ML25266A100
| ML25266A100 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 09/24/2025 |
| From: | Tony Brown NRC/NRR/DANU/UNPO |
| To: | Reese S Oregon State University |
| References | |
| IR 2025201 | |
| Download: ML25266A100 (1) | |
Text
Dr. Steven R. Reese, Director Oregon State University 100 Radiation Center Corvallis, OR 97331-5903
SUBJECT:
OREGON STATE UNIVERSITY - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000243/2025201
Dear Dr. Reese:
From September 15-18, 2025, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Oregon State University TRIGA Reactor facility. The inspection results were discussed with Mr. Tucker and other members of your staff on September 18, 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 inspector reviewed selected procedures and records, observed various activities, and interviewed personnel. Based on the results of this inspection, no violations of more than minor 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 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).
September 24, 2025
S. Reese 2
Should you have any questions concerning this inspection, please contact Jonathan Braisted at (301) 287-3482, or via email at Jonathan.Braisted@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. 50-243 License No. R-106
Enclosure:
As stated cc w/enclosure: GovDelivery Subscribers Signed by Brown, Tony on 09/24/25
ML25266A100 NRC-002 OFFICE NRR/DANU/UNPO NRR/DANU/LA NRR/DANU/BC NAME JBraisted NParker TBrown DATE 9/24/2025 9/24/2025 9/24/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
05-243 License No.:
R-106 Report No.:
05000243/2025201 Licensee:
Oregon State University Facility:
Oregon State University TRIGA Reactor Location:
Corvallis, Oregon Dates:
September 15-18, 2025 Inspector:
Jonathan Braisted 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
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an inspection at the Oregon State University (OSU) TRIGA Reactor (OSTR) facility, 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 No violations of more than minor significance were identified.
Additional Tracking Items Item Type Tracking Number Title Status Report Section URI 05000243/2024201-02 Determine how the licensee is meeting technical specification 3.1.6 Closed 69001.02.03
3 REPORT DETAILS Facility Status The licensee operates the 1.1-megawatt OSTR facility in support of student training in reactor engineering theory and operation, nuclear research, and a range of irradiation services. During the inspection, the reactor was started up, operated, and shut down for annual surveillance and maintenance purposes.
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 inspector 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.
69001 - Class II Research and Test Reactors This inspection included a review of selected aspects of the research and test reactor, since the last inspection, to verify activities were conducted safely and in accordance with regulatory requirements and licensee commitments.
Organization and Staffing (IP Section 02.01)
This inspection included a review of the licensees organizational changes and shift staffing records to verify compliance with technical specification (TS) requirements and licensee commitments. Specifically, the inspection included a review of the following:
radiation center organizational chart reactor facility personnel list in the control room selected annual operating reports selected reactor operations console logbook entries selected TS on administrative controls Procedures (IP Section 02.03)
This inspection included a review of selected licensee procedures to verify: administrative controls were in accordance with the TSs, license requirements, and licensee commitments; the procedures in use were current and reviewed and approved, procedures could be implemented as intended; and reactor personnel were observing administrative controls and TS requirements relative to procedural adherence. Specifically, the inspection included a review of the following:
selected Reactor Operations Committee (ROC) meeting minutes selected operating, surveillance, maintenance, and administrative procedures selected reactor startup and shutdown checklists
4 selected fuel element history file cards selected TS on procedures observed inspections of fuel elements and control rods observed reactor power calibration observed measurements of control rod worth reactor status board Health Physics (IP Section 02.07)
This inspection included a review of the licensees health physics program to verify that the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 19, Notices, Instructions and Reports to Workers: Inspection and Investigations, and 10 CFR Part 20, Standards for Protection Against Radiation, TSs, and the licensees procedural requirements were met. The inspection included a review of: licensees dose limits; required radiation surveys, sampling, and monitoring; calibration of radiological instruments; the personnel dosimetry program; effluent releases; posting requirements; training requirements; the implementation of as low as is reasonably achievable principles; and the radiation protection programs review and approval requirements. Specifically, the inspection included a review of the following:
selected annual operating reports selected daily, weekly, monthly, and annual surveys selected personnel and area dosimetry records selected calibration records for radiation monitors selected radiation safety training records selected heath physics procedures observed notices to workers Design Changes (IP Section 02.08)
This inspection included a review of design changes to determine whether they were reviewed, approved, and implemented in accordance with 10 CFR 50.59, Changes, tests and experiments, the TSs, and the licensees administrative procedures. The inspector verified that modified equipment would continue to meet regulatory and procedural requirements and licensee commitments. Specifically, the inspection included a review of the following:
selected ROC meeting minutes selected annual operating reports selected administrative and personnel procedures selected 50.59 screening and evaluation forms
5 Committees, Audits and Reviews (IP Section 02.09)
This inspection included a review of the licensees committees, audits and reviews to verify the safety review committee and independent audits were conducted in accordance with the TSs and that issues identified from reviews were resolved in accordance with TS requirements and the licensees procedures. Specifically, the inspection included a review of the following:
selected ROC meeting minutes selected audits completed by the ROC and ROC subcommittees selected TS on the ROC, rules, reviews, and audits selected administrative and personnel procedures 86740 - Inspection of Transportation Activities This inspection included a review of the licensees transportation activities to verify they have established and maintained an effective management-controlled program, to ensure radiological and nuclear safety in the receipt, packaging, and delivery of licensed radioactive materials (RAMs). Specifically, the inspection included a review of the following:
selected annual operating reports observed measuring activity and packaging of RAMs for transport selected procedures for transfer, packaging, and transport of RAMs selected RAM shipment records selected ROC audits of radioactive material shipment logs selected quarterly management audits of the transfer, packaging, and transport of RAMs selected shipper training for RAMs and training records list of OSU personnel with designated responsibility for the safe transfer, packaging and transport of RAMs Inspection Results No violations of more than minor significance were identified.
