Text

Radiation Center and Triga Reactor Annual Report July 1, 2011 - June 30, 2012; Cover Page Through Page 49
	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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Submitted by:

~Steve R. Reese, Director Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 0

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To satisy the requirements of OA.

U.S. Nuclear Regulatory Commission, License No. R-1 06 (Docket No. 50-243), Technical Specification 6.7(e).

B. Battelle Energy Alliance, LLC; Subcontract Award No. 00074510.

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ConltenIts Part I-Overview Executive Summary..........

Introduction...............

Overview of the Radiation Center.

Part Il-People Radiation Center Staff........

Reactor Operations Committee Professional & Research Faculty.

Part Ill-Facilities Research Reactor............

Analytical Equipment.........

Radioisotope Irradiation Sources.

Laboratories & Classrooms.....

Instrument Repair & Calibration..

Library...................

5 Part IV-Reactor Operating Statistics.............................

Experiments Performed.......................

Unplanned Shutdowns.........................

Changes Pursuant to 10 CFR 50.59......................

Surveillance & Maintenance....................

Part V-Radiation Protection Introduction........................................................

Environmental Releases...............................................

Personnel Doses......................................................

Facility Survey Data..............................

Environmental Survey Data.............................................

Radioactive Material Shipments..........................................

References.........................................................

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0 Part VI-Work Sum m ary.................

Teaching..................

Research & Service...........

Part VII-Words Documents Published or Accepted.

Presentations...............

Students..................

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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...............................................

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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.............

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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.................................................................

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Executive Summary The data from this reporting year shows that the use of the Radiation Center and the Oregon State TRIGA reactor (OSTR) has continued to grow in many areas.

The Radiation Center supported 58 different courses this year, mostly in the Department of Nuclear Engineering, Radia-tion Health Physics, Medical Physics, and Radiochemistry.

About 29% of these courses involved the OSTR. The number of OSTR hours used for academic courses and training was 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-five percent of the OSTR research hours were in support of off-campus research projects, reflecting the use of the OSTR 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.

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.

Personnel at the Radiation Center conducted 123 tours of the facility, accommodating 1,392 visitors. The visitors included elementary, middle school, high school, and college students; relatives and friends; faculty; current and prospective clients; national laboratory and industrial scientists and engineers; and state, federal and international officials. The Radiation Center is a significant positive attraction on campus because visitors 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 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-tional clientele.

T1he Radiation Center web site provides an easy way for potential users to evaluate the Center's facilities and capabili-ties as well as to apply for a project and check use charges. The address is: ht-tp://radiationcenter.oregonstare.edu.

Introduction The current annual report of the Oregon State University Radiation Center and TRIGA Reactor follows the usual for-mat 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 0

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Overview 0

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be examined separately, if desired. It should be noted that all annual data given in this report covers the period from July 1, 2011 through June 30, 2012. Cumulative reactor operating data in this report relates only to the LEU fueled core. This covers the period beginning July 1, 2008 to the present date.

For a summary of data on the reactor's two other cores, the reader is referred to previous annual reports.

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 Regula-tory 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 eas-ily find the sections of interest.

Overview of the Radiation Center The Radiation Center is a unique facility which serves the entire OSU campus, all other institutions within the Oregon University System, and many other universities and orga-nizations throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assis-tance to Oregon industry. In addition, the Radiation Center provides permanent office and laboratory space for the OSU Department of Nuclear Engineering and Radiation Health Physics, the OSU Institute of Nuclear Science and Engineer-ing, and for the OSU nuclear chemistry, radiation chemistry, geochemistry and radiochemistry programs. There is no other university facility with the combined capabilities of the OSU Radiation Center in the western half of the United States.

Located in the Radiation Center are many items of special-ized equipment and unique teaching and research facilities.

They include a TRIGA Mark II research nuclear reactor; a 6 0Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associ-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 for repair and calibration of radiation protection instrumen-tation; and facilities for packaging radioactive materials for shipment to national and international destinations.

A major non-nuclear facility housed in the Radiation Center is the one-quarter scale thermal hydraulic advanced plant experimental (APEX) test facility for the Westinghouse AP600 and AP1000 reactor designs. The AP600 and AP1000 are next-generation nuclear reactor designs which incorporate many passive safety features as well as considerably simplified plant systems and equipment. APEX operates at pressures up to 400 psia and temperatures up to 450TF using electrical heaters instead of nuclear fuel. All major components of the AP600 and AP1000 are included in APEX and all systems 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 validity of the test results.

Also housed in the Radiation Center is the Advanced Ther-mal Hydraulics Research Laboratory (ATHRL), which is used for state-of-the-art two-phase flow experiments.

The Radiation Center staff regularly provides direct sup-port 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, radiation effects on biological systems, ra-diation dosimetry, environmental radioactivity, production of short-lived radioisotopes, radiation shielding, nuclear instru-mentation, emergency response, transportation of radioactive materials, instrument calibration, radiation health physics, radioactive waste disposal, and other related areas.

In addition to formal academic and research support, the Center's staff provides a wide variety of other services includ-ing public tours and instructional programs, and professional consultation associated with the feasibility, design, safety, and execution of experiments using radiation and radioactive materials.

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TIhis section 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.

It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed. Summary information on the number of people involved is given in Table VIA, while individual names and projects are listed in Table VI.2.

Radiation Center Staff Steve Reese, Director Dina Pope, Office Manager Shaun Bromagem, Business Manager Kimberly Reese, Receptionist S. Todd Keller, Reactor Administrator Gary Wachs, Reactor Supervisor, Senior Reactor Operator Robert Schickler, Senior Reactor Operator Wade Marcum, Reactor Operator ScottMenn, Senior Health Physicist Jim Darrough, Health Physicist Leak Minc, Neutron Activation Analysis Manager Steve Smith, Scientific Instrument Technician, Senior Reactor Operator Erin Cimbri, Custodian Ryne Burgess, Health Physics Monitor (Student)

Kyle Combs, Health Physics Monitor (Student)

Joey DeShields, Health Physics Monitor (Student)

Reactor Operations Committee Andrew Klein, Chair OSU Nuclear Engineering and Radiation Health Physics Rainier Farmer OSU Radiation Safety Abi Tavakoli Farsoni OSU Nuclear Engineering and Radiation Health Physics Michael Hartman University of Michigan Todd Keller OSU Radiation Center Scott Menn OSU Radiation Center Steve Reese (not voting)

OSU Radiation Center Gary Wachs (not voting)

OSU Radiation Center Bill Warnes OSU Mechanical Engineering 0

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Professional and Research Faculty Binney, Stephen E.

Director Emeritus, Radiation Center, Professor Emeritus, Nuclear Engineering and Radiation Health Physics Daniels, Malcolm Professor Emeritus, Chemistry

Hamby, David Professor, Nuclear Engineering and Radiation Health Physics Hart, Lucas P Faculty Research Associate, Chemistry

Higginbotham, Jack E Director, Oregon Space Grant, Professor, Nuclear Engineering and Radiation Health Physics

Higley, Kathryn A.

Department Head, Nuclear Engineering and Radiation Health Physics Johnson, Arthur G.

