ML24227A967
| ML24227A967 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 08/14/2024 |
| From: | Univ of Massachusetts - Lowell |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24227A965 | List: |
| References | |
| Download: ML24227A967 (1) | |
Text
University of Massachusetts Lowell Research Reactor (UMLRR)
2023-2024 OPERATING REPORT
NRC Docket No. 50- 223
NRC License No. R-125
One University Avenue Lowell, Massachusetts 01854
This report is submitted as required by the Technical Specification 6.7.1 of reactor license R-125 and provides the information as outlined in the specification.
CONTENTS
- 1. Narrative Summary - Tabulations
- 2. Inadvertent and Emergency Shutdowns
- 3. Major Preventive and Corrective Maintenance
- 4. Changes and Tests and Experiments Related to 10 CFR 50.59
- 5. Nature and Amount of Radioactive Effluents
- 6. Environmental Surveys
- 7. Personnel Exposures
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- 1. NARRATIVE
SUMMARY
- TABULATIONS
- a. Narrative Summary
The UML research reactor is designed to produce thermal neutrons for radioactivation and neutron radiography purposes, and fast neutrons for radiation effects studies. Uses include neutron activation analysis research, materials atomic displacement damage studies, neutron absorption studies, short-lived radioisotope production, neutron detector studies, and neutron imaging (radiography). Educational uses include a variety of lab courses in the nuclear engineering and radiological sciences programs. Tours and demonstrations are provided to several other UMass Lowell courses, as well as other universities, high schools, and various organizations.
Short lived isotopes (e.g., Al-28, Na-24) are produced for routine practicum and demonstration purposes. The reactor is used for several nuclear engineering and non-nuclear engineering laboratory exercises and demonstrations. In addition, the reactor is used for training student operator license candidates.
- b. Tabulations
Energy generated this period (MWD) 5.13
Critical hours 437.78
Cumulative energy to date (MWD) 105.29
- 2. INADVERTENT AND EMERGENCY SHUTDOWNS
There were no emergency shutdowns for the reporting period. There were five inadvertent non-emergency automatic shutdowns during the reporting period. Four of these occurred from data acquisition system communication errors associated with a display screen. The fifth occurred due to electronic noise on one of the linear power channels. There was no safety significance associated with any of the inadvertent shutdowns. All automatic and manual scrams are reviewed for safety significance and technical specification requirements by the SRO on duty.
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- 3. MAJOR PREVENTIVE AND CORRECTIVE MAINTENANCE
There were no major preventive maintenance activities and one corrective maintenance activity during the reporting period. A shaft seal on the secondary cooling system pump was replaced due to leaking.
- 4. CHANGES AND TESTS AND EXPERIMENTS RELATED TO 10 CFR 50.59
- a. Changes to the Facility
There were no changes to the facility during the reporting period.
- b. Changes to Procedures
Procedure HPP-21 Reactor Water Analysis was revised to provide an improved methodology for determining the minimum detectable activity for Co-60. SP-4 Emergenc y Exhaust System Check w as updated to provide an additional acceptable method for performing the quarterly operability check of the emergency exhaust system.
Several updates were made to the Emergency Plan implementing procedures for compatibility with changes made to the Emergency Plan as submitted to the NRC in June 2023. The changes to these procedures w ere evaluated and implemented under 10CFR 50.59 and reviewed by the Reactor Safety Subcommittee.
- c. New Tests and Experiments
The were no new tests or experiments during the reporting period requiring a 10CFR 50.59 evaluation.
- 5. NATURE AND AMOUNT OF RADIOACTIVE EFFLUENTS
- a. Liquid Wastes and Gaseous Wastes
As part of UMass Lowell ALARA goals, the radiation safety office has set a campus goal of limiting exposures to members of the public to less than 10% of the federal regulatory limits. No activity was released through the reactor sewer, and as such, this is well below the monthly limits for sewer releases. Argon-41 continues to be the only significant reactor produced radioactivity identifiable in the gaseous effluent. The reactor stack 3
released roughly 8.357Ci in 2023 resulting in a (conservative) estimated upper limit to the TEDE of 0.3 mrem/year 100 m from the stack.
REACTOR ENVIRONMENTAL RELEASES SOURCE ACTIVITY DOSE GOAL Ci mrem mrem Sewer Releases 0 <0.1 Stackeas 8.357 3
- b. Solid Wastes
Solid wastes, primarily paper, disposable clothing, and gloves, along with other miscellaneous items have been disposed of in appropriate containers. Most of the activity from these wastes consisted of short-lived induced radioactivity. These wastes were held for decay and then released if no activity remained. Long lived waste (<40 cubic feet) is stored in a designated long lived waste storage area awaiting ultimate disposal at a low -
level radioactive waste disposal site.
- 6. ENVIRONMENTAL SURVEYS
A review of all 2023 Research Reactor Radiation Survey and Contamination forms found no measurable removable contamination levels due to unexpected occurrences in the facility.
The byproduct materials license specifies contamination as > 500 dpm/100cm2 (beta, gamma) or >50 dpm/100cm2 (alpha). No appreciable stray radiation fields (>2mR/hr) were identified in a free area within the reactor. Radiation levels measured in the reactor building have been typically less than 0.1 mrem/hr in general areas. Experiments have been conducted in which transient levels at specific locations have been in excess of 100 mrem/hr. Doses in these instances have been controlled by use of shielding, visual and audial notifications, and/or personnel access control. The pump room and beam port facility remain designated as a high and very high radiation area respectively during reactor operation and access is controlled.
Environmental monitoring external to the reactor building found no measurable doses.
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- 7. PERSONNEL EXPOSURES
An ALARA assessment of the UMass Lowell radiation safety program is performed annually. This review is reported to and reviewed by the Radiation Safety Committee. The 2023 ALARA goal for radiation workers at UMass Lowell was to limit the most exposed radiation worker at UML to less than 10% of the federal radiation exposure limits. In addition, the radiation safety manual requires a 100 mrem per week TEDE administrative level. No occupational exposure exceeded an ALARA limit. Personnel dosimetry was obtained by review of the 2023 Landauer dosimetry reports. These reports include, where appropriate, whole body OSL dosimetry and finger TLD dosimetry. Landauer is a NVLAP accredited dosimetry company.
OCCUPATIONAL EXPOSURES
GROUP PERSONNEL MAX MAX Whole Body Extremity BADGED Dose Dose
(<500mrem) (<5000 mrem)
Reactor 14 330 453
NOTE: No one person exceeded the ALARA limits.
End of Report
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