Text

2013 Annual Report for the University of Texas at Austin
	ML14099A082
Person / Time
Site:	University of Texas at Austin
Issue date:	03/25/2014
From:	Whaley P; University of Texas at Austin
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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COLLEGE OF ENGINEERING THE UNIVERSITY OF TEXAS AT AUSTIN Depanmt ofMechanicalEnginering"1University Station C2200"Austin, Txas 78712-0292 Tdephom(512)471-1131 FAX(512)471-8727 March 25, 2014 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555

Subject:

Annual Report for The University of Texas at Austin, Docket 50-602

Dear Sir:

Enclosed is the 2013 Annual Report for the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin. This report is being submitted in accordance with Section 6.6 of the Technical Specifications.

Please contact me at 512-232-5373 if you have any questions.

Sincere P. M. Whaley NETL Associate Director Aooi

The University of Texas at Austin Nuclear Engineering Teaching Laboratory 2013 Annual Report NRC Docket 50-602 DOE Contract No. DE-AC07-ER03919 Revised 12/2013

2013 NETL Annual Report Department of Mechonical Engineering THE UNIVERSITY OF TEXAS AT AUSTIN ducear Engineering Teaching Laboratory" Austin, 7ixas 78758 512-232-5370 - FAX 512-471-4589" hup//wuw.nme. mtexas.ed/-,net/net.html FORWARD The mission of the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin is to:

Educate the next generation of leaders in nuclear science and engineering.

Conduct leading research at the forefront of the international nuclear community.

Apply nuclear technology for solving multidisciplinary problems.

" Provide service to the citizens of Texas, the U.S., and the international community.

This objective is achieved by carrying out a well-balanced program of education, research, and service. The NETL research reactor supports hands-on education in reactor physics and nuclear science. In addition, students in non-nuclear fields such as physics, chemistry, and biology use the reactor in laboratory course work. The NETL is also used in education programs for nuclear power plant personnel, secondary schools students and teachers, and the general public.

The NETL research reactor benefits a wide range of on-campus and off-campus users, including academic, medical, industrial, and government organizations. The principal services offered by our reactor involve material irradiation, trace element detection, material analysis, and radiographic analysis of objects and processes. Such services establish beneficial links to off-campus users, expose faculty and students to multidisciplinary research and commercial applications of nuclear science, and generate resources to help support Nuclear Engineering activities.

Steven Biegalski, Ph.D., P.E.

Director, Nuclear Engineering Teaching Laboratory ii 3/2014

2013 NETL Annual Report Table of Contents Table of Contents iii Executive Summary v 1.0 NUCLEAR ENGINEERING TEACHING LABORATORY ANNUAL REPORT 1 1.1 General 1 1.2 Purpose of the report 2 2.0 ORGANIZATION AND ADMINSTRATION 4 2.1 Level 1 6 2.2 Level 2 7 2.3 Level 3 11 2.4 Level 4 13 2.5 Other Facility Staff 13 2.6 Faculty and Facility users 13 2.7 NETL Support 16 3.0 FACILITY DESCRIPTION 17 3.1 NETL History 17 3.2 NETL SITE, J.J. Pickle Research Campus 17 3.3 NETL Building Description 18 4.0 UT-TRIGA MARK II RESEARCH REACTOR 19 4.1 Reactor Core 20 4.2 Reactor Reflector 20 4.3 Reactor Control 21 5.0 EXPERIMENT AND RESEARCH FACILITIES 22 5.1 Upper Grid Plate 7L and 3L Experiment Facilities 22 5.2 Central Thimble 22 5.3 Rotary Specimen Rack 23 5.4 Pneumatic Tubes 23 5.5 Beam Port Facilities 24 5.6 Other Experiment and Research Facilities 29 5.7 Experiment Facility Utilization 30 5.8 Nuclear Program Faculty Activities 32 6.0 OPERATING

SUMMARY

35 6.1 Operating Experience 35 6.2 Unscheduled Shutdowns 35 6.3 Utilization 37 6.4 Routine Scheduled Maintenance 38 6.5 Corrective Maintenance 38 6.6 Facility Changes 39 6.7 Oversight & Inspections 41 ioo 3/2014

2013 NETL Annual Report 7.0 RADIOLOGICAL

SUMMARY

44 7.1 Summary of Radiological Exposures 44 7.2 Summary of Radioactive Effluents 45 7.3 Radiological Exposure Received by Facility Personnel and Visitors 46 7.4 Environmental Surveys Performed Outside the Facility 46 iv 3/2014

2013 NETL Annual Report EXECUTIVE

SUMMARY

The Nuclear Engineering Teaching Laboratory (NETL) facility supports the academic and research missions of The University of Texas, and has begun to provide these support functions to other institutions. The environmental research and analysis services performed by the NETL during the past year have been used to support the Sandia National Laboratories, Los Alamos National Laboratory, Oak Ridge National Laboratory, the Canadian government, the National Oceanic and Atmospheric Administration, the University of Illinois, Texas A&M University and the State of Texas.

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2013 NETL Annual Report 1.0 NUCLEAR ENGINEERING TEACHING LABORATORY ANNUAL REPORT The Nuclear Engineering Laboratory Annual Report covers the period from January through December 2013. The report includes descriptions of the organization, NETL facilities, the reactor, experiment and research facilities and summaries of operations and radiological impact.

1.1 General The NETL facility serves a multipurpose role, with the primary function as a "user facility" for faculty, staff, and students of the Cockrell School of Engineering. The NETL supports development and application of nuclear methods for researchers from other universities, government organizations and industry. The NETL provides nuclear analytic services to researchers, industry, and other laboratories for characterization, testing and evaluation of materials. The NETL provides public education through tours and demonstrations.

Figure 1-1, NETL - Nuclear Engineering Teaching Laboratory Activities at NETL are regulated by Federal and State agencies. The nuclear reactor is subject to the terms and specifications of Nuclear Regulatory Commission (NRC) License R-129, a class 104 research reactor license. A second NRC license for special nuclear materials, SNM-180, authorizes possession of a subcritical assembly, neutron sources, and various equipment. The NETL is responsible for administration and management of both licenses. Activities at the I 3/2014

2013 NETL Annual Report University using radioisotopes are conducted under a State of Texas license, L00485. Functions of the broad license are the responsibility of the University Office of Environmental Health and Safety.

1.2 Purpose of this Report This report meets requirements of the reactor Technical Specifications and the Department of Energy Fuels Assistance program, and provides an overview of the education, research, and service programs of the NETL for the calendar year 2013.

1.2.1 TRIGA II Reactor Technical Specifications The NETL TRIGA II reactor Technical Specifications (section 6.6.1) requires submission of an annual report to the Nuclear Regulatory Commission. Table 1.1 correlates specified requirements to the report.

Table 1.1, TRIGA Mark II Technical Specification and the Annual Report Specification Section A narrative summary of reactor operating experience including the energy 5.0, 6.1, 6.3 produced by the reactor or the hours the reactor was critical, or both.

The unscheduled shutdowns & corrective action taken to preclude recurrence 6.2 Major preventive & corrective maintenance operations with safety significance 6.4 Major changes in the reactor facility and procedures, tabulation of new tests or experiments, or both, significantly different from those performed previously, 6.6 including conclusions that no unreviewved safety questions were involved A summary of radioactive effluents (nature & amount) released or discharged to the environs beyond effective control of the university as determined at or before the point of such release or discharge, including to the extent practicable an estimate of individual radionuclides present in the effluent or a statement that the estimated average release after dilution or diffusion is less than 25% of the concentration allowed or recommended A summary of exposures received by facility personnel and visitors where such exposures are greater than 25% of that allowed or recommended.

A summarized result of environmental surveys performed outside the facility 7.4 2 3/2014

2013 NETL Annual Report 1.2.2 The Department of Energy Fuels Assistance Program The DOE University Fuels Assistance program (DE-AC07-05ID14517, subcontract 00078206, 08/01/,2008-08/31/2013) supports the facility for utilization of the reactor in a program of education and training of students in nuclear science and engineering, and for faculty and student research. The contract requires an annual progress report in conjunction with submittal of a Material Balance Report and Physical Inventory Listing report. Specific technical details of the report (listed in Table 1.2) are sent under separate cover to the DOE with this Annual Report.

Table 1.2, DOE Reactor Fuel Assistance Report Requirements Fuel usage (grams Uranium 235 & number of fuel elements)

Inventory of unirradiated fuel elements in storage Inventory of fuel elements in core Inventory of useable irradiated fuel elements outside of core Projected 5-year fuel needs Current inventory of other nuclear material items with DOE-ID project identifier (i.e., "J")

Point of contact for nuclear material accountability 3 3/2014

2013 NETL Annual Report 2.0 ORGANIZATION AND ADMINSTRATION The University of Texas System (UTS) was established by ýthe Texas Constitution in 1876, and currently consists of nine academic universities and six health institutions. The UTS mission is to provide high-quality educational opportunities for the enhancement of the human resources of Texas, the nation, and the world through intellectual and personal growth.

The Board of Regents is the governing body for the UTS. It is composed of members appointed by the Governor and confirmed by the Senate. Terms are of six years each and staggered, with the terms of three members expiring on February 1 of odd-numbered years. Current members of the current Board of Regents are listed in Table 2.1.