Director Emeritus, Radiation Center, Professor Emeritus, Nuclear Engineering and Radiation Health Physics

Keller, S. Todd Reactor Administrator, Radiation Center Klein, Andrew C.

Professor, Nuclear Engineering and Radiation Health Physics

Krane, Kenneth S.

Professor Emeritus, Physics

Loveland, WalterD.

Professor, Chemistry

Menn, Scott A.

Senior Health Physicist, Radiation Center

Minc, Leah Assistant Professor, Anthropology

'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 Reyes, Jr., Josi N.

Professor, Nuclear Engineering and Radiation Health Physics, ATHRL Principal Investigator RingleJohn C.

Professor Emeritus, Nuclear Engineering and Radiation Health Physics Robinson, Alan H.

Department Head, Emeritus, Nuclear Engineering and Radia-tion Health Physics

Schmitt, Roman A.

Professor Emeritus, Chemistry Krystina Tack Medical Physics Program Director

Wachs, Gary Reactor Supervisor, Radiation Center Woods, Brian Associate Professor, Nuclear Engineering and Radiation Health Physics Wu, Qiao Professor, Nuclear Engineer and Radiation Health Physics

OSTR users for research and/or teaching 11-12 Annual Report

Research Reactor The Oregon State University TRIGA Reactor (OSTR) is a water-cooled, swimming pool type research reactor which uses uranium/zirconium hydride fuel elements in a circular grid ar-ray. The reactor core is surrounded by a ring of graphite which serves to reflect neutrons back into the core. The core is situ-ated 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. 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 2500 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 special in-core irradiations, an in-core irradiation tube, and a cadmium-lined in-core irradiation tube for experi-ments requiring a high energy neutron flux.

The pneumatic transfer facility enables samples to be inserted and removed from the core in four to five seconds.

Consequently this facility is normally used for neutron activa-tion 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.

Rotation of the rack ensures that each sample will receive an identical irradiation.

The reactor's thermal column consists of a large stack of graphite blocks which slows down neutrons from the reactor core in order to increase thermal neutron activation of samples.

Over 99% of the neutrons in the thermal column are thermal neutrons. Graphite blocks are removed from the thermal col-umn 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 re-moved. The neutron radiography facility utilized the tangential beam port (beam port #3) to produce ASTM E545 category I radiography capability. The other beam ports are available for a variety of experiments.

If samples to be irradiated require a large neutron fluence, especially from higher energy neutrons, they may be inserted into a dummy fuel element. This device will then be placed into one of the core's inner grid positions which would normally be occupied by a fuel element. Similarly samples can be placed in the in-core irradiation tube (ICIT) which can be inserted in the same core location.

The cadmium-lined in-core irradiation tube (CLICIT) 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 higher energy neutrons only. The cadmium-lined end of this air-filled aluminum irradiation tube is inserted into an inner grid posi-tion of the reactor core which would normally be occupied by a fuel element. It is the same as the ICIT except for the presence of the cadmium lining.

The two main uses of the OSTR are instruction and research.

Instruction Instructional use of the reactor is twofold. First, it is used sig-nificantly for classes in Nuclear Engineering, Radiation Health Physics, and Chemistry at both the graduate and undergradu-ate 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 dem-onstrations and instructional experiments can be performed using the OSTR which cannot be carried out with a commer-cial power reactor. Shorter-term demonstration experiments are also performed for many undergraduate students in Phys-ics, 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 educating reactor operators, operations managers, and 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 pro-vides are more fully described in Part VI of this report.

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During this reporting period the OSTR accommodated a number of different OSU academic classes and other academic programs. In addition, portions of classes from other Oregon universities were also supported by the OSTR.

Research The OSTR is a unique and valuable tool for a wide variety of research applications and serves as an excellent source of neutrons and/or gamma radiation.lThe most commonly used experimental technique requiring reactor use is instrumental neutron activation analysis (INAA).'This is a particularly sen-sitive method of elemental analysis which is described in more detail in Part VI.

The OSTR's irradiation facilities provide a wide range of neu-tron flux levels and neutron flux qualities which are sufficient to meet the needs of most researchers. This is true not only for INAA, but also for other experimental purposes such as the 3 9Ar/ 4 0 Ar ratio and fission track methods of age dating samples.

Analytical Equipment The Radiation Center has a large variety of radiation detec-tion instrumentation. This equipment is upgraded as necessary, especially the gamma ray spectrometers with their associated computers and germanium detectors. Additional equipment for classroom use and an extensive inventory of portable radia-tion detection instrumentation are also available.

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 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 Typically, the irradiator is used by researchers wishing to perform mutation and other biological effects studies; studies in the area of radiation chemistry; dosimeter testing; steril-ization of food materials, soils, sediments, biological speci-men, and other media; gamma radiation damage studies; and other such applications. In addition to the 6 1Co irradiator, the Center is also equipped with a variety of smaller 60Co,

137Cs, 226Ra, plutonium-beryllium, and other isotopic sealed sources of various radioactivity levels which are available for use as irradiation sources.

During this reporting period there was a diverse group of projects using the 60Co irradiator. These projects included the irradiation of a variety of biological materials including dif-ferent types of seeds.

In addition, the irradiator was used for sterilization of several media and the evaluation of the radiation effects on different materials. Table 111.1 provides use data for the Gammacell 220 irradiator.

Laboratories and Classrooms The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate research projects and classes offered by various OSU academ-ic departments or off-campus groups.

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0 Ah I Facilities Instructional facilities available at the Center include a labo-ratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with modular sets of counting equipment which can be configured to accommodate a variety of experiments involving the mea-surement of many types of radiation. T-he Center also has two student computer rooms.

In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equip-ment are regularly used for teaching. In particular, classes are routinely given access to gamma spectrometry equipment located in Center laboratories. A number of classes also regu-larly use the OSTR 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 about 35 and 18 students. In addition, there are two smaller conference rooms and a library suitable for graduate classes and thesis examinations. As 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 Society.

T'his reporting period saw continued high utilization of the Radiation Center's thermal hydraulics laboratory. This labora-tory is being used by Nuclear Engineering faculty members to accommodate a one-quarter scale model of the Palisades Nu-clear Power reactor. The multi-million dollar advanced plant experimental (APEX) facility was fully utilized by the U. S.

Nuclear Regulatory Commission to provide licensing data and to test safety systems in "beyond design basis" accidents.

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 owned by the U.

S. Department of Energy and operated by OSU. In addi-tion, a new building, Advanced Thermal Hydraulics Research Laboratory (ATHRL) was constructed next to the Reactor Building in 1998.

All of the laboratories and classrooms are used extensively during the academic year. A listing of courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table 111.2.

Instrument Repair & Calibration Facility The Radiation Center has a facility for the repair and calibra-tion of essentially all types of radiation monitoring instru-mentation. This includes instruments for the detection and measurement of alpha, beta, gamma, and neutron radiation.

It 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 repair and calibration facility is used regularly throughout the 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 facility 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 instru-ments used on the OSU campus and all other institutions in the Oregon University System, plus instruments from the Oregon Health Division's Radiation Protection Services, the Oregon Department of Energy, the Oregon Public Utili-ties Commission, the Oregon Health Sciences University, the Army Corps of Engineers, and the U. S. Environmental Protection Agency.

