ML23258A162

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Submission of Environmental Report for the University of Texas at Austin Research Reactor in Support of License Renewal
ML23258A162
Person / Time
Site: University of Texas at Austin
Issue date: 09/15/2023
From: Whaley P
University of Texas at Austin
To: Geoffrey Wertz
Office of Nuclear Reactor Regulation, Document Control Desk
References
Download: ML23258A162 (1)


Text

WALKER DEPARTMENT OF MECHANICAL ENGINEERING Nuclear Engineering Teaching Laboratory

Pickle Research Campus R-9000

  • Austin, Te x as 78758
  • 512-232-5380
  • FAX 512-471-4589 nuclear. engr. utexas. edu
  • wcharlton @ austin.ute x as.edu

September 15, 2023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Geoffrey Wertz, P.E.

Non-Power Production and Utilization Facility Licensing Branch Division of Advance Reactors and Non-Power Utilization Nuclear Reactor Regulation

SUBJECT:

Docket No. 50-602, Facility Operating License R-129 - Submission ofEnvironmental Report for the University of Texas at Austin Research Reactor in Support of License Renewal

Sir:

We respectfully submit proposed Enviromental Report, attached. If you have any questions, please contact me at 512-232-5373 or whaley@mail.utexas.edu.

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

W. S. Charlton

ATT:

The University of Texas TRI GA II Research Reactor Environmental Report THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR 08/2023 ENVIRONMENTAL REPORT

1 General

This environmental report is prepared in accordance with 10 CFR Part 51 as part of the nuclear reactor license renewal at the Nuclear Engineering Teaching Laboratory (NETL) at The University of Texas at Austin. The document summarizes the environmental effects as a result of normal operation of the NETL. The reactor is a TRIGA Mark II, light-water cooled and moderated reactor using uranium fuel enriched to less than 20% uranium-235. The maximum steady-state power of the reactor is 1.1 MW. A full description of the reactor is contained in the Safety Analysis Report.

2 Site Description

The NETL is located on the Pickle Research Campus of The University of Texas at Austin. The facility is located in the northeast corner of the campus near the intersectio *n of Burnet Road and Braker Lane in Austin, Travis County, Texas. The operations boundary of the reactor facility is the reactor building. The reactor is at the bottom of an eight-meter deep tank of water and is surrounded by a graphite reflector. The reactor operates at various steady-state power levels up to 1.1 MW. The reactor is brought up to a desired power level and is kept at that power until the experiment or irradiation is completed. This power level is usually maintained for periods ranging from a few minutes to several hours. Repeated operation over several days is possible for long-term irradiations. The main uses of the NETL facility are for education, research, and service work.

3 Environmental Effects of Operation

3.1 Thermal Impact

The thermal energy generated in the NETL core is absorbed in a closed primary coolant system.

The energy is then transferred to a secondary coolant system through a heat exchanger. The heat exchanger secondary side is connected to the campus chilled water loop. The heat is then dissipated to the environment by means of the campus chilling station cooling tower. The campus chilling station capacity is approximately 15 MW. Thus, the heat dissipation from the NETL core is not a significant fraction (7.3%) of the heat load from the campus.

3.2 Radiological Impact During Normal Operations

3.2.1 Environmental Monitoring

Environmental monitoring is performed by dosimetry devices, direct dose rate measurements, and sampling. Ground water near the facility is routinely sampled and measured. No activity above background has been measured in these evaluated samples. Dosimetry devices monitor ambient radiation levels outside the reactor facility. From 2013 to 2023, the highest indicated quarterly dose was 15 mrem (well below the 100 mrem annual limit). This dose was recorded during a period when a repair to the reactor occurred requiring all the fuel from the core to be

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unloaded and moved to storage. Doses were very near background levels during other quarters.

Periodic radiation dose rate surveys around the exterior of the facility typically indicate dose rates at background levels.

3.2.2 Personnel Exposure Monitoring

Each person who may use or handle radioactive materials must receive radiation safety training.

Radiation exposures to reactor personnel are administratively controlled to meet ALARA (as low as reasonably achievable) criteria. Experience from NETL operations shows that all personnel exposures are well below the whole body dose limit of 5000 mrem per year. Representative occupational exposures are presented below.

