IR 05000607/2024201
| ML24032A029 | |
| Person / Time | |
|---|---|
| Site: | University of California-Davis |
| Issue date: | 03/28/2024 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Frey W McClellan Nucleaer Research Center, McClellan Nuclear Research Center |
| Craig Bassett, NRR/DANU | |
| References | |
| IR 2024201 | |
| Download: ML24032A029 (1) | |
Text
SUBJECT:
REGENTS OF THE UNIVERSITY OF CALIFORNIA - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO.
Dear Dr. Frey:
From January 22 - 25, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the University of California-Davis/McClellan Nuclear Research Center. The enclosed report documents the inspection results discussed on January 25, 2024, with you and reactor supervisor, Burton Mehciz.
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 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).
March 28, 2024 If you have any questions concerning this inspection, please contact Craig Bassett at (240) 535-1842, or by email at Craig.Bassett@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. 50-607 License No. R-130 Enclosure:
As stated cc w/enclosure: GovDelivery Subscribers Signed by Tate, Travis on 03/28/24
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-607 License No.:
R-130 Report No.:
05000607/2024201 Licensee:
Regents of the University of California Facility:
University of California-Davis/McClellan Nuclear Research Center Location:
McClellan Park Sacramento, California Dates:
January 22 - 25, 2024 Inspectors:
Craig Bassett Necota Staples, RTR Inspector Trainee 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 University of California-Davis McClellan Nuclear Research Center Inspection Report No. 05000607/2024201 The primary focus of this routine, announced inspection was the onsite review of selected aspects of the University of California-Davis/McClellan Nuclear Research Center (UCD/MNRC)
1-megawatt (MW) Class II research reactor safety program, including: (1) organization and staffing; (2) operations logs and records; (3) procedures; (4) requalification training; (5) surveillance and limiting conditions for operation (LCOs); (6) design changes; (7) committees, audits and reviews; (8) maintenance logs and records; and (9) fuel handling logs and records. The U.S. Nuclear Regulatory Commission (NRC) staff determined the licensees program was acceptably directed toward the protection of public health and safety and in compliance with regulatory requirements.
Organization and staffing
The UCD/MNRC organizational structure and staffing were consistent with technical specifications (TSs) requirements.
Operations Logs and Records
Reactor operations were conducted in accordance with procedures, logs and records were appropriately maintained, and significant activities were logged and recorded.
Procedures
Procedure review, revision, control, and implementation satisfied TSs requirements.
Requalification Training
Operator training, requalification, and medical examinations were conducted in accordance with the NRC approved requalification program and as required by the NRC regulations.
Surveillance and Limiting Conditions for Operation
Surveillance activities at the facility and LCOs were completed within the TSs-prescribed time frames and parameters.
Design Changes
The review, evaluation, and documentation of changes to the facility satisfied the change control procedure and NRC regulations.
Committees, Audits and Reviews
Audits and reviews conducted by the Nuclear Safety Committee (NSC) were in accordance with TSs section 6.2 and the NSC met at the required periodicity.
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Maintenance Logs and Records
Maintenance logs and records were kept, and maintenance activities were conducted in accordance with procedural requirements.
Fuel Handling Logs and Records
Fuel movement and handling was conducted in accordance with procedural requirements and fuel inspections were completed annually as required by the TSs.
- Inspection follow-up of activities and corrective actions for Event Notification 56643 were reviewed and the event was determined to be closed.
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REPORT DETAILS Summary of Facility Status The UCD/MNRC 1 MW Class II Training, Research, Isotope, General Atomics (TRIGA)
Mark-II research reactor continued to be operated in support of neutron radiography, neutron tomography, and sample/product irradiation. During the inspection, the reactor was operated for neutron radiography and an experiment.
1.
Organization and Staffing a.
Inspection Scope (IP 69001)
The inspectors reviewed the following regarding UCD/MNRC reactor operations and staffing to ensure that the requirements of TS section 6.1 were met:
management responsibilities
logbooks Nos. 193 through 197
current UCD/MNRC organizational structure
staffing requirements for safe operation of the research reactor facility
UCD/MNRC 2021 annual report, submitted to the NRC on June 3, 2022
UCD/MNRC 2022 annual report, submitted to the NRC on May 22, 2023
facility procedure UCD/MNRC-0004-DOC-16, Technical Specifications for the University of California, Davis/McClellan Nuclear Radiation Center (UCD/MNRC)
b.
