IR 05000186/2025201
| ML25142A250 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 06/02/2025 |
| From: | Tony Brown NRC/NRR/DANU/UNPO |
| To: | Sanford M Curators of the University of Missouri - Columbia |
| Waugh A | |
| References | |
| IR 2025201 | |
| Download: ML25142A250 (13) | |
Text
SUBJECT:
THE CURATORS OF THE UNIVERSITY OF MISSOURI - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000186/2025201
Dear Mr. Sanford:
From May 12-15, 2025, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Missouri University Research Reactor Facility. The inspection results were discussed with you and members of your staff on May 15, 2025. The enclosed report documents the inspection results.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed various activities, and interviewed personnel.
Based on the results of this inspection, the NRC has determined that one Severity Level IV violation of NRC requirements occurred. Because this violation of very low safety significance was identified by the licensee and was corrected, it is treated as a non-cited violation (NCV)
consistent with section 2.3.2(b) of the NRC Enforcement Policy. The NCV is described in the subject inspection report. If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public inspections, exemptions, requests for withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (Agencywide Documents Access and Management System (ADAMS)). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
June 2, 2025 If you have any questions concerning this inspection, please contact Andrew Waugh at (301) 415-0230, or by email to Andrew.Waugh@nrc.gov.
Sincerely, Tony Brown, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-186 License No. R-103 Enclosure:
As stated cc w/enclosure: GovDelivery Subscribers Signed by Brown, Tony on 06/02/25
ML25142A250 NRC-002 OFFICE NRR/DANU/UNPO NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME AWaugh NParker TBrown DATE 5/22/2025 5/27/2025 6/2/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-186 License No.:
R-103 Report No.:
05000186/2025201 Licensee:
The Curators of the University of Missouri Facility:
Missouri University Research Reactor Location:
Columbia, Missouri Dates:
May 12-15, 2025 Inspectors:
Andrew Waugh, Reactor Inspector Juan Arellano, Reactor Inspector Approved by:
Tony Brown, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
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SUMMARY The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an inspection at the Missouri University Research Reactor (MURR),
in accordance with the research and test reactor inspection program. This is the NRCs program for overseeing the safe operation of licensed research and test reactors. Refer to https://www.nrc.gov/reactors/non-power.html for more information.
List of Violations Non-Cited Violation (NCV 05000186/2025201-1)
69004 The inspectors determined that a Severity Level IV violation of technical specification (TS) 3.10.c occurred for the licensee processing iodine-131 without proper radiation monitoring of the hot cells. This violation of very low safety significance was identified by the licensee and was corrected and is treated as a NCV, consistent with section 2.3.2(b) of the NRC Enforcement Policy.
Additional Tracking Items None.
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REPORT DETAILS Facility Status MURR continued to operate in support of isotope production, reactor operator training, and various types of research. During the inspection, the reactor resumed operation following the weekly maintenance shutdown to support laboratory experiments and product irradiation.
Inspection Scopes Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at https://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Inspections were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2545, Research and Test Reactor Inspection Program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
69004 - Class I Research and Test Reactor Effluent and Environmental Monitoring This inspection included a review of selected documents and procedures to verify the licensees environmental monitoring program monitored, reported, and controlled effluent releases in accordance the requirements of the licensees TSs and Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Standards for Protection against Radiation. Specifically, the inspection included a review of the following:
the inspectors observed a waste tank sample
the inspectors observed sump water samples
the inspectors observed calibration of a continuous air monitor
the inspectors toured radioactive waste storage areas
soil, vegetation, and water samples, dated 2024 to present
select primary water sample analysis, dated 2024 to present
select as low as is reasonably achievable (ALARA) reviews, dated 2024-present
environmental dosimetry records dated 2024 to present
annual reactor operations report 2024
select stack radiation monitor calibration records, dated 2024 to present
select plenum radiation monitor calibration records, dated 2024 to present 69007 - Class I Research and Test Reactor Review and Audit and Design Change Functions This inspection included a review of the licensees review and audit functions to verify compliance with TS and procedural requirements. This inspection also included a review of selected licensee design changes to verify changes were reviewed, approved, and implemented in accordance with TS requirements, licensee procedures, and the requirements of 10 CFR 50.59, Changes, tests and experiments. Specifically, the inspection included a review of the following:
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emergency plan and procedures annual audits for 2023 and 2024
reactor safety corrective action program (CAP) audits for 2023 and 2024
requalification program audits for 2023 and 2024
facility operations audit 2023
select 10 CFR 50.59 screens, dated 2024 to present
select work packages, dated 2024 to present
select modification records, dated 2024 to present
Reactor Advisory Committee meeting minutes dated 2024 to present
Licensee Event Report (LER) 24-03 and 24-04 69011 - Class I Research and Test Reactor Emergency Preparedness This inspection included a review of the licensees emergency procedures, exercises and drills, training, and equipment to verify compliance with the licensees emergency plan and applicable regulatory requirements. Specifically, the inspection included a review of the following:
2024 emergency drill review
2024 annual on-site emergency drill
2024 emergency drill critique
facility emergency organization notification roster
2024 facility emergency organization annual lecture training
emergency plan and procedure review forms for select operators
changes in emergency plan implementing procedures since last inspection
the inspectors toured the emergency electrical power systems 69012 - Class I Research and Test Reactor Radiation Protection This inspection included a review of the licensees radiation protection program to verify that the provisions of 10 CFR Part 19, Notices, Instructions and Reports to Workers: Inspection and Investigations, 10 CFR Part 20, TSs, and the licensees procedural requirements were met.
