen-annual data given in this report covers the period from July tation; and facilities for packaging radioactive materials for 0 1, 2011 through June 30, 2012. Cumulative reactor operating shipment to national and international destinations.
data in this report relates only to the LEU fueled core. This covers the period beginning July 1, 2008 to the present date. A major non-nuclear facility housed in the Radiation Center For a summary of data on the reactor's two other cores, the is the one-quarter scale thermal hydraulic advanced plant reader is referred to previous annual reports. experimental (APEX) test facility for the Westinghouse AP600 and AP1000 reactor designs. The AP600 and AP1000 In addition to providing general information about the are next-generation nuclear reactor designs which incorporate 0 activities of the Radiation Center, this report is designed to many passive safety features as well as considerably simplified meet the reporting requirements of the U. S. Nuclear Regula- plant systems and equipment. APEX operates at pressures tory Commission, the U. S. Department of Energy, and the up to 400 psia and temperatures up to 450TF using electrical 0 Oregon Department of Energy. Because of this, the report is heaters instead of nuclear fuel. All major components of the 0 divided into several distinct parts so that the reader may eas- AP600 and AP1000 are included in APEX and all systems ily find the sections of interest. are appropriately scaled to enable the experimental measure-ments to be used for safety evaluations and licensing of the full scale plant. This world-class facility meets exacting quality assurance criteria to provide assurance of safety as well as Overview of the Radiation Center validity of the test results.
The Radiation Center is a unique facility which serves the entire OSU campus, all other institutions within the Oregon Also housed in the Radiation Center is the Advanced Ther-University System, and many other universities and orga- mal Hydraulics Research Laboratory (ATHRL), which is 0 nizations throughout the nation and the world. The Center used for state-of-the-art two-phase flow experiments.
also regularly provides special services to state and federal 0 agencies, particularly agencies dealing with law enforcement, The Radiation Center staff regularly provides direct sup-0 energy, health, and environmental quality, and renders assis-port and assistance to OSU teaching and research programs.
Areas of expertise commonly involved in such efforts include tance to Oregon industry. In addition, the Radiation Center nuclear engineering, nuclear and radiation chemistry, neutron provides permanent office and laboratory space for the OSU 0 Department of Nuclear Engineering and Radiation Health activation analysis, radiation effects on biological systems, ra-diation dosimetry, environmental radioactivity, production of Physics, the OSU Institute of Nuclear Science and Engineer-0 ing, and for the OSU nuclear chemistry, radiation chemistry, short-lived radioisotopes, radiation shielding, nuclear instru-mentation, emergency response, transportation of radioactive geochemistry and radiochemistry programs. There is no other materials, instrument calibration, radiation health physics, university facility with the combined capabilities of the OSU radioactive waste disposal, and other related areas.
Radiation Center in the western half of the United States.
In addition to formal academic and research support, the Located in the Radiation Center are many items of special-Center's staff provides a wide variety of other services includ-ized equipment and unique teaching and research facilities.
ing public tours and instructional programs, and professional They include a TRIGA Mark II research nuclear reactor; a 60 Co gamma irradiator; a large number of state-of-the art consultation associated with the feasibility, design, safety, and execution of experiments using radiation and radioactive computer-based gamma radiation spectrometers and associ-materials.
ated germanium detectors; and a variety of instruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laborato-ries for plant experiments involving radioactivity; a facility 11-12 Annual Report
0 0
TIhis section contains a listing of all people who were residents of the Radiation Center or who worked a significant amount of 0
time at the Center during this reporting period. 0 It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are 0
listed. Summary information on the number of people involved is given in Table VIA, while individual names and projects are 0 listed in Table VI.2. 0 0
0 Radiation Center Staff Reactor Operations Committee 0 Steve Reese, Director Andrew Klein, Chair 0
DinaPope, Office Manager OSU Nuclear Engineering and Radiation Health Physics 0 Shaun Bromagem, Business Manager RainierFarmer 0 Kimberly Reese, Receptionist OSU Radiation Safety 0 S. Todd Keller, Reactor Administrator Abi Tavakoli Farsoni 0 Gary Wachs, Reactor Supervisor, Senior Reactor Operator OSU Nuclear Engineering and Radiation Health Physics 0 Robert Schickler, Senior Reactor Operator Michael Hartman 0 Wade Marcum, Reactor Operator University of Michigan 0
ScottMenn, Senior Health Physicist Todd Keller OSU Radiation Center 0
Jim Darrough,Health Physicist Scott Menn 0
Leak Minc, Neutron Activation Analysis Manager OSU Radiation Center 0
Steve Smith, Scientific Instrument Technician, Steve Reese (not voting) 0 Senior Reactor Operator OSU Radiation Center 0 Erin Cimbri,Custodian Gary Wachs (not voting) 0 Ryne Burgess, Health Physics Monitor (Student) OSU Radiation Center 0 Kyle Combs, Health Physics Monitor (Student) Bill Warnes 0 Joey DeShields, Health Physics Monitor (Student) OSU Mechanical Engineering 0 0
0 0
0 0
0 0
0 0
6 11-12 Annual Report
PeoplIe 0v 0
0 0 Professional and Research Faculty 0 Binney, Stephen E. Reyes, Jr.,JosiN.
Professor, Nuclear Engineering and Radiation Health Physics, 0 Director Emeritus, Radiation Center, Professor Emeritus, Nuclear Engineering and Radiation Health Physics ATHRL Principal Investigator Daniels,Malcolm RingleJohn C.
0 Professor Emeritus, Chemistry Professor Emeritus, Nuclear Engineering and Radiation
- Hamby,David Health Physics 0 Professor, Nuclear Engineering and Radiation Health Physics Robinson,Alan H.
Hart,Lucas P Department Head, Emeritus, Nuclear Engineering and Radia-Faculty Research Associate, Chemistry tion Health Physics
- Schmitt,Roman A.
- Higginbotham, Jack E 0 Director, Oregon Space Grant, Professor, Nuclear Engineering Professor Emeritus, Chemistry and Radiation Health Physics Krystina Tack 0 *Higley,KathrynA. Medical Physics Program Director Department Head, Nuclear Engineering and Radiation Health *Wachs, Gary 0 Physics Reactor Supervisor, Radiation Center Johnson,Arthur G. Woods, Brian 0 Director Emeritus, Radiation Center, Professor Emeritus, Nuclear Engineering and Radiation Health Physics Associate Professor, Nuclear Engineering and Radiation Health Physics
- Keller,S. Todd 0 Wu, Qiao Reactor Administrator, Radiation Center Professor, Nuclear Engineer and Radiation Health Physics Klein, Andrew C.
0 Professor, Nuclear Engineering and Radiation Health Physics
- Krane,Kenneth S.
0 Professor Emeritus, Physics
- Loveland, WalterD.
Professor, Chemistry 0 *Menn,Scott A.
- OSTR usersfor researchand/or teaching Senior Health Physicist, Radiation Center 0 *Minc,Leah Assistant Professor, Anthropology 0 'Palmer,Todd S.
Professor, Nuclear Engineering and Radiation Health Physics
'Paulenova,Alena Associate Professor, Senior Research, Radiation Center Pope, Dina Office Manager, Radiation Center
'Reese, Steven R.
Director, Radiation Center 11-12 Annual Report
0 0
Research Reactor The Oregon State University TRIGA Reactor (OSTR) is a If samples to be irradiated require a large neutron fluence, water-cooled, swimming pool type research reactor which uses especially from higher energy neutrons, they may be inserted uranium/zirconium hydride fuel elements in a circular grid ar- into a dummy fuel element. This device will then be placed into 0
ray. The reactor core is surrounded by a ring of graphite which one of the core's inner grid positions which would normally be serves to reflect neutrons back into the core. The core is situ- occupied by a fuel element. Similarly samples can be placed in 0 ated near the bottom of a 22-foot deep water-filled tank, and the in-core irradiation tube (ICIT) which can be inserted in the tank is surrounded by a concrete bioshield which acts as a the same core location.
radiation shield and structural support. The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at The cadmium-lined in-core irradiation tube (CLICIT) 0 a maximum steady state power of 1.1 MW and can also be enables samples to be irradiated in a high flux region near the center of the core. The cadmium lining in the facility eliminates 0
pulsed up to a peak power of about 2500 MW.
thermal neutrons and thus permits sample exposure to higher The OSTR has a number of different irradiation facilities energy neutrons only. The cadmium-lined end of this air-filled 0 including a pneumatic transfer tube, a rotating rack, a thermal aluminum irradiation tube is inserted into an inner grid posi-column, four beam ports, five sample holding (dummy) fuel tion of the reactor core which would normally be occupied by a 0 elements for special in-core irradiations, an in-core irradiation tube, and a cadmium-lined in-core irradiation tube for experi-fuel element. It is the same as the ICIT except for the presence of the cadmium lining.
0 ments requiring a high energy neutron flux.
The two main uses of the OSTR are instruction and research.
The pneumatic transfer facility enables samples to be inserted and removed from the core in four to five seconds.
Instruction 0 Instructional use of the reactor is twofold. First, it is used sig-Consequently this facility is normally used for neutron activa-nificantly for classes in Nuclear Engineering, Radiation Health tion analysis involving short-lived radionuclides. On the other Physics, and Chemistry at both the graduate and undergradu-hand, the rotating rack is used for much longer irradiation of ate levels to demonstrate numerous principles which have been 0
samples (e.g., hours). The rack consists of a circular array of 40 presented in the classroom. Basic neutron behavior is the same tubular positions, each of which can hold two sample tubes.
in small reactors as it is in large power reactors, and many dem-0 Rotation of the rack ensures that each sample will receive an identical irradiation.
onstrations and instructional experiments can be performed 0 using the OSTR which cannot be carried out with a commer-cial power reactor. Shorter-term demonstration experiments 0
The reactor's thermal column consists of a large stack of graphite blocks which slows down neutrons from the reactor are also performed for many undergraduate students in Phys- 0 core in order to increase thermal neutron activation of samples. ics, Chemistry, and Biology classes, as well as for visitors from 0 Over 99% of the neutrons in the thermal column are thermal other universities and colleges, from high schools, and from neutrons. Graphite blocks are removed from the thermal col- public groups.
umn to enable samples to be positioned inside for irradiation.