Library The Radiation Center has a library containing a 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 vari-ety 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, the Center library maintains a current collection of leading nuclear re-search and regulatory documentation. In addition, the Center has a collection of a number of nuclear power reactor Safety Analysis Reports 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 Radiologi-cal 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, 00 0

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0 the U.S. Department of Transportation, and other appropriate federal agencies, plus regulations of various state regulatory agencies are also available at the Center.

The Radiation Center videotape library has over one hundred tapes on nuclear engineering, radiation protection, and radio-logical emergency response topics. 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 reproduced, recorded, and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center.

The Radiation Center library is used mainly to provide refer-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 and periodically thereafter.

Table 111.1 Gammacell 220 6 0Co Irradiator Use Purpose of Irradiation Samples Sterilization Material Evaluation Botanical Studies wood, honey, pig skin silicon polymers, polymers, chemicals, electronic components wood, wheat pollen, potatoes, pollen, carnation leaves Dose Range (rads) 2.5x10 6 to 2.5x10 6 3.0x105 to 1.0x10 7 5.0x10 2 to 2.5x10 6 Number of Irradiations 13 25 22 UseTime (hours) 1377 662 183 4

Biological Studies mice 5.0x102 to 1.0x103 11 71 0

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Table 111.2 Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Number of Students Course #

CREDIT COURSE TITLE Summer Fall Winter Spring 2011 2011 2012 2012 NE/ RHP 114*

2 Introduction to Nuclear Engineering and Radiation 58 Health Physics------

NE/ RHP 115 2

Introduction to Nuclear Engineering and Radiation 58 Health Physics NE/RHP 116"*

2 Introduction to Nuclear Engineering and Radiation 56 Health Physics 5

NE/ RHP 234 4

Nuclear and Radiation Physics I 66 NE/ RHP 235 4

Nuclear and Radiation Physics II 64 NE/ RHP 236*

4 Nuclear Radiation Detection & Instrumentation 50 NE 311 4

Intro to 'hermal Fluids 6

32 NE 312 NE 319 NE 331 NE 332 NE/RHP 333 NE/RHP/MP 401/501/601 NE/RHP/MP 405/505/605 4

3 4

4 3

1-16 1-16

'Thermodynamics Societal Aspects of Nuclear technology Intro to Fluid Mechanics Heat Transfer Mathematical methods for NE/RHP 5

27 68 27 10 5

5 I Research 24 2

Reading and Conference 35 19 1

57 14 10 31 19 1

91 00 0

S 0

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0 NE/RHP/MP 406/506/606 1-16 Projects NE/RHP/MP 407/507/607 NE/ RHP/MP 410/510/610 1

1-12 Nuclear Engineering Seminar Internship 96 NE/ RHP 415/515 2

Nuclear Rules and Regulations 72 NE 451/551 4

NE 452/552 NE 455/555"*

NE 457/557' 4

3 3

Neutronic Analysis Neutronic Analysis Reactor Operator Training I Neuclear Reactor Lab

_______ 'I 35 31 23 27 NE 467/567 NE 667 NE/RHP 435/535 NE 474/574 NE/RHP 475/575 4

4 Nuclear Reactor Ihermal Hydraulics Nuclear Reactor Thermal Hydraulics 31 3

4 4

External Dosimetry & Radiation Shielding Nuclear System Design I Nuclear System Design II 44 72 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 0

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Course #

NE?RHP 479*

NE/RHP 481*

CREDIT COURSE TITLE 1-4 Individual Design Project 4

Radiation Protection Number of Students Summer Fall Winter Spring 2010 2010

_ 2011 2011 55 NE/RHP 582*

RHP 483/583 RHP 488/588*

NE/RHP 590 NE/RHP/MP 503/603*

NE/ RHP 516*

NE 526 NE/RHP/MP 531 NE/RHP/MP 536*

NE/RHP 537 MP541 NE 550 NE 553*

NE 568 17 39 4

Applied Radiation Safety 4

Radiation Biology 3

Radioecology Internal Dosimetry 36 4

4 3

3 3

3 Thesis Radiochemistry Numerical Methods for Engineering Analysis Nuclear Physics for Engineers and Scientists Advanced Radiation Detection & Measurement SDigital Spectrometer Design

-Diagnostic Imaging Physics Nuclear Medicine Advanced Nuclear Reactor Physics Nuclear Reactor Safety 28 15 14 39 41 i

48 13 21 21 16 Course From Other OSU Departments CH 123*

CH 222*

CH 225H*

CH 462*

GEo 330*

5 5

5 3

3 General Chemistry 1 -.

General Chemistry (Science Majors)

Honors General Chemistry Experimental Chemistry II Laboratory Environme ntal Conservation 545 I

527 40 12 28 ST Special Topics OSTR used occasionally for demonstration and/or experiments OSTR used heavily 11-12 Annual Report 13

Operating Status During the operating period between July 1, 2011 and June 30,2012, the reactor produced 1418 MWH of thermal power during its 1510 critical hours.

Experiments Performed During the current reporting period there were nine approved reactor experiments available for use in reactor-related programs. They are:

A-1 Normal TRIGA Operation (No Sample Irradia-tion).

B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities.

B-11 Irradiation of Materials Involving Specific Quantities of Uranium and Thorium in the Standard OSTR Irradiation Facilities.

Inactive Experiments Presently 33 experiments are in the inactive file. This consists of experiments which have been performed in the past and may be reactivated. Many of these experi-ments are now performed under the more general experi.

ments listed in the previous section. The following list identifies these 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 Ir-radiation Facilities.

B-8 Isotope 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-12 B-23 B-29 B-31 B-33 Exploratory Experiments.

Studies Using TRIGA Thermal Column.

Reactivity Worth of Fuel.

TRIGA Flux Mapping.

Irradiation of Combustible Liquids in Rotating Rack.

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B-34 Irradiation of enriched uranium in the Neutron Radiography Facility.

B-35 Irradiation of enriched uranium in the PGNAA Facility.

Of these available experiments, four were used during the reporting period. Table IV.4 provides information related to the frequency of use and the general purpose of their use.

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0 B-16 Production and Preparation of "FE B-17 Fission Fragment Gamma Ray Angular Cor-relations.

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.

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.

B-30 NAA of Jet, Diesel, and Furnace Fuels.

B-32 Argon Production Facility C-1 PuO 2 Transient Experiment.

Unplanned Shutdowns There were four unplanned reactor shutdowns during the current reporting period. Table IV.5 details these events.

Changes Pursuant tol 0 CFR 50-59 One safety evaluation was performed in support of the reactor this year. It was:

11-01, Changes to Reactor Experiment B-35, Irra-diation of Enriched Uranium in the Prompt Gamma Neutron Activation Analysis Facility Description The use of the PGNAA irradiation facility was expand-ed to include the installation of a pneumatic transfer system. This change takes into account the experience gained concerning assumed limits due to fission gas buildup and venting requirements.