Table 2.1 The University of Texas Board for 2014 Paul L. Foster, Chairman Win. Eugene Powell, Vice Chairman R. Steven Hicks, Vice Chairman Members with term set to expire May 2014 Student Regent Nash M. Home Members with term set to expire February 2015 Vice Chairman Win. Eugene Powell Vice Chairman R. Steven Hicks Regent Robert L. Stillwell Members with term set to expire February2017 Regent Alex M. Cranberg Regent Wallace L. Hall, Jr.

Regent Brenda Pejovich Members with term set to expire February2019 Chairman Paul L. Foster Regent Ernest Aliseda Regent Jeffery D. Hildebrand http://www.utsystem.edu/board-of-regents/current-regents, 03/23/2014 The chief executive officer of the UTS is the Chancellor. The Chancellor has direct line responsibility for all aspects of UTS operations, and reports to and is responsible to the Board of Regents. The current Chancellor and Staff are listed in Table 2.2.

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2013 NETL Annual Report Table 2.2 University of Texas System Chancellor's Office Francisco G. Cigarroa, MD, Chancellor Pedro Reyes, PhD, Executive Vice Chancellorfor Academic Affairs Scott C. Kelley, PhD, Executive Vice Chancellorfor Business Affairs Kenneth I. Shine, MD, Executive Vice Chancellorfor Health Randa S. Safady, Vice Chancellorfor External Relations Dan Sharphorn, Vice Chancellorand GeneralCounsel ad interim Stephanie A.Bond Huie, Vice Chancellorfor Strategic Initiatives ad interim Barry McBee, JD, Vice Chancellorfor Governmental Relations Francie A.Frederick, JD, GeneralCounsel to the Board of Regents http://www.utsystem.edu/sites/utsfiles/assets/general-files/OrgChart.pdf, 03/23/2014 UT Austin is the flagship campus of the UTS. The facility operating license for the TRIGA Mark II at the NETL is issued to the University of Texas at Austin. Figure 2-1 reflects the organizational structure for 4 levels of line management of the NETL reactor, as identified in the Technical Specifications, as well as oversight functions. Other NETL resources (in addition to line management positions) include staff with specialized functions, and faculty and facility users. NETL support is through a combination of State allocation, research programs, and remuneration for service.

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R*'O seatiOs staff Reactor & Senior Opeatzor Figure 2-1, Organizational Structure for the University of Texas at Ausitn TRIGA Reactor 2.1 Level 1 Personnel Level 1 represents the central administrative functions of the University and the Cockrell School of Engineering. The University of Texas at Austin is composed of 16 separate colleges and schools; the Cockrell School of Engineering manages eight departments with individual degree programs. The Nuclear Engineering Teaching Laboratory (NETL) is one of several education and research functions within the School. Current Level 1 personnel are reported in Table 2.3.

2.1.1 President, University of Texas at Austin The President is the individual vested by the University of Texas system with responsibility for the University of Texas at Austin.

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2013 NETL Annual Report 2.1.2 Executive Vice president and Provost (Provost)

Research and educational programs are administered through the Office of the Executive Vice President and Provost. Separate officers assist with the administration of research activities and academic affairs with specific management functions delegated to the Dean of the Cockrell School of Engineering and the Chairman of the Mechanical Engineering Department.

2.1.3 Dean of the Cockrell School of Engineering The Dean of the Cockrell School of Engineering reports to the Provost. The School consists of 8 departments and undergraduate degree programs and 12 graduate degree programs.

2.1.4 Department of Mechanical Engineering Chairman The Chairman reports to the Dean of the Cockrell School of Engineering. The Department manages 8 areas of study, including Nuclear and Radiation Engineering.

Table 2.3 The University of Texas at Austin Administration (Level 1)

William Powers Jr., JD, President Greg Fenves, PhD, Executive Vice President and Provost Steven W. Leslie, PhD, Executive Vice President and Provost Gregory L. Fenves, PhD, Dean, Cockrell School of Engineering Wood, Sharon, PhD, (interim) Dean, Cockrell School of Engineering Jayathi Murthy, Chair of Department of Mechanical Engineering 2.2 Level 2 Personnel The Nuclear Engineering Teaching Laboratory operates as a unit of the Department of Mechanical Engineering at The University of Texas. Level 2 personnel are those with direct responsibilities for administration and management of resources for the facility, including the Chair of the Mechanical Engineering Department, the NETL Director and Associate Director.

Oversight roles are provided at Level 2 by the Radiation Safety Committee, the Radiation Safety 7 3/2014

2013 NETL Annual Report Officer and the Nuclear Reactor Committee. The current complement of Level 2 personnel is reported along with the NETL facility staff and the Nuclear and Radiation Engineering program faculty in Table 2.4.

Table 2.4 Facility Staff & NRE Facultv NETL Facility Staff NRE Faculty Director S. Biegalski S. Biegalski Associate Director P. M. Whaley S. Landsberger Reactor Supervisor M. Krause E. Schneider Health Physicist & Lab manager T. Tipping M. Deinhert Administrative Associate D. Judson Electronics Technician/ Reactor Operator L. Welch N. Mohammed A. Davis J. Navar U. Chatterjee Health Physics Technician J. Sims 2.2.1 Director, Nuclear Engineering Teaching Laboratory (NETL Director)

Nuclear Engineering Teaching Laboratory programs are directed by an engineering faculty member with academic responsibilities in nuclear engineering and research related to nuclear applications. The Director is a member of the Cockrell School of Engineering, and the Department of Mechanical Engineering.

2.2.2 Associate Director The Associate Director is responsible for safe and effective conduct of operations and maintenance of the TRIGA nuclear reactor. Other activities performed by the Associate Director and staff include neutron and gamma irradiation service, operator/engineering training courses, and teaching reactor short courses. In addition to Level 3 staff, an Administrative Assistant and an Electronics Technician report to the Associate Director. Many staff functions overlap, with significant cooperation required.

2.2.4 Safety Oversight 8 3/2014

2013 NETL Annual Report Safety oversight is provided for radiation protection and facility safety functions. A University of Texas Radiation Safety Committee is responsible programmatically for coordination, training and oversight of the University radiation protection program, with management of the program through a Radiation Safety Officer. Current personnel on the Radiation Safety Committee are listed on Table 2.5.

Nuclear reactor facility safety oversight is the responsibility of a Nuclear Reactor Committee; a request has been made to the Nuclear Regulatory Commission to change the name "Nuclear Reactor Committee" to "Reactor Oversight Committee" to better describe the committee function for the University and avoid confusion with other NRC organizations. "Reactor Oversight Committee" will be used in this report pending approval. Current personnel on the Reactor Oversight Committee are listed on Table 2.6.

Radiation Safety Committee. The Radiation Safety Committee reports to the President and has the broad responsibility for policies and practices regarding the license, purchase, shipment, use, monitoring, disposal and transfer of radioisotopes or sources of ionizing radiation at The University of Texas at Austin. The Committee meets at least three times each calendar year. The Committee is consulted by the Office of Environmental Health and Safety concerning any unusual or exceptional action that affects the administration of the Radiation Safety Program.

Table 2.5 Radiation Safety Committee 2013-2014 Gerald W. Hoffinann, Ph.D., Chair, Department of Physics Juan M. Sanchez, Ph.D., Vice Chair,Vice President for Research Neal Armstrong, Ph.D., Vice Provost Kevin Dalby, Ph.D., College of Pharmacy W. Scott Pennington, ex-officio, Office of Environmental Health & Safety Rick Russell, Ph.D., Associate Professor,Department ofMolecular Biosciences John Salsman, Director,EnvironmentalHealth and Safety Bob G. Sanders, Ph.D., Professor,Department of Molecular Biosciences Tracy Tipping, Nuclear Engineering Teaching Laboratory http://www.utexas.edu/research/resources/committees#rsc, 03/24/2014 Radiation Safety Officer. A Radiation Safety Officer holds delegated authority of the Radiation Safety Committee in the daily implementation of policies and practices regarding the safe use of radioisotopes and sources of radiation as determined by the Radiation Safety Committee. The 9 3/2014

2013 NETL Annual Report Radiation Safety Officer's responsibilities are outlined in The University of Texas at Austin Radiation Safety Manual. The Radiation Safety Officer has an ancillary function reporting to the NETL Director as required on matters of radiological protection. The Radiation Safety Program is administered through the University Office of Environmental Health and Safety.

A NETL Health Physicist (Level 3) manages daily radiological protection functions at the NETL, and reports to the Radiation Safety Officer as well as the Associate Director. This arrangement assures independence of the Health Physicist through the Radiation Safety Officer while maintaining close interaction with NETL line management.

Reactor Oversight Committee (ROC). The Reactor Oversight Committee (formerly known as the Nuclear Reactor Committee) evaluates, reviews, and approves facility standards for safe operation of the nuclear reactor and associated facilities. The ROC meets at least semiannually.

The ROC provides reports to the Dean on matters as necessary throughout the year and submits a final report of activities no later than the end of the spring semester. The ROC makes recommendations to the NETL Director for enhancing the safety of nuclear reactor operations.

Specific requirements in the Technical Specifications are incorporated in the committee charter, including an audit of present and planned operations. The ROC is chaired by a professor in the Cockrell School of Engineering. ROC Membership varies, consisting of ex-officio and appointed positions. The Dean appoints at least three members to the Committee that represent a broad spectrum of expertise appropriate to reactor technology, including personnel external to the School.

