IR 05000243/2024201
| ML24079A184 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 04/04/2024 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Reese S Oregon State University |
| Andrew Waugh, NRR/DANU | |
| References | |
| IR 2024201 | |
| Download: ML24079A184 (1) | |
Text
SUBJECT:
OREGON STATE UNIVERSITY - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000243/2024201
Dear Dr. Reese:
From March 4-7, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Oregon State University TRIGA reactor. The enclosed report presents the inspection results, which were discussed on March 7, 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 inspector reviewed selected procedures and records, observed various activities, and interviewed personnel.
Based on the results of this inspection, the NRC has determined that a Severity Level IV violation of NRC requirements occurred. This violation is being treated as non-cited violation (NCV), consistent with section 2.3.2 of the Enforcement Policy. This 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 U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001 with copies to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, 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 the NRCs document system (Agencywide Documents Access and Management System (ADAMS)). ADAMS is accessible from the NRC website at https://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
April 4, 2024 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, 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.: 50-243 License No.: R-106 Enclosure:
As stated cc w/enclosure: GovDelivery Subscribers Signed by Tate, Travis on 04/04/24
ML24079A184 NRC-002 OFFICE NRR/DANU/UNPO NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME AWaugh NParker TTate DATE 03/19/2024 03/21/2024 04/04/2024
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-243 License No.:
R-106 Report No.:
05000243/2024201 Licensee:
Oregon State University Facility:
Oregon State University TRIGA Reactor Location:
Corvallis, Oregon Dates:
March 4-7, 2024 Inspectors:
Andrew Waugh 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 Oregon State University Oregon State University TRIGA Reactor Inspection Report No. 05000243/2024201 The primary focus of this routine announced inspection was the onsite review of selected aspects of the Oregon State University (OSU, the licensees) 1.1 megawatt (MW) Class II research reactor facility safety program, including: (1) organization and staffing; (2) operations logs and records; (3) requalification training; (4) surveillance and limiting conditions for operation (LCO); (5) experiments; (6) emergency planning; (7) maintenance logs and records; and (8) fuel handling logs and records. 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.
Organization and Staffing
The inspector determined that the organization and staffing were in compliance with the technical specification (TS) requirements.
Operations Logs and Records
The inspector determined that the operations logs and records were maintained in accordance with the applicable TS and the licensees procedural requirements.
Requalification Training
The inspector determined that the operator requalification program was conducted and completed in accordance with the NRC-approved program and regulatory requirements.
Surveillance and Limiting Conditions for Operation
The inspector determined that contrary to TS 3.1.1 the licensee raised reactor power above the 1.1 MW limit during non-pulsing operations on May 31, 2023.
- The inspector determined that surveillances were conducted and LCO were maintained in accordance with TS requirements, with the exception noted above.
Experiments
The inspector determined that experiments were reviewed, approved, and conducted in accordance TS, procedural, and regulatory requirements.
Emergency Planning
The inspector determined that the emergency preparedness program was conducted in accordance with the emergency plan.
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Maintenance Logs and Records
The inspector determined that the maintenance activities were performed and documented in accordance with TS requirements.
Fuel Handling Logs and Records
With the potential exception noted in section 8 of this report, the inspector determined that the fuel movements and inspections were conducted in accordance with TS and the licensees procedural requirements.
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REPORT DETAILS Summary of Facility Status The licensees 1.1 megawatt TRIGA research reactor was operated in support of laboratory experiments, and various types of irradiation projects. During the inspection the reactor was started up, operated, and shut down as required to support these ongoing activities.
1.
Organization and Staffing a.
Inspection Scope (Inspection Procedure [IP] 69001, Section 02.01)
The inspector reviewed the following regarding the licensees organization and staffing to ensure that the requirements of TS 6.1 and 6.7.2 were met:
select console logbook entries, dated 2022-present
2022 and 2023 annual operating reports b.
Observations and Findings The inspector found that the licensees organization was consistent with that specified in the TS, and that the NRC was made aware of the personnel changes in accordance with the TS requirements.
The inspector found the minimum shift staffing for reactor operations continued to meet the TS requirement.
c.
Conclusion The inspector determined that the organization and staffing were in compliance with the TS requirements.
2.
Operations Logs and Records a.
