IR 05000186/2024201
| ML24130A189 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 05/29/2024 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Sanford M Curators of the University of Missouri |
| Waugh A | |
| References | |
| IR 2024201 | |
| Download: ML24130A189 (1) | |
Text
SUBJECT:
THE CURATORS OF THE UNIVERSITY OF MISSOURI - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000186/2024201
Dear Mr. Sanford:
From April 22-25, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Missouri University Research Reactor facility. The enclosed report presents the results of that inspection, which were discussed on April 25, 2024, with you and members of your staff.
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, no findings of significance were identified. No response to this letter is required.
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 the 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).
May 29, 2024 If you have any questions concerning this inspection, please contact Andrew Waugh at (301) 415-0230, or by email at Andrew.Waugh@nrc.gov.
Sincerely, Travis L. Tate, 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 Tate, Travis on 05/29/24
ML24130A189 NRC-002 OFFICE NRR/DANU/UNPO NRR/DRO/IRAB NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME AWaugh MKeefe-Forsyth NParker TTate DATE 5/13/2024 5/14/2024 5/15/2024 5/29/2024
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-186 License No.:
R-103 Report No:
05000186/2024201 Licensee:
The Curators of the University of Missouri Facility:
Missouri University Research Reactor Location:
Columbia, Missouri Dates:
April 22-25, 2024 Inspectors:
Andrew Waugh, Reactor Inspector Brian Lin, Reactor Inspector Molly Keefe-Forsyth, Safety Culture Program Manager Necota Staples, Safety Culture Assessor/ Reactor Inspector in Training Wesley Deschaine, Safety Culture Assessor in Training Approved by:
Travis L. Tate, 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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EXECUTIVE SUMMARY The Curators of the University of Missouri Missouri University Research Reactor Inspection Report No. 05000186/2024201 The primary focus of this routine announced inspection was the onsite review of selected aspects of the Missouri University Research Reactor (MURR) facility safety program, including:
(1) effluent and environmental monitoring; (2) review and audit and design change functions; (3) emergency preparedness; (4) radiation protection; (5) transportation activities; and (6) safety-conscious work environment. The U.S. Nuclear Regulatory Commission (NRC) staff determined that the licensees program was acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.
Effluent and Environmental Monitoring
The inspectors determined that effluent and environmental monitoring was conducted in accordance with technical specifications (TS) and regulatory requirements.
Review and Audit and Design Change Functions
The inspectors determined that the licensees audit review program was conducted in accordance with TS and procedural requirements.
- The inspectors determined that design changes were conducted in accordance with TS, procedural, and regulatory requirements.
The inspectors determined that the licensees emergency preparedness program was conducted in accordance with the licensees emergency plan, TS, procedural, and regulatory requirements.
Radiation Protection
The inspectors determined that the licensees radiation protection program was conducted in accordance with TS, procedural, and regulatory requirements.
Transportation Activities
The inspectors determined that the licensees radioactive material transportation program was in accordance with procedural and regulatory requirements.
Safety-Conscious Work Environment
The inspectors determined that the licensees safety-conscious work environment program was in accordance with procedural requirements.
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REPORT DETAILS Summary of 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.
1.
Effluent and Environmental Monitoring a.
Inspection Scope (Inspection Procedure [IP] 69004)
The inspectors observed portions of the licensees environmental sampling process and a radioactive waste shipment. The inspectors also reviewed the following to ensure the licensee effluent and environmental monitoring program was conducted as required by Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Standards for Protection Against Radiation, and TS 3.7 and 4.7:
2023 annual operating report
POL-03, Radiation Protection Program, dated March 12, 2024
select monthly effluent reports, dated 2023-present
select personnel dosimetry records, dated 2023-present
select environmental dosimetry records, dated 2023-present
select stack monitor calibration records, dated 2023-present
various instrument calibration records, dated 2023-present
meeting minutes for the Reactor Advisory Committee (RAC) and subcommittees, dated 2023-present
2023 Dose to Individual Members of the Public, dated February 15, 2024
waste tank sample analysis, dated April 24, 2024
OP-HP-353, Waste Tank Sample Analysis, dated September 1, 2023 b. Observations and Findings The inspectors found that the licensees effluent releases were within the regulatory limits and were controlled, monitored, and recorded as required by TS 3.7 and 4.7. The inspectors also found that implementation of the environmental monitoring program met TS 3.7, 4.7, and regulatory requirements. The inspectors found that radioactive waste was stored as required by 10 CFR Part 20.
c. Conclusion The inspectors determined that effluent and environmental monitoring was conducted in accordance with TS and regulatory requirements.
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2.
Review and Audit and Design Change Functions a.