Unresolved Item Closed Determine how the licensee is meeting TS 3.1.6 URI 05000243/2024201-02 69001.02.03
==
Description:==
During a routine inspection (Agencywide Documents Access and Management System Accession No. ML24079A184), the inspector identified an issue that required additional information to determine whether it was acceptable or constituted a noncompliance.
TS 3.1.6 states, in part, that fuel will be considered damaged if the transverse bend exceeds 0.0625 inches over the length of the cladding or if it exceeds its original length by 0.125 inches. The inspector noted that the licensee has an annual surveillance to inspect fuel elements. The licensees fuel element inspection consists of checking for fuel element swelling and visually inspecting the fuel elements for signs of damage or deterioration.
However, at the time of the inspection, the licensee was unable to provide the NRC with data on the bend and length measurements of the fuel elements.
During this inspection, the inspector reviewed surveillance requirement TS 4.1.e, which states, in part, that fuel elements shall be inspected visually for damage or deterioration and measured for concentric or other swelling on an annual basis. The inspector also reviewed
6 the NRCs safety evaluation report (SER) (ML082540035) related to the renewal of OSTRs operating license, during which TS 4.1.e was last revised. The SER noted that experience has shown that swelling provides a leading indication of fuel condition and that it precedes changes in bend or length. It also stated that fuel swelling is likely precluded by fuel temperatures remaining below a threshold during normal operations and only briefly exceeding it during pulsing. Since the licensee established an acceptance criterion for swelling during its fuel inspections and the NRC previously accepted that monitoring swelling would preclude any changes in length and bend, the inspector did not identify any violations of regulatory requirements.
This closes URI 05000243/2024201-02.
Minor Violation (VIO 05000243/2025201-01) 69001.02.03 Minor Violation: On May 8, 2024, the licensee notified the NRC Operations Center of an event that occurred the previous day. This event was logged as Event Number57113. A written report detailing the circumstances was later submitted by the licensee on May 21, 2024 (ML24145A126).
On May 7, 2024, the reactor operator shut down the reactor by inserting the control rods and removing the console key, which removes power to the control rod drives. However, following shutdown, one control rod was indicated to be not fully inserted, remaining 1 percent withdrawn. After confirming that the console key was removed and verifying with the core camera that the control rods appeared fully inserted, the reactor operator left the control room to assist with investigating the condition.
TS 6.1.3.a.1 states, in part, that [t]he minimum staffing when the reactor is not secured shall be a reactor operator or the senior reactor operator on duty (Duty SRO) in the control room.
Given the reactor core configuration at the time, the reactor could be secured only when all four control rods were fully inserted.
Contrary to the above, on May 7, 2024, the licensee failed to meet minimum staffing with a reactor operator or the Duty SRO in the control room when the reactor was not secured.
Specifically, no licensed operator was present in the control room when one of the four control rods was not fully inserted.
Screening: The inspector concluded that the violation was of minor significance, as it did not result in any safety or security consequences and did not align with any examples of more-than-minor violations outlined in the NRC Enforcement Policy.
Enforcement: The licensee has taken corrective actions to restore compliance, including replacing the components that prevented full insertion of the control rod, providing additional training to reactor operators, and conducting further inspections of the control rods. This failure to comply with TS 6.1.3.a.1 constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy.
This closes EN 57113.
7 Exit Meeting and Debriefs The inspector verified no proprietary information was retained or documented in this report.
On September 18, 2025, the inspector presented the inspection results to Mr. Tucker and other members of the licensee staff.