Inspection Scope (IP 69001, Section 02.02)
The inspector observed completion of a reactor startup checklist, reactor startup, reactor shutdown, and reactor shutdown checklist. The inspector also reviewed the following to ensure that logs and records were maintained as required by the licensees administrative procedures and TS 6.8:
Oregon State TRIGA Reactor Operating Procedures (OSTROP) 2, Reactor Startup Checklist Procedures, dated October 2023
OSTROP 3, Reactor Shutdown Checklist Procedure, dated March 2023
OSTROP 4, Reactor Operation Procedures, dated October 2023
OSTROP 5, Procedures for Maintaining Reactor Operational Records, dated August 2022
select console logbook entries, dated 2022-present
select reactor startup and shutdown checklists, dated 2022-present
select reactor daily power logs, dated 2022-present
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select reactor control room log sheets, dated 2022-present b.
Observations and Findings The inspector found that the licensees operation logs and records were maintained as required by the licensees TS and administrative procedures.
The inspector observed that the measured parameters for several reactor operations met the TS requirements.
c.
Conclusion The inspector determined that the operations logs and records were maintained in accordance with the applicable TS and the licensees procedural requirements.
3.
Requalification Training a.
Inspection Scope (IP 69001, Section 02.04)
The inspector reviewed the following aspects of the licensees requalification program to verify compliance with Title 10 of the Code of Federal Regulations (10 CFR) Part 55, Operators Licenses, and the licensees NRC-approved operator requalification program:
Requalification Program for licensed operators of the Oregon State TRIGA reactor, dated April 28, 2022
OSTROP 5, Procedures for Maintaining Reactor Operational Records, dated August 2022
select medical examination records for licensed operators
select requalification training records, dated 2022-present
requalification exam records, dated 2022-present
select console logbook entries, dated 2022-present
select reactor operations committee meeting minutes, dated 2022-present b.
Observations and Findings The inspector found that the licensees training was conducted and documented in accordance with their NRC-approved requalification and training program, medical examinations were completed every two years, and that the license operators requalification training and medical records were maintained.
c.
Conclusion The inspector determined that the operator requalification program was conducted and completed in accordance with the NRC approved program and regulatory requirements.
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4.
Surveillance and Limiting Conditions for Operation a.
Inspection Scope (IP 69001, Section 02.05)
The inspector observed a reactor startup checklist, reactor startup, reactor shutdown, and reactor shutdown checklist. The inspector also reviewed the following to verify compliance with TS 3 and to determine if surveillance tests were performed as required by TS 4:
select console logbook entries, dated 2022-present
2022 and 2023 annual operating reports
OSTROP 4, Reactor Operation Procedures, dated October 2023
OSTROP 13, Monthly Surveillance and Maintenance Procedures, dated October 2021
OSTROP 14, Quarterly Surveillance and Maintenance Procedures, dated June 2023
OSTROP 15, Semi-Annual Surveillance and Maintenance Procedures, dated August 2022
OSTROP 16, Annual Surveillance and Maintenance Procedures, dated October 2023
select completed OSTROP 13, 14, 15, and 16 surveillance and maintenance forms, dated 2022-present
select reactor startup and shutdown checklists, dated 2022-present
14-day follow-up to Event Notification 56579 b.
Observations and Findings The inspector found that surveillance tests were completed as required by the TS and LCO verifications were completed on schedule and in accordance with the licensees procedures except as noted below.
While conducting an inspection follow-up of an issue reported in Event Notification 56579, the inspector determined that a violation of TS 3.1.1 occurred and is being assessed in this inspection. Specifically, TS 3.1.1 states, The reactor power level shall not exceed 1.1 MW except for pulsing operations.
Contrary to the above, on May 31, 2023, the reactor power was raised above 1.1 MW during square-wave operation. The licensee was attempting to perform a square-wave operation to raise reactor power from 100 W to 1 MW but performed two steps of the procedure out of sequence. This error, which is described in Event Notification 56579, caused the reactor power to raise from 100 watts (W) to above 1.1 MW in approximately one second and an automatic reactor scram was immediately initiated upon exceeding the safety and percent power channels scram setpoints of 106 percent of 1 MW. The reactor power was above 1.1 MW for less than one second during this operation.
The failure to meet the maximum power level requirement of TS 3.1.1 was a Severity Level IV violation consistent with section 6.1.d.1 of the NRC Enforcement Policy. The NRC staff determined the safety consequences of the event were low due to the short
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duration of the condition and that the reactor protection system responded appropriately.
This issue is being treated as a non-cited violation (NCV), consistent with section 2.3.2.b of the NRC Enforcement Policy (NCV 05000243/2024201-1). The licensee conducted training on the event and updated OSTROP 4 to add safety checks. The inspector determined the licensee has implemented appropriate corrective actions and this issue is closed.
c.
Conclusion The inspector determined that contrary to TS 3.1.1 the licensee raised reactor power above the 1.1 MW limit during non-pulsing operations on May 31, 2023.