Observations and Findings The inspectors noted that the current organization consisted of eleven individuals. The inspectors also verified that the current organization was consistent with the structure specified in the TSs.
The inspectors found that six staff members were licensed senior reactor operators (SROs); the remainder of the staff was comprised of radiographers and helpers. In addition, the inspectors verified that staffing of the research reactor facility as required by the TSs was met.
c.
Conclusion The inspectors determined that the licensees organization and staffing complied with the requirements specified in TS section 6.0.
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2.
Operations Logs and Records a.
Inspection Scope (IP 69001)
The inspectors reviewed the following regarding UCD/MNRC reactor operations to ensure that the requirements of TSs sections 3.0, 6.1, and 6.8 were met:
logbooks Nos. 193 through 197
procedure UCD/MNRC-0016-DOC-12, UCD/MNRC Operating Instructions
various UCD/MNRC startup checklist, shutdown checklist, and facility rounds log forms for 2022 through the present
the two most recent annual reports for UCD/MNRC submitted to the NRC b.
Observations and Findings The inspectors observed various facility activities including a reactor start-up, steady state operation, and shutdown and found operations were conducted in accordance with the applicable procedures and documented in the logs. The inspectors confirmed that the facility logbooks and records listed operational conditions and parameters which were consistent with the license and TSs requirements and indicated that operational limits were not exceeded.
c.
Conclusion The inspectors determined that reactor operations were conducted in accordance with procedures and TSs, and the appropriate logs were maintained.
3.
Procedures a.
Inspection Scope (IP 69001)
To verify compliance with TS section 6.4, the inspectors reviewed selected portions of the following:
UCD/MNRC document list including the dates of the last procedure reviews
procedures UCD/MNRC-0005-DOC-15, Document Control Plan and UCD/MNRC-0043-DOC-05, Facility Modification Procedure b.
Observations and Findings The inspectors noted that TS section 6.4 required procedures be prepared and approved for the activities listed in that section and new procedures and substantive changes to existing procedures be reviewed by the NSC and approved by the UCD/MNRC director. The inspectors verified that this process was followed by the licensee. The inspectors also noted periodic reviews of the procedures were required by procedure UCD/MNRC-0005-DOC-15 to assure that they were current.
The inspectors confirmed that the procedural process for biennial reviews of the majority of the procedures and annual reviews of the security procedures was followed by the licensee.
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c.
Conclusion The inspectors determined the current procedure review, revision, control, and implementation program satisfied TSs requirements.
4.
Requalification Training a.
Inspection Scope (Inspection Procedure (IP) 69001)
The inspectors reviewed selected aspects of the following to verify compliance with the UCD/MNRC operator training and requalification program outlined in procedure UCD/MNRC-0009-DOC-05, Selection and Training Plan for Reactor Personnel, and section 6.1.4 of the TSs:
logbooks Nos. 193 through 197
status of qualified operators licenses
selected operator physical examination, training and lecture attendance, reactivity manipulations and active-duty performance records, and annual operating tests and requalification written examinations for the current training cycle
current memorandum from Dr. Wesley Frey, UCD/MNRC Director, dated July 19, 2023, designating facility personnel who were authorized to perform the functions of a SRO
the two most recent annual reports for UCD/MNRC submitted to the NRC b.
Observations and Findings The inspectors noted that there were six SROs on staff at the facility and confirmed that all operators licenses were current in that the operators maintained active-duty status in accordance with the qualification program. The inspectors also reviewed medical records for the operators and verified that they received medical examinations every two years as required by the NRC regulations.
c.
Conclusion The inspectors determined each operators training, requalification, and medical examination was completed and maintained up to date as required by the licensees requalification program and regulatory requirements.
5. Surveillance and Limiting Conditions for Operation a.
Inspection Scope (IP 69001)
To verify that the licensee complied with TS sections 3.0 and 4.0, the inspectors reviewed selected aspects of:
logbooks Nos. 193, 194, 195
surveillances, chart recorder records and logs
select LCOs
select reactor status logs, dated 2022 through the present
select console operations logs, dated 2022 through the present
select reactor startup and shutdown checks, dated 2022 through the present
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procedure UCD/MNRC-0007-DOC-05, Maintenance Procedures
nuclear instrument power calibrations records and corrective action entries
selected maintenance work orders (MWOs) documenting various completed and pending surveillance items for 2023 and to date in 2024 b.
