ML15289A436

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Oregon State University - Annual Report for the Period July 1, 2014 Through June 30, 2015, Part 1 of 2
ML15289A436
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Issue date: 10/09/2015
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OSo OreonStat Radiation Center Oregon State University, 100 Radiation Center, Corvallis, Oregon 97331-5903 T 541-737-2341 I F 541-737-0480 I http:llne.oregonstate.edulfacilitieslradiationcenter October 9, 2015 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Oregon State University TRIGA Reactor (OSTR)

Docket No. 50-243, License No. R-106 In accordance with section 6.7.1 of the OSTR Technical Specifications, we are hereby submitting the Oregon State University Radiation Center and OSTR Annual Report for the period July 1, 2014 through June 30, 2015.

The Annual Report continues the pattern established over many years by including information about the entire Radiation Center rather than concentrating primarily on the reactor. Because this report addresses a number of different interests, it is rather lengthy, but we have incorporated a short executive summary which highlights the Center's activities and accomplishments over the past year.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: /ic'// *

Sincerely, Director Cc: Michael Balazik, USNRC Dr. Cynthia Sagers, OSU Craig Bassett, USNRC Dr. Rich Holdren, OSU Ken Niles, ODOE Dr. Andy Klein, OSU AcgcJ

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3m Executive Summary Introduction The data from this reporting year shows that the use of the The current annual report of the Oregon State University Radiation Center and the Oregon State TRIGA reactor Radiation Center and TRIGA Reactor follows the usual for-(OSTR) has continued to grow in many areas. mat by including information relating to the entire Radiation Center rather than just the reactor. However, the information The Radiation Center supported 69 different courses this year, is still presented in such a manner that data on the reactor may mostly in the Department of Nuclear Engineering and Radia-be examined separately, if desired. It should be noted that all tion Health Physics. About 30% of these courses involved the annual data given in this report covers the period from July 1, OSTR. T-he number of OSTR hours used for academic courses 2014 through June 30, 2015. Cumulative reactor operating data and training was 43, while 2,541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br /> were used for research in this report relates only to the LEU fueled core. This covers projects. Sixty-three percent (63%) of the OSTR research the period beginning July 1, 2008 to the present date. For a hours were in support of off-campus research projects, reflect-summary of data on the reactor's two other cores, the reader is ing the use of the OSTR nationally and internationally. Radia-referred to previous annual reports.

tion Center users published or submitted 46 articles this year, and made 64 presentations on work that involved the OSTR In addition to providing general information about the activi-or Radiation Center. T-he number of samples irradiated in the ties of the Radiation Center, this report is designed to meet reactor during this reporting period was 992. Funded OSTR the reporting requirements of the U. S. Nuclear Regulatory use hours comprised 96% of the research use. Commission, the U. S. Department of Energy, and the Oregon Department of Energy. Because of this, the report is divided Personnel at the Radiation Center conducted 99 tours of the into several distinct parts so that the reader may easily find the facility, accommodating 1,555 visitors. T'he visitors included sections of interest.

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 Overview of the Radiation Center is a significant positive attraction on campus because visitors The Radiation Center is a unique facility which serves the leave with a good impression of the facility and of Oregon entire OSU campus, all other institutions within the Oregon State University. University System, and many other universities and organiza-The Radiation Center projects database continues to provide tions throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, a usefuil way of tracking the many different aspects of work at the facility. T-he number of projects supported this year was particularly agencies dealing with law enforcement, energy, 123. Reactor related projects comprised 74% of all projects. The health, and environmental quality, and renders assistance to total research dollars in some way supported by the Radiation Oregon industry. In addition, the Radiation Center provides Center, as reported by our researchers, was $11 million. The ac- permanent office and laboratory space for the OSU Depart-tual total is likely considerably higher. T'his year the Radiation ment of Nuclear Engineering and Radiation Health Physics, Center provided service to 50 different organizations/institu- the OSU Institute of Nuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, geochem-tions, 40% of which were from other states and 44% of which were from outside the U. S. and Canada. So while the Center's istry and radiochemistry programs. There is no other university primary mission is local, it is also a facility with a national and facility with the combined capabilities of the OSU Radiation international clientele. Center in the western half of the United States.

The Radiation Center web site provides an easy way for Located in the Radiation Center are many items of special-potential users to evaluate the Center's facilities and capabili- ized equipment and unique teaching and research facilities.

ties as well as to apply for a project and check use charges. The address is: http://radiationcenter.oregonstate.edu.d 14-15 Annual Report

They 6

include a TRIGA Mark II research nuclear reactor; a Over 7 international organizations are involved in this stan-

°Co gamma irradiator; a large number of state-of-the art dard problem at OSU.

computer-based gamma radiation spectrometers and associ-ated germanium detectors; and a variety of instruments for T'he Advanced Nuclear Systems Engineering Laboratory radiation measurements and monitoring. Specialized facilities (ANSEL) is the home to two major thermal-hydraulic test fa-for radiation work include teaching and research laboratories cilities-the High Temperature Test Facility (HTTF) and the with instrumentation and related equipment for performing Hydro-mechanical Fuel Test Facility (HMFTF). The HTTF neutron activation analysis and radiotracer studies; laborato- is a 1/4 scale model of the Modular High Temperature Gas ries for plant experiments involving radioactivity; a facility Reactor. The vessel has a ceramic lined upper head and for repair and calibration of radiation protection instrumen- shroud capable of operation at 850oC (well mixed helium).

tation; and facilities for packaging radioactive materials for TIhe design will allow for a maximum operating pressure of shipment to national and international destinations. 1.0MPa and a maximum core ceramic temperature of 1600°C.

The nominal working fluid will be helium with a core power A major non-nuclear facility housed in the Radiation Center of approximately 600 kW (note that electrical heaters are used is the one-quarter scale thermal hydraulic advanced plant ex- to simulate the core power). The test facility also includes a perimental (APEX) test facility for the Westinghouse AP600 scaled reactor cavity cooling system, a circulator and a heat and AP1000 reactor designs. The AP600 and AP1000 are sink in order to complete the cycle. The HTTF can be used next-generation nuclear reactor designs which incorporate to simulate a wide range of accident scenarios in gas reac-many passive safety features as well as considerably simplified tors to include the depressurized conduction cooldown and plant systems and equipment. APEX operates at pressures pressurized conduction cooldown events. The HMFTF is a up to 400 psia and temperatures up to 450 0 F using electrical testing facility which will be used to produce a database of heaters instead of nuclear fuel. All major components of the hydro-mechanical information to supplement the qualifica-AP600 and AP1000 are included in APEX and all systems tion of the prototypic ultrahigh density U-Mo Low Enriched are appropriately scaled to enable the experimental measure- Uranium fuel which will be implemented into the U.S. High ments to be used for safety evaluations and licensing of the Performance Research Reactors upon their conversion to low full scale plant. Tlhis world-class facility meets exacting qual- enriched fuel. This data in turn will be used to verify current ity assurance criteria to provide assurance of safety as well as theoretical hydro- and thermo- mechanical codes being used validity of the test results. during safety analyses. The maximum operational pressure of the HMFTF is 600 psig with a maximum operational Also housed in the Radiation Center is the Advanced Ther-temperature of 450°F.

mal Hydraulics Research Laboratory (ATHRL), which is used for state-of-the-art two-phase flow experiments. Tlhe Radiation Center staff regularly provides direct sup-port and assistance to OSU teaching and research programs.

The Multi-Application Light Water Reactor (MASLWR) is Areas of expertise commonly involved in such efforts include a nuclear power plant test facility that is instrumental in the nuclear engineering, nuclear and radiation chemistry, neutron development of next generation commercial nuclear reac-activation analysis, radiation effects on biological systems, ra-tors currently seeking NRC certification. The Test Facility is diation dosimetry, environmental radioactivity, production of constructed of all stainless steel components and is capable of short-lived radioisotopes, radiation shielding, nuclear instru-operation at full system pressure (1500 psia), and full system mentation, emergency response, transportation of radioactive temperature (600F).

materials, instrument calibration, radiation health physics, All components are 1/3 scale height and 1/2 54.7 volume radioactive waste disposal, and other related areas.

scale. The current testing program is examining methods In addition to formal academic and research support, the for natural circulation startup, helical steam generator heat Center's staff provides a wide variety of other services includ-transfer performance, and a wide range of design basis, and ing public tours and instructional programs, and professional beyond design basis, accident conditions. In addition, the consultation associated with the feasibility, design, safety, MASLWR Test Facility is currently the focus of an interna-and execution of experiments using radiation and radioactive tional collaborative standard problem exploring the operation materials.

and safety of advanced natural circulations reactor concepts.

14-15 Annual Report

This 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 VI.1, while individual names and projects are listed in Table VJ.2.

Radiation Center Staff Reactor Operations Committee Steve Reese, Director Andrewv Klein, Chair Dina Pope, Office Manager OSU Nuclear Engineering and Radiation Health Physics Shaun Bromagem, Business Manager Dan Harlan Brittany Combs, Receptionist OSU Radiation Safety S. Todd Keller, Reactor Administrator Abi Tavakoli Farsoni OSU Nuclear Engineering and Radiation Health Physics Gary Wachs, Reactor Supervisor, Senior Reactor Operator S. Todd Keller Robert Schickler, Reactor Engineer, OSU Radiation Center Senior Reactor Operator Wade marcum, Senior Reactor Operator Scott Menn OSU Radiation Center ScottmA'enn, Senior Health Physicist Steve Reese (not voting)

JTim Darrough, Health Physicist OSU Radiation Center Leak minc, Neutron Activation Analysis Manager Mark Trump Steve Smith, Development Engineer, Penn State University Senior Reactor Operator Gary Wachs (not voting)

Celia Oney, Reactor Operator OSU Radiation Center Erin Cimbri, Custodian Julie Tucker Jarvis Ca]ffrey, Reactor Operator (Student)

OSU Mechanical, Industrial and Manufacturing Engineering Joshua Graves, Reactor Operator (Student)

Trevor Howoard, Reactor Operator (Student)

Griffen L atimer, Reactor Operator (Student)

Top her Matthews, Reactor Operator (Student)

Joey DeShields, Health Physics Monitor (Student)

Shara Howoard, Health Physics Monitor (Student)

Kien Tran, Health Physics Monitor (Student)

Sophia Uchiyama, Health Physics Monitor (Student) 14-15 Annual Report

Professional and Research Faculty Farsoni,A bi *Palmer,Todd S.

Professional andEngineering Associate Professor, Nuclear Research Faculty

& Radiation Health Professor, Nuclear Engineering and Radiation Health Physics Physics *Paulenova, Alena John DeNoma Associate Professor, Nuclear Engineering and Radiation Health Research Assistant Physics

  • Hamby, David Pope, Dina Professor, Nuclear Engineering and Radiation Health Physics Office Manager, Radiation Center Hart, Lucas P. *Reese, Steven R.

Faculty Research Associate, Chemistry Director, Radiation Center

  • Higley, Kathryn A. Reyes, Jr., Jos N.

Department Head, Professor, Nuclear Engineering and Professor, Nuclear Engineering and Radiation Health Physics Radiation Health Physics Tack, Krystina

  • Keller, S. Todd Assistant Professor, Medical Physics Program Director Reactor Administrator, Radiation Center *Wachs, Gary Klein, Andrew C. Reactor Supervisor, Radiation Center Professor, Nuclear Engineering and Radiation Health Physics Aaron Weiss
  • Krane, Kenneth S. Faculty Research Assistant Professor Emeritus, Physics Woods, Brian
  • Loveland, Walter D. Professor, Nuclear Engineering and Radiation Health Physics Professor, Chemistry Wu, Qiao Marcum, Wade Professor, Nuclear Engineer and Radiation Health Physics Assistant Professor Nuclear Engineering and Radiation Yanez, Rica rdo Health Physics Faculty Research Associate, Chemistry
  • Mlenn, ScottA.

Yang, Haori Senior Health Physicist, Radiation Center Assistant Professor, Nuclear Engineering and Radiation Health

  • Minc, Leah Physics Associate Professor, Anthropology *OSTR usersfor research and/or teaching Cam ille Palmer Research Faculty and Instructor 14-15 Annual Report 0

a Research Reactor The Oregon State University TRIGA Reactor (OSTR) is a Consequently this facility is normally used for neutron activa-water-cooled, swimming pool type research reactor which uses tion analysis involving short-lived radionucides. On the other uranium/zirconium hydride friel elements in a circular grid ar- hand, the rotating rack is used for much longer irradiation of ray. The reactor core is surrounded by a ring of graphite which samples (e.g., hours).The rack consists of a circular array of 40 serves to reflect neutrons back into the core. The core is situ- tubular positions, each of which can hold two sample tubes.

ated near the bottom of a 22-foot deep water-filled tank, and Rotation of the rack ensures that each sample will receive an the tank is surrounded by a concrete bioshield which acts as a identical irradiation.

radiation shield and structural support. The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at The reactor's thermal column consists of a large stack of a maximum steady state power of 1.1 1VPN and can also be graphite blocks which slows down neutrons from the reactor pulsed up to a peak power of about 2500 MW. core in order to increase thermal neutron activation of samples.

Over 99% of the neutrons in the thermal column are thermal The OSTR has a number of different irradiation facilities neutrons. Graphite blocks are removed from the thermal col-including a pneumatic transfer tube, a rotating rack, a thermal umn to enable samples to be positioned inside for irradiation.

column, four beam ports, five sample holding (dummy) fuel elements for special in-core irradiations, an in-core irradiation The beam ports are tubular penetrations in the reactor's main tube, and a cadmium-lined in-core irradiation tube for experi- concrete shield which enable neutron and gamma radiation to ments requiring a high energy neutron flux. stream from the core when a beam port's shield plugs are re-moved. The neutron radiography facility utilized the tangential The pneumatic transfer facility enables samples to be beam port (beam port #3) to produce ASTM E545 category I inserted and removed from the core in four to five seconds. radiography capability. The other beam ports are available for a variety of experiments.

0 14-15 Annual Report

If samples to be irradiated require a large neutron fluence, Research especially from higher energy neutrons, they may be inserted The OSTR is a unique and valuable tool for a wide variety into a dummy fuel element. This device will then be placed of research applications and serves as an excellent source of into one of the core's inner grid positions which would nor- neutrons and/or gamma radiation. The most commonly used meally be occupied by a fuel element. Similarly samples can b e experimental technique requiring reactor use is instrumental placed in the in-core irradiation tube (ICIT) which can be neutron activation analysis (INAA). This is a particularly inserted in the same core location. sensitive method of elemental analysis which is described in more detail in Part VI.

The cadmium-lined in-core irradiation tube (CLICIT) enables samples to be irradiated in a high flux region near th, e The OSTR's irradiation facilities provide a wide range of center of the core. The cadmium lining in the facility elimi- neutron flux levels and neutron flux qualities which are suf-nates thermal neutrons and thus permits sample exposure to ficient to meet the needs of most researchers. This is true not higher energy neutrons only. The cadmium-lined end of this only for INAA, but also for other experimental purposes such air-filled aluminum irradiation tube is inserted into an inner as the 3 9 Ar/4 0 Ar ratio and fission track methods of age dat-grid position of the reactor core which would normally be o - ing samples.

cupied by a fuel element. It is the same as the ICIT except fo the presence of the cadmium lining.

The two main uses of the OSTR are instruction and research

  • Analytical Equipment The Radiation Center has a large variety of radiation detec-Instruction tion instrumentation. This equipment is upgraded as nec-Instructional use of the reactor is twofold. First, it is used essary, especially the gamma ray spectrometers with their significantly for classes in Nuclear Engineering, Radiation associated computers and germanium detectors. Additional Health Physics, and Chemistry at both the graduate and un-equipment for classroom use and an extensive inventory of dergraduate levels to demonstrate numerous principles whicf portable radiation detection instrumentation are also avail-have been presented in the classroom. Basic neutron behavioi r able.

is the same in small reactors as it is in large power reactors, and many demonstrations and instructional experiments can Radiation Center nuclear instrumentation receives intensive be performed using the OSTR which cannot be carried out use in both teaching and research applications. In addition, with a commercial power reactor. Shorter-term demonstratic *n service projects also use these systems and the combined use experiments are also performed for many undergraduate stu- often results in 24-hour per day schedules for many of the dents in Physics, Chemistry, and Biology classes, as well as fc)r analytical instruments. Use of Radiation Center equipment visitors from other universities and colleges, from high schoo ls, extends beyond that located at the Center and instrumenta-and from public groups. tion may be made available on a loan basis to OSU research-ers in other departments.

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 Radioisotope Irradiation Sources an operating reactor and in associated laboratories. The many ¢ The Radiation Center is equipped with a 1,644 curie (as of types of educational programs that the Radiation Center pro - 7/27/01) Gammacell1220 60Co irradiator which is capable vides are more fully described in Part VI of this report. of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.