One new safety evaluation screen was performed in support of the reactor this year. It was:

11-05, Installation of a Pneumatic Transfer System in the PGNAA Instrument Description This screen allows the installation of a fast pneumatic transfer system within the main PGNAA irradiation chamber to allow rapid measurement of short lived fis-sion fragments outside the irradiation chamber where background levels are low.

Surveillance and Maintenance Non-Routine Maintenance October 2011 Reconstructed the drain basin for Beam Port #1 to include a catch tray and easy drain system.

November 2011 Replaced failing fission chamber detector due to cable insulation breakdown.

December 2011 Completed painting of reactor pedestal and NRF structure.

Rebuilt the Transient rod drive assembly with new bearings and air seals.

Inspected the Transient rod to determine if pos-sible catastrophic failure was likely to occur due to TRTR report.

February 2012 Replaced rabbit system blower with similar new, and rebuilt the two original motors.

Replaced #5 local ARM detector due to failure.

Rebuilt the cooling tower chemical injection pump.

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

0 0

S 0

0 0

0 Table IV.1 Present OSTR Operating Statistics Operational Data For LEU Core Annual Values Cumulative Values (2011/2012)

MWH of energy produced 1418 4676 MWD of energy produced 59 194.8 Grams "35U used 81 269 Number of fuel elements added to (÷) or removed(-) from 0

90 the core Number of pulses 39 134 Hours reactor critical 1510 5096 Hours at fiull power (1 MW) 1415 4655 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 Table IV.2 OSTR Use Time in Terms of Specific Use Categories Annual Values Cumulative Values OSTR Use Category (hours)

(hours)

Teaching (departmental and others) 28 13,559.5 OSU Research 1,716 15,994 Off Campus research 3,133 37,275 Demonstrations 5

25 Reactor preclude time 789 30,197 Facility time 1

7,197 Total Reactor Use Time 5,672 104,481.5 Table IV.3 OSTR Multiple Use Time Cumulative Values Number of Users Annual Values (hours)

(hours)

Two 187 8,174 Three 452 3,984 Four 452 2,110 Five 180 640 Six 42 140 Seven 14 37 Total Multiple Use Time 1,327 15,085 0

0 0

18 11-12 Annual Report

Reactor 0

0 0

Table IVA4 Use of OSTR Reactor Experiments Experiment Research Teaching Other Total Number A-1 9

0 0

9 B-3 286 20 0

306 B-35 1

0 0

1 B-31 22 0

0 22 Total 318 20 0

338 Table IV.5 Unplanned Reactor Shutdowns and Scrams Number of Type of Event Occurrences Cause of Event Percent Power Channel 2

Air voids in core during power calibration Percent Power Chennel 1

Excessive operator rod withdrawal rate Vacuum inadvertently plugged into inverter circuit Console Voltage Interruption (D-106) 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]

LIMITS ASFOUND DATE NOTECE COMPLETED N&

IEXCEEDED CMLTD INITIALS 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 / 3rd / 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 I I 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 / 4th Quarter of 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT TO DATE REMARKS &

LIMITS AS FOUNDD DAE RM KS

[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 NOT REMARKS SURVEILLANCE & MAINTENANCE TARGET TE DATE

[SHADE INDICATES LICENSE REQUIREMENT]

LIMITS ASDATEE COMPLETED FONTAGT 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 2SAFETY

Ž C

2 SAEYPERIOD SCRAM

>_3 sec 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 I

I TARGET D

DATE REMARKS &

[SHADE INDICATES LICENSE REQUIREMENT]

LIMITS AS FOUND DATE TO BE NOT COMPLETED 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 SAFETY CHANNEL NONl 14 ION CHAMBER RESISTANCE MEASUREMENTS WITH (info Only)

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 N800 V

Al =

AMPS (info Only)

CALCULATION R = -

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 IDATE NOT TREMARKS SURVEILLANCE AND MAINTENANCE AS TARGET DATE 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 Introduction

'The purpose of the radiation protection program is to ensure the safe use of radiation and radioactive material in the Cen-ter's teaching, research, and service activities, and in a similar manner to 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.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, and several part-time Health Physics Monitors (see Part 11).

Assistance is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director.

The data contained in the following sections have been prepared to comply with the current requirements of Nuclear Regulatory Commission (NRC) Facility License No. R-106 (Docket No. 50-243) and the Technical Specifications con-tained in that license. The material has also been prepared in compliance with Oregon Department of Energy Rule No.

345-30-010, which requires an annual report of environmental effects due to research reactor operations.

Within the scope of Oregon State University's radiation pro-tection program, it is standard operating policy to maintain all releases of radioactivity to the unrestricted environment and all exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable" (ALARA).

Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee, as measured at, or prior to, the point of such release or discharge." The liquid and gaseous effluents released, and the solid waste generated and transferred are discussed briefly below. Data regarding these effluents are also summarized in detail in the designated tables.

Liquid Effluents Released Liquid Effluents Oregon State University has implemented a policy to re-duce the volume of radioactive liquid effluents to an absolute minimum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water. Waste water from Radiation Center laboratories and the OSTR is collected at a holdup tank prior to release to the sanitary sewer.

Liquid effluent are analyzed for radioactivity content at the time it is released to the collection point. For this reporting period, the Radiation Center and reactor made three liquid ef-fluent releases to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to this release are contained in Table V.2.

Liquid Waste Generated and Transferred Liquid waste generated from glassware and laboratory experi-ments is transferred by the campus Radiation Safety Office 0

0 0

28 11-12 Annual Report I

RadIialtion~ I01e4IcciOm 0

0 0

to its waste processing facility. The annual summary of liquid waste generated and transferred is contained in Table V.3.

Airborne Effluents Released Airborne effluents are discussed in terms of the gaseous com-ponent and the particulate component.

Gaseous Effluents Gaseous effluents from the reactor facility are monitored by the reactor stack effluent monitor. Monitoring is continuous, i.e., prior to, during, and after reactor operations. It is normal for the reactor facility stack effluent monitor to begin opera-tion as one of the first systems in the morning and to cease operation as one of the last systems at the end of the day. All gaseous effluent data for this reporting period are summarized in Table V.4.

Particulate effluents from the reactor facility are also moni-tored by the reactor facility stack effluent monitor.

Particulate Effluents Evaluation of the detectable particulate radioactivity in the stack effluent confirmed its origin as naturally-occurring radon daughter products, within a range of approximately 3x10 11 1iCi/ml to 1 x 10' pCi/ml. This particulate radioactivity is predominantly 214Pb and 214Bi, which is not associated with reactor operations.

There was no release of particulate effluents with a half life greater than eight days and therefore the reporting of the average concentration of radioactive particulates with half lives greater than eight days is not applicable.

Solid Waste Released Data for the radioactive material in the solid waste generated and transferred during this reporting period are summarized in Table V.5 for both the reactor facility and the Radiation Center. Solid radioactive waste is routinely transferred to OSU Radiation Safety. Until this waste is disposed of by the Radiation Safety Office, it is held along with other campus radioactive waste on the University's State of Oregon radioac-tive materials license.

Solid radioactive waste is disposed of by OSU Radiation Safety by transfer to the University's radioactive waste disposal vendor.