The second instructional application of the OSTR involves The beam ports are tubular penetrations in the reactor's main educating reactor operators, operations managers, and health concrete shield which enable neutron and gamma radiation to physicists. The OSTR is in a unique position to provide such stream from the core when a beam port's shield plugs are re- education since curricula must include hands-on experience at moved. The neutron radiography facility utilized the tangential an operating reactor and in associated laboratories. The many beam port (beam port #3) to produce ASTM E545 category I types of educational programs that the Radiation Center pro-radiography capability. The other beam ports are available for a vides are more fully described in Part VI of this report.
variety of experiments.
8 11-12 Annual Report
F4acilities 0
0 During this reporting period the OSTR accommodated a Typically, the irradiator is used by researchers wishing to 0 number of different OSU academic classes and other academic perform mutation and other biological effects studies; studies programs. In addition, portions of classes from other Oregon in the area of radiation chemistry; dosimeter testing; steril-universities were also supported by the OSTR. ization of food materials, soils, sediments, biological speci-men, and other media; gamma radiation damage studies; and Research other such applications. In addition to the 61Co irradiator, the 0 The OSTR is a unique and valuable tool for a wide variety of research applications and serves as an excellent source of Center is also equipped with a variety of smaller 6 0Co, 1 37Cs, 226 Ra, plutonium-beryllium, and other isotopic sealed sources neutrons and/or gamma radiation.lThe most commonly used of various radioactivity levels which are available for use as 0 experimental technique requiring reactor use is instrumental irradiation sources.
neutron activation analysis (INAA).'This is a particularly sen-0 sitive method of elemental analysis which is described in more During this reporting period there was a diverse group of projects using the 60Co irradiator. These projects included the detail in Part VI.
irradiation of a variety of biological materials including dif-0 The OSTR's irradiation facilities provide a wide range of neu-tron flux levels and neutron flux qualities which are sufficient ferent types of seeds.
0 to meet the needs of most researchers. This is true not only In addition, the irradiator was used for sterilization of several 0 for INAA, but also for other experimental purposes such as media and the evaluation of the radiation effects on different 0 the 3 9 Ar/ 4 0 Ar ratio and fission track methods of age dating samples.
materials. Table 111.1 provides use data for the Gammacell 0 220 irradiator.
0 Analytical Equipment Laboratories and Classrooms 0 The Radiation Center has a large variety of radiation detec-The Radiation Center is equipped with a number of different tion instrumentation. This equipment is upgraded as necessary, 0 especially the gamma ray spectrometers with their associated radioactive material laboratories designed to accommodate research projects and classes offered by various OSU academ-computers and germanium detectors. Additional equipment 0 for classroom use and an extensive inventory of portable radia-ic departments or off-campus groups.
tion detection instrumentation are also available.
0 Radiation Center nuclear instrumentation receives intensive use in both teaching and research applications. In addition, 0 service projects also use these systems and the combined use 0 often results in 24-hour per day schedules for many of the analytical instruments. Use of Radiation Center equipment 0 extends beyond that located at the Center and instrumenta-tion may be made available on a loan basis to OSU researchers in other departments.
Radioisotope Irradiation Sources The Radiation Center is equipped with a 1,644 curie (as of 7/27/01) Gammacell 220 60Co irradiator which is capable of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.
11-12 Annual Report 9
0 Ah I Facilities 0
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Instructional facilities available at the Center include a labo- Instrument Repair & Calibration 0 ratory especially equipped for teaching radiochemistry and a Facility 0 nuclear instrumentation teaching laboratory equipped with The Radiation Center has a facility for the repair and calibra- 0 modular sets of counting equipment which can be configured to accommodate a variety of experiments involving the mea-tion of essentially all types of radiation monitoring instru- 0 mentation. This includes instruments for the detection and surement of many types of radiation. T-he Center also has two measurement of alpha, beta, gamma, and neutron radiation.
0 student computer rooms. It encompasses both high range instruments for measuring 0 In addition to these dedicated instructional facilities, many intense radiation fields and low range instruments used to 0 measure environmental levels of radioactivity.
other research laboratories and pieces of specialized equip- 0 ment are regularly used for teaching. In particular, classes are routinely given access to gamma spectrometry equipment The Center's instrument repair and calibration facility is used 0 regularly throughout the year and is absolutely essential to the located in Center laboratories. A number of classes also regu-continued operation of the many different programs carried 0
larly use the OSTR and the Reactor Bay as an integral part of their instructional coursework.
out at the Center. In addition, the absence of any comparable 0 facility in the state has led to a greatly expanded instrument 0 calibration program for the Center, including calibration of
'There are two classrooms in the Radiation Center which are capable of holding about 35 and 18 students. In addition, essentially all radiation detection instruments used by state and 0 there are two smaller conference rooms and a library suitable federal agencies in the state of Oregon. This includes instru- 0 for graduate classes and thesis examinations. As a service to ments used on the OSU campus and all other institutions in the Oregon University System, plus instruments from the 0
the student body, the Radiation Center also provides an office area for the student chapters of the American Nuclear Society Oregon Health Division's Radiation Protection Services, the 0 and the Health Physics Society. Oregon Department of Energy, the Oregon Public Utili- 0 T'his reporting period saw continued high utilization of the ties Commission, the Oregon Health Sciences University, the Army Corps of Engineers, and the U. S. Environmental 0
Radiation Center's thermal hydraulics laboratory. This labora- Protection Agency. 0 tory is being used by Nuclear Engineering faculty members to 0 accommodate a one-quarter scale model of the Palisades Nu-clear Power reactor. The multi-million dollar advanced plant 0 experimental (APEX) facility was fully utilized by the U. S. Library 0 Nuclear Regulatory Commission to provide licensing data and to test safety systems in "beyond design basis" accidents.
The Radiation Center has a library containing a significant collections of texts, research reports, and videotapes relating to 0
The fully scaled, integral model APEX facility uses electrical nuclear science, nuclear engineering, and radiation protection. 0 heating elements to simulate the fuel elements, operates at 450'F and 400 psia, and responds at twice real time. It is the The Radiation Center is also a regular recipient of a great vari- 0 only facility of its type in the world and is owned by the U. ety of publications from commercial publishers in the nuclear 0 field, from many of the professional nuclear societies, from S. Department of Energy and operated by OSU. In addi-tion, a new building, Advanced Thermal Hydraulics Research the U. S. Department of Energy, the U. S. Nuclear Regulatory 0 Laboratory (ATHRL) was constructed next to the Reactor Commission, and other federal agencies. Therefore, the Center 0 library maintains a current collection of leading nuclear re-Building in 1998.
search and regulatory documentation. In addition, the Center 0 All of the laboratories and classrooms are used extensively has a collection of a number of nuclear power reactor Safety 0 Analysis Reports and Environmental Reports specifically during the academic year. A listing of courses accommodated prepared by utilities for their facilities. 0 at the Radiation Center during this reporting period along with their enrollments is given in Table 111.2. The Center maintains an up-to-date set of reports from such 0
organizations as the International Commission on Radiologi- 0 cal Protection, the National Council on Radiation Protection and Measurements, and the International Commission on 0
Radiological Units. Sets of the current U.S. Code of Federal 0 Regulations for the U.S. Nuclear Regulatory Commission, 0 0
0 10 11-12 Annual Report 0
Facilities 0w 0
0 the U.S. Department of Transportation, and other appropriate federal agencies, plus regulations of various state regulatory 0 agencies are also available at the Center.
The Radiation Center videotape library has over one hundred 0 tapes on nuclear engineering, radiation protection, and radio-logical emergency response topics. In addition, the Radiation Center uses videotapes for most of the technical orientations 0 which are required for personnel working with radiation and radioactive materials. These tapes reproduced, recorded, and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center.
0 The Radiation Center library is used mainly to provide refer-0 ence material on an as-needed basis. It receives extensive use during the academic year. In addition, the orientation video-tapes are used intensively during the beginning of each term 0 and periodically thereafter.