Table 2.6 Reactor Oversight Committee 2013-2014 Erich Schneider (ME), Chair Howard Liljestrand (CAEE)

Lynn Katz (CAEE)

Steven Biegalski (ME)

Lawrence R. Jacobi (External Representative)

Jodi Jenkins (External Representative)

Jayathi Murthy, ex-officio (ME)

Michael Krause, ex-officio (NETL)

Tracy Tipping, ex-officio (NETL)

Mike Whaley, ex-officio (NETL)

John G. Ekerdt, ex-officio Scott Pennington, other (Radiation Safety Officer) https://www.engr.utexas.edu/faculty/committees/225-roc, 03/23/2014 10 3/2014

Ip 2013 NETL Annual Report 2.3 Level 3 Personnel Level 3 personnel are responsible for managing daily activities at the NETL. The Reactor Supervisor and Health Physicist are Level 3. The current Reactor Supervisor and Health Physicist are listed on Table 2.4.

2.3.1 Reactor Supervisor The Reactor Supervisor function is incorporated in a Reactor Manager position, responsible for daily operations, maintenance, scheduling, and training. The Reactor Manager is responsible for the maintenance and daily operations of the reactor, including coordination and performance of activities to meet the Technical Specifications of the reactor license. The Reactor Manager plans and coordinates emergency exercises with first responders and other local support (Austin Fire Department, Austin/Travis County EMS, area hospitals, etc.).

The Reactor Manager, assisted by Level 4 personnel and other NETL staff, implements modifications to reactor systems and furnishes design assistance for new experiment systems.

The Reactor Manager assists initial experiment design, fabrication, and setup. The Reactor Manager provides maintenance, repair support, and inventory control of computer, electronic, and mechanical equipment. The Administrative Assistant and Reactor Manager schedule and coordinate facility tours, and support coordination of building maintenance.

2.2.1 Health Physicist The Health Physicist function is incorporated into a Laboratory Manager position, responsible for radiological protection (Health Physics), safe and effective utilization of the facility (Lab Management), and research support. Each of these three functions is described below. The Laboratory Manager is functionally responsible to the NETL Associate Director, but maintains a strong reporting relationship to the University Radiation Safety Officer and is a member of the Radiation Safety Committee. This arrangement allows the Health Physicist to operate independent of NETL operational constraints in consideration of radiation safety.

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2013 NETL Annual Report Health Physics. NETL is a radiological facility operating in the State of Texas under a facility operating license issued by the Nuclear Regulatory Commission (NRC). Radioactive material and activities associated with operation of the reactor are regulated by the NRC, and the uses of radioactive materials at the NETL not associated with the reactor are regulated by the Texas Department of State Health Services (TDSHS) Radiation Control Program. The NETL Health Physicist ensures operations comply with these requirements, and that personnel exposures are maintained ALARA ("as low as is reasonably achievable"). One or more part-time Undergraduate Research Assistant (URA) may assist as Health Physics Technicians.

Lab Management. The lab management function is responsible for implementation of occupational safety and health programs at the NETL. The Laboratory Manager supports University educational activities through assistance to student experimenters in their projects by demonstration of the proper radiation work techniques and controls. The Laboratory Manager participates in emergency planning for NETL and the City of Austin to provide basic response requirements and conducts off-site radiation safety training to emergency response personnel such as the Hazardous Materials Division of the Fire Department, and Emergency Medical Services crews.

Research Support. The mission of The University of Texas at Austin is to achieve excellence in the interrelated areas of undergraduate education, graduate education, research and public service. The Laboratory Manager and research staff supports the research and educational missions of the university at large, as well as development or support of other initiatives.

The Laboratory Manager is responsible for coordinating all phases of a project, including proposal and design, fabrication and testing, operation, evaluation, and removal/dismantlement.

Researchers are generally focused on accomplishing very specific goals, and the research support function ensures the NETL facilities are utilized in a safe efficient manner to produce quality data. The Laboratory Manager obtains new, funded research programs to promote the capabilities of the neutron beam projects division for academic, government and industrial organizations and/or groups.

The NETL provides unique facilities for nuclear analytic techniques, including but not limited to elemental analysis (instrumental neutron activation analysis, prompt gamma analysis),

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2013 NETL Annual Report measurements of physical characteristics (neutron depth profiling, neutron radiography) and experimental techniques investigating fundamental issues related to nuclear physics and condensed matter. Nuclear analytical techniques support individual projects ranging from class assignments to measurements for faculty research.

The Laboratory Manager manages the use of the five beam ports with the Texas Cold Neutron Source, Neutron Depth Profiling, Neutron Guide and Focusing System, Prompt Gamma Activation Analysis Neutron Radiography and Texas Intense Positron Source. Projects are supported in engineering, chemistry, physics, geology, biology, zoology, and other areas.

Research project support includes elemental measurements for routine environmental and innovative research projects. The neutron activation analysis technique is made available to different state agencies to assist with quality control of sample measurements.

2.4 Level 4 Personnel Reactor Operators and Senior Reactor Operators (RO/SRO) operate and maintain the reactor and associated facilities. An RO/SRO may operate standard reactor experiment facilities as directed by the Reactor Supervisor.

2.5 Other Facility Staff In addition to the line management positions defined in Figure 2-1, NETL staff includes an Administrative Assistant, and Electronics Technician, and variously one or more Undergraduate Research Assistants assigned either non-licensed maintenance support (generally but not necessarily in training for Reactor Operator licensure) or to support the Laboratory Manager as Health Physics Technicians and/or research support.

2.6 Faculty and Facility Users The complement of faculty and facility users at the NETL is extremely variable. Functionally faculty and facility users are associated with the NETL in the capacity of academic utilization, other educational efforts, or research & service. A description of these activities follows.

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2013 NETL Annual Report 2.6.1 Academic Utilization The NETL is integrated in the Nuclear and Radiation Engineering program (NRE) of Mechanical Engineering (ME). The ME faculty complement directly supporting the nuclear education program is listed in Table 2.7. Successful participation in the undergraduate program results in a Bachelor of Science in Mechanical Engineering, Nuclear Engineering certification; the degree is essentially a major in Mechanical Engineering with a minor in Nuclear Engineering. All Mechanical Engineering degree requirements must be met with an additional set of specific nuclear engineering courses successfully completed.

Table 2.7 University of Texas Nuclear and Radiation Engineering Program Faculty Dr. Steven Biegalski, Nuclear and Radiation Engineering Associate Professor Dr.Mark Deinert, Nuclear and Radiation Engineering, Thermal Fluid Systems, Assistant Professor Dr. Kendra M. Foltz-Biegalski, Nuclear and Radiation Engineering Research Engineer Dr. Dael Klein, Associate Vice Chancellor for Research Dr. Sheldon Landsberger, Nuclear and Radiation Engineering Professor Dr.Mitch Pryor, Robotics Research Group Research Associate Dr. Erich Schneider, Nuclear and Radiation Engineering Assistant Professor https://nuclear.engr.utexas.edu/index.php/faculty-and-staff, 03/23/2014 Of the five undergraduate Nuclear Engineering courses and the dozen graduate Nuclear Engineering courses, five courses make extensive use of the reactor facility. Table 2.8 lists the courses currently in the UT course catalog, many of which use the reactor and its experiment facilities.

Table 2.8, Nuclear Engineering Courses Undergraduate ME 136N, 236N: Concepts in Nuclear and Radiological Engineering ME 337C: Introduction to Nuclear Power Systems ME337F: Nuclear Environmental Protection 11 ME 337G: Nuclear Safety and Security ME 361E: Nuclear Operations and Reactor Engineering ME 361F: Radiation and Radiation protection Laboratory 14 3/2014

2013 NETL Annual Report Table 2.8, Nuclear Engineering Courses Graduate ME 388C: Nuclear Power Engineering ME 388D: Nuclear Reactor Theory IL'1 11 ME 388F: Computational Methods in Radiation Transport[

ME 388G: Nuclear Radiation Shieldingll ME 388H: Nuclear Safety and Security ME 388J: Neutron Interactions and their Applications in Nuclear Science and Engineering[1]

ME 388M: Mathematical Methods for Nuclear and Radiation Engineersll ME 388N: Design of Nuclear Systems Ill]

1 ME 388P: Applied Nuclear Physics[ ]

11 ME 388S: Modem Trends in Nuclear and Radiation Engineering ]

ME 389C: Nuclear Environmental Protection 111 NE 389F: The Nuclear Fuel Cycle ME 390F: Nuclear Analysis Techniques ME 390G: Nuclear Engineering Laboratory ME390T: Nuclear- and Radio-Chemistry NOTE[)),Academic courses with minimal or no use of the reactorfacilities The NRE program's graduate degrees are completely autonomous; they are Master of Science in Engineering (Concentration in Nuclear Engineering) and Doctor of Philosophy (Concentration in Nuclear Engineering). Course requirements for these degrees and the qualifying examination for the Ph.D. are separate and distinct from other areas of Mechanical Engineering. A Dissertation Proposal and Defense of Dissertation are required for the Ph.D. degree and acted on by a NRE dissertation committee.

2.6.2 Other Education Efforts The NETL has participated in the IAEA Fellowship programs for the past decade. Several Fellows and Visiting Scientists spend 3-6 months at the NETL per year.

The Nuclear Engineering Teaching Lab also extends its facilities to two Historically Black Colleges or Universities (HBCUs). Both Hutson-Tillotson University in Austin and Florida Memorial University in Miami Gardens, Florida have participated in this these educational efforts.