8 Documents Reviewed Inspection Procedure Type Designation Description or Title Revision or Date Procedures OSTROP 6 Administrative and Personnel Procedures LEU-11 Radiation Center and TRIGA Reactor Annual Report 10/14/2024 Radiation Center and TRIGA Reactor Annual Report 10/26/2023 69001.02.01 Miscellaneous Reactor Operations Console Logbooks 2023-2025 OSTROP 2 Reactor Startup Checklist Procedures LEU-19 OSTROP 5 Procedures for Maintaining Reactor Operational Records LEU-13 OSTROP 6 Administrative and Personnel Procedures LEU-11 OSTROP 8 Reactor Power Calibration Procedures LEU-5 OSTROP 11 Fuel Element Handling Procedures LEU-9 OSTROP 16 Annual Surveillance and Maintenance Procedures LEU-15 Procedures OSTROP 12 Control Rod Maintenance, Removal, and Replacement Procedures LEU-6 Fuel Element Index Transfer Sheet 49 Fuel Element Index Transfer Sheet 48 Fuel Element History File 11573 Fuel Element History File 11593 Fuel Element History File 11567 Fuel Element History File 11560 69001.02.03 Miscellaneous OSU TRIGA Reactor Startup Checklist 2023-2025
9 Inspection Procedure Type Designation Description or Title Revision or Date OSU TRIGA Reactor Shutdown Checklist 2023-2025 Radiation Center and TRIGA Reactor Annual Report 10/14/2024 Radiation Center and TRIGA Reactor Annual Report 10/26/2023 Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis 2023-2025 Supplemental Sheet for Determining the Suitability for Disposal of Licensed Material into the Sanitary Sewerage 2023-2025 Miscellaneous Occupational Radiation Exposure Report 2023-2025 RCHPP 1 Guidelines for the Radiation Protection Program at the OSU Radiation Center 11 RCHPP 8 Water Analysis 7
RCHPP 13 Procedures for Collection and Biological Analysis of Environmental Soil, Water and Vegetation Samples 5
RCHPP 24 Procedures for Performing Routine (Daily, Weekly, Monthly, and Annual)
Radiation Surveys and Non-Routine (Special) Radiation Surveys 11 RCHPP 27 Procedure for Performing the Routine Semi-Annual Floor Survey for Fixed and Removable Radioactive Contamination 7
RCHPP 32 Stack Gaseous Effluent Analysis 2
Procedures RCHPP 37 Dosimetry 4
69001.02.07 Radiation Form #RCHPP-24A Daily Routine Radiation Survey 2023-2025
10 Inspection Procedure Type Designation Description or Title Revision or Date Form #RCHPP-24B Weekly Routine Radiation Survey Record 2023-2025 Form #RCHPP-24C Monthly Routine Radiation Survey Record 2023-2025 Surveys Form #RCHPP-24F Annual Survey 2023-2025 25-01 Minor Updates to Experiments A1, B31, and B36 6/23/2025 23-02 Revisions to OSTROP 6 (ROC Charter) and OSTROP 14 6/30/2023 50.59 Evaluations 23-01 Beam Port #4 Decommissioning 3/2/2023 25-08 Ventilation System Overhaul 8/22/2025 25-05 OSTROP 10 Update for NRC Shielding 4/21/2025 25-03 Addition of Neutron Shielding to the NRF 4/21/2025 24-10 Revisions to Emergency Response Implementing Procedures (ERIPs) 9/25/2024 24-06 Revision of OSTROPs 13 and 16 (Water Conductivity/pH Measurements) 6/23/2024 24-02 Modifications to Reactor Bay South Wall 6/10/2024 23-15 Revisions to OSTROP 25 12/22/2023 50.59 Screens 23-05 Addendum to Evaluation 23-01 (Beam Port #4 Decommission) 3/30/2023 69001.02.08 Procedures OSTROP 6 Administrative and Personnel Procedures LEU-11 Minutes of the Reactor Operations Committee 5/16/2025 Minutes of the Reactor Operations Committee 2/12/2025 69001.02.09 Miscellaneous Minutes of the Reactor Operations Committee 11/7/2024
11 Inspection Procedure Type Designation Description or Title Revision or Date Minutes of the Reactor Operations Committee 5/23/2024 Minutes of the Reactor Operations Committee 3/21/2024 Minutes of the Reactor Operations Committee 11/27/2023 RCHPP 20 Radiation Survey Procedure for the Release of Items for Unrestricted Use 5/12/2025 Fuel Inventory and Transfers 5/12/2025 Emergency Plan Implementation Procedures 9/13/2024 Results of Annual Reactor Operator Requalification 12/2/2024 Results of Annual Reactor Operator Requalification 5/17/2024 Results of Annual Reactor Operator Requalification 11/16/2023 Emergency Response Plan and Emergency Response Plan Implementation Procedures Revisions for 2023 11/27/2023 Audits Reports of Annual Reactor Operator Requalification 11/16/2023 Radiation Center and TRIGA Reactor Annual Report 10/14/2024 Radiation Center and TRIGA Reactor Annual Report 10/26/2023 Miscellaneous Radioactive Material Training 2023-2025 Shipping Records Radioactive Materials (R.A.M.)
Shipping Record 2023-2025 86740 Procedures RCHPP 6 OSU Procedures for Transfer, Packaging and Transport of Radioactive Materials Other Than Radioactive Wastes 17
12 Inspection Procedure Type Designation Description or Title Revision or Date RAM Shipment Log 5/13/2025 RAM Shipment Log 2/12/2025 Radioactive Materials Shipping Log 11/27/2024 R.A.M. Shipment Logs 4/18/2024 Audits Record of Quarterly Management Audit of the Transfer, Packaging, and Transport of Radioactive Materials in Accordance with NRC IE Bulletin No. 79-19 and OSHD EA Bulletin No.
79-1 2023-2025