0 0
0 Table 111.1 0 Gammacell 220 6 0Co Irradiator Use Dose Range Number of UseTime 0 Purpose of Irradiation Samples (rads) Irradiations (hours) 0 wood, honey, 6 6 2.5x10 to 2.5x10 13 1377 0 Sterilization pig skin 0
silicon polymers, 5 7 Material Evaluation polymers, chemicals, 3.0x10 to 1.0x10 25 662 electronic components wood, wheat pollen, 2 6 Botanical Studies potatoes, pollen, 5.0x10 to 2.5x10 22 183 carnation leaves 4
Biological Studies mice 5.0x102 to 1.0x10 3 11 0 Totals 71 2222 11-12 Annual Report II
Facilities F
t 0
0 0
S Table 111.2 0 0
Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center 0
Number of Students 0
Course # CREDIT COURSE TITLE Summer Fall Winter Spring 0 2011 2011 2012 2012 0 NE/ RHP 114* 2 Introduction to Nuclear Engineering and Radiation Health Physics------
58 0 0
NE/ RHP 115 2 Introduction to Nuclear Engineering and Radiation 58 Health Physics 0 NE/RHP 116"* 2 Introduction to Nuclear Engineering and Radiation Health Physics 5 56 0 NE/ RHP 234 4 Nuclear and Radiation Physics I 66 0
NE/ RHP 235 4 Nuclear and Radiation Physics II 64 0 NE/ RHP 236* 4 Nuclear Radiation Detection & Instrumentation 50 0 NE 311 4 Intro to 'hermal Fluids 6 32 5 0 NE 312 4 'Thermodynamics 27 14 0 NE 319 Societal Aspects of Nuclear technology NE 331 3
4 Intro to Fluid Mechanics 68 27 10 0
NE 332 4 Heat Transfer 10 5 31 0
NE/RHP 333 3 Mathematical methods for NE/RHP 35 0 NE/RHP/MP 1-16 IResearch 5 24 19 19 0
401/501/601 0 NE/RHP/MP 405/505/605 1-16 Reading and Conference 2 0 NE/RHP/MP 1-16 Projects 1 1 0
406/506/606 0 NE/RHP/MP 407/507/607 1 Nuclear Engineering Seminar 96 57 91 0 NE/ RHP/MP 1-12 Internship 0
410/510/610 0 NE/ RHP 415/515 2 Nuclear Rules and Regulations 72 0 NE 451/551 4 Neutronic Analysis NE 452/552 4 Neutronic Analysis
_______ 'I 35 31 0
NE 455/555"* 3 Reactor Operator Training I 23 0
NE 457/557' 3 Neuclear Reactor Lab 27 0 NE 467/567 4 Nuclear Reactor Ihermal Hydraulics 31 0 NE 667 4 Nuclear Reactor Thermal Hydraulics 0 NE/RHP 435/535 3 External Dosimetry & Radiation Shielding 72 NE 474/574 4 Nuclear System Design I 44 NE/RHP 475/575 4 Nuclear System Design II 37 12 11-12 Annual Report
Facilities Table 111.2 (continued)
Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Number of Students Summer Fall Winter Spring Course # CREDIT COURSE TITLE 2010 2010 _ 2011 2011 0 NE?RHP 479* 1-4 Individual Design Project 0 NE/RHP 481* 4 Radiation Protection 55 NE/RHP 582* 4 Applied Radiation Safety 17 0 RHP 483/583 4 Radiation Biology 39 0 RHP 488/588* 3 Radioecology 36 NE/RHP 590 4 Internal Dosimetry 14 0 NE/RHP/MP 503/603* Thesis 28 39 41 48 S NE/ RHP 516* 4 Radiochemistry 15
- i 13 NE 526 3 Numerical Methods for Engineering Analysis 0 NE/RHP/MP 531 3 Nuclear Physics for Engineers and Scientists 21 NE/RHP/MP 536* 3 Advanced Radiation Detection & Measurement 21 NE/RHP 537 3 SDigital Spectrometer Design 0 MP541 3 -Diagnostic Imaging Physics 0 NE 550 3 Nuclear Medicine Advanced Nuclear Reactor Physics 16 NE 553* 3 0 NE 568 3 Nuclear Reactor Safety 0 Course From Other OSU Departments CH 123* 5 General Chemistry . .. .. . ... .
545 1 -.
CH 222* 5 General Chemistry (Science Majors) 527 0 CH 225H* 5 Honors General Chemistry I
40 0 CH 462* 3 Experimental Chemistry II Laboratory 12 GEo 330* 3 Environme ntal Conservation 28 ST Special Topics OSTR used occasionallyfor demonstrationand/or experiments OSTR used heavily 11-12 Annual Report 13
0 Operating Status 0
Inactive Experiments 0
Presently 33 experiments are in the inactive file. This During the operating period between July 1, 2011 and June 30,2012, the reactor produced 1418 MWH of thermal power consists of experiments which have been performed in 0 during its 1510 critical hours. the past and may be reactivated. Many of these experi- 0 ments are now performed under the more general experi.
ments listed in the previous section. The following list 0
identifies these inactive experiments. 0 Experiments Performed 0 During the current reporting period there were nine A-2 Measurement of Reactor Power Level via Mn approved reactor experiments available for use in reactor- Activation. 0 related programs. They are: A-3 Measurement of Cd Ratios for Mn, In, and Au 0 A-1 Normal TRIGA Operation (No Sample Irradia-in Rotating Rack. 0 tion). A-4 Neutron Flux Measurements in TRIGA. 0 B-3 Irradiation of Materials in the Standard OSTR A-5 Copper Wire Irradiation. 0 Irradiation Facilities. A-6 In-core Irradiation of LiF Crystals. 0 B-11 Irradiation of Materials Involving Specific A-7 Investigation of TRIGA's Reactor Bath Water 0 Temperature Coefficient and High Power Level Quantities of Uranium and Thorium in the Power Fluctuation.
0 Standard OSTR Irradiation Facilities.
B-1 Activation Analysis of Stone Meteorites, Other 0
B-12 Exploratory Experiments. Meteorites, and Terrestrial Rocks. 0 B-23 Studies Using TRIGA Thermal Column. B-2 Measurements of Cd Ratios of Mn, In, and Au 0 B-29 Reactivity Worth of Fuel.
in Thermal Column. 0 B-4 Flux Mapping. 0 B-31 TRIGA Flux Mapping. B-5 In-core Irradiation of Foils for Neutron Spectral 0 Measurements.
B-33 Irradiation of Combustible Liquids in Rotating B-6 Measurements of Neutron Spectra in External 0
Rack.
Irradiation Facilities. 0 B-34 Irradiation of enriched uranium in the Neutron B-7 Measurements of Gamma Doses in External Ir- 0 Radiography Facility.
radiation Facilities. 0 B-35 Irradiation of enriched uranium in the PGNAA B-8 Isotope Production. 0 Facility. B-9 Neutron Radiography. 0 B-10 Neutron Diffraction. 0 Of these available experiments, four were used during the reporting period. Table IV.4 provides information B-13 This experiment number was changed to A-7. 0 related to the frequency of use and the general purpose B-14 Detection of Chemically Bound Neutrons. 0 of their use. B-15 This experiment number was changed to C-1. 0 0
0 1I
Reactor 0
0 B-16 Production and Preparation of "FE One new safety evaluation screen was performed in support of the reactor this year. It was:
B-17 Fission Fragment Gamma Ray Angular Cor-0 relations.
0 B-18 A Study of Delayed Status (n, y) Produced 11-05, Installation of a Pneumatic Transfer System in the PGNAA Instrument Nuclei.
0 B-19 Instrument Timing via Light Triggering.
Description This screen allows the installation of a fast pneumatic B-20 Sinusoidal Pile Oscillator.
0 B-21 Beam Port #3 Neutron Radiography Facility.
transfer system within the main PGNAA irradiation chamber to allow rapid measurement of short lived fis-0 B-22 Water Flow Measurements Through TRIGA sion fragments outside the irradiation chamber where background levels are low.
0 Core.
B-24 General Neutron Radiography.
0 B-25 Neutron Flux Monitors.
B-26 Fast Neutron Spectrum Generator.
Surveillance and Maintenance B-27 Neutron Flux Determination Adjacent to the Non-Routine Maintenance OSTR Core.
October 2011 B-28 Gamma Scan of Sodium (TED) Capsule.
- Reconstructed the drain basin for Beam Port #1 to B-30 NAA of Jet, Diesel, and Furnace Fuels.
0 B-32 Argon Production Facility include a catch tray and easy drain system.
C-1 PuO 2 Transient Experiment. November 2011 0 - Replaced failing fission chamber detector due to Unplanned Shutdowns 0 There were four unplanned reactor shutdowns during cable insulation breakdown.
0 the current reporting period. Table IV.5 details these December 2011 events.
S - Completed painting of reactor pedestal and NRF structure.
0 Changes Pursuant tol 0 CFR 50-59 - Rebuilt the Transient rod drive assembly with new bearings and air seals.
0 One safety evaluation was performed in support of the
- Inspected the Transient rod to determine if pos-reactor this year. It was:
sible catastrophic failure was likely to occur due to 11-01, Changes to Reactor Experiment B-35, Irra- TRTR report.
diation of Enriched Uranium in the Prompt Gamma Neutron Activation Analysis Facility February 2012 Description - Replaced rabbit system blower with similar new, The use of the PGNAA irradiation facility was expand- and rebuilt the two original motors.
ed to include the installation of a pneumatic transfer - Replaced #5 local ARM detector due to failure.
system. This change takes into account the experience
- Rebuilt the cooling tower chemical injection pump.
gained concerning assumed limits due to fission gas buildup and venting requirements.
11-12 Annual Report I:)
Reactor March 2012
- Replace reactor stack guide wires using SS wire due to one broken and the other three rusty.
- Added a new HOBBs meter to monitor run hours on the new rabbit blowers to more closely control brush replacement needs.
April 2012
- Installed a rented charcoal filter and resin bed in the Heat Exchanger room to provide high quality makeup water during weekly drain and refill of reac-tor tank.
I
Ileauior S
Table IV.1 0 Present OSTR Operating Statistics 0
Operational Data For LEU Core Annual Values Cumulative Values (2011/2012) 0 0 MWH of energy produced 1418 4676 0 MWD of energy produced 59 194.8 Grams "35U used 81 269 0
S Number of fuel elements added to (÷) or removed(-) from 0 90 the core Number of pulses 39 134 0
0 Hours reactor critical 1510 5096 0 Hours at fiull power (1 MW) 1415 4655 0
Number of startup and shutdown checks 250 688 Number of irradiation requests processed 338 805 Number of samples irradiated 1352 3660 11-12 Annual Report 1 1
Reactor 0
0 0
Table IV.2 0 OSTR Use Time in Terms of Specific Use Categories 0 Annual Values Cumulative Values 0
OSTR Use Category (hours) (hours) 0 0
Teaching (departmental and others) 28 13,559.5 0
OSU Research 1,716 15,994 0
0 Off Campus research 3,133 37,275 0 0
Demonstrations 5 25 0 0
Reactor preclude time 789 30,197 0
Facility time 1 7,197 0
0 Total Reactor Use Time 5,672 104,481.5 0 0
0 0
0 Table IV.3 0 OSTR Multiple Use Time 0 Number of Users Annual Values (hours)
Cumulative Values (hours) 0 0
Two 187 8,174 0 Three 452 3,984 0
0 Four 452 2,110 0 Five 180 640 0
0 Six 42 140 0 0
Seven 14 37 0
Total Multiple Use Time 1,327 15,085 0 0
0 18 11-12 Annual Report
Reactor 0
0 0
0 Table IVA4 0 Use of OSTR Reactor Experiments Experiment Research Teaching Other Total 0 Number A-1 9 0 0 9 0
B-3 286 20 0 306 0
0 B-35 1 0 0 1 0 B-31 22 0 0 22 Total 318 20 0 338 0
0 0 Table IV.5 Unplanned Reactor Shutdowns and Scrams Number of Type of Event Occurrences Cause of Event 0
0 Percent Power Channel 2 Air voids in core during power calibration Percent Power Chennel 1 Excessive operator rod withdrawal rate Console Voltage Interruption (D-106) inadvertently plugged into inverter circuit Vacuum 11-12 Annual Report I(
Figure IV.1 Monthly Surveillance and Maintenance (Sample Form)
OSTROP 13, Rev. LEU- 1 Surveillance & Maintenance for the Month of SURVEILLANCE & MAINTENANCE TARGET DATE DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT] LIMITSIEXCEEDEDASFOUND DATE NOTECE COMPLETED N&
INITIALS
- CMLTD MAXIMUM UP: INCHES REACTOR TANK HIGH AND LOW WATER MOVEMENT LEVEL ALARMS D_ ICE
+ 3 INCHES ANN:
2 BULK WATER TEMPERATURE ALARM CHECK FUNCTIONAL CHANNEL TEST OF REACTOR TOP CAM AND Rx Top__
STACK CAM 3600+/-100 cpm Stack 4.A MEASUREMENT OF REACTOR PRIMARY 4.A WATER CONDUCTIVITY 5 pmho\cm MIN: 5 4.B PRIMARY WATER Ph MEASUREMENT MAX: 5 MAX: 8.5 BULK SHIELD TANK WATER Ph MIN: 5 MEASUREMENT MAX: 8.5 FILTER 6 CHANGE LAZY SUSAN FILTER CHANED CHANGED 7 REACTOR TOP CAM OIL LEVEL CHECK OSTROP 13. 10 NEED OIL?