In addition to formal classes, the NETL routinely provides short courses or tours for Texas agencies, high schools and pre-college groups such as the Boy Scouts of America. Tours and 15 3/2014

2013 NETL Annual Report special projects are available to promote public awareness of nuclear energy issues. A typical tour is a general presentation for high school and civic organizations. Other tours given special consideration are demonstrations for interest groups such as physics, chemistry and science groups.

2.6.3 Research & Service A more comprehensive description of the nuclear analytic techniques and facilities available at the NETL is provided in section 5. Personnel support for these activities includes faculty, graduate and undergraduate research assistants, and NETL staff.

2.7 NETL Support NETL funding is provided by state appropriations, research grants, and fees accrued from service activities. Research funding supplements the base budget provided by the State and is generally obtained through competitive research and program awards. Funds from service activities supplement base funding to allow the facility to provide quality data acquisition and analysis capabilities. Both sources of supplemental funds (competitive awards and service work) are important to the education and research environment for students. The U.S. Nuclear Regulatory Commission supported development of the Summer Nuclear Engineering Institute, and supports continuation of the program.

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2013 NETL Annual Report 3.0 FACILITY DESCRIPTION 3.1 NETL History Development of the nuclear engineering program was an effort of both physics and engineering faculty during the late 1950's and early 1960's. The program became part of the Mechanical Engineering Department where it currently resides. The program installed and operated the first UT TRIGA nuclear reactor in Taylor Hall on the main campus. Initial criticality for the first UT reactor was August 1963. Power at startup was 10 kilowatts with a power upgrade to 250 kilowatts in 1968. Total burnup during the 25 year period from 1963 to final operation in April 1988 was 26.1 megawatt-days. Pulse capability of the reactor was 1.4% Ak/k with a total of 476 pulses during the operating history.

In October 1983, planning was initiated for the NETL to replace the original UT TRIGA installation. Construction was initiated December 1986 and completed in May 1989. The NETL facility operating license was issued in January 1992, with initial criticality on March 12, 1992.

Dismantling and decommissioning of the first UT TRIGA reactor facility was completed in December 1992.

3.2 NETL SITE, J.J. Pickle Research Campus Land development in the area of the current NETL installation began as an industrial site during the 1940's. Following the 1950's, lease agreements between the University and the Federal government led to the creation of the Balcones Research Center. The University became owner of the site in the 190's, and in 1994 the site name was changed to the J.J. Pickle Research Campus (PRC) in honor of retired U.S. Congressman James "Jake" Pickle.

The PRC is a multidiscipline research campus on 1.87 square kilometers. The site consists of two approximately equal areas, east and west. An area of about 9000 square meters on the east tract is the location of the NETL building. Sixteen separate research units and at least five other academic research programs conduct research at locations on the PRC. Adjacent to the NETL site are the Center for Research in Water Resources, the Bureau of Economic Geology, and the Research Office Complex, illustrating the diverse research activities on the campus. A 17 3/2014

2013 NETL Annual Report Commons Building provides cafeteria service, recreation areas, meeting rooms, and conference facilities.

3.3 NETL Building Description The NETL building is a 1950 sq meter (21,000 sq ft), facility with laboratory and office spaces.

Building areas consist of two primary laboratories of 330 sq m (3600 sq ft) and 80 sq m (900 sq ft), eight support laboratories (217 sq m, 2340 sq ft), and six supplemental areas (130 sq m, 1430 sq ft). Conference and office space is allocated to 12 rooms totaling 244 sq m (2570 sq ft). One of the primary laboratories contains the TRIGA reactor pool, biological shield structure, and neutron beam experiment area. A second primary laboratory consists of 1.3 meter (4.25 ft) thick walls for use as a general purpose radiation experiment facility. Other areas of the building include shops, instrument & measurement laboratories, and material handling facilities.

The NETL Annex was installed in 2005, a 24 by 60 foot modular class room building adjacent to the NETL building. The building provides classroom space and offices for graduate students working at the NETL.

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2013 NETL Annual Report 4.0 UT-TRIGA MARK II RESEARCH REACTOR TRIGA is an acronym for Training, Research, Isotope production, General Atomics. The TRIGA Mark II reactor is a versatile and inherently safe research reactor conceived and developed by General Atomics to meet education and research requirements. The UT-TRIGA reactor provides sufficient power and neutron flux for comprehensive and productive work in many fields including physics, chemistry, engineering, medicine, and metallurgy

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The reactor core is surrounded by a reflector, a 1 foot thick graphite cylinder. The reactor is controlled by manipulating cylindrical "control rods" containing boron.

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2013 NETL Annual Report 4.1 Reactor Core.

The reactor core is an assembly of about 100 fuel elements surrounded by an annular graphite neutron reflector. Fuel elements are positioned by an upper and lower grid plate, with penetrations of various sizes in the upper grid plate to allow insertion of experiments. Each fuel element consists of a fueled region with graphite sections at top and bottom, contained in a thin-walled stainless steel tube. The fuel region is a metallic alloy of low-enriched uranium in a zirconium hydride (UZrH) matrix. Physical properties of the TRIGA fuel provide an inherently safe operation. Rapid power transients to high powers are automatically suppressed without using mechanical control; the reactor quickly and automatically returns to normal power levels.

Pulse operation, a normal mode, is a practical demonstration of this inherent safety feature.

N . ,

Figure 4-2, Core and Support Structure Details 4.2 Reactor Reflector.

The reflector is a graphite cylinder in a welded aluminum-canister. A 10" well in the upper surface of the reflector accommodates an irradiation facility, the rotary specimen rack (RSR), and horizontal penetrations through the side of the reflector allow extraction of neutron beams. In 2000 the canister was flooded to limit deformation stemming from material failure in welding 20 3/2014

2013 NETL Annual Report joints. In 2004, the reflector was replaced with some modification, including a modification to the upper grid plate for more flexible experiment facilities.

4.3 Reactor Control.

The UT-TRIGA research reactor can operate continuously at nominal powers up to 1.1 MW, or in the pulsing mode with maximum power levels up to 1500 MW (with a trip setpoint of 1750 MW) for durations of about 10 msec. The pulsing mode is particularly useful in the study of reactor kinetics and control. The UT-TRIGA research reactor uses a compact microprocessor-driven control system. The digital control system provides a unique facility for performing reactor physics experiments as well as reactor operator training. This advanced system provides for flexible and efficient operation with precise power level and flux control, and permanent retention of operating data.

The power level of the UT-TRIGA is controlled by a regulating rod, two shim rods, and a transient rod. The control rods are fabricated with integral extensions containing fuel (regulating and shim rods) or air (transient rod) that extend through the lower grid plate for full span of rod motion. The regulating and shim rods are fabricated from B4C contained in stainless steel tubes; the transient rod is a solid cylinder of borated graphite clad in aluminum. Removal of the rods from the core allows the rate of neutron induced fission (power) in the UZrH fuel to increase.

The regulating rod can be operated by an automatic control rod that adjusts the rod position to maintain an operator-selected reactor power level. The shim rods provide a coarse control of reactor power. The transient rod can be operated by pneumatic pressure to permit rapid changes in control rod position. The transient rod moves within a perforated aluminum guide tube.

21 3/2014

2013 NETL Annual Report 5.0 EXPERIMENT AND RESEARCH FACILITIES Neutrons produced in the reactor core can be used in a wide variety of research applications including nuclear reaction studies, neutron scattering experiments, nuclear analytical techniques, and irradiation of samples. Facilities for positioning samples or apparatus in the core region include cut-outs fabricated in the upper grid plate, a central thimble in the peak flux region of the core, a rotary specimen rack in the reactor graphite reflector, and a pneumatically operated transfer system accessing the core in an in-core section. Beam ports, horizontal cylindrical voids in the concrete shield structure, allow neutrons to stream out away from the core. Experiments may be performed inside the beam ports or outside the concrete shield in the neutron beams.

Areas outside the core and reflector are available for large equipment or experiment facilities.

Current NRE and NETL personnel and active projects are tabulated at the end of this section (Table 5.3, 5.4).

In addition to reactor facilities, the NETL has a subcritical assembly, various radioisotope sources, radiation producing machines, and laboratories for spectroscopy and radiochemistry.

5.1 Upper Grid Plate 7L and 3L Facilities The upper grid plate of the reactor contains four removable sections configured to provide space for experiments otherwise occupied by fuel elements (two three-element and two seven-element spaces). Containers can be fabricated with appropriate shielding or neutron absorbers to tailor the gamma and neutron spectrum to meet specific needs. Special cadmium-lined facilities have been constructed that utilize three element spaces.

5.2 Central Thimble The reactor is equipped with a central thimble for access to the point of maximum flux in the core. The central thimble is an aluminum tube extending through the central penetration of the top and bottom grid plates. Typical experiments using the central thimble include irradiation of small samples and the exposure of materials to a collimated beam of neutrons or gamma rays.

22 3/2014

2013 NETL Annual Report 5.3 Rotary Specimen Rack (RSR)

A rotating (motor-driven) multiple-position specimen rack located in a well in the top of the graphite reflector provides for irradiation and activation of multiple samples and/or batch production of radioisotopes. Rotation of the RSR minimizes variations in exposure related to sample position in the rack. Samples are loaded from the top of the reactor through a tube into the RSR using a specimen lifting device. A design feature provides the option of using pneumatic pressure for inserting and removing samples.

5.4 Pneumatic Tubes A pneumatic transfer system supports applications using short-lived radioisotopes. The in-core terminus of the system is normally located in the outer ring of fuel element positions, with specific in-core sections designed to support thermal and epithermal irradiations. The sample capsule is conveyed to a sender-receiver station via pressure differences in the tubing system. An optional transfer box permits the sample to be sent and received to three different sender-receiver stations. One station is in the reactor confinement, one is in a fume hood in a laboratory room, and the third operates in conjunction with an automatic sample changer and counting system.