During this reporting period the OSTR accommodated a number of different OSU academic classes and other acaderwiic Typically, the irradiator is used by researchers wishing to programs. In addition, portions of classes from other Oregon S perform mutation and other biological effects studies; studies universities were also supported by the OSTR. 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 14-15 Annual Report 0

other such applications. In addition to the 60Co irradiator, the All of the laboratories and classrooms are used extensively dur-Center is also equipped with a variety of smaller 6°Co, 137Cs, ing the academic year. A listing of courses accommodated at 226 the Radiation Center during this reporting period along with Ra, plutonium-beryllium, and other isotopic sealed sources of various radioactivity levels which are available for use as their enrollments is given in Table 111.2.

irradiation sources. Instrument Repair & Calibration During this reporting period there was a diverse group of Facility projects using the 6°Co irradiator. Tlhese projects included the The Radiation Center has a facility for the repair and calibra-irradiation of a variety of biological materials including differ- tion of essentially all types of radiation monitoring instru-ent types of seeds. mentation. This includes instruments for the detection and measurement of alpha, beta, gamma, and neutron radiation.

In addition, the irradiator was used for sterilization of several It encompasses both high range instruments for measuring media and the evaluation of the radiation effects on different intense radiation fields and low range instruments used to materials. Table 111.1 provides use data for the Gammacell measure environmental levels of radioactivity.

220 irradiator.

The Center's instrument repair and calibration facility is used regularly throughout the year and is absolutely essential to the Laboratories and Classrooms continued operation of the many different programs carried out at the Center. In addition, the absence of any comparable TIhe Radiation Center is equipped with a number of different facility in the state has led to a greatly expanded instrument radioactive material laboratories designed to accommodate calibration program for the Center, including calibration of research projects and classes offered by various OSU academic essentially all radiation detection instruments used by state and departments or off-campus groups. federal agencies in the state of Oregon. This includes instru-ments used on the OSU campus and all other institutions Instructional facilities available at the Center include a labo- in the Oregon University System, plus instruments from the ratory especially equipped for teaching radiochemistry and a Oregon Health Division's Radiation Protection Services, the nuclear instrumentation teaching laboratory equipped with Oregon Department of Energy, the Oregon Public Utilities modular sets of counting equipment which can be configured Commission, the Oregon Health and Sciences University, to accommodate a variety of experiments involving the mea- the Army Corps of Engineers, and the U. S. Environmental surement of many types of radiation. The Center also has two Protection Agency.

student computer rooms.

In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equip- Library ment are regularly used for teaching. In particular, classes are The Radiation Center has a library containing a significant routinely given access to gamma spectrometry equipment collections of texts, research reports, and videotapes relating to located in Center laboratories. A number of classes also regu- nuclear science, nuclear engineering, and radiation protection.

larly use the OSTR and the Reactor Bay as an integral part of their instructional coursework. The Radiation Center is also a regular recipient of a great vari-ety of publications from commercial publishers in the nuclear T]here are two classrooms in the Radiation Center which are field, from many of the professional nuclear societies, from capable of holding about 35 and 18 students. In addition, the U. S. Department of Energy, the U. S. Nuclear Regulatory Commission, and other federal agencies. Therefore, the Center there are two smaller conference rooms and a library suitable library maintains a current collection of leading nuclear re-for graduate classes and thesis examinations. As a service to search and regulatory documentation. In addition, the Center the student body, the Radiation Center also provides an office has a collection of a number of nuclear power reactor Safety area for the student chapters of the American Nuclear Society Analysis Reports and Environmental Reports specifically and the Health Physics Society. prepared by utilities for their facilities.

S14-15 Annual Rpr

T'he Center maintains an up-to-date set of reports from such radiological emergency response topics. In addition, the organizations as the International Commission on Radiologi- Radiation Center uses videotapes for most of the technical cal Protection, the National Council on Radiation Protection orientations which are required for personnel working with and Measurements, and the International Commission on radiation and radioactive materials. TIhese tapes are repro-Radiological Units. Sets of the current U.S. Code of Federal duced, recorded, and edited by Radiation Center staff, using Regulations for the U.S. Nuclear Regulatory Commission, the Center's videotape equipment and the facilities of the the U.S. Department of Transportation, and other appropriate OSU Communication Media Center.

federal agencies, plus regulations of various state regulatory agencies are also available at the Center. The Radiation Center library is used mainly to provide ref-erence material on an as-needed basis. It receives extensive T-he Radiation Center videotape library has over one hun- use during the academic year. In addition, the orientation dred tapes on nuclear engineering, radiation protection, and videotapes are used intensively during the beginning of each term and periodically thereafter.

Table II1.1 Gammacel1 220 *°Co IrradiatorUse Purpose ofIrdain ofIrdito SmlsDose Smls(rads) Range Number of Irradiations Use Time (hours)

Sterilization wood, dill pollen, 2.0x10 6 to 2.5x10 6 81200 chitosan Material Evaluation silicon polymers 3.0x10 5 to 3.0x10 5 113 Botanical Studies seeds, barley 1.0x10 3 to 1.6x10 4 143 BilgclSuisfibronectic, zebra fish, 5.0x10 2 to 2.5x10 6 37 109 Biolgica Stuiesmice Totals 60 1325 14-15 Annual Report 0

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 2014 2014 2015 2015 NE/RHP 114* 2 Introduction to Nuclear Engineering and Radiation 69 Health Physics ___

NE/RHP 115 2 Introduction to Nuclear Engineering and Radiation 62 Health Physics ___

NE!/RI-P 234 4 Nuclear and Radiation Physics I ____ 66 NE!/RHP 235 4 Nuclear and Radiation Physics II 59 ____

NE!/RHP 236* 4 Nuclear Radiation Detection & Instrumentation 49 NE 311 4 Intro to T'hermal Fluids 3 38 25 NE 312 4 T'hermodynamics 29 20 NE 319 3 Societal Aspects of Nuclear technology ____ 76 NE 331 4 Intro to Fluid Mechanics 21 24 NE 332 4 Heat Transfer 11 6 18 NE/RHP 333 3 Mathematical methods for NE/RHP _ __68 N/IPMP1-16 Research 4 20 17 18 401/501/601 NE/HPMP1-16 Reading and Conference2 405/505/605 NE/HPMP1-16 Projects 406/506/606 NE/RHP/MP 407/507/607 1 Nuclear Engineering Seminar 77 79 72 NE/ RI-P/MP 4050601-12 Internship 2 4 5 6 NE!/RHP 415/515 2 Nuclear Rules and Regulations 46 ___

NE 45 1/551 4 Neutronic Analysis ____ 38 ___

NE 452/552 4 Neutronic Analysis 36 NE 455/555"* 3 Reactor Operator Training I NE 456/556"* 3 Reactor Operator Training II3 NE 457/557"* ~ 3 tNeuclear Reactor Lab 34 NE 467/567 4 Nuclear Reactor T'hermal Hydraulics 29 ___

NE 667 4 Nuclear Reactor T'hermal Hydraulics ___ ______

NE/RHP 435/535 3 Extemnal Dosimetry & Radiation Shielding 56 NE 565 3 Applied Thermal Hydraulics9 ___

NE 473/573 3 Nuclear Reactor Systems Analysis 16 ___

14-15 Annual Report

Table 111.2 (continued)

Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Number of Students Course # CREDIT COURSE TITLESumr Fl Witr pin 2014 2014 2015 2015 NE/RHP 474/574 4 Nuclear System Design I 36 NE/RHP 475/575 4 Nuclear System Design II 37 NE/RHP 479* 1-4 Individual Design Project NE/RHP 481*" Radiation Protection 53 NE/RHP 582* 4 Applied Radiation Safety 10 RHP 483/583 4 Radiation Biology 16 RHP 488/588*" Radioecology 14 NE/RHP 590 4 Internal Dosimetry 3 NE/RI-P/MP 503/603* 1 Thesis 18 38 35 56 NE!/RHP 516* 4 Radiochemistry 6 NE 526 3 Numerical Methods for Engineering Analysis NE/RHP/MP 531 3 Nuclear Physics for Engineers and Scientists 28 NE/RHP/MP 536* 3 Advanced Radiation Detection & Measurement 26 NE/RHP 537 3 Digital Spectrometer Design 4 MP 541 3 Diagnostic Imaging Physics____

NE 550 3 Nuclear Medicine NE 553 3 Advanced Nuclear Reactor Physics ____ ____ 13 MP 563 4 Applied Medical Physics 4 ___

NE 468/568 3 Nuclear Reactor Safety ____ ____ 13 ___

NE/RHP/MP 599 _____Special Topics 20 27 5 11 Course From Other OSU Departments CH 233* 5 General Chemistry 111 _ ______ 711 CH 233H* 5 Honors General Chemistry _ __________ 28 CH____462* ___ __3_ Experimental Chemistry II Laboratory ________ 8______

ENGR 111" 3 Engineering Orientation 248 224 143 ENGR 212H* 3 Honors Engineering ____ ____4 ST Special Topics

  • OSTR used occasionallyfor demonstration and/or experiments
    • OSTR used heavily 14-15 Annual Report

B Operating Status Inactive Experiments During the operating period between July 1, 2014 and June Presently 33 experiments are in the inactive file. This 30,2015, the reactor produced 1403 M'WH of thermal power consists of experiments which have been performed in during its 1512 critical hours. 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 Experiments Performed identifies these inactive experiments.

During the current reporting period there were ten ap- A-2 Measurement of Reactor Power Level via Mn proved reactor experiments available for use in reactor- Activation.

related programs. They are: A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack.

A-i Normal TRIGA Operation (No Sample Irradia-tion). A-4 Neutron Flux Measurements in TRIGA.

A-S Copper Wire Irradiation.

B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities. A-6 In-core Irradiation of LiF Crystals.

A-7 Investigation ofTRIGA~s Reactor Bath Water B-li Irradiation of Materials Involving Specific Temperature Coefficient and High Power Level Quantities of Uranium and Thorium in the Power Fluctuation.

Standard OSTR Irradiation Facilities.

B-i Activation Analysis of Stone Meteorites, Other B-12 Exploratory Experiments. Meteorites, and Terrestrial Rocks.

B-23 Studies Using TRIGA Thermal Column. B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column.

B-29 Reactivity Worth of Fuel.

B-4 Flux Mapping.

B-3i TRIGA Flux Mapping. B-5 In-core Irradiation of Foils for Neutron Spectral Measurements.

B-33 Irradiation of Combustible Liquids in Rotating Rack. B-6 Measurements of Neutron Spectra in External Irradiation Facilities.

B-34 Irradiation of Enriched Uranium in the Neutron B-7 Measurements of Gamma Doses in External Ir-Radiography Facility.

radiation Facilities.

B-35 Irradiation of Fissile Materials in the Prompt B-S Isotope Production.

Gamma Neutron Activation Analysis (PGNAA)

B-9 Neutron Radiography.

Facility.

B-10 Neutron Diffraction.

B-13 T'his experiment number was changed to A-7.

Of these available experiments, four were used during the reporting period. Table IV.4 provides information B-14 Detection of Chemically Bound Neutrons.

related to the frequency of use and the general purpose B-15 T'his experiment number was changed to C-i.

of their use.

B-16 Production and Preparation of 15F.

B-17 Fission Fragment Gamma Ray Angular Cor- There were six new screens performed in support of the relations. reactor this year. They were:

B-18 A Study of Delayed Status (n, 'y) Produced 14-04, Pneumatic Rabbit System Modification Nuclei.

Description B-19 Instrument Timing via Light Triggering.

Modifies the pneumatic transfer system to allow B-20 Sinusoidal Pile Oscillator. samples to be cycled repeatedly between the reactor and B-21 a detector in the bay.

Beam Port #3 Neutron Radiography Facility.

B-22 Water Flow Measurements Through TRIGA Core. 14-05, Reactor Bay East Wall Penetrations B-24 General Neutron Radiography. Description B-25 Neutron Flux Monitors. Allows a hole to be drilled in the Reactor Bay east wall B-26 Fast Neutron Spectrum Generator. to accommodate a 1.0 inch conduit carrying electrical cables to the APEX facility.

B-27 Neutron Flux Determination Adjacent to the OSTR Core.

14-06, Damper Control Modification B-28 Gamma Scan of Sodium (TED) Capsule.

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

Removes pressure regulators from several hoods and B-32 Argon Production Facility ventilation systems in the Reactor Building and modi-C-1 PuO 2 Transient Experiment. fies the associated isolation dampers so that they will no longer close.

15-01, Modification of CAM Flow Monitoring Unplanned Shutdowns There were seven unplanned reactor shutdowns during Description the current reporting period. Table IV.5 details these Replaces the current air flow sensors on the reactor events. top and stack continuous air monitors with Magnahe-lic flow sensors, which are positioned closer to the air sampling point and farther from the pump. Tlhis change Changes Pursuant tolO0 CFR 50-59 provides local flow indication and makes flow measure-ment and control more reliable.

There was one safety evaluation performed in support of the reactor this year. It was:

15-02, Heat Exchanger Room Wall Penetrations 15-01, New Procedure: OSTROP 31, "Scanning Description Documents for Permanent Archival Storage and Retrieval" Allows two 1.5 inch diameter holes to be drilled in the Heat Exchanger Room (south and east walls) to accom-Description modate a 1.25 inch conduit carrying electrical cables to This new procedure provides instructions for creating support an upgrade to the loads supplied by the emer-electronic versions of reactor related documents and gency diesel generator.

transferring the original paper records to the OSU Val-ley Library for long-term storage.

14-15 Annual Report

15-03, Changes to OSTROP 26 - Replaced the internal power supply on the CAM particulate channel monitor.

Description Updates to Background Investigation Procedures: Work December 2014 history checks now cover the last 7 years, and finger-printing and FBI background check are repeated every - Replaced the demineralizer inlet and outlet piping 10 years. Also adds information about Export Control, and the demineralizer pump.

rights under Fair Credit Reporting Act, and access to Safeguards Information and Category 1 or 2 quantities February 2015 of radioactive material.

- Changed demineralizer resin. Also replaced the resin retention elements in the demineralizer tank. T-he bottom one had failed, which was discovered during Surveillance and Maintenance the resin change.

Non-Routine Maintenance March 2015 July2014 - Added new flow orifice and Magnahelic gauge to the stack monitor and CAM.

-Lubricated rotating rack drive mechanism to elimi-nate binding. - Drilled two 1.5" holes in the heat exchanger room walls (see 50.59 15-02) to be used for conduits for

-Began modifications on pneumatic transfer system to the emergency power distribution system.

allow repeated cycling of a sample into and out of the reactor, with an analyzer in the reactor bay. - Upgraded emergency power distribution system to provide backup to some lights and equipment in the Radiation Center.

August 2014

-Completed pneumatic transfer system modifications.

April 2015 September 2014 - Replaced the reactor bay supply fan heating coil.

-Replaced Safety Channel high voltage and signal - Constructed a new antimony storage cave.

connectors.

June 2015 October 2014 - Replaced a relay and a filter capacitor in the console

-Removed control dampers for 4th floor hood exhaust left-hand drawer.

filters.

-Replaced a deck on the console reset switch.

-Replaced the Regulating Rod magnet and cleaned the base tube. Rust had accumulated due to conden-sation.

-Facilities Services repaired the cooling tower south fan and fan shaft.

November 2014

-Repaired an internal short in the stack monitor pump motor.