8 PROPANE TANK LIQUID LEVEL CHECK > 50%
9 PRIMARY PUMP BEARINGS OIL LEVEL CHECK OSTROP 13.13 NEED OIL?
10 WATER MONITOR CHECK
- Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last month plus six weeks.
0000000000000000000000000000000000000000000o
Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU- I Surveillance & Maintenance for the 1S' / 2nd / 3 rd / 4 th Quarter of 20 SURVEILLANCE & MAINTENANCE LIMITS ASFOUND TARGET DATE NOT TO DATE REMARKS &
[SHADE INDICATES LICENSE REQUIREMENT] DATE BE EXCEEDED* COMPLETED INITIALS I REACTOR OPERATION COMMITTEE (ROC) AUDIT QUARTERLY 2 QUARTERLY ROC MEETING QUARTERLY 3 NOT CURRENTLY USED N/A N/A 4 ERP INSPECTIONS QUARTERLY 5 NOT CURRENTLY USED N/A N/A 6 ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 7 WATER MONITOR ALARM CHECK FUNCTIONAL MOTORS OILED STACK MONITOR CHECKS PART: 1150V+50 V (OIL DRIVE MOTORS. H.V. READINGS)
GAS: 900 V + 50 V 9 CHECK FILTER TAPE SPEED ON STACK MONITOR I"/HR + 0.2 10 INCORPORATE 50.59 & ROCAS INTO DOCUMENTATION QUARTERLY ALARM ON II STACK MONITOR ALARM CIRCUIT CHECKS CONTACT CONTACT
Figure IV.2 (continued)
Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU-1 Surveillance & Maintenance for the 1st / 2 nd / 3 rd / 4 th Quarter of 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT TO DATE REMARKS &
[SHADE INDICATES LICENSE REQUIREMENT] LIMITS DATE BE EXCEEDED* COMPLETED INITIALS ARM SYSTEM ALARM CHECKS CHAN 1 2 3S 3E 4 5 7 8 9 10 11 12 13 14 12 Afr FUNCTIONAL LIGHT PANFl, OPERATOR LOG a) TIME b) OPERATING EXERCISE a) >4 hours: at console (RO) or as Rx. Sup. (SRO) 13 b) Complete Operating Exercise
- Date not be exceeded only applies to shaded items. It is equal to the date completed last quarter plus four months.
Figure IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 15, Rev. LEU-l Surveillance & Maintenance for the 1St / 2nd Half of 20 DATE REMARKS TARGET TENOT DATE &
SURVEILLANCE & MAINTENANCE ASDATEE FONTAGT COMPLETED
[SHADE INDICATES LICENSE REQUIREMENT] LIMITS EXCEEDED* IIIL NO WITHDRAW NEUTRON SOURCE COUNT RATE INTERLOCK
>5 cps TRANSIENT ROD AIR INTERLOCK NO PULSE FUNCTIONAL PULSE PROHIBIT ABOVE 1 kW >1 kW CHECKS OF REACTOR TWO ROD WITHDRAWAL PROHIBIT I only INTERLOCKS PULSE MODE ROD MOVEMENT INTERLOCK NO MOVEMENT MAXIMUM PULSE REACTIVITY INSERTION LIMIT <_ $2.50 PULSE INTERLOCK ON RANGE SWITCH NO PULSE 2 2SAFETY SAEYPERIOD SCRAM Ž sec
>_3 C CIRCUIT TEST 3 NOT CURENTLY USED PULSE# <20% PULSE#
_MW MW 4 TEST PULSE °C CHANGE °C 5 NOT CURRENTLY USED N/A 6 NOT CURRENTLY USED N/A 7 NOT CURRENTLY USED N/A
- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.
- m
Figure IV.3 (continued)
Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 15, Rev. LEU- 1 Surveillance & Maintenance for the 1st / 2 nd Half of 20 SURVEILLANCE & MAINTENANCE
[SHADE INDICATES LICENSE REQUIREMENT]
I LIMITS I AS FOUND TARGET DATE D
TO BENOT DATE COMPLETED REMARKS &
INITIALS EXCEEDED*
8 CLEANING & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL BARREL 9 LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 10 LUBRICATION OF THE ROTATING RACK BEARINGS IOW OIL II CONSOLE CHECK LIST OSTROP 15.XI 12 INVERTER MAINTENANCE See User Manual 13 STANDARD CONTROL ROD MOTOR CHECKS LO-I 7 Bodine Oil NONE NONl SAFETY CHANNEL (info Only) 14 ION CHAMBER RESISTANCE MEASUREMENTS WITH MEGGAR INDUCED VOLTAGE NONE
%POWER CHANNEL(IfOny (info Only) d 100 V. I = AMPS FISSION CHAMBER RESISTANCE @ 900 V. I = AMPS 15 NONE C L CALCULATION N800 R=- V Al = AMPS (info Only)
AI R= __
HIGH 16 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP 15.XVIII FULL BRUSH INSPECTION INSPECTION OF THE PNEUMATIC TRANSFER SOLENOID VALVE INSPECTION FUNCTIONAL SYSTEM SAMPLE INSERTION TIME CHECK <6 SECONDS
- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.
Figure IV.4 Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-1 Annual Surveillance and Maintenance for 20 AS IDATETARGET NOT DATE TREMARKS SURVEILLANCE AND MAINTENANCE LI MITS I A TRGT TO BE DAE&
[SHADE INDICATES LICENSE REQUIREMENT] I FOUND DATE COMPLETED EXCEEDED* INITIALS FFCRS BIENNIAL INSPECTION OF CONTROL 12.0 ______
RODS: TRANS 2 ANNUAL REPORT NOV I OCT1 NOVI NORMAL 3 CONTROL ROD CALIBRATION: CLICIT OSTROP 9.0 ICIT/DUMMY 4 REACTOR POWER CALIBRATION OSTROP 8.0 CALIBRATION OF REACTOR TANK WATER TEMP TEMPERATURE METERS CONTINUOUS Particulate Monitor 6 AIR MONITOR RCHPP 18 CALIBRATION: Gas Monitor STACK MONITOR Particulate Monitor RCHPP 7 CALIBRATION Gas Monitor 18 & 26 8 AREA RADIATION MONITOR CALIBRATION RCHPP 18.0 9 DECOMMISSIONING COST UPDATE N/A N/A AUGUST !
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
- m
Figure IVA4 (continued)
Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU- 1 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT] LIMITS FOUND DATE TO BE COMPLETED & INITIALS
__ _________________________________ __________ ________EXCEEDED*______
10 SNM PHYSICAL INVENTORY N/A N/A OCTOBER 1 11 MATERIAL BALANCE REPORTS N/A N/A NOVEMBER 12 STANDARD CONTROL ROD DRIVE INSPECTION OSTROP 16.13 NORMAL 13 CORE EXCESS <$7.55 ICIT_
CLICIT CFD TRAINING GOOD SAM TRAINING ERP REVIEW ERP DRILL EMERGENCY FIRST AID FOR:
14 RESPONSE PLAN FIRST AID FOR:
EVACUATION DRILL AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIENNIAL SUPPORT AGREEMENTS OSP/DPS TRAINING PSP REVIEW PHYSICAL PSP DRILL 15 SECURITY PLAN LOCK/SAFE COMBO CHANGES AUTHORIZATION LIST UPDATE SPOOF MEASUREMENTS
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
Figure IV.4 (continued)
Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-1 Annual Surveillance and Maintenance for 20 DATE NOT SURVEILLANCE AND MAINTENANCE AS TARGET DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT] LIMITS FOUND DATE TO BE COMPLETED & INITIALS EXCEEDED*
16 KEY INVENTORY ANNUAL CONTROL ROD TRANS SAFE SHIM REG <2 sec WITHDRAWAL SCRAM _
INSERTION & WID <50 sec SCRAM TIMES INSERT <50 sec Is' Floor 18 REACTOR BAY VENTILLATION SYSTEM DAMPERS CLOSE IN <5 SHUTDOWN TEST SECONDS 2 "d Floor 19 CALIBRATION OF THE FUEL ELEMENT Per TEMPERATURE CHANNEL Checksheet
> 20 FE's inspected FUEL ELEMENT INSPECTION No damage, deteriora.tion or swell.
FOR SELECTED ELEMENTS At least one FE from each ring inspected.
100% of irradiated FE's inspected after 5 years.