5.5 Beam Port Facilities Five neutron beam ports penetrate the concrete biological shield and reactor water tank at core level. Specimens may be placed inside a beam port or outside the beam port in a neutron beam from the beam port. The beam ports were designed with different characteristics to accommodate a wide variety of experiments. Shielding reduces radiation levels outside the concrete biological shield to safe values when beam ports are not in use. Beam port shielding is configured with an inner shield plug, outer shield plug, lead-filled shutter, and circular steel cover plate. A neutron beam coming from a beam port may be modified by using collimators, moderators and/or neutron filters. Collimators are used to limit beam size and beam divergence. Moderators and filters are used to change the energy distribution of neutrons in beams (e.g., cold moderator).

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2013 NETL Annual Report BP #3 BP#4 BP#5 I BP#1 Figure 5-2, Beam Ports I Table 5-2, Dimensions of Standard Beam Ports I BP# 1, BP#2, BP#4 At Core 6 in. 15.24 cm At Exit 8 in. 20.32 cm BP #3, BP#5 At Core 6 in. 15.24 cm 8 in. 20.32 cm 10 in. 25.40 cm At Exit: 16 in. 40.64 cm 5.5.1 Beam Port 1 (BP1)

BPI is connected to BP5, forming a through port. The through port penetrates the graphite reflector tangential to the reactor core, as seen in Figure 5-2. This configuration allows introduction of specimens adjacent to the reactor core to gain access to a high neutron flux from either side of the concrete biological shield, and can provide beams of thermal neutrons with relatively low fast-neutron and gamma-ray contamination.

24 3/2014

2013 NETL Annual Report A reactor-based slow positron beam facility is being fabricated at BP1. The facility (Texas Intense Positron Source) will be one of a few reactor-based slow positron beams in the world.

The Texas Intense Positron Source consists of a copper source, a source transport system, a combined positron moderator/remoderator assembly, a positron beam line and a sample chamber.

The copper source will be irradiated in the middle section of the through port (BP1-BP5).

The isotope 6 4 Cu formed by neutron capture in 6 3 Cu (69 % in natural copper) has a half life of 12.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , with the branching ratio for V3+emission of 19 %.. A source transport system in a 4 meter aluminum system will be used to move the source to the irradiation location and out of the biological shield. The source will be moved away from the neutron beam line outside the biological shielding to an ultra high vacuum (at around 10- 10 torr) chamber, where the moderator assembly is located. High energy positrons from the source will be slowed down to a few eV by a tungsten foil moderator that also acts as a remoderator to reduce the beam size to enable beam transport to a target for experimentation. The beam will be electrostatically guided to deliver about 108 positrons/sec in the energy range of 0 - 50 keV.

5.5.2 Beam Port 2 (BP2)

BP2 is a tangential beam port, terminating at the outer edge of the reflector. A void in the graphite reflector extends the effective source of neutrons into the reflector for a thermal neutron beam with minimum fast-neutron and gamma-ray backgrounds. Tangential beams result in a "softer" (or lower average-) energy neutron beam because the beam consists of scattered reactor neutrons. BP2 is configured to support neutron depth profiling applications, with a prompt-gamma neutron activation analysis sharing the beam port.

Neutron Depth Profiling (NDP) Some elements produce charged particles with characteristic energy in neutron interactions. When these elements are distributed near a surface, the particle energy spectrum is modulated by the distance the particle traveled through the surface. NDP uses this information to determine the distribution of the elements as a function of distance to the surface.

Prompt-Gamma Neutron Activation Analysis (PGNAA) Characteristic gamma radiation is produced when a neutron is absorbed in a material. PGNAA analyzes gamma radiation to 25 3/2014

2013 NETL Annual Report identify the material and concentration in a sample. PGNAA applications include: i) determination of B and Gd concentration in biological samples which are used for Neutron Capture Therapy studies, ii) determination of H and B impurity levels in metals, alloys, and semiconductor, iii) multi-element analysis of geological, archeological, and environmental samples for determination of major components such as Al, S, K, Ca, Ti, and Fe, and minor or trace elements such as H, B, V, Mn, Co, Cd, Nd, Sm, and Gd, and iv) multi-element analysis of biological samples for the major and minor elements H, C, N, Na, P, S, Cl, and K, and trace elements like B and Cd.

0 11.E+01 I.E+O0 1.E-03 1.E-02 0 1000 2000 3000 4000 5000 6000 7000 8000 Energy [kev]

Figure 5-3, PGAA Spectra of Carbon Composite Flywheel 5.5.3 Beam Port 3 (BP3)

BP3 is a radial beam port. BP3 pierces the graphite reflector and terminates at the inner edge of the reflector. This beam port permits access to a position adjacent to the reactor core, and can provide a neutron beam with relatively high fast-neutron and gamma-ray fluxes. BP3 contains the Texas Cold Neutron Source Facility, a cold source and neutron guide system.

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2013 NETL Annual Report

- C Ciwuonmi sr I 4 b co u t Figure 5-4, Prompt Gamma Focused-Neutron Activation Analysis Facility Texas Cold Neutron Source. The TCNS provides a low background subthermal neutron beam for neutron reaction and scattering research. The TCNS consists of a cooled moderator, a heat pipe, a cryogenic refrigerator, a vacuum jacket, and connecting lines. The TCNS uses eighty milliliters of mesitylene moderator, maintained by the cold source system at -36 K in a chamber within the reactor graphite reflector. A three-meter aluminum neon heat pipe, or thermosyphon, is used to coco. th(. moderater chamber. The heat pipe working fluid evaporates at the moderator chamber and conienses at the cold head.

Cold neutrons from the moderator chamber are transported by a 2-m-long neutron guide inside the beam port to a 4-m-long neutron guide (two 2-m sections) outside the beam port. Both neutron guides have a radius of curvature equal to 300 m. All reflecting surfaces are coated with Ni-58. The guide cross-sectional areas are separated into three channels by i-mm-thick vertical walls that block line-of-sight radiation streaming.

Prompt Gamma Focused-Neutron Activation Analysis Facility The UT-PGAA facility utilizes the focused cold-neutron beam from the Texas Cold Neutron Source. The PGAA sample is located at the focal point of the converging guide focusing system to provide an enhanced reaction rate with lower background at the sample-detector area as compared to other facilities 27 3/2014

2013 NETL Annual Report using filtered thermal neutron beams. The sample handling system design permits the study of a wide range of samples and quick, reproducible sample-positioning.

5.5.4 Beam Port 4 (BP4)

BP4 is a radial beam port that terminates at the outer edge of the reflector. A void in the graphite reflector extends the effective source of neutrons to the reactor core. This configuration is useful for neutron-beam experiments which require neutron energies higher than thermal energies. BP4 was configured in 2005 to support student laboratories.

5.5.5 Beam Port 5 (BP5)

A Neutron Radiography Facility is installed at BP5 (Figure 5-5). Neutrons from BP5 illuminate a sample. The intensity of the exiting neutron field varies according to absorption and scattering characteristics of the sample. A conversion material generates light proportional to the intensity of the neutron field as modified by the sample.

Disksou Remior RAfisor camw Coflirw~or COiMM"o Figure 5-5, Neutron Radiography System The conversion material is integral in one imaging system at the NETL; there are two independent conversion devices available at the NETL. A Micro-Channel Plate image intensifying technology system (NOVA Scientific) is characterized by high resolution (up to 30 ptm) over a small (approximately 1/2 in.) field of view. A larger image can be obtained using a more conventional 7X7 in. 2 6LiF/ZnS scintillation screen.

28 3/2014

2013 NETL Annual Report A conversion screen mounted on a video tube provides a direct single in one neutron radiography camera at the NETL. The image produced by the independent conversion apparatuses can eb recorded in one of three available digital cameras. Cameras include a charge injection device (CID) camera, a cryogenically cooled charge coupled device (CCD) camera, and an electronically cooled CCD camera. The digital image is captured in a computer, where image analysis software produces the final product.

5.6 Other Experiment and Research Facilities The NETL facility makes available several types of radiation facilities and an array of radiation detection equipment. In addition to the reactor, facilities include a subcritical assembly, various radioisotope sources, machine produced radiation fields, and a series of laboratories for spectroscopy and radiochemistry.

5.6.1 Subcritical Assembly A subcritical assembly of 20% enriched uranium in a polyethylene moderated cylinder provides an experimental device for laboratory demonstrations of neutron multiplication and neutron flux measurements. A full critical loading of fuel previously at the Manhattan College Zero Power Reactor is currently at the facility.

5.6.2 Radioisotopes Radioisotopes are available in a variety of quantities. Gamma and beta sources generally in microcurie to millicurie quantities are available for calibration and testing of radiation detection equipment. Neutron sources of plutonium-beryllium and californium-252 are available.

Laboratories provide locations to setup radiation experiments, test instrumentation, prepare materials for irradiation, process radioactive samples and experiment with radiochemical reactions.

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2013 NETL Annual Report 5.6.3 Radiation Producing Machines The NETL houses a 14-MeV neutron generator. The generator is currently being developed for high-energy neutron activation analysis and portable neutron radiography applications.

5.6.4 Support Laboratories There are several laboratories adjacent to the reactor. One laboratory supports sample and standards preparation. Labs are also used for various types of radio assay, with one dedicated to a receiving station for rabbit system operations and sample counting. A control system permits automated operations.