0 14-15 Annual Report

~~~Ta l IV:,J1...

Present OSTR Operating Statistics _________

Oprtinl o LUCoeAnnual aa Values Cumulative Values Opertioal or EU ore(2014/2015) ata MW\H of energy produced 1,403 8,662 MWND of energy produced 58 351.8 235 Grams U used 80 496 Number of fuel elements added to (+) or removed(-) from 0 90 the core Number of pulses 24 226 Hours reactor critical 1,512 9,347 Hours at fulil power (1 MW) 1,399 8,631 Number of startup and shutdown checks 249 1,432 Number of irradiation requests processed 189 1,546 Number of samples irradiated 992 11,790 14-15 Annual Report

~Table IV.2 OSTR Use Time in Terms of Specific Use Categories OSTR Use Category (hours) (hours)

Teaching (departmental and others) 36 13,672 OSU research 414 18,784 Off campus research 2,127 45,023 Demonstrations 7 45 Reactor preclude time 767 33,075 Facility time 39 7,261 Total Reactor Use Time 3,390 117,860 Table IV.3 OSTR Multiple Use Time__________

Cumulative Values Number of Users Annual Values (hours) (hours)

Two 491 9,380 TIhree 208 4,868 Four 56 2,644 Five 15 941 Six 0 241 Seven 0 69 Eight 0 3 Total Multiple Use Time 770 18,146 0 14-15 Annual Report

Table IV.4

___________ Use of OSTR Reactor Experiments ______

ENumbert Research Teaching Facility Use Total A-i 0 3 1 4 B-3 164 14 4 182 B-13 0 0 2 2 B-31 0 0 1 1 Total 164 17 8 189 Table IV.5 Unplanned Reactor Shutdowns and Scrams Typeof EentNumber of Typeof EentOccurrences Cause of Event Mannual 2 Dropped Reg rod Mannual 1 Dropped Safety rod Manual 1 CAM Particulate high activity Safety channel high power 2 Power fluctuations while stabilizing during startup Automatic - no annunciator 1 Unknown mechanical issue 14-15 Annual Report 0I

Figure IV.1 Monthly Surveillance and Maintenance (Sample Form)

OSTROP 13, Rev. LEU-4 Surveillance & Maintenance for the Month of__________________

I SURVEILLANCE & MAINTENANCE

[SHADE INDICATES LICENSE REQUIREMENT]

LIMITS AS FOUND TARGET DATE NOT TO BE EXEDD*COMPLETED DATE DT EAK IIIL HIGH: INCHES 1 REACTOR TANK HIGH AND LOW WATERMAIU LEVEL ALARMS MOVEMENT LOW: INCHnES

+ 3 INCHES AN:_ _ _ _ ______ _ _ _ _ _ _____

2 BULK WATER TEMPERATURE ALARM CHECK FUNCTIONAL Tested @.___

8.500O'+ Ann.? _cpm _Ann.

3B CHANNEL TEST OF STACK CAM PARTICULATE 8.5x10_+

3B CHANNEL 8500 cpm Ann.? _cpm Ann.

3C CHANNEL PARTICULATE TEST OF REACTOR TOP CAM CHANNEL 8.5xlO+/-

8500 cpm n.?

Ann.?_

__pm_

Ann.____ ______ ____

MEASUREMENT OF REACTOR PRIMARY 4__ WATER CONDUCTIVITY <5 *.tmho\cm MIN: 5N/

5 PRIMARY WATER pH MEASUREMENT MAX: 9N/

6 BULK SHIELD TANK WATER pH MIN: 5 N/A MEASUREMENT MAX: 9 7 CHANGE LAZY SUSAN FILTER CHANGED N/A 8 REACTOR TOP CAM OIL LEVEL CHECK OSTROP 13.8 NEED OIL?___ N/A 9 STACK CAM OIL LEVEL CHECK OSTROP 13.9 NEED OIL?___ N/A 10 PRIMARY PUMP BEARING OIL LEVEL CHECK OSTROP 13.10 NEED OIL?__ N/A 11 EMERGENCY DIESEL GENERATOR CHECKS >5% Olo?~jjjjjj~N/A Total hours _ _ _ _ _ _ _ _ _ _ _ _

12 RABBIT SYSTEM RUN TIME Total hours N/A 13 OIL TRANSIENT ROD BRONZE BEARING WD 40 N/A 14 COLBALT SOURCE PRESENT IN A128 SOURCE PRESENT? N/A 15 WATER MONITOR CHECK RCHPP 8 App. F.4 N/A

  • Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last month plus six weeks.

Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)

OSTROP 14, Rev. LEU-2 Surveillance & Maintenance for the 1st / 2nd / 3 rd / 4th Quarter of 20 SURVEILLANCE & MAINTENANCE I LMT ASFUD1TARGET IDATE NOT TO I DATE IREMARKS &

[SHADE INDICATES LICENSE REQUIREMENT] jDATE jBE EXCEEDED* jCOMPLETED INITIALS I REACTOR OPERATION COMMITT7EE (ROC) AUDIT QUARTERLY _____ ______

2 QUARTERLY ROC MEETING QUARTERLY 3 ERP INSPECTIONS QUARTERLY 4 ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 5 WATER MONITOR ALARM CHECK FUNCTIONAL 6A CHECK FILTER TAPE SPEED ON STACK MONITOR I"/HR + 0.2 6B CHECK FILTER TAPE SPEED ON CAM MONITOR I"/HR + 0.2 7 INCORPORATE 50.59 & ROCAS INTO DOCUMENTATION QUARTERLY ARM SYSTEM ALARM CHECKS ARM I 2 3S3E4 5 78 9 10 1112 AUD 8 FUNCTIONAL LIGHT PANEL ANN

  • Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last quarter plus four months.

Figure IV.2 (continued)

Quarterly Surveillance and Maintenance (Sample Form)

OSTROP 14, Rev. LEU-2 Surveillance & Maintenance for the Is / 2 nd / 3 rd / 4 th Quarter of 20 SURVEILLANCE & MAINTENANCE

[SHADE INDICATES LICENSE REQUIREMENT]

1 LMTASFUD j__________

1DATE COMPLETED 1

J REMARKS &

INITIALS OPERATOR NAM E a) TOTAL OPERATION TIME Ib) DATE OF OPERATING EXERCISE REMARKS & INITIALS 4 4 I t 4 r a) >4 hours: at 4 I console (RO) or as Rx. Sup.

(SRO) 4 1 9

b) Date of Complete 4 I Operating Exercise I 4

  • *1 I 4

-I * *4. I 4

_________________________________________________________________________________________ L .1. i .1.

Figure IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP 15, Rev. LEU-2 Surveillance & Maintenance for the 1st / 2 na Half of 20 DATE NOT REMARKS SURVEILLANCE & MAINTENANCE LIMITS AS FOUND TARGET TO BE DATE &

[SHADE INDICATES LICENSE REQUIREMENT] DATE COMPLETED EXC EEDED* INITIALS NO WITHDRAW NEUTRON SOURCE COUNT RATE INTERLOCK______ ______

>5 cps ________ ____ ______

TRANSIENT ROD AIR INTERLOCK NO PULSE CHANNEL TESTS PULSE MODE ROD MOVEMENT INTERLOCK NO MOVEMENT IOF REACTOR INTERLOCKS PULSE INTERLOCK ON RANGE SWITCH NO PULSE MAXIMUM PULSE REACTIVITY INSERTION LIMIT ** $2.25 TWO ROD WITHDRAWAL PRHOHIBIT I ONLY PULSE PROHIBIT ABOVE I kW >1 kW 2 SAFETYPEIDSRM>se CIRCUIT TEST PEIDSRM3se PREVIOUS PULSE DATA FOR COMPARION <20%, PULSE # __

PULSE # -o $_____

$_________ _____MW 3TEST PULSE MW CHANGE ° 4 CLEANING & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL BARREL 5 LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 6 LUBRICATION OF THE ROTATING RACK BEARINGS l0W OIL 7 CONSOLE CHECK LIST OSTROP 15.VII1 8 INVERTER MAINTENANCE See User Manual 9 STANDARD CONTROL ROD MOTOR CHECKS LO-17 Bodine Oil

  • aenot to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.

Figure IV.3 (continued)

Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP 15, Rev. LEU-2 Surveillance & Maintenance for the 1S / 2 nd Half of 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT DATE REMARKS &

[SHADE INDICATES LICENSE REQUIREMENT] LIMITS AS FOUND DATE TO BEED CMPLETED INITIALS NONE SAFETY CHtANNEL(IfOny 10ION CHAMBER RESISTANCE MEASUREMENTS WITH (ln____Only)

NONE

%POWER CtIANNEL(IfOny

(/a 100 V.I _________ AMPS FISSION CHAMBER RESISTANCE @ 900 V. I = _________AMPS NN CALCULATION R 800- Al = ________AMPS (IfOny Al HIGH ___

12 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP I 5.XII FULL____

BRUSH INSP~ECTION 13INSPECTION OF THE PNEUMATIC TRANSFER__________

SYSTEM SAMPLE INSERTION TIME CHECK ~~1.0 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-2 AnnualSurveillance and Maintenance for 20 ____

SURVEILLANCE AND MAINTENANCE LIISAS I TARGET DATE NOT TBEDATE& REMARKS

[SHADE INDICATES LICENSE REQUIREMENT]

IFOUND IIEXCEEDED*

DATE COMPLETED INITIALS BIENNIAL INSPECTION OF FFCRSOTRP1.

CONTROL RODS: TRANS__________________

2 STANDARD CONTROL ROD DRIVE INSPECTON OSTROP 16.2 NORMAL CONTROL ROD 3 CLICIT CALIBRATION: OSTROP 9.0 ICITiDUMMY TRANS SAFE SHIM REG CONTROL ROD <2 sec WITHDRAWAL SCA INSERTION & WiD ___ __ __ <50

-- sec INSERT <50 sec 5 FUEL ELEMENT INSPECTION FOR SELECTED ELEMENTS .2%F' 6 REACTOR POWER CALIBRATION OSTROP 8 7 FUEL ELEMENT TEMPERATURE CHANNEL CALIBRATION Per Checklist 8CALIBRATION OF REACTOR TANK WATER TEMPOSRP1.

TEMPERATURE METERS _________ _________

CONTINUOUS Particulate Monitor 9AIR MONITOR RCHPP 18 CALIBRATION rGas Monitor 10 CAM OIL/GREASE MAINTENANCE 11STACK MONITOR IParticulate Monitor RCHPP CALIBRATION jGas Monitor 18 & 26 12 STACK MONITOR OIL/GREASE MAINTENANCE 13 AREA RADIATION MONITOR CALIBRATION RCHPP 18

  • 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-2 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DAENT DATE REMARKS

[SHADE INDICATES LICENSE REQUIREMENT] LIIS FOUND DATE TOCEBED COMPLETED & INITIALS NORMAL $

14 CORE EXCESS <$7.55 ICIT $

______ ______ ______ ______ ____ _ ______ CLICIT$$_ _ _ _ _ _ _ _

DAMPERS 1 ST FLOOR__

15 RACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSE IN<5

__________________________________ SECONDS 4 TH FLOOR 16 DECOMMISSIONING COST UPDATE N/A N/A AUGUST 17 *NM PHYSICAL INVENTORY N/A N/A OCTOBER 18 ATERIAL BALANCE REPORTS N/A N/A NOVEMBER CFD TRAINING______________

GOOD SAM TRAINING__________

ERP REVIEW ERP DRILL__ _ _ _ _ _ _ _ __ _ _ _

CPR CERT FOR:

CPR CERT FOR:________________

EMERGENCY 19 RESPONSE FIRST AID FOR:

PLAN FIRST AID FOR:

EVACUATION DRILL AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIENNIAL SUPPORT AGRE*EMENTS PSP REVIEW PHYSICAL PSP DRILL 20 SECURITY OSP/DPS TRAINING PLAN LOCK/SAFE COMBO CHANGES AUTHORIZATION LIST UPDATE

  • 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-2 Annual Surveillance and Maintenance for 20 DATE NOT SURVEILLANCE AND MAINTENANCE LIISAS TARGET TO BE DATE REMARKS

[SHADE INDICATES LICENSE REQUIREMENT] FOUND DATE COMPLETED & INITIALS 21 ANNUAL REPORT NOVI1 OCTI1 NOVI1 22 KEY INVENTORY ANNUAL REACTOR TANK AND CORE COMPONENT 23 NO WHITE SPOTS

__INSPECTION ______

24 EMERGENCY LIGHT LOAD TEST RCHPP 18.0 25 NEUTRON RADIOGRAPHY FACILTIY INTERLOCKS 26 PGNAA FACILITY INTERLOCKS ANNUAL REQUALIFICATION BIENNIAL MEDICAL EVERY 6 YEARS LICENSE REACTOR OPERATOR LICENSE CONDITIONS WRITTEN OPERATING TEST APIAIN EPRTO APPLIATION EXPDATIO DATE DA[E EXAM DTEDE DATE

~~~DATE DUE DT COMPLETED DUE DATE OPERATOR NAME DUE PASSED DAEDE PASSED ___________ DATE MAILED 27

  • Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus t15 months.

For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.

'.g. I I a S Introduction Liquid Effluents Released T-he purpose of the radiation protection program is to ensure Liquid Effuents the safe use of radiation and radioactive material in the Cen- Oregon State University has implemented a policy to re-ter's teaching, research, and service activities, and in a similar duce the volume of radioactive liquid effluents to an absolute manner to the fulfillment of all regulatory requirements of the minimum. For example, water used during the ion exchanger State of Oregon, the U.S. Nuclear Regulatory Commission, resin change is now recycled as reactor makeup water. Waste and other regulatory agencies. TIhe comprehensive nature of water from Radiation Center laboratories and the OSTR is the program is shown in Table V.1, which lists the program's collected at a holdup tank prior to release to the sanitary sewer.

major radiation protection requirements and the performance Liquid effluent are analyzed for radioactivity content at the frequency for each item. time it is released to the collection point. For this reporting period, the Radiation Center and reactor made seven liquid ef-The radiation protection program is implemented by a staff fluent releases to the sanitary sewer. All Radiation Center and consisting of a Senior Health Physicist, a Health Physicist, reactor facility liquid effluent data pertaining to this release are and several part-time Health Physics Monitors (see Part II). contained in Table V.2.

Assistance is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Liquid Waste Generated and Transferred Technician, and the Radiation Center Director. Liquid waste generated from glassware and laboratory experi-ments is transferred by the campus Radiation Safety Office TIhe data contained in the following sections have been to its waste processing facility. The annual summary of liquid prepared to comply with the current requirements of Nuclear waste generated and transferred is contained in Table V.3.

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. Airborne Effluents Released 345-30-010, which requires an annual report of environmental Airborne effluents are discussed in terms of the gaseous com-effects due to research reactor operations. ponent and the particulate component.

Within the scope of Oregon State University's radiation pro- Gaseous Effuents tection program, it is standard operating policy to maintain all Gaseous effluents from the reactor facility are monitored by releases of radioactivity to the unrestricted environment and all the reactor stack effluent monitor. Monitoring is continuous, exposures to radiation and radioactive materials at levels which i.e., prior to, during, and after reactor operations. It is normal are consistently "as low as reasonably achievable" (ALARA). for the reactor facility stack effluent monitor to begin operation as one of the first systems in the morning and to cease opera-nion as one of the last systems at the end of the day. All gaseous Environmental Releases effluent data for this reporting period are summarized in Table V.4.

The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a Particulate effluents from the reactor facility are also moni-summary of the nature and amount of radioactive effluents tored by the reactor facility stack effluent monitor.

released or discharged to the environs beyond the effective Particulate Effluents control of the licensee, as measured at, or prior to, the point Evaluation of the detectable particulate radioactivity in the of such release or discharge." Tlhe liquid and gaseous effluents stack effluent confirmed its origin as naturally-occurring radon released, and the solid waste generated and transferred are daughter products, within a range of approximately 3x10~11 discussed briefly below. Data regarding these effluents are also pCi/ml to 1 x 10.9 1 tCi/ml. T-his particulate radioactivity is summarized in detail in the designated tables.

d 14-15 Annual Report

predominantly 214pb and 214Bi, which is not associated with Facilities Services maintenance personnel are normally is-reactor operations. sued a gamma sensitive electronic dosimeter as their basic 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 Xti(7) TLD badge and other average concentration of radioactive particulates with half lives dosimeters as appropriate for the work being performed.

greater than eight days is not applicable.

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

Solid Waste Released Data for the radioactive material in the solid waste generated Students or small groups of students who attend a one-time and transferred during this reporting period are summarized lab demonstration and do not handle radioactive materials are in Table V.5 for both the reactor facility and the Radiation usually issued a gamma sensitive electronic dosimeter. These Center. Solid radioactive waste is routinely transferred to results are not included with the laboratory class students.

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 XIg(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 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.

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

Personnel Dose An annual summary of the radiation doses received by each of the above six groups is shown in Table V.6. There were no per-The OSTR annual reporting requirements specify, that the sonnel radiation exposures in excess of the limits in 10 CFR licensee shall present a summary of the radiation exposure re-20 or State of Oregon regulations during the reporting period.

ceived by facility personnel and visitors. Tfhe 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 Facility Survey Data personnel, facilities services maintenance personnel, students The OSTR Technical Specifications require an annual in laboratory classes, police and security personnel, and visitors. summary of the radiation levels and levels of contamination Facility operating personnel include the reactor operations and health physics staff. T'he 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.

14-15 Annual Report 0

observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program Environmental Survey Data The annual reporting requirements of the OSTR Technical encompasses the Radiation Center as well as the OSTR, and Specifications include "an annual summary of environmental therefore monitoring results for both facilities are reported. surveys performed outside the facility."

Area Radiation Dosimeters Area monitoring dosimeters capable of integrating the radia-tion dose are located at strategic positions throughout the Gamma Radiation Monitoring reactor facility and Radiation Center. All of these dosimeters On-site Monitoring contain at least a standard personnel-type beta-gamma film or Monitors used in the on-site gamma environmental radiation TLD pack. In addition, for key locations in the reactor facility monitoring program at the Radiation Center consist of the and for certain Radiation Center laboratories a CR-39 plastic reactor facility stack effluent monitor described in Section V track-etch neutron detector has also been included in the and nine environmental monitoring stations.

monitoring package.