21 REACTOR TANK AND CORE COMPONENT NO WHITE SPOTS INSPECTION 22 EMERGENCY LIGHT LOAD TEST RCHPP 18.0 ANNUAL REQUALIFICATION BIENNIAL MEDICAL EVERY 6 YEARS LICENSE REACTOR OPERATOR LICENSE CONDITIONS WRITTEN EXPIRATION EXAM OPERATING TEST DUE DATE APPLICATION DATE DATE DATE DATE COMPLETED DUE DATE OPERATOR NAME DUE PASSED DATE DUE PASSED DATE MAILED 23 NEUTRON RADIOGRAPHY FACILITY INTERLOCKS
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
)n XM... Prot 0
0 Introduction 0
'The purpose of the radiation protection program is to ensure compliance with Oregon Department of Energy Rule No. 0 345-30-010, which requires an annual report of environmental the safe use of radiation and radioactive material in the Cen-ter's teaching, research, and service activities, and in a similar effects due to research reactor operations.
0 manner to the fulfillment of all regulatory requirements of the 0 Within the scope of Oregon State University's radiation pro-State of Oregon, the U.S. Nuclear Regulatory Commission, tection program, it is standard operating policy to maintain all 0
and other regulatory agencies. The comprehensive nature of the program is shown in Table V.1, which lists the program's releases of radioactivity to the unrestricted environment and all 0 major radiation protection requirements and the performance exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable" (ALARA).
0 frequency for each item. 0
'The radiation protection program is implemented by a staff 0 consisting of a Senior Health Physicist, a Health Physicist, Environmental Releases 0 and several part-time Health Physics Monitors (see Part 11).
Assistance is also provided by the reactor operations group, the The annual reporting requirements in the OSTR Technical 0 neutron activation analysis group, the Scientific Instrument Specifications state that the licensee (OSU) shall include "a 0 summary of the nature and amount of radioactive effluents Technician, and the Radiation Center Director.
released or discharged to the environs beyond the effective 0
The data contained in the following sections have been control of the licensee, as measured at, or prior to, the point 0 prepared to comply with the current requirements of Nuclear Regulatory Commission (NRC) Facility License No. R-106 of such release or discharge." The liquid and gaseous effluents 0 released, and the solid waste generated and transferred are (Docket No. 50-243) and the Technical Specifications con- discussed briefly below. Data regarding these effluents are also 0
tained in that license. The material has also been prepared in summarized in detail in the designated tables. 0 0
0 Liquid Effluents Released 0
LiquidEffluents Oregon State University has implemented a policy to re-0 duce the volume of radioactive liquid effluents to an absolute 0 minimum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water. Waste 0
water from Radiation Center laboratories and the OSTR is 0 collected at a holdup tank prior to release to the sanitary sewer. 0 Liquid effluent are analyzed for radioactivity content at the time it is released to the collection point. For this reporting 0
period, the Radiation Center and reactor made three liquid ef- 0 fluent releases to the sanitary sewer. All Radiation Center and 0 reactor facility liquid effluent data pertaining to this release are contained in Table V.2.
0 0
Liquid Waste Generatedand Transferred Liquid waste generated from glassware and laboratory experi-0 ments is transferred by the campus Radiation Safety Office 0 0
I 28 11-12 Annual Report
RadIialtion~ I01e4IcciOm 0
0 to its waste processing facility. The annual summary of liquid Personnel Dose 0 waste generated and transferred is contained in Table V.3. The OSTR annual reporting requirements specify that the 0 licensee shall present a summary of the radiation exposure re-ceived by facility personnel and visitors. The summary includes 0 Airborne Effluents Released all Radiation Center personnel who may have received expo-sure to radiation. These personnel have been categorized into 0 Airborne effluents are discussed in terms of the gaseous com-six groups: facility operating personnel, key facility research ponent and the particulate component.
0 personnel, facilities services maintenance personnel, students Gaseous Effluents in laboratory classes, police and security personnel, and visitors.
Gaseous effluents from the reactor facility are monitored by Facility operating personnel include the reactor operations and 0 the reactor stack effluent monitor. Monitoring is continuous, i.e., prior to, during, and after reactor operations. It is normal health physics staff. The dosimeters used to monitor these in-dividuals include quarterly TLD badges, quarterly track-etch/
0 for the reactor facility stack effluent monitor to begin opera-tion as one of the first systems in the morning and to cease albedo neutron dosimeters, monthly TLD (finger) extremity dosimeters, pocket ion chambers, electronic dosimetry.
0 operation as one of the last systems at the end of the day. All gaseous effluent data for this reporting period are summarized Key facility research personnel consist of Radiation Center 0 in Table V.4. staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other Particulate effluents from the reactor facility are also moni-0 tored by the reactor facility stack effluent monitor.
research facilities present at the Center. The individual dosim-etry requirements for these personnel will vary with the type of 0 ParticulateEffluents research being conducted, but will generally include a quarterly TLD film badge and TLD (finger) extremity dosimeters. If 0 Evaluation of the detectable particulate radioactivity in the stack effluent confirmed its origin as naturally-occurring radon the possibility of neutron exposure exists, researchers are also daughter products, within a range of approximately 3x10 11 monitored with a track-etch/ albedo neutron dosimeter.
0 1 iCi/ml to 1 x 10' pCi/ml. This particulate radioactivity is Facilities Services maintenance personnel are normally is-predominantly 214Pb and 214Bi, which is not associated with sued a gamma sensitive electronic dosimeter as their basic reactor operations.
monitoring device. A few Facilities Services personnel who There was no release of particulate effluents with a half life routinely perform maintenance on mechanical or refrigeration greater than eight days and therefore the reporting of the equipment are issued a quarterly XMfl(y) TLD badge and other average concentration of radioactive particulates with half lives dosimeters as appropriate for the work being performed.
0 greater than eight days is not applicable.
Students attending laboratory classes are issued quarterly 0 Xg(,y) TLD badges, TLD (finger) extremity dosimeters, and track-etch/albedo or other neutron dosimeters, as appropriate.
Solid Waste Released Students or small groups of students who attend a one-time Data for the radioactive material in the solid waste generated lab demonstration and do not handle radioactive materials are and transferred during this reporting period are summarized usually issued a gamma sensitive electronic dosimeter. These in Table V.5 for both the reactor facility and the Radiation results are not included with the laboratory class students.
Center. Solid radioactive waste is routinely transferred to OSU Radiation Safety. Until this waste is disposed of by the OSU police and security personnel are issued a quarterly Radiation Safety Office, it is held along with other campus Xf9(y) TLD badge to be used during their patrols of the Ra-radioactive waste on the University's State of Oregon radioac- diation Center and reactor facility.
tive materials license.
Visitors, depending on the locations visited, may be issued a Solid radioactive waste is disposed of by OSU Radiation gamma sensitive electronic dosimeters. OSU Radiation Center Safety by transfer to the University's radioactive waste disposal policy does not normally allow people in the visitor category to vendor.
11-12 Annual Report 29
0 Radiation Protection 0
0 0
become actively involved in the use or handling of radioactive on-the-spot personal observations (along with recorded data),
0 materials. which will provide advance warning of needed corrections and 0 An annual summary of the radiation doses received by each thereby help to ensure the safe use and handling of radiation 0 sources and radioactive materials. A third objective, which is of the above six groups is shown in Table V.6. There were no really derived from successful execution of the first two objec-0 personnel radiation exposures in excess of the limits in 10 tives, is to gather and document information which will help to 0 CFR 20 or State of Oregon regulations during the reporting period.
ensure that all phases of the operational and radiation protec- 0 tion programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment 0
"as low as reasonably achievable" (ALARA). 0 Facility Survey Data The annual summary of radiation and contamination levels 0
The OSTR Technical Specifications require an annual measured during routine facility surveys for the applicable 0 summary of the radiation levels and levels of contamination observed during routine surveys performed at the facility. The reporting period is given in Table V.9.
0 Center's comprehensive area radiation monitoring program 0 encompasses the Radiation Center as well as the OSTR, and Environmental Survey Data 0 therefore monitoring results for both facilities are reported.
The annual reporting requirements of the OSTR Technical 0 Area RadiationDosimeters Area monitoring dosimeters capable of integrating the radia-Specifications include "an annual summary of environmental 0 tion dose are located at strategic positions throughout the surveys performed outside the facility." 0 reactor facility and Radiation Center. All of these dosimeters 0 contain at least a standard personnel-type beta-gamma film or TLD pack. In addition, for key locations in the reactor fa- Gamma Radiation Monitoring 0 cility and for certain Radiation Center laboratories a CR-39 On-site Monitoring 0
plastic track-etch neutron detector has also been included in Monitors used in the on-site gamma environmental radiation 0 the monitoring package. monitoring program at the Radiation Center consist of the reactor facility stack effluent monitor described in Section V 0
The total dose equivalent recorded on the various reactor and nine environmental monitoring stations. 0 facility dosimeters is listed in Table V.7 and the total dose equivalent recorded on the Radiation Center area dosimeters During this reporting period, each fence environmental sta-0 is listed in Table V.8. Generally, the characters following tion utilized an LiF TLD monitoring packet supplied and pro- 0 the Monitor Radiation Center (MRC) designator show the cessed by Mirion Technologies, Inc., Irvine, California. Each 0 room number or location. GDS packet contained three LiF TLDs and was exchanged quarterly for a total of 108 samples during the reporting period 0
Routine Radiationand ContaminationSurveys (9 stations x 3 TLDs per station x 4 quarters). The total num- 0 The Center's program for routine radiation and contamina-tion surveys consists of daily, weekly, and monthly measure-ber of GDS TLD samples for the reporting period was 108. A 0 ments throughout the TRIGA reactor facility and Radiation summary of the GDS TLD data is also shown in Table V.10.