The DOE is anticipating a loss of nuclear workforce with limited prospects for replacement of radio chemists in the national laboratory system. Therefore, a graduate-level radiochemistry laboratory was developed with support from the Department of Energy (DOE). The laboratory consists of state-of-the-art Alpha Spectroscopy Systems, Liquid Scintillation Counting System and several High Resolution Gamma Counting Systems. Students are encouraged to develop skills and interests that make them viable replacements for the nuclear workforce.

5.7 Experiment Facility Utilization Figure 5-1 provides the number of hours of reactor operation allocated to experiments in the applicable facility, with abbreviations in Figure 5-1 explained in Table 5.1 that follows. There were 776.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months utilized for experiments in 2013. In addition, operations supported irradiation in more than one experiment facility simultaneously for 72.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Therefore, total time for reactor operations was 848.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . The number of operating hours allocated to experiments includes the "console key on" time.

30 3/2014

2013 NETL Annual Report Classroom and 2013 ODeratine Hours Distribution Operator Training 6%

Tours and Pulses Bps 2%

BP4*0 0 3

BP 0% 6%

BP2 1% Bp Cd3L 3%

Figure 5-1, Utilization of Experiment Hours Table 5.1 Terminology for Figure 5-1 PGNAA Prompt Gamma Neutron Activation Analysis Sample material irradiated in the lead-lined (enhanced for lower gamma) 3-Pb3L element position in-core facility (isotope production)

Sample material irradiated in the cadmium-lined (enhanced for epithermal Cd3L neutrons) 3-element position in-core facility (generally used for NAA)

NAA Neutron Activation Analysis for samples irradiated in epithermal neutron EPTNT pneumatic tube (irradiation position lined with cadmium)

Neutron Activation Analysis for samples irradiated in thermal neutron NAA TPNT pneumatic tube NAA RSR Neutron Activation Analysis for samples irradiated in rotary specimen rack BP 1-5 Beam Port Tour General facility tours Academic support (ME337, ME361, ME388, ME389N, Health Physics, Classes Summer Nuclear EngineeringInstitute)

Training Operations supporting reactor operator training or requalification program Pulse Time required to support approximately 36 pulses Radiography Neutron radiography 31 3/2014

2013 NETL Annual Report 5.8 Nuclear Program Faculty Activities Projects and publications associate with the NETL during 2013 are provided below.

., ,,,.iTable 5. ,Publication%,*1*

Reviewed Coq~ferenc *loceeding , "...

C.E. Cox, W. HenAg,*A%.C, Huber;A.K. Warburton, P.M. Grudberg, S.J. Asztaos, H. Tan, S.

Biegalski,j,4k4-eierint Siiiwc I'ldiode detector fer high resolution radioxqnon measuremctr sihigsnimulianeous X~ray and electron spectroscopy," sub' itted to IEEE Transactions, O ctober 2013. (Role:'Conducted tests of detector with radioxenon isotopes at The University of 'lexasat Austin.)

A. Reinhart, A. Athey,, S.'Biegat~ki, "Spatially-Aware Temporal Mapping of Gamma Spectra,"

accepted to IEEE Transactions 'onNuclear Science (201 J.Ji. (RoleE Aided in the student advising and testing of the system). . .

P.W. Eslinger, T.W. Bowyer, M.W. Cooper, D.A. Haas, J.C. Hayes, H.S. Miley, J.P. Rishel, V.T.

Woods, S.R. Biegalski, I. Hoffman, E. Korpach, J. Yi, K. Ungar, and B. White," Source term estimation of radioxenon released from the Fukushima Dai-ichi nuclear reactors using measured air concentrations and atmospheric transport modeling," Journal of Environmental Radioactivity (2013), http://dx.doi.org/10.1016/j.jenvrad.2013.10.013 (Role: Data analysis and nuclear forensics.)

C. M. Egnatuk and S.R. Biegalski, "Radioargon production through the irradiation of calcium oxide, "Journal of Radioanalytical and Nuclear Chemistry, DOI 10.1007/s 10967-012-2400-z, 2013. (Role: Project PI, student advisor, and reviewed paper.).

JD Lowrey, S.R. Biegalski, AG Osborne, MRDeinert," Subsurface mass transport alters the radioxenon signatures that are used to identify clandestine nuclear tests," Geophysical Research Letters, 40, 1-5, 2013. (Role: Project.P1, student advisor, and reviewed paper.)

Recktenwald, GD, MR Deinert (2013): increasing the power density when using inert matrix fuels to reduce production of transturarjics. GLOBAL 2013: International Fuel Cycle Conference, Salt Lake City, Utah, USA, September'29th - October 3rd.

Osborne, AG, TA Smith, MR Deinert (2013): Comparison of actinide production in traveling wave and pressurized water reactors. GLOBAL 2013: International Fuel Cycle Conference, Salt Lake City, Utah, USA, September 29th - October 3rd.

Osborne, AG, DW Harding, MR Deinert (2013): Practical methods to improve the development of computational software. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, USA, May 5-9.

Osborne, AG, MR Deinert (2013): Comparison of neutron diffusion and Monte Carlo models for a fission wave. International Conference on Mathematics and Computational Methods Applied to Nuclear Science & Engineering (M&C 2013), Sun Valley, Idaho, USA, May 5-9.

S. Biegalski, "Utilization of Wavelet Tranforms for Denoising Fission Product Radionuclide Spectra," Transactions of the American Nuclear Society, Vol. 109, 2013. (Role: Conducted all 32 3/2014

2013 NETL Annual Report Table 5.4, Publications - 2013 work and wrote abstract.) Invited.

R. Gomez and S. Biegalski, "Aerosol Filter Sample Inhomogeneity in Samples with Debris from the Fukushima Daiichi Nuclear Accident," Transactions of the American Nuclear Society, Vol.

109, 2013. (Role: Student advisor and reviewed abstract.) Invited.

K. Dayman and S. Biegalski, "Measurement of Short-Lived Fission Product Yeilds,"

Transactions of the American Nuclear Society, Vol. 109, 2013. (Role: Student advisor and reviewed abstract.)

K. Dayman, T. Tipping, S. Biegalski, "A Field Survey Laboratory for a Course in Nuclear Instrumentation," Transactions of the American Nuclear Society, Vol. 109, 2013. (Role: Student advisor and reviewed abstract.)

S. Biegalski, F. Klingberg, "Facility Advancements in Radioxenon Production at The University of Texas at Austin," Transactions of the American Nuclear Society, Vol. 108, 2013. (Role:

Project PI, student advisor, and wrote abstract.)

C. Johnson, S. Biegalski "Background Radioxenon Soil Concentrations Due to Spontaneous Fission", Transactions of the American Nuclear Society, Vol. 108, 2013. (Role: Project PI, student advisor, and reviewed abstract.)

Journalpapers Shin, J-H, J-Y Parlange, MR Deinert (2013): Scale effects in the latent heat of melting in nanopores. Journal of Chemical Physics, 139, 044701.

Osborne, AG, MR Deinert (2013): Comparison of neutron diffusion and Monte Carlo simulations of a fission wave. Annals of Nuclear Energy, 62, 269-273.

Dembia, CL, GD Recktenwald, MR Deinert (2013): Bondarenko method for obtaining group cross sections in a multi-region collision probability model. Progress in Nuclear Energy, 67, 124-131.

Recktenwald, GD, MR Deinert (2013): Effect of burnable absorbers on inert matrix fuel performance and transuranic burnup in a low power density light water reactor. Energies, 6, 2291-2304.

Gilbert, AJ, MR Deinert (2013): Neutron tomography of axisymmetric flow fields in porous media. Nuclear Instruments and Methods in Physics Research:B, 301, 15, 23-28.

Stoll, BL, TA Smith, MR Deinert (2013): Potential for rooftop photovoltaics in Tokyo to replace nuclear capacity. Environmental Research Letters, 8, 014042.

Lowrey, JD, SR Biegalski, AG Osborne, MR Deinert (2013): Subsurface mass transport affects the radioxenon signatures that are used to identify clandestine nuclear tests. Geophysical Research Letters, 40, 1-5.

Talks & Seminars Cornell University, (Invited speaker) Energy Seminar Series, November 25, 2013. MR Deinert MIT, Engineering Systems Division, invited speaker, Workshop on Modeling Social, Technical and Natural Systems for Policy, September 25-27, 2013. MR Deinert Math and Computation 2013 - International Conference on Mathematics and Computational 33 3/2014

2013 NETL Annual Report 6.0 FACILITY OPERATING SUMMARIES 6.1 Operating Experience The UT-TRIGA reactor operated for 776 hours0.00898 days 0.216 hours 0.00128 weeks 2.95268e-4 months on 190 days in 2012, producing a total energy output of 305.7 MW-hrs. The history of operations over the past 21 years of facility operation is provided in Figures 6-1 and 6-2. As illustrated, operating time has shown a marked increase from the first several years and has been relatively stable for the past decade. Varying research requirements over the past few years have led to a decrease in total energy generation.

