IR 05000284/2024201
| ML24253A163 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 09/18/2024 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Dunzik-Gougar M Idaho State University |
| References | |
| IR 2024201 | |
| Download: ML24253A163 (1) | |
Text
SUBJECT:
IDAHO STATE UNIVERSITY - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 05000284/2024201
Dear Dr. Dunzik-Gougar:
From August 12 - 15, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Idaho State University Aerojet General Nucleonics-201 Modified Research Reactor Facility. The enclosed report documents the inspection results discussed on August 15, 2024, with you (via Zoom), Larry Foulkrod, Reactor Supervisor; Dr. Chad Pope, Professor and Program Director, Nuclear Engineering Department; Mason Jaussi, campus Radiation Safety Officer; and, Kermit Bunde, Chair, Reactor Safety Committee (via Zoom).
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 the 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 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 18, 2024
M. Dunzik-Gougar
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Should you have any questions concerning this inspection, please contact Craig Bassett at (240) 535-1842, or by email to 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. 50-284 License No. R-110 Enclosure:
As stated cc: GovDelivery Subscribers Signed by Tate, Travis on 09/18/24
ML24253A163 NRC-002 OFFICE NRR/DANU/UNPO/PM NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME CBassett NParker TTate DATE 09/09/2024 09/11/2024 09/18/2024
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-284 License No.:
R-110 Report No.:
05000284/2024201 Licensee:
Idaho State University Facility:
AGN-201M Research Reactor Facility Location:
Pocatello, Idaho Dates:
August 12 - 15, 2024 Inspector:
Craig Bassett 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 Idaho State University Aerojet General Nucleonics-201 Modified Research Reactor Facility Inspection Report No. 05000284/2024201 This routine announced inspection included onsite review of selected aspects of the Idaho State University (ISU, the licensee) Class II research reactor safety program including: (1)
organization and staffing; (2) procedures; (3) health physics; (4) design changes; (5)
committees, audits, and reviews; (6) emergency planning; and (7) transportation activities since the last U.S. Nuclear Regulatory Commission (NRC) inspection of these areas. The NRC staff determined the licensees program was acceptably directed toward the protection of public health and safety and in compliance with NRC requirements.
Organization and Staffing
The licensees organization structure and staffing complied with requirements specified in the technical specifications (TSs).
Procedures
Facility procedural review, revision, and control satisfied TS requirements.
Health Physics
The facility radiation protection program was implemented and satisfied the regulatory and TS requirements.
Design Changes
The design change program developed and implemented by the licensee was in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.59, Changes, tests and experiments, requirements.
Committees, Audits and Reviews
The Reactor Safety Committee (RSC) met at least annually as required by the TSs and completed the review and audit program.
Emergency Planning
The emergency preparedness program was conducted in accordance with the Emergency Plan (E-Plan) and implementing procedures.
Transportation Activities
No radioactive material was shipped from the reactor facility under the reactor license during the past 2 years.
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REPORT DETAILS Summary of Facility Status The ISU Aerojet General Nucleonics-201 Modified (AGN-201M) Research Reactor, licensed to operate at a maximum steady-state thermal power of 5 watts, continued to operate in support of operator training, surveillance, experiments, and laboratory work. During the inspection, the reactor was not operated due to ongoing work on the heating and cooling systems on campus.
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 the TS sections 6.1 and 6.2 were met:
organizational structure and staffing for the facility
administrative controls and management responsibilities
ISU AGN-201M reactor facility master logs for the periods from August 2022 through the present
ISU AGN-201M reactor facility annual operating reports for 2022 and 2023, dated June 23, 2023, and April 8, 2024 b.
Observations and Findings Through document review and licensee interviews, the inspector found that no changes occurred in the organizational structure since the last NRC inspection at the facility in August 2023 and the organization was as stipulated in TS section 6.1. The inspector noted that the individual designated as the administrative reactor supervisor was redesignated as the reactor supervisor by the licensee via letter dated June 24, 2024.
The inspector noted that the reactor supervisor and other individuals occupying the various management and operations positions met the qualifications specified in the TS.
c.
Conclusion The inspector determined that the organization and staffing at the facility met the requirements specified in the TSs.
2.
Procedures a.
Inspection Scope (IP 69001, Section 02.03)
To ensure the requirements of TS section 6.6 were met, the inspector reviewed the following:
various ISU AGN-201M operations, maintenance, and administrative procedures
ISU Nuclear Engineering Laboratory Administrative Procedure, AP-ISU-NEL-001, 10 CFR 50.59 Evaluations, Revision 1
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b.
Observations and Findings The inspector found that the required procedures were in place to support current facility operations. The inspector confirmed that new and revised procedures were submitted to the RSC for review and approval as required by the TSs. The inspector noted that the facility procedures were revised and updated as needed.
c.
Conclusion The inspector determined procedural review, revision, control, and implementation satisfied the TS requirements.
3.
Health Physics a.