Inspection Scope (IP 69007)
The inspectors reviewed the following to ensure that review and audit and design functions were conducted as required by 10 CFR 50.59, Changes, tests and experiments, and TS 6.2:
2023 annual operating report
various modification records, dated 2023-present
various 10 CFR 50.59 screenings, dated 2023-present
AP-RR-003, 10 CFR 50.59 Evaluations, dated September 2, 2022
AP-RO-115, Modification Records, dated April 25, 2023
meeting minutes for the RAC and subcommittees, dated 2023-present
various completed TS 6.2.e audits, dated 2023-present b.
Observations and Findings (1) Review and Audit Functions The inspectors found that the RAC (or subcommittees thereof) membership satisfied TS 6.2, met as required by TS 6.2.b, and provided the reviews as specified in TS 6.2.a. The inspectors found that audits were conducted in accordance with TS 6.2.e. The inspectors also found that audit findings, and licensee actions taken in response to the findings, were appropriate.
(2) Design Change Function The inspectors found that design changes were reviewed and approved as required by 10 CFR 50.59. The inspectors also found that the acceptance and pre-operational tests of modified equipment and the procedures and drawings related to that equipment met regulatory, TS, and procedural requirements.
c.
Conclusion The inspectors determined that the licensees audit review program was conducted in accordance with TS and procedural requirements.
The inspectors determined that design changes were conducted in accordance with TS, procedural, and regulatory requirements.
3.
Inspection Scope (IP 69011)
The inspectors reviewed the following selected portions of the licensees emergency preparedness program to verify compliance with Appendix E, Emergency Planning and
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Preparedness for Production and Utilization Facilities, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, and the licensees emergency plan:
MURR emergency plan, dated December 8, 2022
meeting minutes for the RAC and subcommittees, dated 2023-present
2023 annual drill records
select personnel training records, dated 2023-present
select emergency implementing procedures
select long form startup check-sheets, dated 2023-present
select emergency locker inventory forms, dated 2023-present
EP-RO-020, Emergency Equipment Maintenance, dated August 2, 2022 b.
Observations and Findings The inspectors found that the emergency plan training was conducted, drills were performed, emergency response call lists were maintained and posted, and emergency equipment was maintained and available as required by the emergency plan and licensee procedures. The inspectors also found that implementing procedures were consistent with emergency plan requirements and revisions to the emergency plan were made in accordance with 10 CFR 50.54(q).
c.
Conclusion The inspectors determined that the licensees emergency preparedness program was conducted in accordance with the licensees emergency plan, TS, procedural, and regulatory requirements.
4.
Radiation Protection a.
Inspection Scope (IP 69012)
The inspectors toured the facility, observed radiation swipes and surveys, observed movement of a fuel cask, observed a radioactive waste shipment, and observed radiological signs and postings. The inspectors also reviewed the following to ensure the licensees radiation protection program adheres to the requirements of 10 CFR Part 19, Notices, Instructions, and Reports to Workers: Inspection and Investigations, 10 CFR Part 20, and TS 3.7 and 4.7:
2023 annual operating report
select personnel dosimetry records, dated 2023-present
select training records, dated 2023-present
internal audits reports of the radiation protection and as low as is reasonably achievable (ALARA) programs for 2023
select calibration records for radiation monitors and detectors, dated 2023-present
select radiation work permits, dated 2023-present
select radiation surveys, dated 2023-present
select primary sample results, dated 2023-present
select respirator training records, dated 2023-present
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POL-03, Radiation Protection Program, dated March 12, 2024
POL-25, MURR Respiratory Protection Program, dated March 8, 2024
OP-RO-420, Primary and Pool Water Analysis, dated December 29, 2022 b. Observations and Findings The inspectors found that practices regarding the use of dosimetry, radiation monitoring equipment, placement of radiological postings, posting of notices, use of protective clothing, and the handling and storing of radioactive material or contaminated equipment was in accordance with regulations and the licensees radiation protection program. The inspectors found that the licensee met the TS and procedural requirements concerning radiation survey, sampling, and monitoring. The inspectors also found that training was conducted for radiation workers and ALARA principles were implemented as required by licensee procedures.
c. Conclusion The inspectors determined that the licensees radiation protection program was conducted in accordance with TS, procedural, and regulatory requirements.
5.
Transportation Activities a.
Inspection Scope (IP 86740)
The inspectors toured shipping and receiving areas, observed the preparation of various packages for shipment, observed a radioactive waste shipment, and observed the movement of a fuel cask. The inspectors also reviewed the following to ensure the licensees program for transporting radioactive materials met NRC and Department of Transportation (DOT) requirements:
records of licensee employees shipping training
internal audits of Type A shipping, dated March 7, 2024
select records of radioactive material (RAM) shipments including Type A and Type B shipments from 2023-present
forms 540, 540A, 541 Uniform Low-Level Radioactive Waste Manifest
AP-SH-001, Administrative Procedure - Radioactive Material Shipping, Revision (Rev.) 15
QAB-SH-005, Type B QA Personnel Training, Rev. 7
OP-HP-300, Receipt of Radioactive Material, Rev. 15
FB-SH-110, Type B shipment of Spent Fuel Using the BEA Research Reactor Package, Rev. 11
various radioactive waste preparation and shipping procedures b.