Personnel Dose The OSTR annual reporting requirements specify that the licensee shall present a summary of the radiation exposure re-ceived by facility personnel and visitors. The summary includes all Radiation Center personnel who may have received expo-sure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, facilities services maintenance personnel, students in laboratory classes, police and security personnel, and visitors.

Facility operating personnel include the reactor operations and health physics staff. The dosimeters used to monitor these in-dividuals include quarterly TLD badges, quarterly track-etch/

albedo neutron dosimeters, monthly TLD (finger) extremity dosimeters, pocket ion chambers, electronic dosimetry.

Key facility research personnel consist of Radiation Center staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other research facilities present at the Center. The individual dosim-etry requirements for these personnel will vary with the type of research being conducted, but will generally include a quarterly TLD film badge and TLD (finger) extremity dosimeters. If the possibility of neutron exposure exists, researchers are also monitored with a track-etch/ albedo neutron dosimeter.

Facilities Services maintenance personnel are normally is-sued a gamma sensitive electronic dosimeter as their basic monitoring device. A few Facilities Services personnel who routinely perform maintenance on mechanical or refrigeration equipment are issued a quarterly XMfl(y) TLD badge and other dosimeters as appropriate for the work being performed.

Students attending laboratory classes are issued quarterly Xg(,y) TLD badges, TLD (finger) extremity dosimeters, and track-etch/albedo or other neutron dosimeters, as appropriate.

Students or small groups of students who attend a one-time lab demonstration and do not handle radioactive materials are usually issued a gamma sensitive electronic dosimeter. These results are not included with the laboratory class students.

OSU police and security personnel are issued a quarterly Xf9(y) TLD badge to be used during their patrols of the Ra-diation Center and reactor facility.

Visitors, depending on the locations visited, may be issued a gamma sensitive electronic dosimeters. OSU Radiation Center policy does not normally allow people in the visitor category to 29 11-12 Annual Report

0 Radiation Protection become actively involved in the use or handling of radioactive materials.

An annual summary of the radiation doses received by each of the above six groups is shown in Table V.6. There were no personnel radiation exposures in excess of the limits in 10 CFR 20 or State of Oregon regulations during the reporting period.

Facility Survey Data The OSTR Technical Specifications require an annual summary of the radiation levels and levels of contamination observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program encompasses the Radiation Center as well as the OSTR, and therefore monitoring results for both facilities are reported.

Area Radiation Dosimeters Area monitoring dosimeters capable of integrating the radia-tion dose are located at strategic positions throughout the reactor facility and Radiation Center. All of these dosimeters contain at least a standard personnel-type beta-gamma film or TLD pack. In addition, for key locations in the reactor fa-cility and for certain Radiation Center laboratories a CR-39 plastic track-etch neutron detector has also been included in the monitoring package.

The total dose equivalent recorded on the various reactor facility dosimeters is listed in Table V.7 and the total dose equivalent recorded on the Radiation Center area dosimeters is listed in Table V.8. Generally, the characters following the Monitor Radiation Center (MRC) designator show the room number or location.

Routine Radiation and Contamination Surveys The Center's program for routine radiation and contamina-tion surveys consists of daily, weekly, and monthly measure-ments throughout the TRIGA reactor facility and Radiation Center. The frequency of these surveys is based on the nature of the radiation work being carried out at a particular loca-tion or on other factors which indicate that surveillance over a specific area at a defined frequency is desirable.

The primary purpose of the routine radiation and con-tamination survey program is to assure regularly scheduled surveillance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and characteristic data on the status of radiological condi-tions. A second objective of the program is to assure frequent on-the-spot personal observations (along with recorded data),

which will provide advance warning of needed corrections and thereby help to ensure the safe use and handling of radiation sources and radioactive materials. A third objective, which is really derived from successful execution of the first two objec-tives, is to gather and document information which will help to ensure that all phases of the operational and radiation protec-tion programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA).

The annual summary of radiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.9.

Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual summary of environmental surveys performed outside the facility."

Gamma Radiation Monitoring On-site Monitoring Monitors used in the on-site gamma environmental radiation monitoring program at the Radiation Center consist of the reactor facility stack effluent monitor described in Section V and nine environmental monitoring stations.

During this reporting period, each fence environmental sta-tion utilized an LiF TLD monitoring packet supplied and pro-cessed by Mirion Technologies, Inc., Irvine, California. Each GDS packet contained three LiF TLDs and was exchanged quarterly for a total of 108 samples during the reporting period (9 stations x 3 TLDs per station x 4 quarters). The total num-ber of GDS TLD samples for the reporting period was 108. A summary of the GDS TLD data is also shown in Table V.10.

From Table V.10 it is concluded that the doses recorded by the dosimeters on the TRIGA facility fence can be attributed to natural back-ground radiation, which is about 110 mrem per year for Oregon (Refs. 1, 2).

Off-site Monitoring The off-site gamma environmental radiation monitoring program consists of twenty monitoring stations surrounding the Radiation Center (see Figure V.1) and six stations located within a 5 mile radius of the Radiation Center.

00 0

0 0

0 30 11-12 Annual Report

Radiation Protection 0

0 0

0 S

Each monitoring station is located about four feet above the ground (MRCTE 21 and MRCTE 22 are mounted on the roof of the EPA Laboratory and National Forage Seed Laboratory, respectively). These monitors are exchanged and processed quarterly, and the total number of TLD samples during the current one-year reporting period was 240 (20 stations x 3 chips per station per quarter x 4 quarters per year). The total number of GDS TLD samples for the report-ing period was 240. A summary of GDS TLD data for the off-site monitoring stations is given in Table V.11.

After a review of the data in Table V.11, it is concluded that, like the dosimeters on the TRIGA facility fence, all of the doses recorded by the off-site dosimeters can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs. 1, 2).

the LLD were averaged in at the corresponding LLD con-centration. Table V.13 gives the concentration and the range of values for each sample category for the current reporting period.

As used in this report, the LLD has been defined as the amount or concentration of radioactive material (in terms of pCi per unit volume or unit mass) in a representative sample, which has a 95% probability of being detected.

Identification of specific radionuclides is not routinely carried out as part of this monitoring program, but would be conducted if unusual radioactivity levels above natural background were detected. However, from Table V.12 it can be seen that the levels of radioactivity detected were consis-tent with naturally occurring radioactivity and comparable to values reported in previous years.

Soil, Water, and Vegetation Surveys Radioactive Materials Shipments The soil, water, and vegetation monitoring program consists of the collection and analysis of a limited number of samples in each category on a annual basis. The program monitors highly unlikely radioactive material releases from either the TRIGA reactor facility or the OSU Radiation Center, and also helps indicate the general trend of the radioactivity concentration in each of the various substances sampled. See Figure V.1 for the locations of the sampling stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 foot radius of the reactor facility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the posi-tions indicated in Figure V.1.

There are a total of 22 sampling locations: four soil locations, four water locations (when water is available), and fourteen vegetation locations.

The annual concentration of total net beta radioactivity (mi-nus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is 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 A summary of the radioactive material shipments originat-ing from the TRIGA reactor facility, NRC license R-106, is shown in Table V.14. A similar summary for shipments originating from the Radiation Center's State of Oregon radioactive materials license ORE 90005 is shown in Table V.15. A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license 10 CFR 110.23 is shown in Table V.16.