During this reporting period, each fence environmental sta-The total dose equivalent recorded on the various reactor facil-tion utilized an LiF TLD monitoring packet supplied and pro-ity dosimeters is listed in Table V.7 and the total dose equiva-cessed by Mirion Technologies, Inc., Irvine, California. Each lent recorded on the Radiation Center area dosimeters is listed GDS packet contained three LiP TLDs and was exchanged in Table V.8. Generally, the characters following the Monitor quarterly for a total of 108 samples during the reporting period Radiation Center (MRC) designator show the room number (9 stations x 3 TLDs per station x 4 quarters). The total num-or location. ber of GDS TLD samples for the reporting period was 108. A Routine Radiation and Contamination Surveys summary of the GDS TLD data is also shown in Table V.10.

The Center's program for routine radiation and contamination From Table V.10 it is concluded that the doses recorded by the surveys consists of daily, weekly, and monthly measurements dosimeters on the TRIGA facility fence can be attributed to throughout the TRIGA reactor facility and Radiation Center.

natural back-ground radiation, which is about 110 mrem per The frequency of these surveys is based on the nature of the year for Oregon (Refs. 1, 2).

radiation work being carried out at a particular location or on other factors which indicate that surveillance over a specific Off-site Monitoring area at a defined frequency is desirable. The off-site gamma environmental radiation monitoring program consists of twenty monitoring stations surrounding The primary purpose of the routine radiation and contamina-the Radiation Center (see Figure V.1) and six stations located tion survey program is to assure regularly scheduled surveil-within a 5 mile radius of the Radiation Center.

lance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and character- Each monitoring station is located about four feet above istic data on the status of radiological conditions. A second the ground (MRCTE 21 and MRCTE 22 are mounted on objective of the program is to assure frequent on-the-spot the roof of the EPA Laboratory and National Forage Seed personal observations (along with recorded data), which wl Laboratory, respectively). These monitors are exchanged and provide advance warning of needed corrections and thereby processed quarterly, and the total number of TLD samples dur-help to ensure the safe use and handling of radiation sources ing the current one-year reporting period was 240 (20 stations and radioactive materials. A third objective, which is really x3 chips per station per quarter x 4 quarters per year). The total derived from successful execution of the first two objectives, is number of GDS TLD samples for the reporting period was to gather and document information which will help to ensure 240. A summary of GDS TLD data for the off-site monitoring that all phases of the operational and radiation protection stations is given in Table V.11.

programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as After a review of the data in Table V.11, it is concluded that, low as reasonably achievable" (ALARA). like the dosimeters on the TRIGA facility fence, all of the doses recorded by the off-site dosimeters can be attributed to The annual summary of radiation and contamination levels natural background radiation, which is about 110 mrem per measured during routine facility surveys for the applicable year for Oregon (Refs. 1, 2).

reporting period is given in Table V.9.

D 14-15 Annual Report

Soil, Water, and Vegetation Surveys Radioactive Materials Shipments The soil, water, and vegetation monitoring program consists A summary of the radioactive material shipments originat-of the collection and analysis of a limited number of samples ing from the TRIGA reactor facility, NRC license R-106, in each category on a annual basis. Tlhe program monitors is shown in Table V.14. A similar summary for shipments highly unlikely radioactive material releases from either the originating from the Radiation Center's State of Oregon ra-TRIGA reactor facility or the OSU Radiation Center, and dioactive materials license ORE 90005 is shown in Table V.15.

also helps indicate the general trend of the radioactivity A summary of radioactive material shipments exported under concentration in each of the various substances sampled. See Nuclear Regulatory Commission general license 10 CFR Figure V.1 for the locations of the sampling stations for grass 110.23 is shown in Table V.16.

(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 References over a local area having a radius of about ten feet at the posi-tions indicated in Figure V.1. 1. U. S. Environmental Protection Agency, "Estimates of Ionizing Radiation Doses in the United States,

'T-here are a total of 22 sampling locations: four soil locations, 1960-2000," O RP/C SD 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, "Radiologi-

'The annual concentration of total net beta radioactivity (mi- cal Quality of the Environment in the United States, nus tritium) for samples collected at each environmental soil, 1977," EPA 520/1-77-009, Office of Radiation water, and vegetation sampling location (sampling station) is 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.

'Ihe annual concentrations were calculated using sample results which exceeded the lower limit of detection (LLD),

except that sample results which were less than or equal to the 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 1 iCi 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.

14-15 Annual Report 0

Table V. 1 Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement Daily/Weekly/Monthly 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 Monthly exposure reports.

Inspect laboratories.

Calculate previous month's gaseous effluent discharge.

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.

As Required 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.

Quarterly Collect and analyze samples from reactor stack effluent line.

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

Semi-nnualLeak 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 Annualfilters 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.

14-15 Annual Report

~Table V.2

..... Monthly Summary of Liquid Effluent Release to the Sanitary Sewert 1 )

Specific Activity for Toal Quantity of Aeae Preto plcbeTotal Volume Date of Total Each Detectable Ra- Tto vrg ecn fApial Deectble Dateof f uantty ionclid in Each Detectable Concentration Monthly Average of LiqudEfun adRdincd thWatWeete Radionuclide Of Released Concentration for Rlae nldn Dishare adiaciviy adinulid te Wst, Wer th Rleaedin the Radioactive Material Released Radioactive Diun (Month and Released in the Waste Release Concentration WatDttePitoiRlae Mtra gl)en Year) (Curies) Was>1 x 10- (Curies) ( .tCi ml-1) (%)(2)(gl

__________( 1iCi m1-')

Feray21 .61 4 C-30H349x0 H-3, 1.12x10-4 H-3, 4.97x10-7 H-,005943 Febuar

.1610-205 Co60H-3 4.7x1-7 Co-60, 4.27x10-6 Co-60, 1.90x10-5 Co-60, 0.06 June 2015 3.23x10-5 H-3 H-3, 3.23x10-s H-3, 3.23x10-8 H-3, 0.0003 264,172 Annual TotalH3,14x0 for Radiation 1.48x10"4 H-3, Co-60, 4.97x10-7 Co-3, 4.24x10-4 5.48x10_7 0.065 323,607 Center C-0 .71-(1) Tlhe 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.

Table V.3 Annual Summary of Liquid Waste Generated and Transferred Volume of Liquid Detectable Total Quantity of Daefo Wranster Pickup Origin of Liquid WsePackagedW) Radionuclides Radioactivity in the foTrnertth WseWaste Waste Processing (gallons) in the Waste Waste (Curies) Facility TRIGA Reactor 2H-3 8.16x10-4 7/18/14 Facility Radiaion CnterU-238 Raito etr8.75 Cs-134 2.54x10-7 7/18/14 Laboratories Ag-110m ________

TOTAL 10.75 See above 8.16x10-4 (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.

0 14-15 Annual Report

Table V.4 Montly TIGAReactor Gaseous Waste Discharges and Analysis EstiatedFraction of the Technical Total Total Atmospheric Diluted Specification MnhEstimated Estimated Quantity ot Concentration of Annual Average MnhActivity Argon-41 Argon-41 at Point of rgn4 Released (Curies) Released{') (Curies) Release Agn4 (ji~lcc)Concentration Limit (%)

July 1.27 1.27 1.02x10-7 2.55 August 2.12 2.12 1"69x10"7 4.23 September 1.56 1.56 1.29x10-7 3.23 October 1.77 1.77 1.41x10-7 3.54 November 1.15 1.15 949x10-s 2.37 December 1.54 1.54 1.23x10-7 3.08 January 1.33 1.33 1.07x10-7 2.67 February 1.51 1.51 1.34x10-1 3.34 March 1.97 1.97 1.58x10"7 3.95 April 2.75 2.75 2.27x10-7 5.67 May 1.71 1.71 1.37x10-7 3.41 June 2.14 2.14 1.77x10"7 4.43 TOTAL

('14-'15) 20.82 20.82 1.42x10"7 3.54 Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionu-(1) clide was argon-41.

(2) Annual Average.

14-15 Annual Report

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 O SU Solid Waste Packaged")1 in Solid Waste Waste Processing (Cubic Feet) inteWse(Curies) Facility TRIGA Co-60, Zn-65, Sc-46, Cr-51, Fe-59, 11/5/14 Reactor 23 Co-58, As-74, H-3, Mn-54, Sb-124, 5.19x10-3 Facility Eu-152, Se-75, Ga-72, Eu-154 6/28/15 Radiation P-3,A-4,S-5 u12 Center 53 Pu29,A -243,r85Eu52 3.21x10O4 6/26/15 LaboratoriesU-3 TOTAL 76 See Above 5.51x10-3 (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 14-15 Annual Report

Table V.6 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Total Person-mrem Dose"1* Dose") for the Group(1)

Pesonl rop Whole Body Extremities Whole Body Extremities Whole Body Extremities PronlGop (mrem) (mnrem) (mrem) (mtrem) (mrem) (mtrnm)

Facility Operating 93.63 237.25 210 942 749 1,898 Personnel Key Facility Research 2.46 30.11 32 46 32 271 Personnel Facilities Services Maintenance <1 N/A <1 N/A 1.11 N/A Personnel Laboratory Class 5.94 29.7 88 90 856 446 Students Campus Police and0N/0NA0NA Security Personnel Visitors <1 N/A 7.6 N/A 98.57 N/A Contractors 391.9 N/A 434.7 N/A 1,175.8 N/A (1) "N/A"indicates that there was no extremity monitoring conducted or required for the group.

14-15 Annual Report

Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total MntrTRIGA Reactor Reodd Dose Equivalent(1)(2)

I.D. Facility LocationX()Neto (See Figure V.1) (mrem) (meutro MRCTNE D104: North Badge East Wall 237 ND MRCTSE D104: South Badge East Wall 157 ND MRCTSW D104: South Badge West Wall 545 ND MRCTNW D104: North Badge West Wall 184 ND MRCTWN D104: West Badge North Wall 532 ND MRCTEN D104: East Badge North Wall 336 ND MRCTES D104: East Badge South Wall 1,701 ND MRCTWS D104: West Badge South Wall 481 ND MRCTTOP D104: Reactor Top Badge 1,177 ND MRCTHXS D104A: South Badge HX Room 567 ND MRCTHXW D104A: West Badge HX Room 312 ND MRCD-302 D302: Reactor Control Room 469 ND MRCD-302A D302A: Reactor Supervisor's Office 133 N/A MRCBP1 D104: Beam Port Number 1 402 ND MRCBP2 D104: Beam Port Number 2 262 ND MRCBP3 D104: Beam Port Number 3 684 ND MRCBP4 D104: Beam Port Number 4 872 ND (1) '-he 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) Tlhese dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.

0 14-15 Annual Report

Table V.8 Total Dose Equivalent Recorded on Area Dosimeters

___________Located Within the Radiation Center Total Recorded Monitor Radiation Center Dose Equivalent(1

  • I.D. Facility Location I..(See Figure V.1) Xf?,(y) Neutron

______________ ___________________________________________ (mrem) (mrem)

MRCA100 A100: Receptionist's Office 11 N/A MRCBRF A102H: Front Personnel Dosimetry Storage Rack 58 N/A MRCA120 A120: Stock Room 62 N/A MRCA120A A120A: NAA Temporary Storage 105 N/A MRCA126 A126: Radioisotope Research Laboratory 210 N/A 6

MRCCO-60 A128: °Co Irradiator Room 814 N/A MRCA130 A130: Shielded Exposure Room 84 N/A MRCA132 A132: TLD Equipment Room 59 N/A MRCA138 A138: Health Physics Laboratory 59 N/A MRCA146 A146: Gamma Analyzer Room (Storage Cave) 147 N/A MRCB 100 B 100: Gamma Analyzer Room (Storage Cave) 167 N/A MRCB114 B114: Lab (226Ra Storage Facility) 1,538 N/A MRCB119-1 B119: Source Storage Room 147 N/A MRCB119-2 B119: Source Storage Room 241 N/A MRCB119A B119A: Sealed Source Storage Room 6,818 2,611 MRCB120 B120: Instrument Calibration Facility 78 N/A MRCB122-2 B122: Radioisotope Hood 237 N/A MRCB122-3 B122: Radioisotope Research Laboratory 94 N/A MRCB124-1 B124: Radioisotope Research Laboratory (Hood) 62 N/A MRCB124-2 B124: Radioisotope Research Laboratory 47 N/A MRCB124-6 B124: Radioisotope Research Laboratory 50 N/A MRCB128 B128: Instrument Repair Shop 72 N/A MRCB136 B136 Gamma Analyzer Room 22 N/A MRCC100 C100: Radiation Center Director's Office 36 N/A (1) T'he 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.

14-15 Annual Report 0

Table V.8 cnnu)

Total Dose Equivalent Recorded on Area Dosimeters

__________Located Within the Radiation Center Total Recorded Monitor Radiation Center Dose Equivalent")

I.D. Facility Location (See Figure V.1) X1g(y ) Neutron (mrem) (mrem)

MRCC106A C106A: Office 57 N/A MRCC106B C106B: Custodian Supply Storage 57 N/A MRCC106-H C106H: East Loading Dock 53 N/A MRCC118 Gl18: Radiochemistry Laboratory 0 N/A MRCC120 0120: Student Counting Laboratory 20 N/A MRCF100 F100: APEX Facility 10 N/A MRCF102 F102: APEX Control Room 24 N/A MRCB125N B125: Gamma Analyzer Room (Storage Cave) 114 N/A MRCN125S B125: Gamma Analyzer Room 56 N/A MRCC 124 C 124: Classroom 56 N/A MRCC130 C130: Radioisotope Laboratory (Hood) 53 N/A MRCD100 Di00: Reactor Support Laboratory 69 N/A MRCD102 D102: Pneumatic Transfer Terminal Laboratory 204 ND MRCD102-H D102H: 1st Floor Corridor at D102 124 ND MRCD106-H D106H: 1st Floor Corridor at D106 333 N/A MRCD200 D200: Reactor Administrator's Office 185 ND MRCD202 D202: Senior Health Physicist's Office 264 ND MRCBRR D200H: Rear Personnel Dosimetry Storage Rack 80 N/A MRCD204 D204: Health Physicist Office 326 ND MRCATHRL F104: ATHRL 49 N/A MRCD300 D300: 3rd Floor Conference Room 153 ND MRCA144 A144: Radioisotope Research Laboratory 44 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.

14-15 Annual Report

Table V.9 Annual Summary of Radiation and Contamination Levels Observed Within the Reactor Facility and Radiation Center

.. .During Routine Radiation Surveys _________

Whole Body Contamination Accessible Location Radiation Levels Levels*')

(See Figure V.1) (mrem/hr) (dpm/cm 2)

Average Maximum Average Maximum TRIGA Reactor Facility:

Reactor Top (D104) 1.7 90 <500 5,577 Reactor 2nd Deck Area (D104) 6.8 42 <500 <500 Reactor Bay SW (D104) <1 25 <500 1,500 Reactor Bay NW (D104) <1 74 <500 49,808 Reactor Bay NE (D104) <1 23 <500 2,115 Reactor Bay SE (D104) <1 6 <500 1,731 Class Experiments (D104, D302) <1 <1 <500 <500 Demineralizer Tank & Make Up Water System <1 10 <500 <500 (D104A)_______

Particulate Filter--Outside Shielding (D104A) <1 4 <500 1,731 Radiation Center:

NAA Counting Rooms (A146, B 100) <1 2.3 <500 <500 Health Physics Laboratory (A138) <1 <1 <500 1,607 6°Co Irradiator Room and Calibration Rooms (A128, B120, A130) <1 4 <500 <500 Radiation Research Labs (A126, A136)<10<5050 (B108, B114, B122, B124, C126, C130, A144)<10<5050 Radioactive Source Storage (B 119, B119A, <1 12 <500 <500 A120A, A132A)

Student Chemistry Laboratory (C 118) <1 <1 <500 <500 Student Counting Laboratory (C120) <1 <1 <500 <500 Operations Counting Room (B136, B 125) <1 <1 <500 <500 Pneumatic Transfer Laboratory (D102) <1 1.5 <500 <500 RX support Room (D100) <1 <1 <500 <500 (1) <500 dpm/100 era2 =Less than the lower limit of detection for the portable survey instrument used.

14-15 Annual Report 0

Table V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence Fence Total Recorded Dose Equivalent Environmental Monitoring Station (Including Background)

(SeeFigre

.1)Based on Mirion TLDs*12)

(See______

Figure________V.1)______(mrem)

MRCFE-1 93+/- 2 MRCFE-2 88+/- 4 MRCFE-3 83 +/-2 MRCFE-4 92 +/- 3 MRCFE-5 94 +/-3 MRCFE-6 91 +/-3 MRCFE-7 90 +/-_3 MRCFE-8 95 +/-7 MRCFE-9 88 +/-6 (1) Average Corvallis area natural background using Mirion TLDs totals 86 -+/-10 mrem for the same period.