250 M 200 0 0 0 100 E 50 z

0 1992 1995 1998 2001 2004 2007 2010 2013 Year of Operation Figure 6-1, Days of Operation 35.00 30.00 w 25.00 o20.00 15.00 (U 10.00 5.00 0.00 1992 1995 1998 2001 2004 2007 2010 2013 Year of Operation Figure 6-2, Energy Generation 6.2 Unscheduled Shutdowns Reactor safety system protective actions are classified as limiting safety system (LSSS) trip, a limiting condition for operation (LCO) trip or a trip of the SCRAM manual switch. The use of 35 3/2014

2013 NETL Annual Report Table 5.4, Publications - 2013 Methods Applied to Nuclear Engineering, Sun Valley ID, May 7, 2013. MR Deinert American Physical Society, Denver CO, April 15, 2013. MR Deinert Pennsylvania State University, (Invited Speaker) Department of Mechanical and Nuclear Engineering, April 4, 2013. MR Deinert USC, (Invited Speaker) Department of Mechanical Engineering, February 28, 2013. MR Deinert I-NEST Fuel Cycle CORE Regional Outreach Meeting, (Invited Speaker) February 20-21, 2013, Austin, TX. MR Deinert Texas A&M University, (Invited Speaker) Department of Nuclear Engineering, February 4, 2013.

MR Deinert 34 3/2014

2013 NETL Annual Report Power level monitoring signals during steady state operations fluctuate because the digital power level monitoring has some intrinsic noise related to signal sampling and analysis. Four reactor trips occurred as transient fluctuations during high power operations exceeded the steady state power level trip point. Safety analyses demonstrate transients (pulses) to orders of magnitude greater than the steady state power level limit do not result in unacceptable consequences, and these trips are not a safety issue.

6.3 Utilization Utilization of the NETL reactor facility is near the maximum possible under a 5-day per week schedule. The main categories of facility utilization include education, undergraduate research, graduate research, and external research collaborations. Table 6.3 lists the external research collaborations at NETL since 2009. Facility usage is largely dominated by the use of nuclear analytical techniques for sample analysis. These techniques include neutron activation analysis, neutron radiography, neutron depth profiling, and prompt gamma activation analysis.

Table 6.3, NETL External Research Collaborations since 2009 External Collaborator Location Facility Utilization Trinitek Services, Inc. Sandia Park, NM Soil sample analysis Gatineau, Quebec, Environment Canada Arctic air filter analysis Canada Bridgeport Instruments Austin, TX Radiation detector development Carollo Engineering Austin, TX Radiation damage studies Evergreen Solar Marlboro, MA Silicon wafer trace element analysis Kaizen Innovations Georgetown, TX Soil sample analysis Idaho National Laboratory Idaho Falls, ID Isotope production Illinois State Geological Champaign, IL Water sample analysis Survey UT Biology Austin, TX Soil sample analysis Department of Geological Austin, TX Geological sample irradiation Sciences Los Alamos National Los Alamos, NM Sample irradiations Laboratory Lolodine, LLC Jersey City, NJ Nut Analysis UT Health Science Center Houston, TX Nanoparticle analysis Pacific Northwest National Richland, WA Isotope Production Laboratory RMT, Inc. Madison, WI Water sample analysis Signature Science Material irradiations and shrapnel Austin, TX analysis Biomedical Engineering Austin, TX Tissue sample analysis Department 37 3/2014

2013 NETL Annual Report the manual scram switch in normal reactor shutdowns is not a protective action. The following definitions in Table 6.1 classify the types of protective actions recorded.

Table 6.1, Protective Action Definitions Protective Action Description Safety System Setting Automatic shutdown actuated by detection of limiting LSSS safety system setting such as fuel temperature or percent power Condition for Operation Automatic shutdown actuated detection of a limiting LCO - (analog detection) condition for operation within a safety channel or the instrument control and safety system such as pool water level, a loss of detector high voltage or an external circuit trip Condition for Operation Automatic shutdown actuated by software action LCO - (digital detection) detecting inoperable conditions within a program function of ýhe instrument control and safety system such as watchdog timers or program database errors Manual Switch Maually initiated; emergency shutdown (protective action)

-- S 4 Table 6.2 lists 12 unscheduled shutdowns that occurred in 2013, all of which were initiated by the reactor safety system.

Table 6.2, SCRAM Log for 2013 Date Time Type Comments 01/29/2013 10:53 SCRAM FTI Thermocouple, Intermittent Failure 01/29/2013 15:10 SCRAM FTI ? Thermocouple, Intermittent Failure 03/29/2013 09:57 SCRAM FT1 Thermocouple, Intermittent Failure 05/06/2013 19:13 SCRAM %PW (NP) Power Fluctuations in Auto Operation Mode 06/14/2013 10:43 SCRAM %PW2-(NP) Power Fluctuations in Auto Operation Mode 08/07/2013 16:32 SP**A) Power Fluctuations in Auto Operation Mode 08/08/2013 16:32 SCIA Power Fluctuations in Auto Operation Mode 12/04/2013 14:17 SCRAM-A Thermocouple, Intermittent Failure 12/13/2013 13.!54 SCRAM fT Y- Thermocouple, Intermittent Failure There were five temperature channel trips in 2013 related to thermocouple intermittent signal failure. In all cases, time dependent data indicates fuel temperatures were normal and the trips occurred because of signal transients not indicative of actual fuel temperature. Attempts to isolate the trip to a specific component or recreate the failure have not been successful. The failure mode is conservative and acceptable until either the channel fails in a more consistent mode or the characteristics leading to the actuations can be identified.

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2013 NETL Annual Report Table 6.3, NETL External Research Collaborations since 2009 External Collaborator Location Facility Utilization TX Plant sample analysis and student Southwestern University Georgetown, TXlaboratreslaboratories Comprehensive Nuclear- Vienna, Austria Radioxenon production Test-Ban Treaty Organization Clarkson University Potsdam, NY Air filter analysis JWK Corporation Annandale, VA Sample irradiations Civil and Environmental Austin, TX Fly ash sample analysis Engineering Department National Center for Energy, Science and Nuclear Rabat, Morocco Soil sample analysis Technologies Nanospectra Biosciences, Houston, TX Tissue sample analysis Inc.

U.S. Nuclear Regulatory Rockville, MD Reactor operations training Commission NTS Albuquerque, NM Isotope production Omaha Public Power District Blair, NE Boral coupon analysis TEKLAB Collinsville, IL Water sample analysis XIA Hayward, CA Radioxenon production Lawrence Livermore Livermore, CA Isotope production National Laboratory Various activation and analysis services were carried out in support of the overall UT mission and for public service. Analytical service work was performed for outside agencies. Over 1100 samples were irradiated during 2013, continuing the decrease that began in 2012, as illustrated in Figure 6-4. There has been no utilization of BP2 or BP4 for the past few years, and a single utilization of the central thimble. Thermal pneumatic irradiations decreased significantly compared to the annual average since 2003, while epithermal irradiations for the manual PNT remained consistent with the historical average, and for the automatic PNT was about twice the historical average. Three element thermal facility irradiations were 55% of the historical average, and 20% for epithermal irradiations.

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2013 NETL Annual Report 3500 i-2000O 5

100W l- 0 1000 Soo 0

2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Yeer Figure 6-4, NETL Sample Activation 6.4 Routine Scheduled Maintenance All surveillances and scheduled maintenance activities were completed during the reporting year at the required frequencies. All results met or exceeded the requirements of the Technical Specifications.

6.5 Corrective Maintenance Activities this reporting period predominately consisted of adjustment of instrument system components (potentiometers or digital system constants) to re-tune or recalibrate the circuits to recommended levels. Corrective maintenance activities included the replacement of individual components or assemblies with like or similar replacement parts. The following list is a summary of the corrective maintenance activities accomplished by facility staff:

Replacement of resin tank bushing for the conductivity probe

" Conductivity probe re-termination

" Particulate CAM pump air pump repair (replacement of carbon vanes)

" Adjustment of discriminator on Argon- CAM to compensate for detector aging.

" Re-termination of regulating rod down switch

" Replacement of DAC hard drive disk, with Main-I retest 39 3/2014

2013 NETL Annual Report

" Replaced NP action pac (PAC- 17) by manufacturer recommendation; Main-2 retests

Replaced Campbell Amp/ Pre-Amp with manufacturer supplied spare

" Replacement of set screw on Regulating Rod position pod within the DAC

" Adjustment of Shim 2'switch.actuatpr In late November, a small leak was discovered in BP-5 experimental area. Appropriate actions were taken to clean up the leaking water, and op'ratio's conithaed*at-minirial power levels. The leak rate increased significantly delaying operations urtil further examination of the leak during the annual maintenance period beginning in 2014. A water transfersystem was set in place to temporarily hold the water until suitable for sewer disposal as deemed by Health Physics standards. This created several temporary weekly maintenance items:

" Transferring water out of a collection volume into a 55 gallon drum

" Pool makeup increased from bimonthly to weekly at approximately 225 liters

" Operations were delayed for troubleshooting and design of a temporary fix

Corrective action in diagnosing is set to begin in early 2014 6.6 Facility Changes During the 2013 calendar year, changes in the facility staffing included the granting of three Reactor Operator (RO) licenses by the NRC and the upgrade of a current RO to a Senior Reactor Operator (SRO) in the month of April. Some maintenance activities resulted in hardware changes as indicated above. Procedure changes were accomplished for administrative and radiation protection procedures.

6.6.1 Staff changes:

There was one Reactor Operator license terminated during the month of December 2013. The reason for termination was the completion of a degree from the University of Texas at Austin, and the operator left to further their career. The recently upgraded Senior Reactor Operator also completed a degree from the University, and chose to return part- time in order to fulfill the federal requirement of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per quarter to maintain the license.