References

1. U. S. Environmental Protection Agency, "Estimates of Ionizing Radiation Doses in the United States, 1960-2000," ORP/CSD 72-1, Office of Radiation Programs, Rockville, Maryland (1972).

2.

U. S. Environmental Protection Agency, "Radio-logical Quality of the Environment in the United States, 1977," EPA 520/1-77-009, Office of Radia-tion Programs; Washington, D.C. 20460 (1977).

Radiation Protection Table V.1 Radiation Protection Program Requirements and Frequencies Frequency Daily/Weekly/Monthly Radiation Protection Requirement Perform Routing area radiation/contamination monitoring Collect and analyze TRIGA primary, secondary, and make-up water.

Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports.

Inspect laboratories.

Calculate previous month's gaseous effluent discharge.

Monthly As Required Quarterly Process and record solid waste and liquid effluent discharges.

Prepare and record radioactive material shipments.

Survey and record incoming radioactive materials receipts.

Perform and record special radiation surveys.

Perform thyroid and urinalysis bioassays.

Conduct orientations and training.

Issue radiation work permits and provide health physics coverage for maintenance operations.

Prepare, exchange and process environmental TLD packs.

Conduct orientations for classes using radioactive materials.

Collect and analyze samples from reactor stack effluent line.

Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports.

Leak test and inventory sealed sources.

Conduct floor survey of corridors and reactor bay.

Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.

Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, and air samplers.

Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA filters as necessary.

Inventory and inspect Radiation Center emergency equipment.

Conduct facility radiation survey of the 6°Co irradiators.

Conduct personnel dosimeter training.

Update decommissioning logbook.

Collect and process environmental soil, water, and vegetation samples.

0 0

Semi-Annual Annual I

11-12 Annual Report

Table V.2 I.

Monthly Summary of Liquid Effluent Release to the Sanitary SewerO)

Date of Discharge (Month and Year)

August 2011 October 2011 January 2012 March 2012 Total Quantity of Radioactivity Released (Curies) 7.2x10-2 6.7x 10-2 6.0x10-3 5.2x10-2 Detectable Radionuclide in the Waste Specific Activity For Each Detectable Radionuclide in the Waste, Where The Release Concentration Was>1 x 10-7 (1iCi ml-')

1.4x10-4 2.5x10-4 2.6x10 5-2.8x10-5 Total Quantity of Each Detectable Radionuclide Released in the Waste (Curies) 7.2x10-2 6.7x1 0-2 6.Ox10-3 5.2x10-2 Average Concentration Of Released Radioactive Material at the Point of Release

( pCi m1-1)

Percent of Applicable Monthly Average Concentration for Released Radioactive Material

(%)(2)

Total Volume of Liquid Effluent Released Including Diluent (gal) 138,430 71,857 62,082 494,016 H-3 H-3 H-3 H-3 1.4X10-4 2.5x 10-4 2.5x 0-5 1.37 2.45 0.26 0.28 April 2012 June 2012 5.2x10-2 0.4 H-3 H-3, Cr-51, Co-58, Co-60 H-3, Cr-51, Co-58, Co-60 9.6x10-5 H-3, 6.0x10-4 1.1x10-3 5.2x10-2 H-3,0.4 Cr-51, 4.3x10-6 Co-58, 1.1x10-61 lCo-60, 1.0x10-H-3, 6.5x10' 2.8xl10' 9.6x105' 6.OX10-4 1.14X10-3 0.96 H-3, 6.0 Cr-51, 0.0001 Co-58, 0.0008 Co-60, 0.0005 11.32 Annual Total for Radiation Center 6.5x101 142,392 177,264 1,086,041 (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

Table V.3 Annual Summary of Liquid Waste Generated and Transferred Volume of Liquid Origin of Liquid Waste Packaged(1)

Waste (gallons)

Detectable Radionuclides in the Waste a-24, Cr-51, Mn-56, o-60, Rb-89, Sb-122, b-124, Cs-137, H-3,

-11Om, Sc-46, Eu152 TRIGA Reactor Facility 15 N

C*

Si Ag Total Quantity of Radioactivity in the Waste (Curies) 3.44x10-3 5.96x10-5 3.50x10-3 Dates of Waste Pickup for Transfer to the Waste Processing Facility 10/21/11 10/21/11 2/22/12 6/10/12 Radiation Center Laboratories 20.25 35.25 Pu-239, C1-36, U-238, C-14, H-3 I

TOTAL See above 0

0 0

0 S

S S

0 0

0 (1) OSTR and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging.

34 11-12 Annual Report

H tId;n1;4hr1 Iprtjti-tidli 0

Table V.4

-Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis 0

Estimated Fraction of the Technical Total Total Atmospheric Diluted Specification Total Totl ISConcetrationoo 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 3.63x105-0.91 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

('10-'11) 6.50 6.50 4.4Nx10-8 1 2

2)

(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 11-12 Annual Report

Radiation Protection Table V.5 Annual Summary of Solid Waste Generated and Transferred Volume of Detectable Total Quantity Dates of Waste Pickup Origin of Solid Waste Radionuclides of Radioactivity for Transfer to the OSU Solid Waste Packaged(,)

in the Waste in Solid Waste Waste Processing (Cubic Feet)

(Curies)

Facility TRIGA Reactor Facility Radiation Center Laboratories TOTAL 30 63 93 Mn-54, Co-58, Co-60, Zn-65, As-74, Cs-134, Eu-152, Sc-46, Fe-59, Sb-124, Se-75, Hf-181, Na-24, Hg-203, Sb-125, Cr-51, Pa-233 C1-36, U-238, Np-237, Pu-242, Eu-152, Eu-154, Pu-239, Am-241, U-235, Uh-232, Tc-99, Mo-99, Co-60, Ir-192, H-3, C-14, Sr-90, Cs-137, Am-243, Pu-242, Cd-109, Hg-203, Na-22, Sn-113, Po-210, Sr-85, Nb-95, Ce-139, Y-88, Cr-51,Te-123m, Cs-134 1.52x10-4 10/21/11 2/22/12 6/10/12 10/21/11 2/22/12 6/10/12 2.35x10-4 0

0 0

See Above 3.88x10-4 (1) OSTR and Radiation Center laboratory waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final packaging.

36 11-12 Annual Report

Radiation Pr,)[,,.ti0.

0 0

0 Table V.6 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest I Dose"'

Dos Whole Body Extremities Whole Body (nrem)

(mrem)

Personnel Group Facility Operating Personnel Key Facility Research Personnel Facilities Services Maintenance Personnel Laboratory Class Students Campus Police and Security Personnel ndividual e{l)

Extremities (mrem) 1269 102.43 2.38

<1 2.63 2.47

<1 339.57 16.17 N/A Total Person-mrem For the Group"(

187 31 0.5 Whole Body (mrem) 717 Extremities (mrem) 2377

-I 139 N/A 208 N/A N/A 31 0.8 1117 75 96.6 194 N/A 573 N/A N/A 5.37 403 N/A N/A 37 Visitors 6.3 (1)

"N/A"indicates that there was no extremity monitoring conducted or required for the group.