Observations and Findings The inspectors confirmed that routine maintenance work and surveillance activities were completed as required by the TSs. The inspectors verified that many major maintenance and surveillance items were completed during the licensees annual maintenance shutdown. The inspectors found the results of surveillances were within the TSs and procedurally prescribed parameters.
c.
Conclusion The inspectors determined that the UCD/MNRC preventive maintenance system was used to track and complete surveillance activities at the facility in a timely manner in accordance with the TSs.
6.
Design Changes a.
Inspection Scope (IP 69001)
To verify that facility changes were reviewed and approved as required by the licensees change process outlined in procedure UCD/MNRC-0043-DOC-05, Facility Modification Procedure, the inspectors reviewed selected aspects of:
NSC meeting minutes for March 2022 through the present
UCD/MNRC facility modification notebook containing facility modification log forms
selected facility modification installation authorization forms and the associated checklist forms processed during 2022 through the present b.
Observations and Findings The inspectors noted that the licensee implemented procedure UCD/MNRC-0043-
-DOC-05, Facility Modification Procedure, which incorporated criteria specified in the NRC regulations. The inspectors verified that various change requests, screenings, and evaluations were processed since the previous NRC inspection.
The inspectors noted that one of the proposed changes required a license amendment which was subsequently issued by the NRC.
c.
Conclusion The inspectors determined that the facility design change program satisfied NRC requirements.
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7.
Committees, Audits and Reviews a.
Inspection Scope (IP 69001)
To verify that the required reviews and audits were completed by the licensee as required by TS section 6.2, the inspectors reviewed selected aspects of:
annual audits conducted for 2022 and 2023
NSC meeting minutes for March 2022 through the present
current NSC charter dated October 2022, Revision 4, with appendix dated February 10, 2023 b.
Observations and Findings The inspectors verified that the NSC met at least annually as required by TS section 6.2.2 and provided the reviews and oversight specified in TS section 6.2.3.
The inspectors confirmed that various audits were conducted which covered the activities specified in TS section 6.2.4.
c.
Conclusion The inspectors determined that the NSC met semiannually, reviewed the topics outlined in the TSs, and conducted annual audits of facility programs as required by TSs.
8.
Maintenance Logs and Records a.
Inspection Scope (IP 69001)
The inspectors reviewed the following regarding the UCD/MNRC routine maintenance and the preventive maintenance programs to ensure that the requirements of TSs sections 3.0 and 6.8 were met:
logbooks Nos. 193, 194,195
preventive maintenance system database including equipment history
selected MNRC work order forms documenting completed maintenance tasks
procedures UCD/MNRC-0007-DOC-05, Maintenance Procedures; UCD/MNRC-0016-DOC-12, Operating Instructions; UCD/MNRC-0012-OMM-05, Primary Cooling System Operation and Maintenance Manual; and, UCD/MNRC-0063-OMM-01, 5340, Reactor Protective System Operation and Maintenance Manual
the two most recent annual reports for UCD/MNRC submitted to the NRC
preventive maintenance program (PMP)
selected records for various TSs required surveillances and results b.
Observations and Findings The PMP produces periodic work schedules and MWOs. The inspectors verified that the MWOs were used to complete and document the maintenance and/surveillance activities. The surveillance records indicated that the required tests, checks, verifications, and calibrations were completed on schedule and in accordance with
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licensee procedures. The results were found to be within the TSs and procedurally prescribed parameters.
The inspectors found once the work was completed, the data from each MWO was entered into the computerized tracking system for tracking maintenance completion. The inspectors verified that the licensee conducted routine maintenance activities at the frequencies required by their maintenance program.
c.
Conclusion The inspectors determined that the facility maintenance logs and records were in accordance with procedures and were performed consistent with TS requirements.
9. Fuel Handling Logs and Records a.
Inspection Scope (IP 69001)
To ensure that the licensee followed the requirements of TS sections 3.1.4, 4.1.4, and 5.3, the inspectors reviewed selected aspects of the following:
logbooks Nos. 193, 194,195
selected UCD/MNRC fuel movement and transfer forms, fuel handling checklists, and fuel inspection and tracking sheets for 2022 and 2023
selected UCD/MNRC element location forms and the core status boards located in the control room and in the reactor room which indicated current fuel element (FE) locations
procedures UCD/MNRC-0019-OMM-04, 5220, Fuel Handling Tools; UCD/MNRC-0011-OMM-07, 5240, Fuel; UCD/MNRC-0011-OMM-07, Fuel - UCD MNRC Operation and Maintenance Manual; and, UCD/MNRC-0013-OMM-04, 5140, Control Rod System, Operation and Maintenance Manual b.
