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Federal Register / Vol. 86, No. 147 / Wednesday, August 4, 2021 / Notices
Area thermo-luminescent dosimeter monitors mounted in the control room and the reactor bay provide an additional monthly measurement of total radiation exposures at those locations. No changes in reactor operation that would lead to an increase in occupational dose are expected or proposed as a result of the proposed action.
The radiation monitoring systems associated with reactor operations at UMLRR are provided and maintained as a means of ensuring compliance with radiation limits established under 10
CFR part 20. The UMLRR radiation monitoring systems consist of area monitors, continuous air monitors, portable radiation survey instruments, personnel monitors, and stack particulate and gas monitors. The stack particulate and gas monitoring systems measure the beta-gamma activity emitted by radioactive particulates and the activity of gaseous radioactive nuclides, respectively, that are exhausted through the UMLRR exhaust stack. Perimeter monitoring at UMLRR
consists of dosimeters that detect X-ray and gamma radiation.
UML conducts an environmental monitoring program to record and track the radiological impact of UMLRR
operation on the surrounding unrestricted area. The environment outside the reactor building is monitored by passive optically stimulated luminescence dosimeters, which are changed out quarterly. These dosimeters are located at strategic locations in and around the Pinanski building, which is attached to the reactor building. The UML Radiation Safety Office analyzes the results to ensure that the reported doses are below 10 CFR part 20 limits, and to monitor for trends that would indicate unusual or elevated exposures. UML states that it has determined that the numbers and placement of environmental dosimeters is sufficient based upon historical data accumulated and analyzed from other dosimetry locations that were part of a previous comprehensive background study of areas around the UML campus.
The renewal application provided total annual environmental monitoring dose results from 2009 through 2013 for dosimeters located in the first and third floor airlocks, and 2 locations within the Pinanski building. For each year and location, the measured doses were below 10 mrem and well below the limits to the public as required by 10
CFR part 20. Year-to-year trends in exposures are consistent between monitoring locations. Also, no correlation exists between total annual
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reactor operation and annual exposures measured at the monitoring locations.
Based on its review of monitoring data in the renewal application, the NRC staff concludes that operation of the UMLRR does not have any significant radiological impact on the surrounding environment. No changes in reactor operation that would affect normal off-site radiation levels are expected or proposed as a result of the proposed action. Therefore, the proposed action would not have a significant radiological impact.
Environmental Effects of Accidents Accident scenarios are discussed in Chapter 13 of the UMLRR SAR. The accidents analyzed in Chapter 13 range from anticipated events to a postulated fission product release with radiological consequences that exceed those of any accident considered to be credible. This limiting accident is referred to as the maximum hypothetical accident MHA.
UML considers the uncontrolled release of the volatile gaseous fission products to be the MHA for UMLRR. This accident would involve the removal of the cladding from one side of one fuel plate while the fuel is in the reactor pool. From there, the release would continue to the reactor confinement building and into the environment.
UML uses this scenario to calculate the maximum concentration of fission products that might be present in the reactor room air following the MHA.
From its calculations, UML concluded that individual worker exposures from the MHA would not exceed 10 CFR part 20 dose limits and that all effluent releases to the environment resulting from the MHA would also meet 10 CFR
part 20 dose limits.
Separate from this EA, the NRC staff is reviewing UMLs MHA analyses of the potential radiological consequences that may result from the proposed license renewal. The results of the NRC
staffs safety review will be documented in a safety evaluation report that will be made publicly available. If the NRC
concludes that the radiological consequences of the MHA are within 10
CFR part 20 dose limits, then the MHA
and the proposed action would not have a significant impact with respect to the radiological consequences of the MHA.
Conclusions Because, in the renewal application, UML has not proposed any physical changes to the reactor facility design, or changes to facility operating conditions, that would significantly affect facility operation, there would be no changes in the types or quantities of routine effluents that may be released off site.

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UML has systems in place for controlling the release of radiological effluents and implements a radiation protection program to monitor personnel exposures and releases of radioactive effluents. Accordingly, there would be no increase in routine occupational or public radiation exposure as a result of the proposed action. As previously discussed, a separate safety evaluation is being conducted by the NRC staff to determine the probability and consequences of accidents that could result from the proposed action. If the safety evaluation finds that the probability and consequences of accidents are within NRC regulatory requirements, then the proposed action would have no significant environmental impact with respect to accidents.
License renewal would not significantly change reactor operations.
As previously discussed, information in the renewal application and data reported to the NRC by UML for the last 5 years of reactor operations were evaluated to determine the radiological impact of reactor operations. The NRC
staff found that releases of radioactive material and personnel exposures were all well within applicable regulatory limits. Based on this evaluation, the proposed action would have no significant radiological impacts.
Non-Radiological Impacts The proposed action does not involve any significant change in the operation of the reactor, change in the emissions or heat load dissipated to the environment, or involve construction or other land disturbance activities. The proposed action would not result in any land use changes or increases in noise or air emissions and would not have a significant impact on air quality, noise, or visual resources. Water is supplied through the city water utility and UML
proposes no increase in water use or effluent discharge. Thus, the proposed action would not incrementally affect surface water or groundwater resources.
There is no potential for the proposed action to affect aquatic or terrestrial resources, or any other environmental resource conditions. Therefore, the proposed action would have no significant non-radiological impacts.
Other Applicable Environmental Laws In addition to the National Environmental Policy Act, which requires Federal agencies to consider the environmental impacts of proposed actions, the NRC has responsibilities that are derived from other environmental laws and policy directives, which include the
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