0 Center. The frequency of these surveys is based on the nature From Table V.10 it is concluded that the doses recorded by the 0 of the radiation work being carried out at a particular loca- dosimeters on the TRIGA facility fence can be attributed to tion or on other factors which indicate that surveillance over natural back-ground radiation, which is about 110 mrem per 0
a specific area at a defined frequency is desirable. year for Oregon (Refs. 1, 2). 0 The primary purpose of the routine radiation and con- Off-site Monitoring 0
tamination survey program is to assure regularly scheduled The off-site gamma environmental radiation monitoring 0 surveillance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current program consists of twenty monitoring stations surrounding 0 the Radiation Center (see Figure V.1) and six stations located and characteristic data on the status of radiological condi- within a 5 mile radius of the Radiation Center. 0 tions. A second objective of the program is to assure frequent 0 30 11-12 Annual Report
Radiation Protection 0
0 Each monitoring station is located about four feet above the LLD were averaged in at the corresponding LLD con-0 the ground (MRCTE 21 and MRCTE 22 are mounted on centration. Table V.13 gives the concentration and the range 0 the roof of the EPA Laboratory and National Forage Seed of values for each sample category for the current reporting Laboratory, respectively). These monitors are exchanged and period.
processed quarterly, and the total number of TLD samples As used in this report, the LLD has been defined as the 0 during the current one-year reporting period was 240 (20 stations x 3 chips per station per quarter x 4 quarters per amount or concentration of radioactive material (in terms of year). The total number of GDS TLD samples for the report- pCi per unit volume or unit mass) in a representative sample, which has a 95% probability of being detected.
ing period was 240. A summary of GDS TLD data for the 0 off-site monitoring stations is given in Table V.11. Identification of specific radionuclides is not routinely carried out as part of this monitoring program, but would 0 After a review of the data in Table V.11, it is concluded that, be conducted if unusual radioactivity levels above natural like the dosimeters on the TRIGA facility fence, all of the doses recorded by the off-site dosimeters can be attributed to background were detected. However, from Table V.12 it can 0 natural background radiation, which is about 110 mrem per be seen that the levels of radioactivity detected were consis-tent with naturally occurring radioactivity and comparable to year for Oregon (Refs. 1, 2).
values reported in previous years.
0 0 Soil, Water, and Vegetation Surveys Radioactive Materials Shipments 0 The soil, water, and vegetation monitoring program consists A summary of the radioactive material shipments originat-ing from the TRIGA reactor facility, NRC license R-106, of the collection and analysis of a limited number of samples 0 in each category on a annual basis. The program monitors is shown in Table V.14. A similar summary for shipments 0 highly unlikely radioactive material releases from either the originating from the Radiation Center's State of Oregon TRIGA reactor facility or the OSU Radiation Center, and radioactive materials license ORE 90005 is shown in Table also helps indicate the general trend of the radioactivity V.15. A summary of radioactive material shipments exported 0 concentration in each of the various substances sampled. See under Nuclear Regulatory Commission general license 10 CFR 110.23 is shown in Table V.16.
Figure V.1 for the locations of the sampling stations for grass 0 (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 foot radius of the reactor facility 0 and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the posi-References
- 1. U. S. Environmental Protection Agency, "Estimates S tions indicated in Figure V.1.
of Ionizing Radiation Doses in the United States, There are a total of 22 sampling locations: four soil locations, 1960-2000," ORP/CSD 72-1, Office of Radiation four water locations (when water is available), and fourteen Programs, Rockville, Maryland (1972).
vegetation locations.
- 2. U. S. Environmental Protection Agency, "Radio-The annual concentration of total net beta radioactivity (mi- logical Quality of the Environment in the United nus tritium) for samples collected at each environmental soil, States, 1977," EPA 520/1-77-009, Office of Radia-water, and vegetation sampling location (sampling station) is tion Programs; Washington, D.C. 20460 (1977).
listed in Table V.12. Calculation of the total net beta disin-tegration rate incorporates subtraction of only the count-ing system back-ground from the gross beta counting rate, followed by application of an appropriate counting system efficiency.
The annual concentrations were calculated using sample results which exceeded the lower limit of detection (LL[)),
except that sample results which were less than or equal to 11-12 Annual Report
Radiation Protection 0
0 0
0 Table V.1 0 Radiation Protection Program Requirements and Frequencies 0
0 Frequency Radiation Protection Requirement 0 Daily/Weekly/Monthly Perform Routing area radiation/contamination monitoring 0 0
Collect and analyze TRIGA primary, secondary, and make-up water. 0 Exchange personnel dosimeters and inside area monitoring dosimeters, and review Monthly exposure reports.
0 Inspect laboratories. 0 Calculate previous month's gaseous effluent discharge.
0 0
Process and record solid waste and liquid effluent discharges.
Prepare and record radioactive material shipments.
0 Survey and record incoming radioactive materials receipts. 0 As Required Perform and record special radiation surveys.
Perform thyroid and urinalysis bioassays.
0 Conduct orientations and training. 0 Issue radiation work permits and provide health physics coverage for maintenance operations.
0 0
Prepare, exchange and process environmental TLD packs. 0 Conduct orientations for classes using radioactive materials. 0 Quarterly Collect and analyze samples from reactor stack effluent line.
Exchange personnel dosimeters and inside area monitoring dosimeters, and review 0 exposure reports. 0 0
Leak test and inventory sealed sources.
Semi-Annual Conduct floor survey of corridors and reactor bay. 0 0
Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.
0 Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation 0 monitors, and air samplers.
Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA 0
Annual filters as necessary. 0 Inventory and inspect Radiation Center emergency equipment.
Conduct facility radiation survey of the 6°Co irradiators.
0 Conduct personnel dosimeter training. 0 Update decommissioning logbook.
Collect and process environmental soil, water, and vegetation samples.
0 0
0 0
0 0
I 11-12 Annual Report
I.
Table V.2 Monthly Summary of Liquid Effluent Release to the Sanitary SewerO)
Average Specific Activity Total Percent of Total Concentration For Each Quantity of Applicable Volume of Total Of Released Detectable Each Monthly Average Liquid Date of Quantity of Detectable Radioactive Radionuclide in Detectable Concentration for Effluent Discharge Radioactivity Radionuclide in Material at the the Waste, Where Radionuclide Released Released (Month and Year) Released the Waste Point of The Release Concentration Released in Radioactive Including (Curies) Release Was>1 x 10-7 the Waste Material Diluent
( pCi m1-1) (%)(2)
(1 iCi ml-') (Curies) (gal)
August 2011 7.2x10-2 H-3 1.4x10-4 7.2x10-2 1.4X10-4 1.37 138,430 October 2011 6.7x 10-2 H-3 2.5x10-4 6.7x1 0-2 2.5x 10-4 2.45 71,857 January 2012 6.0x10-3 H-3 2.6x10 5- 6.Ox10-3 2.5x 0-5 0.26 62,082 March 2012 5.2x10-2 H-3 2.8x10-5 5.2x10-2 2.8xl10' 0.28 494,016 April 2012 5.2x10-2 H-3 9.6x10-5 5.2x10-2 9.6x105' 0.96 142,392 H-3,0.4 H-3, 6.0 H-3, Cr-51, Cr-51, 4.3x10-6 4 Cr-51, 0.0001 June 2012 0.4 H-3, 6.0x10-4 Co-58, 1.1x10-61 6.OX10- 177,264 Co-58, Co-60 Co-58, 0.0008 lCo-60, 1.0x10- Co-60, 0.0005 Annual Total for H-3, Cr-51, 1.1x10-3 1.14X10-3 6.5x101 H-3, 6.5x10' 11.32 1,086,041 Radiation Center Co-58, Co-60 (1) 'he OSU operational policy is to subtract only detector background from the water analysis data and not background radioactivity in the Corvallis city water.
(2) Based on values listed in 10 CFR 20, Appendix B to 20.1001 - 10.2401,Table 3, which are applicable to sewer disposal.
- m
Radiation Protection 0 0
0 0
Table V.3 0 0
Annual Summary of Liquid Waste Generated and Transferred 0
Volume of Liquid Dates of Waste Pickup Detectable Total Quantity of Origin of Liquid Waste Packaged(1) for Transfer to the Radionuclides Radioactivity in the Waste (gallons) Waste Processing in the Waste Waste (Curies)
Facility 0 0
Na-24, Cr-51, Mn-56, TRIGA C*o-60, Rb-89, Sb-122, Reactor 15 3.44x10-3 10/21/11 S Sib-124, Cs-137, H-3, Facility Ag - 11Om, Sc-46, Eu152 10/21/11 S
Radiation Center Pu-239, C1-36, U-238, 5 20.25 5.96x10- 2/22/12 Laboratories C-14, H-3 6/10/12 TOTAL 35.25 See above 3.50x10-3 S
I (1) OSTR and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final 0 packaging.
0 0
0 0
0 0
34 11-12 Annual Report
H tId;n1;4hr1 Iprtjti-tidli 0
- Table V.4 0*-Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis
- Estimated Fraction of the Technical Total Total Totl Total ISConcetrationoo Atmospheric Diluted Specification Month Estimated Estimated Quantity Concentration of Annual Average Activity of Argon-41 Argon-41 at Point of Argon-41 Released (Curies) Released(1 ) (Curies) Release S(iCi/cc) Concentration Limit (%)
- t July 0.54 0.54 4.36x10- 8 1.09 August 0.58 0.58 4.62xlO' 1.15 September 0.44 0.44 3.63x10 5- 0.91 October 0.53 0.53 4.22x10-8 1.06 November 0.44 0.44 3.64x10- 8 0.91 December 0.53 0.53 4.21x10- 8 1.05 January 0.53 0.53 4.23x10- 8 1.06 February 0.56 0.56 4.78x10- 8 1.20 March 0.67 0.67 5.37x10 8 1.34 April 0.52 0.52 4.28x10- 8 1.07 May 0.66 0.66 5.30x10- 8 1.33 June 0.51 0.51 4.18x10- 8 1.04 TOTAL 1 2 2)
- ('10-'11) 6.50 6.50 4.4Nx10-8 * - . ..
(1) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionuclide was argon-41.
(2) Annual Average.