Table ER.l, Representative Occupational Exposures Numbers of persons in annual-dose categories Year Immeasurable < 0.1 0.1-0.5 0.5-1.0 rem rem rem 2023 11 8 0 0 2022 11 14 1 0 2021 10 14 0 1 2020 3 9 1 0 2019 8 5 0 1 2018 7 6 1 0

3.2.3 Solid Wastes

Solid wastes generated at the NETL are low-level wastes such as ion exchange resins, filters, laboratory supplies and cleaning materials. Average annual solid radioactive waste volume produced at the NETL is approximately 25 cubic feet of low-activity material. However, much of this waste contains radioactive material with a relatively short half-life. Thus, much of this solid waste is held in a restricted area until it has decayed to background levels of radioactivity. Once decayed and surveyed to confirm background levels of radioactivity, the waste is disposed as non-radioactive. The remaining solid waste which contains radioactive materials with a relatively long half-life typically amounts to approximately two cubic feet per year. This remaining waste is held in a restricted area until a sufficient volume is on hand to make it economically feasible to package and transfer the waste for disposal. Solid radioactive waste to be transferred for disposal is packaged according to USDOT, waste processor, and disposal site requirements as applicable and is temporarily stored in a restricted area until transfer for disposal. No solid radioactive waste is intended to be retained or permanently stored on site.

3.2.4 Liquid Wastes

Liquid waste is rarely generated by operation of the NETL. When liquid waste is generated, it typically consists of radioactive material with a relatively short half-life and like solid waste, is held for decay prior to disposal as non-radioactive. The remaining small amount of liquid waste

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which contains radioactive materials with a relatively long half-life typically is held in a restricted area until a sufficient volume is on hand to make it economically feasible to package and transfer the waste for disposal. Liquid radioactive waste to be transferred for disposal is packaged according to USDOT, waste processor, and disposal site requirements as applicable and is temporarily stored in a restricted area until transfer for disposal. No liquid radioactive waste is intended to be retained or permanently stored on site.

3.2.5 Radioactive Gas Effluent

The only routine release of gaseous radioactivity is argon-41 from activation of air in the pool water and beam ports. Radioactive gas effluent is discharged from the building exhaust stack approximately 17 meters above ground level. Historically, the annual activity of argon-41 released from the stack is typically less than 6 Ci. Using a conservative model of ground level concentration at the building, argon-41 concentration was calculated to be approximately an order of magnitude below the effluent limit in 10CFR20 Appendix B. Using CAP88-PC, dose to the maximally exposed individual was calculated to be approximately 0.01 mrem per year due to argon-41.

3.2.6 Radiological Impact During Abnormal Operations

Chapter 13 of the NETL Safety Analysis Report provides accident analysis for the reactor facility.

The Maximum Hypothetical Accident (MHA) for the reactor, as it is with virtually all TRIGA type reactors, is postulated to be an instantaneous loss of coolant water followed by an instantaneous movement of volatile fission products from the fuel uniformly distributed into the reactor room air. Results of these calculations for this scenario predict doses for the general public and occupational workers were all well below the annual dose limits specified in 10 CFR Part 20.

4 Benefits of Continued Facility Operations

The US and the world are highly dependent on nuclear technologies ranging from smoke detectors to sterilization sources used for medical devices. These technologies need trained engineers to create and execute new applications of radiation properties. In addition to industrial needs, nuclear power remains a vital solution to the energy needs of world. To meet these needs, US universities need to maintain a viable educational infrastructure for the next generation of engineers and scientists. The NETL supports education, research, and public service activities.

5 Alternatives to Continued Facility Operations

Each US university research reactor is a unique facility with individual educational and research objectives. The loss of any of the remaining US university reactors would constitute a significant weakening of the US ability to operate and control nuclear-related facilities. However, continued operation of the NETL is not guaranteed and is subject to changes in US policy, regulatory issues,

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and societal pressures. The effect of decommissioning the NETL would probably entail loss of significant educational, research, and service programs. At this time there are no plans for decommissioning the NETL by the university administration.

6 Analysis

The NETL is an integral part of The University of Texas at Austin Nuclear and Radiation Engineering Program. Based on the data presented here, the facility is currently operating with minimal radiation exposures and releases which are well within regulatory limits. Personnel, environmental and area radiation monitoring confirm that all exposures are within ALARA expectations. The NETL is an existing facility. No capital funds are required for continued operation. The desirable and anticipated decision is that the license be renewed.

7 Long Term Effects on the Environment

At the eventual closure of NETL operations, all areas housing or impacted by reactor operations and the affiliated laboratories will be decommissioned and returned to general university use.

The reactor fuel (owned by DOE) will be shipped to a designated DOE facility. The environmental impact associated with renewing the NETL license is deemed to be insignificant compared to the positive benefits resulting from enhanced educational, research, and service opportunities offered by the N ETL.

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