Observations and Findings The inspectors found that the licensees procedures, records, training, packaging, and container labeling concerning the transportation of radioactive material were in accordance with NRC and DOT requirements.
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c.
Conclusion The inspectors determined that the licensees RAM transportation program was in accordance with regulatory and procedural requirements.
6.
Safety-Conscious Work Environment a.
Inspection Scope (IP 93100)
The purpose of this portion of the inspection was to assess the safety-conscious work environment (SCWE), leadership safety values, and other attributes of the licensees safety culture (SC). The inspectors interviewed various staff members and reviewed the following to assess the licensees SC and SCWE:
MURR safety culture assessment conducted in 2024 by third party
AP-RR-023, MURR Safety Oversight Committee, dated February 24, 2021 b.
Observations and Findings The NRC safety culture policy statement (76 FR 34773; June 14, 2011), sets forth the Commission's expectation that licensees establish and maintain a positive SC commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The NRC defines nuclear SC as the core values and behaviors resulting from a collective commitment by leaders and individuals to emphasize safety over competing goals to ensure protection of people and the environment. A SCWE is defined by the NRC as an environment in which employees are encouraged to raise safety concerns, are free to raise concerns to both their management and NRC without fear of retaliation, where concerns are promptly reviewed, given the appropriate priority, and are appropriately resolved, and timely feedback is provided and is one trait of a strong safety culture. NRC Regulatory Issue Summary 05-018, Guidance for Establishing and Maintaining a Safety-Conscious Work Environment, dated August 25, 2005, further describes the NRCs expectations in this area.
The primary focus of this inspection was to determine the licensee staffs: (1) knowledge of methods to raise safety concerns within MURR; (2) willingness to raise safety concerns to their management without fear of retaliation; (3) managers ensure reactor priorities are aligned to reflect nuclear safety as the overriding priority; and (4)
procedural use and adherence. To make this assessment of the environment, the inspectors conducted interviews with MURR staff members having responsibilities related to reactor operations, observed activities of reactor operations, and reviewed procedures. The inspectors assessed the SC by interviewing employees with responsibilities regarding reactor operations and radiation safety.
The NRC staff interviewed 60 employees from Operations, Health Physics, Shipping, Products and Services as well as some first line supervisors and managers. The NRC staff heard that employees are willing to raise safety concerns through all available avenues without fear of retaliation. The NRC staff found no evidence of a chilled work environment. However, the NRC staff determined that the transition to the new way of implementing the corrective action program (CAP) is causing a bit of confusion about what CAP is used for, and the importance of putting all issues into CAP for evaluation,
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resolution and trending.
The NRC staff identified an opportunity for improvement in communication and training about CAP and its fundamental importance to nuclear safety and facility operations. The NRC staff heard that the MURR Safety Oversight Committee (MSOC) was viewed very favorably by the licensee staff. The committee is worker level run which means that employees are able to raise concerns to their peers instead of through CAP or management. This allows for trust and comfort, for sensitive issues. If the MSOC continues to be empowered by the management team to bring up difficult issues, it will be a very useful tool for MURR to ensure all concerns are brought up and addressed.
The licensee staff at MURR acknowledges the growth and expansion of the facility and all of the changes that are happening as a result, and while they trust management is headed in the right direction, there is concern that changes are happening faster than the current infrastructure will allow and there is not enough space, staffing, etc. to keep pace with the growth. The NRC staff understands that there are plans in place to alleviate these challenges with space and staffing, but those plans havent been communicated to the licensee staff yet.
c.
Conclusion The inspectors determined that the licensees SCWE program was in accordance with procedural requirements.
7.
Exit Interview The inspection scope and results were summarized on April 25, 2024, with members of licensee management and staff. The inspectors described the areas inspected and discussed the inspection results. The licensee acknowledged the results of the inspection.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee Reactor Facility Director R. Astrino Reactor Manager R. Hudson Assistant Reactor Manager of Training C. Braun Assistant Reactor Manager of Engineering R. Gibson Assistant Reactor Manager of Operations D. Doenges Health Physics & Safety Manager T. Graham Health Physics Supervisor P. Williams Shipping Manager M. Ell Radiation Technician INSPECTION PROCEDURES USED IP 69004 Class I Research and Test Reactors Effluent and Environmental Monitoring IP 69007 Class I Research and Test Reactor Review and Audit and Design Change Functions IP 69011 Class I Research and Test Reactor Emergency Preparedness IP 69012 Class I Research and Test Reactor Radiation Protection IP 86740 Inspection of Transportation Activities IP 93100 Safety-Conscious Work Environment Issue of Concern Follow-up ITEMS OPENED, CLOSED, AND DISCUSSED Opened:
None Closed:
None