0 0
0 0
0 11-12 Annual Report :.-
Radiation Protection 0
0 Table V.5 Annual Summary of Solid Waste Generated and Transferred 0
Volume of Detectable Total Quantity Dates of Waste Pickup Origin of Solid Waste Radionuclides of Radioactivity for Transfer to the OSU 0 Solid Waste Packaged(,) in the Waste in Solid Waste Waste Processing (Cubic Feet) (Curies) Facility 0 0
Mn-54, Co-58, Co-60, Zn- 10/21/11 TRIGA 65, As-74, Cs-134, Eu-152, Reactor 30 Sc-46, Fe-59, Sb-124, Se-75, 1.52x10-4 2/22/12 0
Facility Hf-181, Na-24, Hg-203, Sb- 0 125, Cr-51, Pa-233 6/10/12 0 C1-36, U-238, Np-237, Pu-0 242, Eu-152, Eu-154, Pu-239, Am-241, U-235, Uh-232, 10/21/11 0
Tc-99, Mo-99, Co-60, Ir-192, Radiation Center 63 H-3, C-14, Sr-90, Cs-137, 2.35x10-4 2/22/12 0
Am-243, Pu-242, Cd-109, Laboratories Hg-203, Na-22, Sn-113, 6/10/12 Po-210, Sr-85, Nb-95, Ce-139, Y-88, Cr-51,Te-123m, Cs-134 0
TOTAL 93 See Above 3.88x10-4 0
(1) OSTR and Radiation Center laboratory waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final packaging.
0 36 11-12 Annual Report
Radiation Pr,)[,,.ti0.
0 Table V.6 0 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest I ndividual Total Person-mrem Dose"' Dose{l) For the Group"(
0 0 Whole Body Extremities Whole Body Extremities Whole Body Extremities Personnel Group (nrem) (mrem) (mrem) (mrem) (mrem) (mrem) 0 Facility Operating 102.43 339.57 187 1269 717 2377 Personnel 0 -I Key Facility Research 2.38 16.17 31 139 31 194 Personnel 0 Facilities Services Maintenance <1 N/A 0.5 N/A 0.8 N/A 0 Personnel 0 Laboratory Class Students 2.63 5.37 403 208 1117 573 0
Campus Police and 0 Security Personnel 2.47 N/A 37 N/A 75 N/A 0
0 Visitors <1 N/A 6.3 N/A 96.6 N/A (1) "N/A"indicates that there was no extremity monitoring conducted or required for the group.
11-12 Annual Renort
- 1 3? -
A n.. .. u a.. .. . . . .
Radiation Protection 0
0 0
Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility 0 Table V.7 Total TRIGA Reactor Dose Equivalent(1)(2)
Monitor Recorded Facility Location I.D. X9(y) Neutron (See Figure V.1)
(mrem) (mrem)
MRCTNE D104: North Badge East Wall 274 ND 0
MRCTSE D104: South Badge East Wall 146 ND 0
MRCTSW D104: South Badge West Wall 905 ND MRCTNW D104: North Badge West Wall 199 ND 0
MRCTWN )104: West Badge North Wall 381 ND 0
MRCTEN )104: East Badge North Wall 346 ND MRCTES )104: East Badge South Wall 1572 ND F-MRCTWS )104: West Badge South Wall 546 ND MRCTTOP )104: Reactor Top Badge 710 ND F-MRCTHXS )104A: South Badge HX Room 878 ND i--.
MRCTHXW )104A: West Badge HX Room 657 ND 0 MRCD-302 )302: Reactor Control Room 447 ND 0
MRCD-302A )302A: Reactor Supervisor's Office 149 N/A 0
F-MRCBP1 )104: Beam Port Number 1 319 ND MRCBP2 D104: Beam Port Number 2 256 ND i
MRCBP3 D104: Beam Port Number 3 929 ND MRCBP4 D104: Beam Port Number 4 854 ND (1) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" in-dicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "N/A" indicates that there was no neutron monitor at that location.
(2) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.
I 3)8( 11-12 Annual Report
Radiation Protection 0
0 0 Table V.8 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center 0 )tal Recorded Radiation Center Do, se Equivalent(')
Monitor Facilitv Location I.D. X9(7y) 1 Neutron 0 (See Figure V.1)
(mrem) (mrem)
MRCA100 A100: Receptionist's Office 31 N/A MRCBRF A102H: Front Personnel Dosimetry Storage Rack ....- 63 ......... ý I- _
- _/
0 MRCA120 A120: Stock Room 96 N/A 0 MRCA120A A120A: NAA Temporary Storage 0 N/A 0 MRCA126 A126: Radioisotope Research Lab 236 N/A 0 MRCCO-60 A128:
6 0CO Irradiator Room 625 N/A 0 MRCA130 A130: Shielded Exposure Room 146 N/A 0 MRCA132 A132: TLD Equipment Room 73 N/A MRCA138 A138: Health Physics Laboratory 51 N/A 0 MRCA146 A146: Gamma Analyzer Room (Storage Cave) 112 N/A MRCB100 B100: Gamma Analyzer Room (Storage Cave) 73 N/A 0 MRCB114 B114: Lab (226Ra Storage Facility) 1612 ND 0 MRCB119-1 B119: Source Storage Room 218 N/A MRCB119-2 B119: Source Storage Room 377 N/A MRCB119A B119A: Sealed Source Storage Room 2906 1303 MRCB120 B120: Instrument Calibration Facility 78 N/A MRCB122-2 B122: Radioisotope Hood 349 N/A MRCB122-3 B122: Radioisotope Research Laboratory 76 N/A MRCB124-1 B124: Radioisotope Research Lab (Hood) 72 N/A MRCB124-2 B124: Radioisotope Research Laboratory 92 N/A MRCB124-6 B124: Radioisotope Research Laboratory 64 N/A MRCB128 B128: Instrument Repair Shop 52 N/A MRCB136 B136 Gamma Analyzer Room 27 N/A MRCC100 C100: Radiation Center Director's Office 63 N/A (1) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equiva-lent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose report-ing threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "N/A" indicates that there was no neutron monitor at that location.
11-12 Annual Report :111)
Radiation Protection Table V.8 (continued) 0 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center 0 Total Recorded Monitor Radiation Center Dose Equivalentý1 ) 0 I.D. Facility Location (See Figure V.1) Xtg(y) Neutron 0
(mrem) (mrem)
MRCC106A C106A: Office 62 N/A 0 MRCC106B C106B: Custodian Supply Storage 45 N/A 0 MRCC106-H C106H: East Loading Dock 42 N/A 0 MRCC118 C118: Radiochemistry Laboratory 35 N/A 0 MRCC120 C120: Student Counting Laboratory 26 N/A 0 MRCF100 F100: APEX Facility 11 N/A 0 MRCF102 F102: APEX Control Room 21 N/A 0
MRCB125N B125: Gamma Analyzer Room (Storage Cave) 37 N/A MRCN125S B125: Gamma Analyzer Room 74 N/A MRCC124 C124: Classroom 67 N/A 0
MRCC130 C130: Radioisotope Laboratory (Hood) 64 N/A MRCD100 D100: Reactor Support Laboratory 90 ND MRCD102 D102: Pneumatic Transfer Terminal Lab' 287 ND MRCD102-H D102H: 1st Floor Corridor at D102 113 ND MRCD106-H D106H: 1st Floor Corridor at D106 351 N/A MRCD200 D200: Reactor Administrator's Office 190 ND MRCD202 D202: Senior Health Physicist's Office 283 ND MRCBRR D200H: Rear Personnel Dosimetry Storage Rack 78 N/A MRCD204 D204: Health Physicist Office 264 ND MRCATHRL F104: ATHRL 42 N/A MRCD300 D300: 3rd Floor Conference Room 192 ND (1) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equiva-lent of "ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose report-ing threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "N/A" indicates that there was no neutron monitor at that location.
40 11-12 Annual Report
Iladiati~on Protectioni 0
0 0
0 Table V.9 0
Annual Summary of Radiation and Contamination Levels 0
Observed Within the Reactor Facility and Radiation Center 0 During Routine Radiation Surveys 0 Whole Body C ontamination 0 Accessible Location Radiation Levels Levels(1 )
(mrem/hr) (dpm/cm 2)
(See Figure V.1)
Average Maximum Average Maximum TRIGA Reactor Facility:
Reactor Top (D104) 1 1.64 90 <500 25,870 Reactor 2nd Deck Area (D104) 6.56 46 <500 926 Reactor Bay SW (D104) <1 50 <500 <500 0 Reactor Bay NW (D104) <1 9 <500 - 3,269 18 0 Reactor Bay NE (D104) <1 <500 2,608
<1 0 Reactor Bay SE (D104) 7 <500 5,179 Class Experiments (D104, D302) <1 <1 <500 <500 0 Demineralizer Tank & Make Up Water System
<1 28 <500 1,300 (D104A) 0 Particulate Filter--Outside Shielding (D104A) <1 6 <500 3,036 Radiation Center:
NAA Counting Rooms (A146, B100) <1 2.7 <500 <500 Health Physics Laboratory (A138) <1 1.7 <500 <500 S 6°Co Irradiator Room and Calibration Rooms <1 31
<500 <500 (A128, B120, A130)
Radiation Research Labs (A126, A136) 12
<500 652 (B108, B114, B122, B124, C126, C130, C132A)
Radioactive Source Storage (B119, B119A, <1 25
<500 <500 A120A, A132A)
Student Chemistry Laboratory (C118) <1 ! <1 <500 <500 Student Counting Laboratory (C120) <1 _ - <1 <500 <500 Operations Counting Room (B136, B125) <1 1.2 <500 <500 Pneumatic Transfer Laboratory (D102) <1 10 <500 11,800 RX support Room (D100) <1 <1 <500 <500 (1) <500 dpm/100 cm2 = Less than the lower limit of detection for the portable survey instrument used.