(2) _+/-values represent the standard deviation of the total value at the 95% confidence level.

14-15 Annual Report

OSo OreonStat Radiation Center Oregon State University, 100 Radiation Center, Corvallis, Oregon 97331-5903 T 541-737-2341 I F 541-737-0480 I http:llne.oregonstate.edulfacilitieslradiationcenter October 9, 2015 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Oregon State University TRIGA Reactor (OSTR)

Docket No. 50-243, License No. R-106 In accordance with section 6.7.1 of the OSTR Technical Specifications, we are hereby submitting the Oregon State University Radiation Center and OSTR Annual Report for the period July 1, 2014 through June 30, 2015.

The Annual Report continues the pattern established over many years by including information about the entire Radiation Center rather than concentrating primarily on the reactor. Because this report addresses a number of different interests, it is rather lengthy, but we have incorporated a short executive summary which highlights the Center's activities and accomplishments over the past year.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: /ic'// *

Sincerely, Director Cc: Michael Balazik, USNRC Dr. Cynthia Sagers, OSU Craig Bassett, USNRC Dr. Rich Holdren, OSU Ken Niles, ODOE Dr. Andy Klein, OSU AcgcJ

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3m Executive Summary Introduction The data from this reporting year shows that the use of the The current annual report of the Oregon State University Radiation Center and the Oregon State TRIGA reactor Radiation Center and TRIGA Reactor follows the usual for-(OSTR) has continued to grow in many areas. mat by including information relating to the entire Radiation Center rather than just the reactor. However, the information The Radiation Center supported 69 different courses this year, is still presented in such a manner that data on the reactor may mostly in the Department of Nuclear Engineering and Radia-be examined separately, if desired. It should be noted that all tion Health Physics. About 30% of these courses involved the annual data given in this report covers the period from July 1, OSTR. T-he number of OSTR hours used for academic courses 2014 through June 30, 2015. Cumulative reactor operating data and training was 43, while 2,541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br /> were used for research in this report relates only to the LEU fueled core. This covers projects. Sixty-three percent (63%) of the OSTR research the period beginning July 1, 2008 to the present date. For a hours were in support of off-campus research projects, reflect-summary of data on the reactor's two other cores, the reader is ing the use of the OSTR nationally and internationally. Radia-referred to previous annual reports.

tion Center users published or submitted 46 articles this year, and made 64 presentations on work that involved the OSTR In addition to providing general information about the activi-or Radiation Center. T-he number of samples irradiated in the ties of the Radiation Center, this report is designed to meet reactor during this reporting period was 992. Funded OSTR the reporting requirements of the U. S. Nuclear Regulatory use hours comprised 96% of the research use. Commission, the U. S. Department of Energy, and the Oregon Department of Energy. Because of this, the report is divided Personnel at the Radiation Center conducted 99 tours of the into several distinct parts so that the reader may easily find the facility, accommodating 1,555 visitors. T'he visitors included sections of interest.

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 Overview of the Radiation Center is a significant positive attraction on campus because visitors The Radiation Center is a unique facility which serves the leave with a good impression of the facility and of Oregon entire OSU campus, all other institutions within the Oregon State University. University System, and many other universities and organiza-The Radiation Center projects database continues to provide tions throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, a usefuil way of tracking the many different aspects of work at the facility. T-he number of projects supported this year was particularly agencies dealing with law enforcement, energy, 123. Reactor related projects comprised 74% of all projects. The health, and environmental quality, and renders assistance to total research dollars in some way supported by the Radiation Oregon industry. In addition, the Radiation Center provides Center, as reported by our researchers, was $11 million. The ac- permanent office and laboratory space for the OSU Depart-tual total is likely considerably higher. T'his year the Radiation ment of Nuclear Engineering and Radiation Health Physics, Center provided service to 50 different organizations/institu- the OSU Institute of Nuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, geochem-tions, 40% of which were from other states and 44% of which were from outside the U. S. and Canada. So while the Center's istry and radiochemistry programs. There is no other university primary mission is local, it is also a facility with a national and facility with the combined capabilities of the OSU Radiation international clientele. Center in the western half of the United States.

The Radiation Center web site provides an easy way for Located in the Radiation Center are many items of special-potential users to evaluate the Center's facilities and capabili- ized equipment and unique teaching and research facilities.

ties as well as to apply for a project and check use charges. The address is: http://radiationcenter.oregonstate.edu.d 14-15 Annual Report

They 6

include a TRIGA Mark II research nuclear reactor; a Over 7 international organizations are involved in this stan-

°Co gamma irradiator; a large number of state-of-the art dard problem at OSU.

computer-based gamma radiation spectrometers and associ-ated germanium detectors; and a variety of instruments for T'he Advanced Nuclear Systems Engineering Laboratory radiation measurements and monitoring. Specialized facilities (ANSEL) is the home to two major thermal-hydraulic test fa-for radiation work include teaching and research laboratories cilities-the High Temperature Test Facility (HTTF) and the with instrumentation and related equipment for performing Hydro-mechanical Fuel Test Facility (HMFTF). The HTTF neutron activation analysis and radiotracer studies; laborato- is a 1/4 scale model of the Modular High Temperature Gas ries for plant experiments involving radioactivity; a facility Reactor. The vessel has a ceramic lined upper head and for repair and calibration of radiation protection instrumen- shroud capable of operation at 850oC (well mixed helium).

tation; and facilities for packaging radioactive materials for TIhe design will allow for a maximum operating pressure of shipment to national and international destinations. 1.0MPa and a maximum core ceramic temperature of 1600°C.

The nominal working fluid will be helium with a core power A major non-nuclear facility housed in the Radiation Center of approximately 600 kW (note that electrical heaters are used is the one-quarter scale thermal hydraulic advanced plant ex- to simulate the core power). The test facility also includes a perimental (APEX) test facility for the Westinghouse AP600 scaled reactor cavity cooling system, a circulator and a heat and AP1000 reactor designs. The AP600 and AP1000 are sink in order to complete the cycle. The HTTF can be used next-generation nuclear reactor designs which incorporate to simulate a wide range of accident scenarios in gas reac-many passive safety features as well as considerably simplified tors to include the depressurized conduction cooldown and plant systems and equipment. APEX operates at pressures pressurized conduction cooldown events. The HMFTF is a up to 400 psia and temperatures up to 450 0 F using electrical testing facility which will be used to produce a database of heaters instead of nuclear fuel. All major components of the hydro-mechanical information to supplement the qualifica-AP600 and AP1000 are included in APEX and all systems tion of the prototypic ultrahigh density U-Mo Low Enriched are appropriately scaled to enable the experimental measure- Uranium fuel which will be implemented into the U.S. High ments to be used for safety evaluations and licensing of the Performance Research Reactors upon their conversion to low full scale plant. Tlhis world-class facility meets exacting qual- enriched fuel. This data in turn will be used to verify current ity assurance criteria to provide assurance of safety as well as theoretical hydro- and thermo- mechanical codes being used validity of the test results. during safety analyses. The maximum operational pressure of the HMFTF is 600 psig with a maximum operational Also housed in the Radiation Center is the Advanced Ther-temperature of 450°F.

mal Hydraulics Research Laboratory (ATHRL), which is used for state-of-the-art two-phase flow experiments. Tlhe Radiation Center staff regularly provides direct sup-port and assistance to OSU teaching and research programs.

The Multi-Application Light Water Reactor (MASLWR) is Areas of expertise commonly involved in such efforts include a nuclear power plant test facility that is instrumental in the nuclear engineering, nuclear and radiation chemistry, neutron development of next generation commercial nuclear reac-activation analysis, radiation effects on biological systems, ra-tors currently seeking NRC certification. The Test Facility is diation dosimetry, environmental radioactivity, production of constructed of all stainless steel components and is capable of short-lived radioisotopes, radiation shielding, nuclear instru-operation at full system pressure (1500 psia), and full system mentation, emergency response, transportation of radioactive temperature (600F).

materials, instrument calibration, radiation health physics, All components are 1/3 scale height and 1/2 54.7 volume radioactive waste disposal, and other related areas.

scale. The current testing program is examining methods In addition to formal academic and research support, the for natural circulation startup, helical steam generator heat Center's staff provides a wide variety of other services includ-transfer performance, and a wide range of design basis, and ing public tours and instructional programs, and professional beyond design basis, accident conditions. In addition, the consultation associated with the feasibility, design, safety, MASLWR Test Facility is currently the focus of an interna-and execution of experiments using radiation and radioactive tional collaborative standard problem exploring the operation materials.

and safety of advanced natural circulations reactor concepts.

14-15 Annual Report

This 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 VI.1, while individual names and projects are listed in Table VJ.2.

Radiation Center Staff Reactor Operations Committee Steve Reese, Director Andrewv Klein, Chair Dina Pope, Office Manager OSU Nuclear Engineering and Radiation Health Physics Shaun Bromagem, Business Manager Dan Harlan Brittany Combs, Receptionist OSU Radiation Safety S. Todd Keller, Reactor Administrator Abi Tavakoli Farsoni OSU Nuclear Engineering and Radiation Health Physics Gary Wachs, Reactor Supervisor, Senior Reactor Operator S. Todd Keller Robert Schickler, Reactor Engineer, OSU Radiation Center Senior Reactor Operator Wade marcum, Senior Reactor Operator Scott Menn OSU Radiation Center ScottmA'enn, Senior Health Physicist Steve Reese (not voting)

JTim Darrough, Health Physicist OSU Radiation Center Leak minc, Neutron Activation Analysis Manager Mark Trump Steve Smith, Development Engineer, Penn State University Senior Reactor Operator Gary Wachs (not voting)

Celia Oney, Reactor Operator OSU Radiation Center Erin Cimbri, Custodian Julie Tucker Jarvis Ca]ffrey, Reactor Operator (Student)

OSU Mechanical, Industrial and Manufacturing Engineering Joshua Graves, Reactor Operator (Student)

Trevor Howoard, Reactor Operator (Student)

Griffen L atimer, Reactor Operator (Student)

Top her Matthews, Reactor Operator (Student)

Joey DeShields, Health Physics Monitor (Student)

Shara Howoard, Health Physics Monitor (Student)

Kien Tran, Health Physics Monitor (Student)

Sophia Uchiyama, Health Physics Monitor (Student) 14-15 Annual Report

Professional and Research Faculty Farsoni,A bi *Palmer,Todd S.

Professional andEngineering Associate Professor, Nuclear Research Faculty

& Radiation Health Professor, Nuclear Engineering and Radiation Health Physics Physics *Paulenova, Alena John DeNoma Associate Professor, Nuclear Engineering and Radiation Health Research Assistant Physics

  • Hamby, David Pope, Dina Professor, Nuclear Engineering and Radiation Health Physics Office Manager, Radiation Center Hart, Lucas P. *Reese, Steven R.

Faculty Research Associate, Chemistry Director, Radiation Center

  • Higley, Kathryn A. Reyes, Jr., Jos N.

Department Head, Professor, Nuclear Engineering and Professor, Nuclear Engineering and Radiation Health Physics Radiation Health Physics Tack, Krystina

  • Keller, S. Todd Assistant Professor, Medical Physics Program Director Reactor Administrator, Radiation Center *Wachs, Gary Klein, Andrew C. Reactor Supervisor, Radiation Center Professor, Nuclear Engineering and Radiation Health Physics Aaron Weiss
  • Krane, Kenneth S. Faculty Research Assistant Professor Emeritus, Physics Woods, Brian
  • Loveland, Walter D. Professor, Nuclear Engineering and Radiation Health Physics Professor, Chemistry Wu, Qiao Marcum, Wade Professor, Nuclear Engineer and Radiation Health Physics Assistant Professor Nuclear Engineering and Radiation Yanez, Rica rdo Health Physics Faculty Research Associate, Chemistry
  • Mlenn, ScottA.

Yang, Haori Senior Health Physicist, Radiation Center Assistant Professor, Nuclear Engineering and Radiation Health

  • Minc, Leah Physics Associate Professor, Anthropology *OSTR usersfor research and/or teaching Cam ille Palmer Research Faculty and Instructor 14-15 Annual Report 0

a Research Reactor The Oregon State University TRIGA Reactor (OSTR) is a Consequently this facility is normally used for neutron activa-water-cooled, swimming pool type research reactor which uses tion analysis involving short-lived radionucides. On the other uranium/zirconium hydride friel elements in a circular grid ar- hand, the rotating rack is used for much longer irradiation of ray. The reactor core is surrounded by a ring of graphite which samples (e.g., hours).The rack consists of a circular array of 40 serves to reflect neutrons back into the core. The core is situ- tubular positions, each of which can hold two sample tubes.

ated near the bottom of a 22-foot deep water-filled tank, and Rotation of the rack ensures that each sample will receive an the tank is surrounded by a concrete bioshield which acts as a identical irradiation.

radiation shield and structural support. The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at The reactor's thermal column consists of a large stack of a maximum steady state power of 1.1 1VPN and can also be graphite blocks which slows down neutrons from the reactor pulsed up to a peak power of about 2500 MW. core in order to increase thermal neutron activation of samples.

Over 99% of the neutrons in the thermal column are thermal The OSTR has a number of different irradiation facilities neutrons. Graphite blocks are removed from the thermal col-including a pneumatic transfer tube, a rotating rack, a thermal umn to enable samples to be positioned inside for irradiation.

column, four beam ports, five sample holding (dummy) fuel elements for special in-core irradiations, an in-core irradiation The beam ports are tubular penetrations in the reactor's main tube, and a cadmium-lined in-core irradiation tube for experi- concrete shield which enable neutron and gamma radiation to ments requiring a high energy neutron flux. stream from the core when a beam port's shield plugs are re-moved. The neutron radiography facility utilized the tangential The pneumatic transfer facility enables samples to be beam port (beam port #3) to produce ASTM E545 category I inserted and removed from the core in four to five seconds. radiography capability. The other beam ports are available for a variety of experiments.

0 14-15 Annual Report

If samples to be irradiated require a large neutron fluence, Research especially from higher energy neutrons, they may be inserted The OSTR is a unique and valuable tool for a wide variety into a dummy fuel element. This device will then be placed of research applications and serves as an excellent source of into one of the core's inner grid positions which would nor- neutrons and/or gamma radiation. The most commonly used meally be occupied by a fuel element. Similarly samples can b e experimental technique requiring reactor use is instrumental placed in the in-core irradiation tube (ICIT) which can be neutron activation analysis (INAA). This is a particularly inserted in the same core location. sensitive method of elemental analysis which is described in more detail in Part VI.

The cadmium-lined in-core irradiation tube (CLICIT) enables samples to be irradiated in a high flux region near th, e The OSTR's irradiation facilities provide a wide range of center of the core. The cadmium lining in the facility elimi- neutron flux levels and neutron flux qualities which are suf-nates thermal neutrons and thus permits sample exposure to ficient to meet the needs of most researchers. This is true not higher energy neutrons only. The cadmium-lined end of this only for INAA, but also for other experimental purposes such air-filled aluminum irradiation tube is inserted into an inner as the 3 9 Ar/4 0 Ar ratio and fission track methods of age dat-grid position of the reactor core which would normally be o - ing samples.

cupied by a fuel element. It is the same as the ICIT except fo the presence of the cadmium lining.

The two main uses of the OSTR are instruction and research

  • Analytical Equipment The Radiation Center has a large variety of radiation detec-Instruction tion instrumentation. This equipment is upgraded as nec-Instructional use of the reactor is twofold. First, it is used essary, especially the gamma ray spectrometers with their significantly for classes in Nuclear Engineering, Radiation associated computers and germanium detectors. Additional Health Physics, and Chemistry at both the graduate and un-equipment for classroom use and an extensive inventory of dergraduate levels to demonstrate numerous principles whicf portable radiation detection instrumentation are also avail-have been presented in the classroom. Basic neutron behavioi r able.

is the same in small reactors as it is in large power reactors, and many demonstrations and instructional experiments can Radiation Center nuclear instrumentation receives intensive be performed using the OSTR which cannot be carried out use in both teaching and research applications. In addition, with a commercial power reactor. Shorter-term demonstratic *n service projects also use these systems and the combined use experiments are also performed for many undergraduate stu- often results in 24-hour per day schedules for many of the dents in Physics, Chemistry, and Biology classes, as well as fc)r analytical instruments. Use of Radiation Center equipment visitors from other universities and colleges, from high schoo ls, extends beyond that located at the Center and instrumenta-and from public groups. tion may be made available on a loan basis to OSU research-ers in other departments.

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 Radioisotope Irradiation Sources an operating reactor and in associated laboratories. The many ¢ The Radiation Center is equipped with a 1,644 curie (as of types of educational programs that the Radiation Center pro - 7/27/01) Gammacell1220 60Co irradiator which is capable vides are more fully described in Part VI of this report. of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.