11-12 Annual Renort 3?

1 A n u a

Radiation Protection Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Table V.7 Monitor I.D.

MRCTNE TRIGA Reactor Facility Location (See Figure V.1)

Total Recorded X9(y)

(mrem) 274 146 905 Dose Equivalent(1)(2)

D104:

North Badge East Wall MRCTSE Neutron (mrem)

ND ND ND ND MRCTSW D104:

South Badge East Wall D104:

South Badge West Wall D104:

North Badge West Wall MRCTNW 199 MRCTWN MRCTEN MRCTES MRCTWS MRCTTOP F-F-

)104:

West Badge North Wall

)104:

East Badge North Wall

)104:

East Badge South Wall

)104:

West Badge South Wall

)104:

Reactor Top Badge

)104A:

South Badge HX Room

)104A: West Badge HX Room

)302:

Reactor Control Room

)302A: Reactor Supervisor's Office

)104:

Beam Port Number 1 381 346 1572 546 710 878 657 447 ND ND ND ND ND ND ND ND N/A ND 0

0 0

MRCTHXS i--.

MRCTHXW MRCD-302 MRCD-302A MRCBP1 F-149 319 MRCBP2 D104: Beam Port Number 2 256 i

MRCBP3 MRCBP4 D104: Beam Port Number 3 D104: Beam Port Number 4 929 854 ND ND 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.

3)8(

11-12 Annual Report I

Radiation Protection 0

0 0

0 Table V.8 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Radiation Center Do, Facilitv Location

)tal Recorded se Equivalent(')

Monitor I.D.

MRCA100 MRCBRF MRCA120 MRCA120A MRCA126 MRCCO-60 MRCA130 MRCA132 MRCA138 MRCA146 MRCB100 MRCB114 MRCB119-1 MRCB119-2 MRCB119A MRCB120 MRCB122-2 MRCB122-3 MRCB124-1 MRCB124-2 MRCB124-6 MRCB128 MRCB136 MRCC100 (See Figure V.1)

A100:

A102H:

A120:

A120A:

A126:

A128:

A130:

A132:

A138:

A146:

B100:

B114:

B119:

B119A:

B120:

B122:

B124:

B128:

B136 C100:

Receptionist's Office Front Personnel Dosimetry Storage Rack Stock Room NAA Temporary Storage Radioisotope Research Lab 60CO Irradiator Room Shielded Exposure Room TLD Equipment Room Health Physics Laboratory Gamma Analyzer Room (Storage Cave)

Gamma Analyzer Room (Storage Cave)

Lab (226Ra Storage Facility)

Source Storage Room Source Storage Room Sealed Source Storage Room Instrument Calibration Facility Radioisotope Hood Radioisotope Research Laboratory Radioisotope Research Lab (Hood)

Radioisotope Research Laboratory Radioisotope Research Laboratory Instrument Repair Shop Gamma Analyzer Room Radiation Center Director's Office X9(7y) 1 Neutron (mrem)

(mrem) 31 N/A 63

ý

_/

......... I-

96 0

236 625 146 73 51 112 73 1612 218 377 2906 78 349 76 72 92 64 52 27 63 N/A N/A N/A N/A N/A N/A N/A N/A N/A ND N/A N/A 1303 N/A N/A N/A N/A N/A N/A N/A N/A 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)

Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Monitor Radiation Center Dose Equivalentý1)

I.D.

Facility Location (See Figure V.1)

Xtg(y)

Neutron (mrem)

(mrem)

MRCC106A C106A: Office 62 N/A MRCC106B C106B: Custodian Supply Storage 45 N/A MRCC106-H C106H: East Loading Dock 42 N/A MRCC118 C118:

Radiochemistry Laboratory 35 N/A MRCC120 C120:

Student Counting Laboratory 26 N/A MRCF100 F100:

APEX Facility 11 N/A MRCF102 F102:

APEX Control Room 21 N/A MRCB125N B125:

Gamma Analyzer Room (Storage Cave) 37 N/A MRCN125S B125:

Gamma Analyzer Room 74 N/A MRCC124 C124:

Classroom 67 N/A MRCC130 C130:

Radioisotope Laboratory (Hood) 64 N/A MRCD100 D100:

Reactor Support Laboratory 90 ND MRCD102 D102:

Pneumatic Transfer Terminal Lab' 287 ND 0

0 0

0 MRCD102-H MRCD106-H MRCD200 MRCD202 MRCBRR MRCD204 MRCATHRL MRCD300 D102H:

D106H:

1st Floor Corridor at D102 1st Floor Corridor at D106 113 351 190 ND N/A ND D200:

Reactor Administrator's Office D202:

Senior Health Physicist's Office D200H: Rear Personnel Dosimetry Storage Rack D204:

Health Physicist Office F104:

ATHRL 283 78 264 42 192 ND N/A ND N/A ND D300:

3rd Floor Conference Room (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 S

Table V.9 Annual Summary of Radiation and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys Accessible Location (See Figure V.1)

TRIGA Reactor Facility:

Reactor Top (D104)

Reactor 2nd Deck Area (D104)

Reactor Bay SW (D104)

Reactor Bay NW (D104)

Reactor Bay NE (D104)

Reactor Bay SE (D104)

Class Experiments (D104, D302)

Demineralizer Tank & Make Up Water System (D104A)

Particulate Filter--Outside Shielding (D104A)

Whole Body Radiation Levels (mrem/hr)

Average 1

1.64 6.56

< 1

<1

<1 Maximum 90 46 50 9

18 7

<1 C

Average

<500

<500 ontamination Levels(1 )

(dpm/cm 2)

Maximum 25,870 926

<500 3,269 2,608 5,179

<500 1,300 3,036 28

<1 6

Radiation Center:

NAA Counting Rooms (A146, B100)

< 1 2.7 Health Physics Laboratory (A138)

<1 1.7 6°Co Irradiator Room and Calibration Rooms

<1 31 (A128, B120, A130)

Radiation Research Labs (A126, A136) 12 (B108, B114, B122, B124, C126, C130, C132A)

Radioactive Source Storage (B119, B119A,

<1 25 A120A, A132A)

Student Chemistry Laboratory (C118)

<1

<1 Student Counting Laboratory (C120)

<1

<1 Operations Counting Room (B136, B125)

<1 1.2 Pneumatic Transfer Laboratory (D102)

< 1 10 RX support Room (D100)

<1

< 1 (1)

<500 dpm/100 cm2 = Less than the lower limit of detection for the portable survey instrument used.

<500

<500 652

<500

<500 11,800

<500 11-12 Annual Report

,II

Radiation Protection Table V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence Fence Environmental Monitoring Station (See Figure V.1)

Total Recorded Dose Equivalent (Including Background)

Based on Mirion TLDsO.2)

(mrem)

MRCFE-1 MRCFE-2 MRCFE-3 MRCFE-4 MRCFE-5 MRCFE-6 MRCFE-7 MRCFE-8 MRCFE-9 87+ 4 83+/- 5 77+/- 7 85+/- 4 91+/- 8 83+/- 6 84+/- 5 80 +/- 5 80 +/- 4 0

0 0

0 00 0

0 0

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.