The inspection included a review of: the licensees radiation protection procedures; posting requirements; the personnel dosimetry program; training requirements; required radiation surveys, sampling, and monitoring; calibration of radiological instruments; exposure limits; the radiation protection programs review and approval requirements; and the implementation of ALARA principles. Specifically, the inspection included a review of the following:
the inspectors observed radiation and contamination surveys
select personnel dosimetry records, dated 2024 to present
select radiation and contamination surveys, dated 2024 to present
select facility-controlled document revision forms, dated 2024 to present
select dose report reviews, dated 2024 to present
select area radiation monitor calibration records, dated 2024 to present
2025 ALARA audit
annual training records, dated 2024 to present
respirator training Excel sheet
LER 24-01 and 24-02
event review report 24-04 and 24-05
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86740 - Inspection of Transportation Activities This inspection included a review of the licensees transportation activities to verify they have established and are maintaining an effective management-controlled program, to ensure radiological and nuclear safety in the receipt, packaging, and delivery of licensed radioactive materials. Specifically, the inspection included a review of the following:
the inspectors observed packaging of a Type A shipment
the inspectors observed loading of a Type B shipment onto a transportation vehicle
the inspectors observed the placarding of a transportation vehicle
Type A Shipping Program Audit 2024
Type B Quality Assurance Program Audit 2024
select material licenses for receivers of radioactive shipments Inspection Results Non-Cited Violation (NCV 05000186/2025201-1)
69004 The inspectors determined that a Severity Level IV violation of TS 3.10.c occurred for the licensee processing iodine-131 without proper radiation monitoring of the hot cells. This violation of very low safety significance was identified by the licensee and was corrected and is treated as a non-cited violation, consistent with section 2.3.2(b) of the NRC Enforcement Policy.
Violation: TS 3.10.c states, Processing of iodine-131 shall not be performed in the iodine-131 processing hot cells unless the following minimum number of radiation monitoring channels are operable. Item 2 of the table for TS 3.10.c states that at least one iodine-131 processing hot cells radiation monitor must be operable.
Contrary to TS 3.10.c, three iodine-131 processes were performed in the hot cells without radiation monitoring available. The dates of the process were April 25, May 2, and May 9, 2024.
The licensee determined that iodine-131 processing hot cells radiation monitors assigned to monitor the exhaust filters in the bay above the hot cells were monitoring the off-service filter train, rather than the on-service filter train during the time of the above processing dates. The condition was immediately corrected by the licensee. The failure to meet the radiation monitoring requirements of TS 3.10.c is a Severity Level IV violation in accordance with the NRC Enforcement Policy section 6.7.d. The NRC staff determined the safety consequences of the event were low due to the short duration of the violation, several other radiation detectors were monitoring the Iodine processing suite during the violation, and no radiation releases occurred in the Iodine hot cells during the violation. The inspectors determined that the problem was identified by the licensee and reported to the NRC. Corrective actions were identified and completed. As a result, this non-willful, non-repetitive, licensee-identified and licensee-corrected violation will be treated as a non-cited violation consistent with section 2.3.2.a of the NRC Enforcement Policy (NCV 05000186/2025201-1).
Minor Violation (VIO 05000186/2025201-2)
69004
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Minor Violation: TS 3.10.d states, At least three (3) charcoal filter banks each having an efficiency of 99% or greater shall be operable when processing iodine-131 in the iodine-131 processing hot cells.
Contrary to the above, the licensee operated from July 2022 to April 2024, in a configuration that the filter banks did not meet the requirements of TS 3.10.d.
Screening: Because the in service filter banks had an equivalent iodine removal efficiency of greater than 99 percent when considered in series and the exhaust system radiation monitors were in service during the period of non-compliance and did not indicate abnormal rises in iodine the NRC staff determined the failure to meet the requirements of TS 3.10.d constitutes a violation of minor significance in accordance with section 2 of the Enforcement Policy. This minor violation (VIO 05000186/2025201-2) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 3.10.d constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy.
This closes inspection event notification 57180.
Minor Violation (VIO 05000186/2025201-3)
69007 Minor Violation: TS 3.2.g states, The reactor safety system and the number (N) of associated instrument channels necessary to provide the following scrams shall be operable whenever the reactor is in operation. Each of the safety system functions shall have 1/N logic where N is the number of instrument channels required for the corresponding mode of operation.