During this reporting period the OSTR accommodated a number of different OSU academic classes and other acaderwiic Typically, the irradiator is used by researchers wishing to programs. In addition, portions of classes from other Oregon S perform mutation and other biological effects studies; studies universities were also supported by the OSTR. 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 14-15 Annual Report 0

other such applications. In addition to the 60Co irradiator, the All of the laboratories and classrooms are used extensively dur-Center is also equipped with a variety of smaller 6°Co, 137Cs, ing the academic year. A listing of courses accommodated at 226 the Radiation Center during this reporting period along with Ra, plutonium-beryllium, and other isotopic sealed sources of various radioactivity levels which are available for use as their enrollments is given in Table 111.2.

irradiation sources. Instrument Repair & Calibration During this reporting period there was a diverse group of Facility projects using the 6°Co irradiator. Tlhese projects included the The Radiation Center has a facility for the repair and calibra-irradiation of a variety of biological materials including differ- tion of essentially all types of radiation monitoring instru-ent types of seeds. mentation. This includes instruments for the detection and measurement of alpha, beta, gamma, and neutron radiation.

In addition, the irradiator was used for sterilization of several It encompasses both high range instruments for measuring media and the evaluation of the radiation effects on different intense radiation fields and low range instruments used to materials. Table 111.1 provides use data for the Gammacell measure environmental levels of radioactivity.

220 irradiator.

The Center's instrument repair and calibration facility is used regularly throughout the year and is absolutely essential to the Laboratories and Classrooms continued operation of the many different programs carried out at the Center. In addition, the absence of any comparable TIhe Radiation Center is equipped with a number of different facility in the state has led to a greatly expanded instrument radioactive material laboratories designed to accommodate calibration program for the Center, including calibration of research projects and classes offered by various OSU academic essentially all radiation detection instruments used by state and departments or off-campus groups. federal agencies in the state of Oregon. This includes instru-ments used on the OSU campus and all other institutions Instructional facilities available at the Center include a labo- in the Oregon University System, plus instruments from the ratory especially equipped for teaching radiochemistry and a Oregon Health Division's Radiation Protection Services, the nuclear instrumentation teaching laboratory equipped with Oregon Department of Energy, the Oregon Public Utilities modular sets of counting equipment which can be configured Commission, the Oregon Health and Sciences University, to accommodate a variety of experiments involving the mea- the Army Corps of Engineers, and the U. S. Environmental surement of many types of radiation. The Center also has two Protection Agency.

student computer rooms.

In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equip- Library ment are regularly used for teaching. In particular, classes are The Radiation Center has a library containing a significant routinely given access to gamma spectrometry equipment collections of texts, research reports, and videotapes relating to located in Center laboratories. A number of classes also regu- nuclear science, nuclear engineering, and radiation protection.

larly use the OSTR and the Reactor Bay as an integral part of their instructional coursework. The Radiation Center is also a regular recipient of a great vari-ety of publications from commercial publishers in the nuclear T]here are two classrooms in the Radiation Center which are field, from many of the professional nuclear societies, from capable of holding about 35 and 18 students. In addition, the U. S. Department of Energy, the U. S. Nuclear Regulatory Commission, and other federal agencies. Therefore, the Center there are two smaller conference rooms and a library suitable library maintains a current collection of leading nuclear re-for graduate classes and thesis examinations. As a service to search and regulatory documentation. In addition, the Center the student body, the Radiation Center also provides an office has a collection of a number of nuclear power reactor Safety area for the student chapters of the American Nuclear Society Analysis Reports and Environmental Reports specifically and the Health Physics Society. prepared by utilities for their facilities.

S14-15 Annual Rpr

T'he Center maintains an up-to-date set of reports from such radiological emergency response topics. In addition, the organizations as the International Commission on Radiologi- Radiation Center uses videotapes for most of the technical cal Protection, the National Council on Radiation Protection orientations which are required for personnel working with and Measurements, and the International Commission on radiation and radioactive materials. TIhese tapes are repro-Radiological Units. Sets of the current U.S. Code of Federal duced, recorded, and edited by Radiation Center staff, using Regulations for the U.S. Nuclear Regulatory Commission, the Center's videotape equipment and the facilities of the the U.S. Department of Transportation, and other appropriate OSU Communication Media Center.

federal agencies, plus regulations of various state regulatory agencies are also available at the Center. The Radiation Center library is used mainly to provide ref-erence material on an as-needed basis. It receives extensive T-he Radiation Center videotape library has over one hun- use during the academic year. In addition, the orientation dred tapes on nuclear engineering, radiation protection, and videotapes are used intensively during the beginning of each term and periodically thereafter.

Table II1.1 Gammacel1 220 *°Co IrradiatorUse Purpose ofIrdain ofIrdito SmlsDose Smls(rads) Range Number of Irradiations Use Time (hours)

Sterilization wood, dill pollen, 2.0x10 6 to 2.5x10 6 81200 chitosan Material Evaluation silicon polymers 3.0x10 5 to 3.0x10 5 113 Botanical Studies seeds, barley 1.0x10 3 to 1.6x10 4 143 BilgclSuisfibronectic, zebra fish, 5.0x10 2 to 2.5x10 6 37 109 Biolgica Stuiesmice Totals 60 1325 14-15 Annual Report 0

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 2014 2014 2015 2015 NE/RHP 114* 2 Introduction to Nuclear Engineering and Radiation 69 Health Physics ___

NE/RHP 115 2 Introduction to Nuclear Engineering and Radiation 62 Health Physics ___

NE!/RI-P 234 4 Nuclear and Radiation Physics I ____ 66 NE!/RHP 235 4 Nuclear and Radiation Physics II 59 ____

NE!/RHP 236* 4 Nuclear Radiation Detection & Instrumentation 49 NE 311 4 Intro to T'hermal Fluids 3 38 25 NE 312 4 T'hermodynamics 29 20 NE 319 3 Societal Aspects of Nuclear technology ____ 76 NE 331 4 Intro to Fluid Mechanics 21 24 NE 332 4 Heat Transfer 11 6 18 NE/RHP 333 3 Mathematical methods for NE/RHP _ __68 N/IPMP1-16 Research 4 20 17 18 401/501/601 NE/HPMP1-16 Reading and Conference2 405/505/605 NE/HPMP1-16 Projects 406/506/606 NE/RHP/MP 407/507/607 1 Nuclear Engineering Seminar 77 79 72 NE/ RI-P/MP 4050601-12 Internship 2 4 5 6 NE!/RHP 415/515 2 Nuclear Rules and Regulations 46 ___

NE 45 1/551 4 Neutronic Analysis ____ 38 ___

NE 452/552 4 Neutronic Analysis 36 NE 455/555"* 3 Reactor Operator Training I NE 456/556"* 3 Reactor Operator Training II3 NE 457/557"* ~ 3 tNeuclear Reactor Lab 34 NE 467/567 4 Nuclear Reactor T'hermal Hydraulics 29 ___

NE 667 4 Nuclear Reactor T'hermal Hydraulics ___ ______

NE/RHP 435/535 3 Extemnal Dosimetry & Radiation Shielding 56 NE 565 3 Applied Thermal Hydraulics9 ___

NE 473/573 3 Nuclear Reactor Systems Analysis 16 ___

14-15 Annual Report

Table 111.2 (continued)

Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Number of Students Course # CREDIT COURSE TITLESumr Fl Witr pin 2014 2014 2015 2015 NE/RHP 474/574 4 Nuclear System Design I 36 NE/RHP 475/575 4 Nuclear System Design II 37 NE/RHP 479* 1-4 Individual Design Project NE/RHP 481*" Radiation Protection 53 NE/RHP 582* 4 Applied Radiation Safety 10 RHP 483/583 4 Radiation Biology 16 RHP 488/588*" Radioecology 14 NE/RHP 590 4 Internal Dosimetry 3 NE/RI-P/MP 503/603* 1 Thesis 18 38 35 56 NE!/RHP 516* 4 Radiochemistry 6 NE 526 3 Numerical Methods for Engineering Analysis NE/RHP/MP 531 3 Nuclear Physics for Engineers and Scientists 28 NE/RHP/MP 536* 3 Advanced Radiation Detection & Measurement 26 NE/RHP 537 3 Digital Spectrometer Design 4 MP 541 3 Diagnostic Imaging Physics____

NE 550 3 Nuclear Medicine NE 553 3 Advanced Nuclear Reactor Physics ____ ____ 13 MP 563 4 Applied Medical Physics 4 ___

NE 468/568 3 Nuclear Reactor Safety ____ ____ 13 ___

NE/RHP/MP 599 _____Special Topics 20 27 5 11 Course From Other OSU Departments CH 233* 5 General Chemistry 111 _ ______ 711 CH 233H* 5 Honors General Chemistry _ __________ 28 CH____462* ___ __3_ Experimental Chemistry II Laboratory ________ 8______

ENGR 111" 3 Engineering Orientation 248 224 143 ENGR 212H* 3 Honors Engineering ____ ____4 ST Special Topics

  • OSTR used occasionallyfor demonstration and/or experiments
    • OSTR used heavily 14-15 Annual Report

B Operating Status Inactive Experiments During the operating period between July 1, 2014 and June Presently 33 experiments are in the inactive file. This 30,2015, the reactor produced 1403 M'WH of thermal power consists of experiments which have been performed in during its 1512 critical hours. 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 Experiments Performed identifies these inactive experiments.

During the current reporting period there were ten ap- A-2 Measurement of Reactor Power Level via Mn proved reactor experiments available for use in reactor- Activation.

related programs. They are: A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack.

A-i Normal TRIGA Operation (No Sample Irradia-tion). A-4 Neutron Flux Measurements in TRIGA.

A-S Copper Wire Irradiation.

B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities. A-6 In-core Irradiation of LiF Crystals.

A-7 Investigation ofTRIGA~s Reactor Bath Water B-li Irradiation of Materials Involving Specific Temperature Coefficient and High Power Level Quantities of Uranium and Thorium in the Power Fluctuation.

Standard OSTR Irradiation Facilities.

B-i Activation Analysis of Stone Meteorites, Other B-12 Exploratory Experiments. Meteorites, and Terrestrial Rocks.

B-23 Studies Using TRIGA Thermal Column. B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column.

B-29 Reactivity Worth of Fuel.

B-4 Flux Mapping.

B-3i TRIGA Flux Mapping. B-5 In-core Irradiation of Foils for Neutron Spectral Measurements.

B-33 Irradiation of Combustible Liquids in Rotating Rack. B-6 Measurements of Neutron Spectra in External Irradiation Facilities.

B-34 Irradiation of Enriched Uranium in the Neutron B-7 Measurements of Gamma Doses in External Ir-Radiography Facility.

radiation Facilities.

B-35 Irradiation of Fissile Materials in the Prompt B-S Isotope Production.

Gamma Neutron Activation Analysis (PGNAA)

B-9 Neutron Radiography.

Facility.

B-10 Neutron Diffraction.

B-13 T'his experiment number was changed to A-7.

Of these available experiments, four were used during the reporting period. Table IV.4 provides information B-14 Detection of Chemically Bound Neutrons.

related to the frequency of use and the general purpose B-15 T'his experiment number was changed to C-i.

of their use.

B-16 Production and Preparation of 15F.

B-17 Fission Fragment Gamma Ray Angular Cor- There were six new screens performed in support of the relations. reactor this year. They were:

B-18 A Study of Delayed Status (n, 'y) Produced 14-04, Pneumatic Rabbit System Modification Nuclei.

Description B-19 Instrument Timing via Light Triggering.

Modifies the pneumatic transfer system to allow B-20 Sinusoidal Pile Oscillator. samples to be cycled repeatedly between the reactor and B-21 a detector in the bay.

Beam Port #3 Neutron Radiography Facility.

B-22 Water Flow Measurements Through TRIGA Core. 14-05, Reactor Bay East Wall Penetrations B-24 General Neutron Radiography. Description B-25 Neutron Flux Monitors. Allows a hole to be drilled in the Reactor Bay east wall B-26 Fast Neutron Spectrum Generator. to accommodate a 1.0 inch conduit carrying electrical cables to the APEX facility.

B-27 Neutron Flux Determination Adjacent to the OSTR Core.

14-06, Damper Control Modification B-28 Gamma Scan of Sodium (TED) Capsule.

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

Removes pressure regulators from several hoods and B-32 Argon Production Facility ventilation systems in the Reactor Building and modi-C-1 PuO 2 Transient Experiment. fies the associated isolation dampers so that they will no longer close.

15-01, Modification of CAM Flow Monitoring Unplanned Shutdowns There were seven unplanned reactor shutdowns during Description the current reporting period. Table IV.5 details these Replaces the current air flow sensors on the reactor events. top and stack continuous air monitors with Magnahe-lic flow sensors, which are positioned closer to the air sampling point and farther from the pump. Tlhis change Changes Pursuant tolO0 CFR 50-59 provides local flow indication and makes flow measure-ment and control more reliable.

There was one safety evaluation performed in support of the reactor this year. It was:

15-02, Heat Exchanger Room Wall Penetrations 15-01, New Procedure: OSTROP 31, "Scanning Description Documents for Permanent Archival Storage and Retrieval" Allows two 1.5 inch diameter holes to be drilled in the Heat Exchanger Room (south and east walls) to accom-Description modate a 1.25 inch conduit carrying electrical cables to This new procedure provides instructions for creating support an upgrade to the loads supplied by the emer-electronic versions of reactor related documents and gency diesel generator.

transferring the original paper records to the OSU Val-ley Library for long-term storage.

14-15 Annual Report

15-03, Changes to OSTROP 26 - Replaced the internal power supply on the CAM particulate channel monitor.

Description Updates to Background Investigation Procedures: Work December 2014 history checks now cover the last 7 years, and finger-printing and FBI background check are repeated every - Replaced the demineralizer inlet and outlet piping 10 years. Also adds information about Export Control, and the demineralizer pump.

rights under Fair Credit Reporting Act, and access to Safeguards Information and Category 1 or 2 quantities February 2015 of radioactive material.

- Changed demineralizer resin. Also replaced the resin retention elements in the demineralizer tank. T-he bottom one had failed, which was discovered during Surveillance and Maintenance the resin change.

Non-Routine Maintenance March 2015 July2014 - Added new flow orifice and Magnahelic gauge to the stack monitor and CAM.

-Lubricated rotating rack drive mechanism to elimi-nate binding. - Drilled two 1.5" holes in the heat exchanger room walls (see 50.59 15-02) to be used for conduits for

-Began modifications on pneumatic transfer system to the emergency power distribution system.

allow repeated cycling of a sample into and out of the reactor, with an analyzer in the reactor bay. - Upgraded emergency power distribution system to provide backup to some lights and equipment in the Radiation Center.

August 2014

-Completed pneumatic transfer system modifications.

April 2015 September 2014 - Replaced the reactor bay supply fan heating coil.

-Replaced Safety Channel high voltage and signal - Constructed a new antimony storage cave.

connectors.

June 2015 October 2014 - Replaced a relay and a filter capacitor in the console

-Removed control dampers for 4th floor hood exhaust left-hand drawer.

filters.

-Replaced a deck on the console reset switch.

-Replaced the Regulating Rod magnet and cleaned the base tube. Rust had accumulated due to conden-sation.

-Facilities Services repaired the cooling tower south fan and fan shaft.

November 2014

-Repaired an internal short in the stack monitor pump motor.