'12 I

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 Table V.12 Sample Location (See Fig. V.1)

Annual Average Concentration of the Total Net Beta Radioactivity (minus 3H) for Environmental Soil, Water, and Vegetation Samples Sample Annual Average Concentration Type Of the Total Net Beta (Minus 3H)

Re Radioactivity'"

Water 7.29x10-6(2)

Water 7.29x10-6(2) 1-W 4-W 11-W porting Units Ii ml1 Ii m1-1

ýi m1-1 Ii m1-1 1 of dry soil 19-RW 3-S i

Water Water Soil Soil i

5-S 7.29x106 (2 )

7.29x106 12 1 2.36x10-5 12) - 525x10-6 1.22x10-5 +/-, 4.07x10-6 1.66x10-5 (2) - 4.63x10-6 8.37x10-6 12) 4.20x10-4 +/- 4.61X10-5 PCi g-20-S 21-S Soil pCi g-1 of dry soil pCi g-1 of dry soil PCi g-1 of dry soil pCi g-1 of dry ash Soil 2-G Grass 0

0 0

0 6-G Grass 2.29x10-4 2.42x10- 5 PCi g-1 of dry ash 7-G Grass 2.93x10- 4 _ 3.34x10-5 PCi g-1 of dry ash 8-G Grass 3.46x10- 4 _ 2.92x10- 5 PCi g-1 of dry ash 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 18-G Grass 2.18x10-4 + 2.60x10-5 22-G Grass 1.10x10-4+ 2.70x10-5 (1) +/- values represent the standard deviation of the value at the 95% confidence level.

(2) Less than lower limit of detection value shown.

pCi g-1 of dry ash pCi g-1 of dry ash pCi g-1 of dry ash

/14 I

11-12 Annual Report

7 IRadiation Protectioni S

0 0

0 S

0 Table V.13 Beta-Gamma Concentration and Range of LLD Values for Soil, Water, and Vegetation Samples Sample Type Soil Water Vegetation Average Value 9.17x10-6 7.29x10- 6 (1 4.03x10-5 Range of Values 8.37x10- 6 to 1.03x10-5 7.29x10-6 2.37x10-5 to 7.22x10-5 Reporting Units PCi g-1 of dry soil laCi m1-1 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

_ F Number of Shipments Shipped To Berkeley Geochronology Center Berkeley, CA USA C.O.R.D. University of Wisconsin-Madison Madison, WI USA Cal State Fullerton Fullerton, CA USA California Institue of Technology Pasadena, CA USA Lehigh University Bethlehem, PA USA Materion Coperation Elmore, OH USA Materion Natural Resources Delta, UT USA Occidental College Los Angeles, CA USA Oregon State University Corvallis, OR USA Plattsburgh State University Plattsburgh, NY USA Stanford University Stanford, CA, USA Syracuse University Syracuse, NY USA

'Total Activity Exempt 1.58x10-6 5

1 7xo-5.17x106-0 6.33xl1~

5.84xl 0-1.20x10-'

3.73x 0-2 0

2 Limited Quantity 2

0 0

0 Yellow II 0

0 0

1 0

0 Yellow III 0

16 0

0 0

4 Total 0

0 1.08x10-1 0

3.87x10 9 1 1 5.60x106 1

1.17x10 8-2 1.01x108 1

0 2

I 0

0 1~

Union College Schenectady, NY USA University of Arizona Tucson, AZ USA University of California at Berkeley Berkeley, CA USA University of California at Santa Barbara Santa Barbara, CA USA University of Florida Gainesville, FL USA University of Michigan Ann Arbor, MI USA University of Minnesota Minneapolis, MN USA University of Wisconsin-Madison Madison, WI USA 4.81x10 7' 8.48x10-'

8.16x 10-'

~~~1~~

3 2

7 0

3.49x1 0-7 9.10x10-8 4.41x1 0-5.00x10-1 1.14xl0-5 1

0 1

0 0

0 1

0 0

0 4

0 0

2 2

0 0

22 0

0 0

0 7

5 16 1

1 2

4 22 1

S 3

5 2

1 4

2 5

S 2

5 2

3 5

1 1

30 72 0

Report 3

1 1

0 31 0

0 0

0 3

0 11 26 Totals

_7 1.4x1O'1 40 I

11-12 Annual

Radiatiori Protection 0

0 0

0 Table V.15 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Shipped To Argonne National Lab Argonne, IL USA Lawrence Berkeley National Laboratory Berkeley, CA USA Los Alamos National Lab Los Alamos, NM USA Pacific Northwest National Lab Richland, WA USA Total Activity (TBq)

Exempt Number of Shipments Limited W

quWhite I

Total 1

8.01X101 2 2.05x 0-9 6.14x1O-'

6.5Ox1O-"

1 1

0 0

1 5

1 3

3 11 0

3 0

3 1

Totals 6.14x10-6 8

14 11-12 Annual Report 1 7

Radiation Protectioi Table V.1 6 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 Number of Shipments Shipped To Glasgow University Glasgow SCOTLAND Institute of Geology, China Earthquake Admin Beijing PR CHINA Lanzhou University Lanzhou, Gansu CHINA Lund University Lund, SWEDEN Polish Academy of Sciences Krakow, POLAND QUAD-Lab, Roskilde University Roskilde, DENMARK Scottish Universities Research & Reactor Centre East Kilbride, SCOTLAND Universitat Gottingen Gottingen, GERMANY Universitat Potsdam Postdam, GERMANY Universite Paris-Sud Paris, FRANCE University of Geneva Geneva, SWITZERLAND Total Activity (TBq) 2.49x10-8 3.12x10-9 1.04x10-8 3.17x10-7 2.92x108-2.57x1O-'

2.13x10-6 2.46x108-Exempt 1

1 1

Limited Quantity 0

0 0

Yellow II Total 0

1 0

1 3

0 0

3 I

I-

-~

2 2

0 0

2 0

0 2

T 5.37x10-9 4.77x10-6 2.74x10-7

+

-i University of Melbourne Parkville, Victoria AUSTRALIA 9.23x10-7 1

2 1

0 6

0 1

2 0

1 3

2 0

0 0

0 1

0

-0 27 7

2 1

2 University of Milano-Bicocca Milano, ITALY University of Padova Padova, ITALY University of Queensland Brisbane, Queensland AUSTRALIA University of Rennes Rennes, FRANCE University of Zurich Zurich, SWITZERLAND Victoria University of Wellington Wellington, NEW ZELAND 1.27x10-9 6.50x10'-9 2.31JX10-6 3.67x108' l.18x10-'

1.29x10-8 0

0 0

0 i

0 0

1 0

0 0

1 1

3 2

Totals 1.08x105-29 5

5 39 48 11-12 Annual Report

Rad~iationi Proteciioi 0

0 0

Figure V.1 MonitoringStations for the OSU TRIGA Reactor 9 smWAM V wa IAWT M&IXUUIALMMIUM3T 11-12 Annual Report I()

ML12306A510

Text

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