11-12 Annual Report ,II
Radiation Protection 0
0 0
Table V.10 0 Total Dose Equivalent at the TRIGA Reactor Facility Fence 0 0
Fence Total Recorded Dose Equivalent 0 (Including Background)
Environmental Monitoring Station Based on Mirion TLDsO.2) 0 (See Figure V.1)
(mrem) 0 MRCFE-1 87+ 4 0 MRCFE-2 83+/- 5 0
0 MRCFE-3 77+/- 7 0 MRCFE-4 85+/- 4 0 MRCFE-5 91+/- 8 0 MRCFE-6 0
83+/- 6 0
MRCFE-7 84+/- 5 0 MRCFE-8 80 +/- 5 00 0
MRCFE-9 80 +/- 4 0
(1) Average Corvallis area natural background using Mirion TLDs totals 75 +/- 11 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
I '12 11-12 Annual Report
0 0
- Table V.11
- Total Dose Equivalent at the Off-Site Gamma Radiation S.. ............ Monitoring Stations OTotal Recorded Dose Equivalent Monitoring Station (Including Background)
Mo(See Figure V.1) Based on Mirion TLDsO, 2)
(mrem)
- MRCTE-2 82 +/-5 MRCTE-3 54 t 5
- MRCTE-4 81+/-6 MRCTE-5 87 +/- 6 MRCTE-6 82 +/- 9 MRCTE-7 81 +/- 5 MRCTE-8 94 t 5 MRCTE-9 85 +/-6 MRCTE-10 76 t 5 MRCTE-12 89 t 7 MRCTE-13 55 +/- 6 MRCTE-14 83 +/-3 MRCTE-15 76 t 6 MRCTE-16 85 +/- 5 MRCTE-17 82 t 5 MRCTE-18 79 t 6 MRCTE-19 86 t 5 MRCTE-20 79 t 4
- _MRCTE-21 74 t 9
- MRCTE-22 _ 77 t 5 (1) Average Corvallis area natural background using Mirion TLDs totals 75 _ 11 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
0 0
0 11-12 Annual Report 13 0
Radiation Protection 0
0 Table V.12 Annual Average Concentration of the Total Net Beta Radioactivity (minus 3H) for Environmental Soil, Water, and Vegetation Samples 0
Sample Sample Annual Average Concentration 0
Location Type Of the Total Net Beta (Minus 3H) Re porting 0 (See Fig. V.1) Radioactivity'"
Units 1-W Water 7.29x10-6(2) Ii ml1 4-W Water 7.29x10-6(2) Ii m1-1 0 2
11-W Water 7.29x106 () ýi m1-1 19-RW i
Water 7.29x106 2
11 Ii m1-1 0
3-S Soil 2.36x10-5 12) - 525x10-6 PCi g- 1 of dry soil i
6 5-S Soil 1.22x10-5 +/-, 4.07x10- pCi g- 1 of dry soil 20-S Soil 1.66x10-5 (2) - 4.63x10-6 pCi g-1 of dry soil 0 6
21-S Soil 8.37x10- 12)
PCi g-1 of dry soil 2-G Grass 4.20x10-4 +/- 4.61X10-5 pCi g-1 of dry ash 0 6-G Grass 2.29x10-4 2.42x10- 5 PCi g-1 of dry ash 0 7-G Grass 2.93x10- 4 _ 3.34x10- 5 PCi g- 1 of dry ash 0 8-G Grass 3.46x10- 4 _ 2.92x10- 5 PCi g- 1 of dry ash 0
9-G Grass 3.64x10- 4 +/- 3.00x10- 5 pCi g-1 of dry ash 10-G Grass 2.88xj0-4 +/-2.35x10-5 lCi g 1 of dry ash 12-G Grass 3.27x10- 4 _ 2.04x10- 5 pCi g- 1 of dry ash 13-G Grass 2.90x10- 4 _ 2.33x10- 5 pCi g- 1 of dry ash 14-G Grass 1.55x10- 4 _ 2.15x10- 5 PCi g- 1 of dry ash 15-G Grass 2.09x10- 4 + 2.38x10- 5 1Ci g- 1 of dry ash 16-G Grass 1.31x10- 4 _ 1.75x10- 5 pCi g-1 of dry ash 17-G Grass 2.57x10- 4 +/- 2.35x10-5 pCi g- 1 of dry ash 18-G Grass 2.18x10-4 + 2.60x10-5 pCi g- 1 of dry ash 22-G Grass 1.10x10-4+ 2.70x10-5 pCi g- 1 of dry ash (1) +/-values represent the standard deviation of the value at the 95% confidence level.
(2) Less than lower limit of detection value shown.
I /14 11-12 Annual Report
7 IRadiation Protectioni S
0 0 Table V.13 Beta-Gamma Concentration and Range of LLD Values for Soil, Water, and 0 Vegetation Samples 0 Sample Average Range of Values Reporting Units Type Value 0
S Soil 9.17x10-6 8.37x10- 6 to 1.03x10-5 PCi g- 1 of dry soil 0
6 6 Water 7.29x10- (1 7.29x10- laCi m1-1 Vegetation 4.03x10-5 2.37x10- 5 to 7.22x10-5 PCi g- 1 of dry ash (1) Less than lower limit of detection value shown.
S Radiation Protection Table V.14 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-1 06
'Total
_ F Number of Shipments Shipped To Activity Exempt Limited Quantity Yellow II Yellow III Total 0 Berkeley Geochronology Center Berkeley, CA USA 1.58x10-6 5 2 0 0 7 5 C.O.R.D. University of Wisconsin-Madison 1 7xo-5.17x106- 0 0 0 16 16 Madison, WI USA Cal State Fullerton Fullerton, CA USA California Institue of Technology 6.33xl 1~ 0 0 0 1 5.84xl 0- 0 0 1 0 1 Pasadena, CA USA Lehigh University 1.20x10-' 2 0 0 0 2 Bethlehem, PA USA Materion Coperation 0 4 3.73x 0-2 0 0 4 Elmore, OH USA Materion Natural Resources 1.08x10- 1 0 0 0 22 22 Delta, UT USA Occidental College Los Angeles, CA USA 3.87x10 9 1 1 0 0 1 S Oregon State University Corvallis, OR USA 5.60x106 1 0 2 0 3 5 Plattsburgh State University 1.17x10 8- 2 0 0 0 2 Plattsburgh, NY USA Stanford University I 1.01x108 1 0 0 0 1 Stanford, CA, USA Syracuse University Syracuse, NY USA Union College 1~
4.81x10 7' 8.48x10-'
3 2
1 0
0 0
0 0
4 2 5 Schenectady, NY USA University of Arizona Tucson, AZ USA 8.16x 10-' 7 0 2 0
_ S
~~~1~~
University of California at Berkeley Berkeley, CA USA 0 0 2 0 2 5 University of California at Santa Barbara 3.49x1 0-7 1 1 0 0 2 Santa Barbara, CA USA University of Florida Gainesville, FL USA 9.10x10-8 3 0 0 0 3 5 University of Michigan 1 4.41x1 0- 0 0 0 1 Ann Arbor, MI USA University of Minnesota 1 5.00x10-1 0 0 0 1 Minneapolis, MN USA University of Wisconsin-Madison 1.14xl0-5 0 3 0 Madison, WI USA 30 Totals _7 1.4x1O'1 31 4 11 26 72 0 I 40 11-12 Annual Report
Radiatiori Protection 0
0 0 Table V.15 0 Annual Summary of Radioactive Material Shipments 0 Originating From the Radiation Center's 0 State of Oregon License ORE 90005 Number of Shipments Total Activity 0 Shipped To (TBq) Exempt Limited quWhite W
I Total 0 Argonne National Lab 8.01X10 1 2 1 0 0 1 Argonne, IL USA Lawrence Berkeley National Laboratory 9 1 2.05x 0- 0 0 1 Berkeley, CA USA Los Alamos National Lab 6.14x1O-' 5 3 3 11 0 Los Alamos, NM USA Pacific Northwest National Lab 1 6.5Ox1O-" 0 0 1 Richland, WA USA 0 6 14 Totals 6.14x10- 8 3 3 0
0 0
0 11-12 Annual Report 17
Radiation Protectioi Table V.1 6 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 Number of Shipments Total Activity Limited Shipped To (TBq)
Exempt Quantity Yellow II Total 0
Glasgow University 1 2.49x10-8 0 Glasgow SCOTLAND 0 1 Institute of Geology, China Earthquake Admin Beijing PR CHINA 3.12x10-9 1 0 0 1 0 Lanzhou University 1 1.04x10-8 0 0 1 Lanzhou, Gansu CHINA 0 Lund University 3.17x10-7 3 0 0 3 Lund, SWEDEN I I- -~
Polish Academy of Sciences Krakow, POLAND 2.92x108- 2 0 0 2 0 QUAD-Lab, Roskilde University 2.57x1O-' 2 0 0 2 Roskilde, DENMARK Scottish Universities Research & Reactor Centre 1 2.13x10-6 East Kilbride, SCOTLAND Universitat Gottingen Gottingen, GERMANY 2.46x10 8- 2 Universitat Potsdam T 1 0 5.37x10-9 Postdam, GERMANY Universite Paris-Sud 4.77x10-6 0
0 Paris, FRANCE University of Geneva 2.74x10-7 6 1 0 7 0
Geneva, SWITZERLAND University of Melbourne Parkville, Victoria AUSTRALIA
+
9.23x10-7
-i 0 -0 27 2 0
University of Milano-Bicocca 1 Milano, ITALY 1.27x10-9 0 0 1 University of Padova Padova, ITALY 6.50x10'-9 2 0 0 2
__ _ _ _ i -.
University of Queensland 1 Brisbane, Queensland AUSTRALIA 2.31JX10-6 0 0 1 University of Rennes 1 1 Rennes, FRANCE 3.67x10 8' 0 0 University of Zurich l.18x10-' 3 0 0 3 Zurich, SWITZERLAND Victoria University of Wellington 1.29x10-8 0 2 0 2 Wellington, NEW ZELAND Totals 1.08x10 5- 29 5 5 39 48 11-12 Annual Report
Rad~iationi Proteciioi 0
0 0
0 0 Figure V.1 0
0 MonitoringStations for the OSU TRIGA Reactor 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0 9 smWAM M&IXUUIALMMIUM3T 0 V wa IAWT 0
0 0
0 11-12 Annual Report I()