0 14-15 Annual Report

~~~Ta l IV:,J1...

Present OSTR Operating Statistics _________

Oprtinl o LUCoeAnnual aa Values Cumulative Values Opertioal or EU ore(2014/2015) ata MW\H of energy produced 1,403 8,662 MWND of energy produced 58 351.8 235 Grams U used 80 496 Number of fuel elements added to (+) or removed(-) from 0 90 the core Number of pulses 24 226 Hours reactor critical 1,512 9,347 Hours at fulil power (1 MW) 1,399 8,631 Number of startup and shutdown checks 249 1,432 Number of irradiation requests processed 189 1,546 Number of samples irradiated 992 11,790 14-15 Annual Report

~Table IV.2 OSTR Use Time in Terms of Specific Use Categories OSTR Use Category (hours) (hours)

Teaching (departmental and others) 36 13,672 OSU research 414 18,784 Off campus research 2,127 45,023 Demonstrations 7 45 Reactor preclude time 767 33,075 Facility time 39 7,261 Total Reactor Use Time 3,390 117,860 Table IV.3 OSTR Multiple Use Time__________

Cumulative Values Number of Users Annual Values (hours) (hours)

Two 491 9,380 TIhree 208 4,868 Four 56 2,644 Five 15 941 Six 0 241 Seven 0 69 Eight 0 3 Total Multiple Use Time 770 18,146 0 14-15 Annual Report

Table IV.4

___________ Use of OSTR Reactor Experiments ______

ENumbert Research Teaching Facility Use Total A-i 0 3 1 4 B-3 164 14 4 182 B-13 0 0 2 2 B-31 0 0 1 1 Total 164 17 8 189 Table IV.5 Unplanned Reactor Shutdowns and Scrams Typeof EentNumber of Typeof EentOccurrences Cause of Event Mannual 2 Dropped Reg rod Mannual 1 Dropped Safety rod Manual 1 CAM Particulate high activity Safety channel high power 2 Power fluctuations while stabilizing during startup Automatic - no annunciator 1 Unknown mechanical issue 14-15 Annual Report 0I

Figure IV.1 Monthly Surveillance and Maintenance (Sample Form)

OSTROP 13, Rev. LEU-4 Surveillance & Maintenance for the Month of__________________

I SURVEILLANCE & MAINTENANCE

[SHADE INDICATES LICENSE REQUIREMENT]

LIMITS AS FOUND TARGET DATE NOT TO BE EXEDD*COMPLETED DATE DT EAK IIIL HIGH: INCHES 1 REACTOR TANK HIGH AND LOW WATERMAIU LEVEL ALARMS MOVEMENT LOW: INCHnES

+ 3 INCHES AN:_ _ _ _ ______ _ _ _ _ _ _____

2 BULK WATER TEMPERATURE ALARM CHECK FUNCTIONAL Tested @.___

8.500O'+ Ann.? _cpm _Ann.

3B CHANNEL TEST OF STACK CAM PARTICULATE 8.5x10_+

3B CHANNEL 8500 cpm Ann.? _cpm Ann.

3C CHANNEL PARTICULATE TEST OF REACTOR TOP CAM CHANNEL 8.5xlO+/-

8500 cpm n.?

Ann.?_

__pm_

Ann.____ ______ ____

MEASUREMENT OF REACTOR PRIMARY 4__ WATER CONDUCTIVITY <5 *.tmho\cm MIN: 5N/

5 PRIMARY WATER pH MEASUREMENT MAX: 9N/

6 BULK SHIELD TANK WATER pH MIN: 5 N/A MEASUREMENT MAX: 9 7 CHANGE LAZY SUSAN FILTER CHANGED N/A 8 REACTOR TOP CAM OIL LEVEL CHECK OSTROP 13.8 NEED OIL?___ N/A 9 STACK CAM OIL LEVEL CHECK OSTROP 13.9 NEED OIL?___ N/A 10 PRIMARY PUMP BEARING OIL LEVEL CHECK OSTROP 13.10 NEED OIL?__ N/A 11 EMERGENCY DIESEL GENERATOR CHECKS >5% Olo?~jjjjjj~N/A Total hours _ _ _ _ _ _ _ _ _ _ _ _

12 RABBIT SYSTEM RUN TIME Total hours N/A 13 OIL TRANSIENT ROD BRONZE BEARING WD 40 N/A 14 COLBALT SOURCE PRESENT IN A128 SOURCE PRESENT? N/A 15 WATER MONITOR CHECK RCHPP 8 App. F.4 N/A

  • Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last month plus six weeks.

Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)

OSTROP 14, Rev. LEU-2 Surveillance & Maintenance for the 1st / 2nd / 3 rd / 4th Quarter of 20 SURVEILLANCE & MAINTENANCE I LMT ASFUD1TARGET IDATE NOT TO I DATE IREMARKS &

[SHADE INDICATES LICENSE REQUIREMENT] jDATE jBE EXCEEDED* jCOMPLETED INITIALS I REACTOR OPERATION COMMITT7EE (ROC) AUDIT QUARTERLY _____ ______

2 QUARTERLY ROC MEETING QUARTERLY 3 ERP INSPECTIONS QUARTERLY 4 ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 5 WATER MONITOR ALARM CHECK FUNCTIONAL 6A CHECK FILTER TAPE SPEED ON STACK MONITOR I"/HR + 0.2 6B CHECK FILTER TAPE SPEED ON CAM MONITOR I"/HR + 0.2 7 INCORPORATE 50.59 & ROCAS INTO DOCUMENTATION QUARTERLY ARM SYSTEM ALARM CHECKS ARM I 2 3S3E4 5 78 9 10 1112 AUD 8 FUNCTIONAL LIGHT PANEL ANN

  • Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last quarter plus four months.

Figure IV.2 (continued)

Quarterly Surveillance and Maintenance (Sample Form)

OSTROP 14, Rev. LEU-2 Surveillance & Maintenance for the Is / 2 nd / 3 rd / 4 th Quarter of 20 SURVEILLANCE & MAINTENANCE

[SHADE INDICATES LICENSE REQUIREMENT]

1 LMTASFUD j__________

1DATE COMPLETED 1

J REMARKS &

INITIALS OPERATOR NAM E a) TOTAL OPERATION TIME Ib) DATE OF OPERATING EXERCISE REMARKS & INITIALS 4 4 I t 4 r a) >4 hours: at 4 I console (RO) or as Rx. Sup.

(SRO) 4 1 9

b) Date of Complete 4 I Operating Exercise I 4

  • *1 I 4

-I * *4. I 4

_________________________________________________________________________________________ L .1. i .1.

Figure IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP 15, Rev. LEU-2 Surveillance & Maintenance for the 1st / 2 na Half of 20 DATE NOT REMARKS SURVEILLANCE & MAINTENANCE LIMITS AS FOUND TARGET TO BE DATE &

[SHADE INDICATES LICENSE REQUIREMENT] DATE COMPLETED EXC EEDED* INITIALS NO WITHDRAW NEUTRON SOURCE COUNT RATE INTERLOCK______ ______

>5 cps ________ ____ ______

TRANSIENT ROD AIR INTERLOCK NO PULSE CHANNEL TESTS PULSE MODE ROD MOVEMENT INTERLOCK NO MOVEMENT IOF REACTOR INTERLOCKS PULSE INTERLOCK ON RANGE SWITCH NO PULSE MAXIMUM PULSE REACTIVITY INSERTION LIMIT ** $2.25 TWO ROD WITHDRAWAL PRHOHIBIT I ONLY PULSE PROHIBIT ABOVE I kW >1 kW 2 SAFETYPEIDSRM>se CIRCUIT TEST PEIDSRM3se PREVIOUS PULSE DATA FOR COMPARION <20%, PULSE # __

PULSE # -o $_____

$_________ _____MW 3TEST PULSE MW CHANGE ° 4 CLEANING & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL BARREL 5 LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 6 LUBRICATION OF THE ROTATING RACK BEARINGS l0W OIL 7 CONSOLE CHECK LIST OSTROP 15.VII1 8 INVERTER MAINTENANCE See User Manual 9 STANDARD CONTROL ROD MOTOR CHECKS LO-17 Bodine Oil

  • aenot to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.

Figure IV.3 (continued)

Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP 15, Rev. LEU-2 Surveillance & Maintenance for the 1S / 2 nd Half of 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT DATE REMARKS &

[SHADE INDICATES LICENSE REQUIREMENT] LIMITS AS FOUND DATE TO BEED CMPLETED INITIALS NONE SAFETY CHtANNEL(IfOny 10ION CHAMBER RESISTANCE MEASUREMENTS WITH (ln____Only)

NONE

%POWER CtIANNEL(IfOny

(/a 100 V.I _________ AMPS FISSION CHAMBER RESISTANCE @ 900 V. I = _________AMPS NN CALCULATION R 800- Al = ________AMPS (IfOny Al HIGH ___

12 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP I 5.XII FULL____

BRUSH INSP~ECTION 13INSPECTION OF THE PNEUMATIC TRANSFER__________

SYSTEM SAMPLE INSERTION TIME CHECK ~~1.0 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-2 AnnualSurveillance and Maintenance for 20 ____

SURVEILLANCE AND MAINTENANCE LIISAS I TARGET DATE NOT TBEDATE& REMARKS

[SHADE INDICATES LICENSE REQUIREMENT]

IFOUND IIEXCEEDED*

DATE COMPLETED INITIALS BIENNIAL INSPECTION OF FFCRSOTRP1.

CONTROL RODS: TRANS__________________

2 STANDARD CONTROL ROD DRIVE INSPECTON OSTROP 16.2 NORMAL CONTROL ROD 3 CLICIT CALIBRATION: OSTROP 9.0 ICITiDUMMY TRANS SAFE SHIM REG CONTROL ROD <2 sec WITHDRAWAL SCA INSERTION & WiD ___ __ __ <50

-- sec INSERT <50 sec 5 FUEL ELEMENT INSPECTION FOR SELECTED ELEMENTS .2%F' 6 REACTOR POWER CALIBRATION OSTROP 8 7 FUEL ELEMENT TEMPERATURE CHANNEL CALIBRATION Per Checklist 8CALIBRATION OF REACTOR TANK WATER TEMPOSRP1.

TEMPERATURE METERS _________ _________

CONTINUOUS Particulate Monitor 9AIR MONITOR RCHPP 18 CALIBRATION rGas Monitor 10 CAM OIL/GREASE MAINTENANCE 11STACK MONITOR IParticulate Monitor RCHPP CALIBRATION jGas Monitor 18 & 26 12 STACK MONITOR OIL/GREASE MAINTENANCE 13 AREA RADIATION MONITOR CALIBRATION RCHPP 18

  • 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-2 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DAENT DATE REMARKS

[SHADE INDICATES LICENSE REQUIREMENT] LIIS FOUND DATE TOCEBED COMPLETED & INITIALS NORMAL $

14 CORE EXCESS <$7.55 ICIT $

______ ______ ______ ______ ____ _ ______ CLICIT$$_ _ _ _ _ _ _ _

DAMPERS 1 ST FLOOR__

15 RACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSE IN<5

__________________________________ SECONDS 4 TH FLOOR 16 DECOMMISSIONING COST UPDATE N/A N/A AUGUST 17 *NM PHYSICAL INVENTORY N/A N/A OCTOBER 18 ATERIAL BALANCE REPORTS N/A N/A NOVEMBER CFD TRAINING______________

GOOD SAM TRAINING__________

ERP REVIEW ERP DRILL__ _ _ _ _ _ _ _ __ _ _ _

CPR CERT FOR:

CPR CERT FOR:________________

EMERGENCY 19 RESPONSE FIRST AID FOR:

PLAN FIRST AID FOR:

EVACUATION DRILL AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIENNIAL SUPPORT AGRE*EMENTS PSP REVIEW PHYSICAL PSP DRILL 20 SECURITY OSP/DPS TRAINING PLAN LOCK/SAFE COMBO CHANGES AUTHORIZATION LIST UPDATE

  • 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-2 Annual Surveillance and Maintenance for 20 DATE NOT SURVEILLANCE AND MAINTENANCE LIISAS TARGET TO BE DATE REMARKS

[SHADE INDICATES LICENSE REQUIREMENT] FOUND DATE COMPLETED & INITIALS 21 ANNUAL REPORT NOVI1 OCTI1 NOVI1 22 KEY INVENTORY ANNUAL REACTOR TANK AND CORE COMPONENT 23 NO WHITE SPOTS

__INSPECTION ______

24 EMERGENCY LIGHT LOAD TEST RCHPP 18.0 25 NEUTRON RADIOGRAPHY FACILTIY INTERLOCKS 26 PGNAA FACILITY INTERLOCKS ANNUAL REQUALIFICATION BIENNIAL MEDICAL EVERY 6 YEARS LICENSE REACTOR OPERATOR LICENSE CONDITIONS WRITTEN OPERATING TEST APIAIN EPRTO APPLIATION EXPDATIO DATE DA[E EXAM DTEDE DATE

~~~DATE DUE DT COMPLETED DUE DATE OPERATOR NAME DUE PASSED DAEDE PASSED ___________ DATE MAILED 27

  • Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus t15 months.

For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.

'.g. I I a S Introduction Liquid Effluents Released T-he purpose of the radiation protection program is to ensure Liquid Effuents the safe use of radiation and radioactive material in the Cen- Oregon State University has implemented a policy to re-ter's teaching, research, and service activities, and in a similar duce the volume of radioactive liquid effluents to an absolute manner to the fulfillment of all regulatory requirements of the minimum. For example, water used during the ion exchanger State of Oregon, the U.S. Nuclear Regulatory Commission, resin change is now recycled as reactor makeup water. Waste and other regulatory agencies. TIhe comprehensive nature of water from Radiation Center laboratories and the OSTR is the program is shown in Table V.1, which lists the program's collected at a holdup tank prior to release to the sanitary sewer.

major radiation protection requirements and the performance Liquid effluent are analyzed for radioactivity content at the frequency for each item. time it is released to the collection point. For this reporting period, the Radiation Center and reactor made seven liquid ef-The radiation protection program is implemented by a staff fluent releases to the sanitary sewer. All Radiation Center and consisting of a Senior Health Physicist, a Health Physicist, reactor facility liquid effluent data pertaining to this release are and several part-time Health Physics Monitors (see Part II). contained in Table V.2.

Assistance is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Liquid Waste Generated and Transferred Technician, and the Radiation Center Director. Liquid waste generated from glassware and laboratory experi-ments is transferred by the campus Radiation Safety Office TIhe data contained in the following sections have been to its waste processing facility. The annual summary of liquid prepared to comply with the current requirements of Nuclear waste generated and transferred is contained in Table V.3.

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. Airborne Effluents Released 345-30-010, which requires an annual report of environmental Airborne effluents are discussed in terms of the gaseous com-effects due to research reactor operations. ponent and the particulate component.

Within the scope of Oregon State University's radiation pro- Gaseous Effuents tection program, it is standard operating policy to maintain all Gaseous effluents from the reactor facility are monitored by releases of radioactivity to the unrestricted environment and all the reactor stack effluent monitor. Monitoring is continuous, exposures to radiation and radioactive materials at levels which i.e., prior to, during, and after reactor operations. It is normal are consistently "as low as reasonably achievable" (ALARA). for the reactor facility stack effluent monitor to begin operation as one of the first systems in the morning and to cease opera-nion as one of the last systems at the end of the day. All gaseous Environmental Releases effluent data for this reporting period are summarized in Table V.4.

The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a Particulate effluents from the reactor facility are also moni-summary of the nature and amount of radioactive effluents tored by the reactor facility stack effluent monitor.

released or discharged to the environs beyond the effective Particulate Effluents control of the licensee, as measured at, or prior to, the point Evaluation of the detectable particulate radioactivity in the of such release or discharge." Tlhe liquid and gaseous effluents stack effluent confirmed its origin as naturally-occurring radon released, and the solid waste generated and transferred are daughter products, within a range of approximately 3x10~11 discussed briefly below. Data regarding these effluents are also pCi/ml to 1 x 10.9 1 tCi/ml. T-his particulate radioactivity is summarized in detail in the designated tables.

d 14-15 Annual Report

predominantly 214pb and 214Bi, which is not associated with Facilities Services maintenance personnel are normally is-reactor operations. sued a gamma sensitive electronic dosimeter as their basic 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 Xti(7) TLD badge and other average concentration of radioactive particulates with half lives dosimeters as appropriate for the work being performed.

greater than eight days is not applicable.

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

Solid Waste Released Data for the radioactive material in the solid waste generated Students or small groups of students who attend a one-time and transferred during this reporting period are summarized lab demonstration and do not handle radioactive materials are in Table V.5 for both the reactor facility and the Radiation usually issued a gamma sensitive electronic dosimeter. These Center. Solid radioactive waste is routinely transferred to results are not included with the laboratory class students.

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 XIg(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 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.

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

Personnel Dose An annual summary of the radiation doses received by each of the above six groups is shown in Table V.6. There were no per-The OSTR annual reporting requirements specify, that the sonnel radiation exposures in excess of the limits in 10 CFR licensee shall present a summary of the radiation exposure re-20 or State of Oregon regulations during the reporting period.

ceived by facility personnel and visitors. Tfhe 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 Facility Survey Data personnel, facilities services maintenance personnel, students The OSTR Technical Specifications require an annual in laboratory classes, police and security personnel, and visitors. summary of the radiation levels and levels of contamination Facility operating personnel include the reactor operations and health physics staff. T'he 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.

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observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program Environmental Survey Data The annual reporting requirements of the OSTR Technical encompasses the Radiation Center as well as the OSTR, and Specifications include "an annual summary of environmental therefore monitoring results for both facilities are reported. surveys performed outside the facility."

Area Radiation Dosimeters Area monitoring dosimeters capable of integrating the radia-tion dose are located at strategic positions throughout the Gamma Radiation Monitoring reactor facility and Radiation Center. All of these dosimeters On-site Monitoring contain at least a standard personnel-type beta-gamma film or Monitors used in the on-site gamma environmental radiation TLD pack. In addition, for key locations in the reactor facility monitoring program at the Radiation Center consist of the and for certain Radiation Center laboratories a CR-39 plastic reactor facility stack effluent monitor described in Section V track-etch neutron detector has also been included in the and nine environmental monitoring stations.

monitoring package.