The inspector determined that the surveillances were conducted and LCO were maintained in accordance with the TS requirements.
5.
Experiments a.
Inspection Scope (IP 69001, Section 02.06)
The inspector observed several irradiation experiments and reviewed the following to ensure that experiments were reviewed and conducted as required by TSs 3.8, 3.10, and 6.5:
select reactor operations committee meeting minutes, dated 2022-present
2022 and 2023 annual operating reports
OSTROP 10, Operating Procedures for Reactor Experimental Facilities, dated January 2024
OSTROP 18, Procedures for the approval and Use of Reactor Experiments, dated September 2022
documentation for various active experiments
select approved irradiation request forms, dated 2022-present b.
Observations and Findings The inspector found that experiments were reviewed and approved as required by TS 6.5 and 10 CFR 50.59, Changes, tests and experiments. The inspector also found that experiments were conducted in accordance with the licensees procedures and TSs 3.8 and 3.10.
c.
Conclusion The inspector determined that experiments were reviewed, approved, and conducted in accordance with the TS, procedural, and regulatory requirements.
6.
Emergency Planning a.
Inspection Scope (IP 69001, Section 02.10)
The inspector 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:
Oregon State University Radiation Center and Oregon State TRIGA reactor Emergency Response Plan, dated December 2023
OSTROP 1, Annunciator Response Procedures, January 2024
select emergency response implementing procedures
select reactor operations committee meeting minutes, dated 2022-present
quarterly and annual emergency equipment inventory checklists, dated 2022-present
emergency drill records, dated 2022-present
select training records, dated 2022-present b.
Observations and Findings The inspector 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.
c.
Conclusion The inspector determined that the emergency preparedness program was conducted in accordance with the emergency plan.
7.
Maintenance Logs and Records a.
Inspection Scope (IP 69001, Section 02.11)
The inspector reviewed the following selected maintenance logs and records to verify compliance with the requirements of TS:
select console logbook entries, dated 2022-present
2022 and 2023 annual operating reports
select completed OSTROP 13, 14, 15, and 16 surveillance and maintenance forms, dated 2022-present
select reactor operations committee meeting minutes, dated 2022-present b.
Observations and Findings The inspector found that the scheduled and unscheduled preventive and corrective maintenance activities were performed and documented in accordance with the TS requirements and the licensees administrative procedures.
c.
Conclusion The inspector determined that the maintenance activities were performed and documented in accordance with the TS requirements.
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8.
Fuel Handling Logs and Records a.
Inspection Scope (IP 69001, Section 02.12)
The inspector observed the licensee conduct a fuel movement. The inspector also reviewed the following fuel handling logs and activities to verify compliance with TS requirements:
OSTROP 11, Fuel Element Handling Procedures, dated December 2022
OSTROP 16, Annual Surveillance and Maintenance Procedures, dated October 2023
select fuel element transfer logs, dated 2022-present
select fuel element history file records, dated 2022-present
select console logbook entries, dated 2022-present b.
Observations and Findings The inspector found that the fuel handling activities were conducted and documented in accordance with TS requirements and the licensees procedural requirements.
During this inspection, the inspector identified an issue which more information is required to determine if it is acceptable or if it constitutes 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 found that the licensee has an annual surveillance to inspect fuel elements. The licensees fuel element inspection consists of a check for fuel element swelling and visually inspecting the fuel elements for damage and deterioration.
During this inspection the licensee was unable to provide the NRC data on the bend and length of the fuel elements. More information is required to determine how TS 3.1.6 is being met, so the NRC staff are opening unresolved item (URI)05000243/2024201-2 to track the issue. URI 05000243/2024201-2 will be reviewed during the next inspection.
c.
Conclusion With the potential exception noted above, the inspector determined that the fuel movements and inspections were conducted in accordance with the TS and licensees procedural requirements.
9.
Exit Interview The inspection scope and results were summarized on March 7, 2024, with members of the licensee management. The inspector described the areas inspected and discussed the inspection results.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel Radiation Center Director R. Schickler Reactor Administrator C. Oney Reactor Supervisor Z. Tucker Reactor Operator P. Sprague Reactor Operator S. Menn Senior Health Physicist INSPECTION PROCEDURES USED IP 69001 Class II Non-Power Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Opened NCV 05000243/2024201-1 Violation of technical specification (TS) 3.1.1, by exceeding 1.1 MW during non-pulsing operations.
URI 05000243/2024201-2 Determine how the licensee is meeting TS 3.1.6.
Closed NCV 05000243/2024201-1 Violation of TS 3.1.1, by exceeding 1.1 MW during non-pulsing operations.
Discussed None