Observations and Findings (1) Routine Inspection Activities The inspectors verified that fuel was moved according to an established procedure and in conjunction with specific fuel movement sheets. The inspectors also noted that fuel inspections were completed annually in compliance with TS sections 3.2.4 and 4.2.4. The inspectors verified that fuel handling tools were maintained and were controlled and secured when not in use. The inspectors confirmed that fuel was used and stored in authorized locations.
(2) Review of Event Notification 56643 On July 28, 2023, in accordance with the requirements of TS 6.7.2 the licensee notified the NRC that they discovered a problem with a stainless steel clad standard TRIGA fuel element (FE) which failed to pass visual inspection. The visual inspection showed pitting and unusual discoloration in the cladding of the fueled and non-fueled section of the FE while measurements showed that other parameters were met.
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During this inspection, the inspectors reviewed the circumstances surrounding this notification. Once identified, the FE was immediately and permanently removed from service and placed in an in-tank fuel storage rack. The inspectors noted that the licensee investigated the issue but could not determine the exact cause of the pitting although it was suspected that it may have been a manufacturing defect. The FE, with serial number 10873, was at approximately twenty-three percent burnup when it failed inspection. The inspectors found that the licensee made notations on the fuel history and tracking sheet associated with the damaged FE, as well as on the fuel tag maintained on the fuel status board in the control room, that this FE was not to be used in future core operations. The inspectors noted that the licensee also submitted a 14-day written report to the NRC on August 10, 2023.
The inspectors verified that the FE was, indeed, removed from the core and was stored in a fuel storage rack. The inspectors verified that the fuel history sheet and the fuel tag on the status board were notated with a caution label indicating that the FE was not to be used. As an additional cautionary measure, the licensee inspected approximately 85 percent of all in-core FEs; no other problems were identified with any of those elements. The inspectors also confirmed that the previous TSs for the facility (in effect prior to November 21, 2022), did not require all the FEs to be inspected but only the lead elements. This resulted in an inspection of only about 20 percent of the same elements in the core for about 20 years. The licensee applied for a down-rate in power from 2 MW to 1 MW which was granted by the NRC in November 2022, along with the issuance of a new set of TSs. With the approval of the new TSs, the licensee is now required to inspect all FEs every 5 years. The inspectors confirmed that the licensees corrective actions, along with the new TS requirements, provide advanced indication of any further fuel issues. The inspectors found that the licensee understood the root cause of the problem and took corrective actions as warranted. This issue, involving Event Notification 56643, which was considered an Inspector Follow-up Item (05000607/2024201-01), is now closed.
c.
Conclusion The inspectors determined that fuel movements and inspections were conducted in accordance with the TSs and procedural requirements. The inspectors reviewed the circumstances surrounding Event Notification 56643 and determined that the issue is closed.
10. Exit Interview The inspection scope and results were summarized on January 25, 2024, with facility management. The inspectors described the areas inspected and discussed in detail the inspection findings. The licensee acknowledged the findings presented.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel C. Dresser Radiography Supervisor and SRO T. Essert Electrical Engineer and SRO Facility Director and SRO E. Gabbler Radiographer and Reactor Operator (RO) trainee J. Lachica Radiographer and RO trainee B. Mehciz Operations Manager, and SRO D. Reap Radiation Safety Officer, Security Officer, and SRO T. Slattery Senior Photo Technician P. Van Gent Radiographer and RO trainee S. Warren Radiographer, Level III, and SRO M. Wilkinson Radiographer, Level II and RO trainee Other Personnel None INSPECTION PROCEDURE USED IP 69001 Class II Research and Test Reactors ITEMS OPENED AND CLOSED Opened 05000607/2024201-01 IFI Follow-up on the problem involving a stainless steel clad standard TRIGA fuel element (FE) which failed to pass visual inspection.
Closed 05000607/2024201-01 IFI Follow-up on the problem involving a stainless steel clad standard TRIGA fuel element (FE) which failed to pass visual inspection.