During this reporting period, each fence environmental sta-The total dose equivalent recorded on the various reactor facil-tion utilized an LiF TLD monitoring packet supplied and pro-ity dosimeters is listed in Table V.7 and the total dose equiva-cessed by Mirion Technologies, Inc., Irvine, California. Each lent recorded on the Radiation Center area dosimeters is listed GDS packet contained three LiP TLDs and was exchanged in Table V.8. Generally, the characters following the Monitor quarterly for a total of 108 samples during the reporting period Radiation Center (MRC) designator show the room number (9 stations x 3 TLDs per station x 4 quarters). The total num-or location. ber of GDS TLD samples for the reporting period was 108. A Routine Radiation and Contamination Surveys summary of the GDS TLD data is also shown in Table V.10.

The Center's program for routine radiation and contamination From Table V.10 it is concluded that the doses recorded by the surveys consists of daily, weekly, and monthly measurements dosimeters on the TRIGA facility fence can be attributed to throughout the TRIGA reactor facility and Radiation Center.

natural back-ground radiation, which is about 110 mrem per The frequency of these surveys is based on the nature of the year for Oregon (Refs. 1, 2).

radiation work being carried out at a particular location or on other factors which indicate that surveillance over a specific Off-site Monitoring area at a defined frequency is desirable. The off-site gamma environmental radiation monitoring program consists of twenty monitoring stations surrounding The primary purpose of the routine radiation and contamina-the Radiation Center (see Figure V.1) and six stations located tion survey program is to assure regularly scheduled surveil-within a 5 mile radius of the Radiation Center.

lance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and character- Each monitoring station is located about four feet above istic data on the status of radiological conditions. A second the ground (MRCTE 21 and MRCTE 22 are mounted on objective of the program is to assure frequent on-the-spot the roof of the EPA Laboratory and National Forage Seed personal observations (along with recorded data), which wl Laboratory, respectively). These monitors are exchanged and provide advance warning of needed corrections and thereby processed quarterly, and the total number of TLD samples dur-help to ensure the safe use and handling of radiation sources ing the current one-year reporting period was 240 (20 stations and radioactive materials. A third objective, which is really x3 chips per station per quarter x 4 quarters per year). The total derived from successful execution of the first two objectives, is number of GDS TLD samples for the reporting period was to gather and document information which will help to ensure 240. A summary of GDS TLD data for the off-site monitoring that all phases of the operational and radiation protection stations is given in Table V.11.

programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as After a review of the data in Table V.11, it is concluded that, low as reasonably achievable" (ALARA). like the dosimeters on the TRIGA facility fence, all of the doses recorded by the off-site dosimeters can be attributed to The annual summary of radiation and contamination levels natural background radiation, which is about 110 mrem per measured during routine facility surveys for the applicable year for Oregon (Refs. 1, 2).

reporting period is given in Table V.9.

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Soil, Water, and Vegetation Surveys Radioactive Materials Shipments The soil, water, and vegetation monitoring program consists A summary of the radioactive material shipments originat-of the collection and analysis of a limited number of samples ing from the TRIGA reactor facility, NRC license R-106, in each category on a annual basis. Tlhe program monitors is shown in Table V.14. A similar summary for shipments highly unlikely radioactive material releases from either the originating from the Radiation Center's State of Oregon ra-TRIGA reactor facility or the OSU Radiation Center, and dioactive materials license ORE 90005 is shown in Table V.15.

also helps indicate the general trend of the radioactivity A summary of radioactive material shipments exported under concentration in each of the various substances sampled. See Nuclear Regulatory Commission general license 10 CFR Figure V.1 for the locations of the sampling stations for grass 110.23 is shown in Table V.16.

(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 References over a local area having a radius of about ten feet at the posi-tions indicated in Figure V.1. 1. U. S. Environmental Protection Agency, "Estimates of Ionizing Radiation Doses in the United States,

'T-here are a total of 22 sampling locations: four soil locations, 1960-2000," O RP/C SD 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, "Radiologi-

'The annual concentration of total net beta radioactivity (mi- cal Quality of the Environment in the United States, nus tritium) for samples collected at each environmental soil, 1977," EPA 520/1-77-009, Office of Radiation water, and vegetation sampling location (sampling station) is 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.

'Ihe annual concentrations were calculated using sample results which exceeded the lower limit of detection (LLD),

except that sample results which were less than or equal to the 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 1 iCi 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.

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Table V. 1 Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement Daily/Weekly/Monthly 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 Monthly exposure reports.

Inspect laboratories.

Calculate previous month's gaseous effluent discharge.

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.

As Required 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.

Quarterly Collect and analyze samples from reactor stack effluent line.

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

Semi-nnualLeak 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 Annualfilters 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.

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~Table V.2

..... Monthly Summary of Liquid Effluent Release to the Sanitary Sewert 1 )

Specific Activity for Toal Quantity of Aeae Preto plcbeTotal Volume Date of Total Each Detectable Ra- Tto vrg ecn fApial Deectble Dateof f uantty ionclid in Each Detectable Concentration Monthly Average of LiqudEfun adRdincd thWatWeete Radionuclide Of Released Concentration for Rlae nldn Dishare adiaciviy adinulid te Wst, Wer th Rleaedin the Radioactive Material Released Radioactive Diun (Month and Released in the Waste Release Concentration WatDttePitoiRlae Mtra gl)en Year) (Curies) Was>1 x 10- (Curies) ( .tCi ml-1) (%)(2)(gl

__________( 1iCi m1-')

Feray21 .61 4 C-30H349x0 H-3, 1.12x10-4 H-3, 4.97x10-7 H-,005943 Febuar

.1610-205 Co60H-3 4.7x1-7 Co-60, 4.27x10-6 Co-60, 1.90x10-5 Co-60, 0.06 June 2015 3.23x10-5 H-3 H-3, 3.23x10-s H-3, 3.23x10-8 H-3, 0.0003 264,172 Annual TotalH3,14x0 for Radiation 1.48x10"4 H-3, Co-60, 4.97x10-7 Co-3, 4.24x10-4 5.48x10_7 0.065 323,607 Center C-0 .71-(1) Tlhe 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.

Table V.3 Annual Summary of Liquid Waste Generated and Transferred Volume of Liquid Detectable Total Quantity of Daefo Wranster Pickup Origin of Liquid WsePackagedW) Radionuclides Radioactivity in the foTrnertth WseWaste Waste Processing (gallons) in the Waste Waste (Curies) Facility TRIGA Reactor 2H-3 8.16x10-4 7/18/14 Facility Radiaion CnterU-238 Raito etr8.75 Cs-134 2.54x10-7 7/18/14 Laboratories Ag-110m ________

TOTAL 10.75 See above 8.16x10-4 (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.

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Table V.4 Montly TIGAReactor Gaseous Waste Discharges and Analysis EstiatedFraction of the Technical Total Total Atmospheric Diluted Specification MnhEstimated Estimated Quantity ot Concentration of Annual Average MnhActivity Argon-41 Argon-41 at Point of rgn4 Released (Curies) Released{') (Curies) Release Agn4 (ji~lcc)Concentration Limit (%)

July 1.27 1.27 1.02x10-7 2.55 August 2.12 2.12 1"69x10"7 4.23 September 1.56 1.56 1.29x10-7 3.23 October 1.77 1.77 1.41x10-7 3.54 November 1.15 1.15 949x10-s 2.37 December 1.54 1.54 1.23x10-7 3.08 January 1.33 1.33 1.07x10-7 2.67 February 1.51 1.51 1.34x10-1 3.34 March 1.97 1.97 1.58x10"7 3.95 April 2.75 2.75 2.27x10-7 5.67 May 1.71 1.71 1.37x10-7 3.41 June 2.14 2.14 1.77x10"7 4.43 TOTAL

('14-'15) 20.82 20.82 1.42x10"7 3.54 Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionu-(1) clide was argon-41.

(2) Annual Average.

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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 O SU Solid Waste Packaged")1 in Solid Waste Waste Processing (Cubic Feet) inteWse(Curies) Facility TRIGA Co-60, Zn-65, Sc-46, Cr-51, Fe-59, 11/5/14 Reactor 23 Co-58, As-74, H-3, Mn-54, Sb-124, 5.19x10-3 Facility Eu-152, Se-75, Ga-72, Eu-154 6/28/15 Radiation P-3,A-4,S-5 u12 Center 53 Pu29,A -243,r85Eu52 3.21x10O4 6/26/15 LaboratoriesU-3 TOTAL 76 See Above 5.51x10-3 (1) OSTR and Radiation Center laboratory waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final packaging.

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Table V.6 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Total Person-mrem Dose"1* Dose") for the Group(1)

Pesonl rop Whole Body Extremities Whole Body Extremities Whole Body Extremities PronlGop (mrem) (mnrem) (mrem) (mtrem) (mrem) (mtrnm)

Facility Operating 93.63 237.25 210 942 749 1,898 Personnel Key Facility Research 2.46 30.11 32 46 32 271 Personnel Facilities Services Maintenance <1 N/A <1 N/A 1.11 N/A Personnel Laboratory Class 5.94 29.7 88 90 856 446 Students Campus Police and0N/0NA0NA Security Personnel Visitors <1 N/A 7.6 N/A 98.57 N/A Contractors 391.9 N/A 434.7 N/A 1,175.8 N/A (1) "N/A"indicates that there was no extremity monitoring conducted or required for the group.

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Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total MntrTRIGA Reactor Reodd Dose Equivalent(1)(2)

I.D. Facility LocationX()Neto (See Figure V.1) (mrem) (meutro MRCTNE D104: North Badge East Wall 237 ND MRCTSE D104: South Badge East Wall 157 ND MRCTSW D104: South Badge West Wall 545 ND MRCTNW D104: North Badge West Wall 184 ND MRCTWN D104: West Badge North Wall 532 ND MRCTEN D104: East Badge North Wall 336 ND MRCTES D104: East Badge South Wall 1,701 ND MRCTWS D104: West Badge South Wall 481 ND MRCTTOP D104: Reactor Top Badge 1,177 ND MRCTHXS D104A: South Badge HX Room 567 ND MRCTHXW D104A: West Badge HX Room 312 ND MRCD-302 D302: Reactor Control Room 469 ND MRCD-302A D302A: Reactor Supervisor's Office 133 N/A MRCBP1 D104: Beam Port Number 1 402 ND MRCBP2 D104: Beam Port Number 2 262 ND MRCBP3 D104: Beam Port Number 3 684 ND MRCBP4 D104: Beam Port Number 4 872 ND (1) '-he 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) Tlhese dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.

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Table V.8 Total Dose Equivalent Recorded on Area Dosimeters

___________Located Within the Radiation Center Total Recorded Monitor Radiation Center Dose Equivalent(1

  • I.D. Facility Location I..(See Figure V.1) Xf?,(y) Neutron

______________ ___________________________________________ (mrem) (mrem)

MRCA100 A100: Receptionist's Office 11 N/A MRCBRF A102H: Front Personnel Dosimetry Storage Rack 58 N/A MRCA120 A120: Stock Room 62 N/A MRCA120A A120A: NAA Temporary Storage 105 N/A MRCA126 A126: Radioisotope Research Laboratory 210 N/A 6

MRCCO-60 A128: °Co Irradiator Room 814 N/A MRCA130 A130: Shielded Exposure Room 84 N/A MRCA132 A132: TLD Equipment Room 59 N/A MRCA138 A138: Health Physics Laboratory 59 N/A MRCA146 A146: Gamma Analyzer Room (Storage Cave) 147 N/A MRCB 100 B 100: Gamma Analyzer Room (Storage Cave) 167 N/A MRCB114 B114: Lab (226Ra Storage Facility) 1,538 N/A MRCB119-1 B119: Source Storage Room 147 N/A MRCB119-2 B119: Source Storage Room 241 N/A MRCB119A B119A: Sealed Source Storage Room 6,818 2,611 MRCB120 B120: Instrument Calibration Facility 78 N/A MRCB122-2 B122: Radioisotope Hood 237 N/A MRCB122-3 B122: Radioisotope Research Laboratory 94 N/A MRCB124-1 B124: Radioisotope Research Laboratory (Hood) 62 N/A MRCB124-2 B124: Radioisotope Research Laboratory 47 N/A MRCB124-6 B124: Radioisotope Research Laboratory 50 N/A MRCB128 B128: Instrument Repair Shop 72 N/A MRCB136 B136 Gamma Analyzer Room 22 N/A MRCC100 C100: Radiation Center Director's Office 36 N/A (1) T'he 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.

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Table V.8 cnnu)

Total Dose Equivalent Recorded on Area Dosimeters

__________Located Within the Radiation Center Total Recorded Monitor Radiation Center Dose Equivalent")

I.D. Facility Location (See Figure V.1) X1g(y ) Neutron (mrem) (mrem)

MRCC106A C106A: Office 57 N/A MRCC106B C106B: Custodian Supply Storage 57 N/A MRCC106-H C106H: East Loading Dock 53 N/A MRCC118 Gl18: Radiochemistry Laboratory 0 N/A MRCC120 0120: Student Counting Laboratory 20 N/A MRCF100 F100: APEX Facility 10 N/A MRCF102 F102: APEX Control Room 24 N/A MRCB125N B125: Gamma Analyzer Room (Storage Cave) 114 N/A MRCN125S B125: Gamma Analyzer Room 56 N/A MRCC 124 C 124: Classroom 56 N/A MRCC130 C130: Radioisotope Laboratory (Hood) 53 N/A MRCD100 Di00: Reactor Support Laboratory 69 N/A MRCD102 D102: Pneumatic Transfer Terminal Laboratory 204 ND MRCD102-H D102H: 1st Floor Corridor at D102 124 ND MRCD106-H D106H: 1st Floor Corridor at D106 333 N/A MRCD200 D200: Reactor Administrator's Office 185 ND MRCD202 D202: Senior Health Physicist's Office 264 ND MRCBRR D200H: Rear Personnel Dosimetry Storage Rack 80 N/A MRCD204 D204: Health Physicist Office 326 ND MRCATHRL F104: ATHRL 49 N/A MRCD300 D300: 3rd Floor Conference Room 153 ND MRCA144 A144: Radioisotope Research Laboratory 44 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.

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Table V.9 Annual Summary of Radiation and Contamination Levels Observed Within the Reactor Facility and Radiation Center

.. .During Routine Radiation Surveys _________

Whole Body Contamination Accessible Location Radiation Levels Levels*')

(See Figure V.1) (mrem/hr) (dpm/cm 2)

Average Maximum Average Maximum TRIGA Reactor Facility:

Reactor Top (D104) 1.7 90 <500 5,577 Reactor 2nd Deck Area (D104) 6.8 42 <500 <500 Reactor Bay SW (D104) <1 25 <500 1,500 Reactor Bay NW (D104) <1 74 <500 49,808 Reactor Bay NE (D104) <1 23 <500 2,115 Reactor Bay SE (D104) <1 6 <500 1,731 Class Experiments (D104, D302) <1 <1 <500 <500 Demineralizer Tank & Make Up Water System <1 10 <500 <500 (D104A)_______

Particulate Filter--Outside Shielding (D104A) <1 4 <500 1,731 Radiation Center:

NAA Counting Rooms (A146, B 100) <1 2.3 <500 <500 Health Physics Laboratory (A138) <1 <1 <500 1,607 6°Co Irradiator Room and Calibration Rooms (A128, B120, A130) <1 4 <500 <500 Radiation Research Labs (A126, A136)<10<5050 (B108, B114, B122, B124, C126, C130, A144)<10<5050 Radioactive Source Storage (B 119, B119A, <1 12 <500 <500 A120A, A132A)

Student Chemistry Laboratory (C 118) <1 <1 <500 <500 Student Counting Laboratory (C120) <1 <1 <500 <500 Operations Counting Room (B136, B 125) <1 <1 <500 <500 Pneumatic Transfer Laboratory (D102) <1 1.5 <500 <500 RX support Room (D100) <1 <1 <500 <500 (1) <500 dpm/100 era2 =Less than the lower limit of detection for the portable survey instrument used.

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Table V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence Fence Total Recorded Dose Equivalent Environmental Monitoring Station (Including Background)

(SeeFigre

.1)Based on Mirion TLDs*12)

(See______

Figure________V.1)______(mrem)

MRCFE-1 93+/- 2 MRCFE-2 88+/- 4 MRCFE-3 83 +/-2 MRCFE-4 92 +/- 3 MRCFE-5 94 +/-3 MRCFE-6 91 +/-3 MRCFE-7 90 +/-_3 MRCFE-8 95 +/-7 MRCFE-9 88 +/-6 (1) Average Corvallis area natural background using Mirion TLDs totals 86 -+/-10 mrem for the same period.

(2) _+/-values represent the standard deviation of the total value at the 95% confidence level.

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