40 3/2014

2013 NETL Annual Report 6.6.2 Facility changes Facility changes in in 2013 principally included replacement of obsolete parts During 2013 enhancements to the existing facility access control and security monitoring sysems supported by the Global Threat Reduction Initiative (DOEFNNSA) continued. Facility modificaions included the upgrading and addition of security systems for the reactor facility.

The action pac providing signal to a console power graph was replaced by a unit based on manufacturer's recommendation.

The pneumatic sample transfer system CO 2 cylinder station was repositioned and moved out of the auxiliary mechanical room to an area in the reactor bay below the stairwell. A small (1/4")

penetration was made in the equipment room wall to the reactor bay to route the gas line.

The DAC ICS hard drive failed, and was replaced with a functional equivalent.

The pneumatic sample system blower was replaced with a functional equivalent.

The integral noble gas monitor internal power supply failed, and was replaced with an external power supply. The failure was preceded by a history of irregular spikes in signal.

6.6.3 Procedure revision/updates Several major rewrites were made to the Health Physics procedure (HP- 1-7) and to administrative procedure 004 (Admn-004). The changes to Admn-004 and HP were revised to conform to ANSI/ ANS-15.11-2009. Additional changes to HP-1-7 include improved personnel monitoring, redefinition of position assignements, and incorporation of changes in regulations over exposure limits and radioactive materials, including:

" Dosimetry required in absence of HP

" Use of electronic dosimeters

" Clarification of NETL radiation worker responsibilities as visitor escorts

Updating records and log sheets used in health physics activities

" Removal of outdated references and obsolete information.

41 3/2014

2013 NETL Annual Report

Clarification of Radiation Work Permits for non-routine activities.

Pending procedure updates indude revision of security procedures based on NRC rulemaking in 10CFR73. Additional changes pending include changes resulting from requested but not yet approved Technical Specification amendments.

6.6.4 Facility Changes Accomplished in Accordance with Other Regulatory Requirements:

There were no changes the license, or Technical Specifications.

Proposed or Pending Changes:

SomeTechnical Specifications and license changes have been proposed and submitted to the USRNC for finad review and approval, including:

i. A set of changes for clarification and correction of terminology, ii. A request for a license amendment/revision to permit byproduct and source material under the control and used by the reactor facility to support reactor operations to be controlled under the reactor license, iii. A request to define initial startup, and iv. A request to require an operator at the controls when the reactor is not secured (currently required when the reactor is not shutdown).

A request for renewal of the facility operating license was made, with notification by the USNRC that the UT facility meets requirements for operation under "timely renewal."

Work to address requests for additional information is in progress.

6.7 Oversight & Inspections Inspections of laboratory operations are conducted by university and licensing agency personnel.

Two committees, a Radiation Safety Committee and a Reactor Oversight Committee review operations of the NETL facility. The Reactor Oversight Committee convened on the dates listed in Table 6.4.

42 3/2014

2013 NETL Annual Report Table 6.4, Reactor Oversight Committee Reviews First Quarter None Second Quarter 23 May 2013 Third Quarter None Fourth Quarter 17 October 2013 Inspections by licensing agencies include federal license activities by the U. S. Nuclear Regulatory Commission (NRC), Nuclear Reactor Regulation Branch (NRR), and state license activities by the Texas Department of State Health Services (TDSHS) Radiation Control Program. NRC inspections conducted in calendar year 2013 are indicated in Table 6.45. No findings of significance were identified.

Table 6.5, License Inspections License Dates R-129 14-17 January 2013 R-129 09-12 December 2013 SNM-180 None L00485 (89) None Routine inspections by the Office of Environmental Health and Safety (OEHS) for compliance with university safety rules and procedures are conducted at varying intervals throughout the year. In response to safety concerns at other sites on the main campus, several additional OEHS inspections have been made. Inspections cover fire, chemical, and radiological hazards. No significant safety problems were found at NETL, which reflects favorably on the positive safety culture for all hazard classes at the NETL. Safety concerns included such items as storage of combustibles, compressed gases, and fire extinguisher access.

43 3/2014

2013 NETL Annual Report 7.0 RADIOLOGICAL

SUMMARY

7.1 Summary of Radiological Exposures The Radiation Protection Program for the NETL facility provides monitoring for personnel radiation exposure, surveys of radiation areas and contamination areas, and measurements of radioactive effluents as indicated in Table 7.1. Site area measurements include exterior points adjacent to and distant from the building.

Table 7.1, Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement Weekly Gamma survey of all Restricted Areas.

Swipe survey of all Restricted Areas.

Swipe survey of Radioactive Materials Areas.

Response check of the continuous air monitor.

Response checks of the area radiation monitors.

Neutron survey of the reactor bay (during reactor operation).

Monthly Gamma, neutron and swipe surveys of exterior walls and roof.

Exchange personnel dosimeters & interior area monitoring dosimeters.

Review dosimetry reports.

Response check emergency locker portable rad. measuring equipment.

Review Radiation Work Permits.

Response check of the argon monitor.

Response check hand and foot monitor.

Collect and analyze TRIGA primary water.

As Required Process and record solid wastes and liquid effluent discharges.

Prepare and record radioactive material shipments.

Survey and record incoming radioactive materials.

Perform and record special radiation surveys.

Issue radiation work permits, provide HP for maintenance operations.

Conduct orientations and training.

Quarterly Exchange OSL environmental monitors.

Gamma and swipe surveys of all non restricted areas.

Swipe survey of building exterior areas.

Semi-Annual Inventory emergency locker.

Calibrate continuous air monitor, argon monitor, area rad. monitors.

Leak test and inventory sealed sources.

Annual Conduct ALARA Committee meeting.

Calibrate portable radiation monitoring instruments.

Calibrate personnel pocket dosimeters.

Calibrate emergency locker portable radiation detection equipment 44 3/2014

2013 NETL Annual Report 7.2 Summary of Radioactive Effluents The radioactive effluent paths are ventilation for air-borne radionuclides, and the sanitary sewer system for liquid radionuclides. The most significant airborne radionuclide effluent is argon-41.

Two other airborne radionuclides, nitrogen-16 and oxygen-19, decay rapidly and do not contribute to effluent releases. Argon-41, with a half-life of 109 minutes, is the only airborne radionuclide emitted by the facility during normal operations.

7.2.1 Released There were no releases of solid radioactive materials during calendar year 2013. A small quantity of radioactive waste is stored for decay or aggregation for a shipment. A small amount of liquid radioactive waste was transferred to OEHS for consolidation and disposal with other university radioactive waste.

7.2.2 Discharged Airborne Releases. A differential pressure control system in the facility assures airborne radioactive releases are controlled. The reactor room is ventilated by a general area system, and a sub-system to collect and discharge argon 41 generated from routine reactor operations. There were 4.10x106 jgCi of argon 41 discharged during calendar year 2013, with the annual average release 2% of the value permitted by Technical Specifications.

Liguid Discharges. There are no routine releases from the facility associated with reactor operation. Large liquid-volume radioactive waste is captured in holding tanks, where liquid radioactive waste may be held for decay or processed to remove the radioactive contaminants as appropriate. A small amount of water contaminated with tritium was discharged to the sanitary sewer in 2013. The concentration was orders of magnitude below the limits of IOCFR20 for discharge to sewerage, with total discharge approximately 15 gtCi.

Small quantities of liquid scintillation cocktail or dilute concentrations below the limits of 10 CFR 20 in the NETL laboratories may be disposed directly to the sanitary sewer. Liquid disposals are infrequent.

45 3/2014

2013 NETL Annual Report 7.3 Radiation Exposure Received by Facility Personnel and Visitors For calendar year 2013, no facility personnel received radiation exposures in excess of 25% of the allowed limit. Similarly, no visitors to the facility received in excess of 25% of the allowed limit.

7.4 Environmental Surveys Performed Outside the Facility NETL monitors exterior locations indicated as positions 1 through 6 on the exterior dosimeter map. For 2013, minimal doses (< I mrem).were reported for al positions for all quarters.

PARK ING Figure 7-1, NETL Environmental Monitor Locations In addition to the NETL monitors, the Texas Department of State Health Services monitors exterior locations near NETL indicated as positions 1 through 5 on the TDSHS TLD map. The reported doses for 2013 were:

Position 1 - 0 mrem

" Position 2 - 4 mrem 46 3/2014 a

2013 NETL Annual Report

Position 3 - 3 mrem

" Position 4 - 13 mrem

" Position 5 - 4 mrem Issues with the dosimetry vendor were encountered in 2012, as noted in the 2012 Annual Report.

TDSHS subsequently modifi*l enr'ro'nmental monitoring in 2013 to use raw dosimetry data rather than background-corrected vendor dose reports. TDSHS corrected the raw data for background using data from a badge located approximately four miles southeast of NETL to develop environmental mc'nitoringdata for the NETL.

The TDSHS enviropiriental monitoring reports for 2013 indicate an increase over historical values that are not reflected in other en vironr -ental monitoring for the facility (reported above).

The 2013 doses are not consis tent with histr icr' values reported by TDSHS. Reactor operations during the 2013 calendar year are lower tf th previous year, and any doses related to reactor operation should therefore be lower. Historical non-reactor activities conducted at the Pickle Research campus have potential to elevate background radiation levels in the area. Therefore, the changes in dose levels as reported by TDSHS may be related to the change in background correction. NETL is requesting the UT Radiation Safety Officer open a dialog with TDSHS to resolve the issue.

47 3/2014

2013 NETL Annual Report I

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