Item 21 of the table for TS 3.2.g states that the number of required instrument channels for the center test hole scram is two.
Contrary to the above, the licensee operated the reactor from October 7-13, 2024, with only one of the two required channels operational.
Screening: Because one channel was still operational and would have automatically shutdown the reactor if the center test hole was not properly seated and the licensee took prompt corrective actions the NRC staff determined the failure to meet the requirements of TS 3.2.g constitutes a violation of minor significance in accordance with section 2 of the Enforcement Policy. This minor violation (VIO 05000186/2025201-3) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 3.2.g constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy.
This closes inspection event notification 57382.
Minor Violation (VIO 05000186/2025201-4)
69007 Minor Violation: TS 3.2.a states, All control blades, including the regulating blade, shall be operable during reactor operation.
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Contrary to the above, the control rod selector switch became inoperable during operations on November 25, 2024, and the licensee was not able to meet the requirements of TS 3.2.a.
Screening: Because the licensee immediately shutdown the reactor and no reactor limits were approached the NRC staff determined the failure to meet the requirements of TS 3.2.a constitutes a violation of minor significance in accordance with section 2 of the Enforcement Policy.
This minor violation (VIO 05000186/2025201-4) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 3.2.a constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy.
This closes inspection event notification 57445.
Exit Meeting and Debriefs The inspectors verified no proprietary information was retained or documented in this report.
- On May 15, 2025, the inspectors presented the NRC inspection results to members of licensee management and staff.
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Documents Reviewed Inspection Procedure Type Designation Description or Title Revision or Date CP-42 Primary Water Analysis November 20, 2017 OP-HP-353 Waste tank sample - analysis October 4, 2023 SV-HP-115 Building Exhaust Stack Effluent -
Tritium Monitoring April 22, 2024 SV-HP-117 Secondary Coolant and Sump Water Analysis May 2, 2025 IC-HP-346 Calibration - Lab Impex Smart MCA Continuous Air Monitor June 21, 2023 IC-HP-311 Calibration - Eberline Model PING 1A Stack Monitor - Iodine Channel January 13, 2021 IC-HP-312 Calibration - Eberline Model PING 1A Stack Monitor - Gas Channel March 1, 2021 Procedure WM-SH-100 Radioactive Waste - Preparation and Storage May 1, 2019 CAP 24-0188 TS 3.10.c Violation September 24, 2024 69004 Miscellaneous CAP 24-0192 Iodine (I-131) Filter Procedure Not Followed July 16, 2024 AP-RR-003 10 CFR 50.59 Evaluations March 28, 2023 LCC-001 Reactor Advisory Committee Charter November 23, 2021 Procedure AP-RR-015 Work Management Procedure May 1, 2025 RX-B3 Replace Switch 1S3 Spring April 30, 2025 Preventative Maintenance RX-B4 Replace FIRST Cables April 30, 2025 69007 Miscellaneous CAP 24-388 FIRST Switch Replacement July 22, 2025
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CAP 24-0438 Unscheduled Shutdown 1411 April 22, 2025 EP-RP-006 Radiological Emergency June 16, 2021 EP-RO-013 Facility Evacuation January 4, 2024 EP-RO-020 Emergency Equipment Maintenance August 2, 2022 Procedure EP-RO-21 Recovery From a Facility Emergency May 6, 2025 69011 Emergency Plan Revision 22 MURR Emergency Plan February 6, 2025 POL-3 Radiation Protection Program March 12, 2024 POL-24 Iodine Bioassay Program March 17, 2025 POL-25 MURR Respiratory Protection Program January 27, 2025 RP-HP-125 Radiation Monitoring - Performing and Documenting a Survey April 22, 2024 OP-220 Tritium Bioassay August 9, 2020 OP-HP-232 Respirator Storage, Maintenance, and Inspection July 2, 2024 69012 Procedure OP-HP-235 Annual Respirator Training July 2, 2024 OP-HP-305 Ordering or Transfer of Radioactive Materials January 23, 2024 BPB-SH-020 Receipt Inspection of Type B Shipping Package June 8, 2023 86740 Procedure BPB-SH-027 Survey and Decontamination of Returned Shipping Containers December 10, 2018
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BP-SH-052 Radioactive Material Shipment Package Documentation and Labeling October 7, 2020 BP-SH-192 Packaging of Radioactive Material Using DOT 7A Model MURR MAXX October 16, 2024 BP-SH-207 ABK Packaging of Radioactive Material Using DOT 7A Model MURR MAXX May 9, 2025 OA-192 Packaging of Radioactive Material Using DOT 7A Model MURR MAXX October 31, 2024 OA-193 ABK Packaging of Radioactive Material Using DOT 7A Model MURR MAXX April 16, 2024 AP-SH-001 Radioactive Material Shipping January 25, 2022