Inspection Scope (IP 69001, Section 02.07)
The inspector observed and reviewed selected aspects of the following to ensure the requirements of 10 CFR Part 19, Notices, Instructions and Reports to Workers:
Inspection and Investigations, and 10 CFR Part 20, Standards for Protection against Radiation, and TS sections 3.4, 4.4, and 6.9 were met:
radiological signs and postings in and around the reactor facility
reactor facility personnel dosimetry records for the past 3 years
radiation safety officer (RSO) annual reports for the past 2 years
Idaho State University Radiation Safety Manual, Revision 13
Radiation Safety - Refresher Training Study Guide, Revision 08/07
maintenance and calibration records of facility radiation monitoring equipment
ISU AGN-201M reactor facility annual operating reports for the previous 2 years
various forms completed by ISU Radiation Safety (Rad Safety) department technicians documenting radiation and contamination surveys of the reactor and associated labs for the past 2 years
Idaho State Universitys Determination of Exposure to Individual Members of the Public, for calendar years 2022 and 2023 b.
Observations and Findings (1) Surveys, Postings, and Notices The inspector noted that daily radiation level checks of the reactor bay were completed by licensee personnel and monthly surveys of the area were completed by the campus radiation safety department personnel. The inspector verified that the results of the surveys were documented and evaluated and met the requirements of 10 CFR Part 20 and TS 4.4. During tours of the facility, the inspector verified that the caution signs and postings were in place and that the controls established for the controlled areas were as required by 10 CFR Part 20.
The inspector confirmed that the current version of copies of NRC Form 3, Notice to Employees, were posted at the facility as required by 10 CFR 19.11, Posting of notices to workers.
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(2) Dosimetry and Radiation Monitoring Equipment Calibration The inspector found that the licensee used optically stimulated luminescence dosimeters for whole body exposure monitoring and thermoluminescent dosimeter (TLD) finger rings for monitoring radiation exposure of the extremities. The inspector confirmed that the exposures at the facility for the past 2 years were well within 10 CFR Part 20 limitations. The inspector also confirmed that portable survey meters and fixed radiation monitors were calibrated annually as required by TS 4.4.
The inspector confirmed that calibration records were maintained and reviewed.
(3) Radiation Protection Program and ALARA Policy The inspector noted that the licensees Radiation Protection Program and as low as reasonably achievable (ALARA) policy were established in various ISU radiation safety documents including: (1) the Radiation Procedures Manual and (2) the ISU Radiation Safety Manual. The inspector confirmed that the facility radiation protection program was reviewed annually, as required by 10 CFR 20.1101, Radiation protection programs, paragraph (c). The inspector also found that the ALARA policy provided guidance for keeping doses low consistent with the regulations in 10 CFR Part 20.
(4) Radiation Worker Training The inspector confirmed that all university employees and students who might receive a dose greater than ten percent of the annual occupational dose limits, including licensee staff, were required to receive training in radiation protection. The inspector reviewed documentation of the training provided to licensee staff members and found that the current staff members received the required initial and/or annual refresher training as applicable. The inspector noted that the personnel training program satisfied requirements in 10 CFR 19.12, Instruction to workers.
(5) Environmental Monitoring and Effluents The inspector found that the airborne concentrations of gaseous releases were calculated by radiation safety personnel. The inspector confirmed that the calculations demonstrated gaseous releases were well within the concentrations stipulated in 10 CFR Part 20, Appendix B, Table 2. The results were documented in the facility annual reports, as required by the TSs. The inspector noted that the calculated dose to the public, resulting from the gaseous releases, was below the dose limit established in 10 CFR 20.1101(d). The inspector confirmed that there were no radioactive liquid releases from the facility to the sanitary sewer within the past 2 years and that no solid waste was transferred from the facility to the campus Rad Safety department.
The inspector confirmed that environmental radiation monitoring was completed using TLDs and an annual survey of the exterior of the reactor room was performed in accordance with the applicable Rad Safety procedures. The data indicated that there were no unusual dose rates in the areas surrounding the facility and that there were no measurable doses above any regulatory limits. The inspector verified these results were also reported in the facility annual reports.
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c.
Conclusion The inspector determined that the radiation protection program implemented by the licensee satisfied regulatory and TS requirements.
4.
Design Changes a.
Inspection Scope (IP 69001, Section 02.08)
To ensure that the requirements of TS sections 6.4.2 and 6.5 were met, the inspector reviewed the following:
RSC meeting minutes for meetings held for the past 2 years
ISU AGN-201M reactor facility annual operating reports for the past 2 years
10 CFR 50.59 screen and evaluation forms for 2023 through the present b.
Observations and Findings The inspector confirmed that the licensee completed screenings and evaluations since the last inspection according to their design change procedure. The inspector noted that only one issue dealt with radiation protection, and it screened out; other screenings and evaluations dealing with reactor operations will be reviewed during the next NRC inspection.
c.
Conclusion The inspector determined that the design change program developed by the licensee was in accordance with 10 CFR 50.59 regulation.
5.
Committees, Audits and Reviews a.
Inspection Scope (IP 69001, Section 02.09)
The inspector reviewed the following to ensure that the requirements of TS section 6.4 were met:
completed audits and reviews documented in RSC meeting minutes
RSC meeting minutes for meetings held on May 25, 2022, March 8, 2023, and March 28, 2024
ISU AGN-201M reactor facility annual operating reports for the past 2 years b.
Observations and Findings The inspector verified that the RSC met at least once per calendar year and that a quorum was present, as required by the TSs. The inspector confirmed that the topics considered during the meetings were as outlined in the TSs and members of the RSC completed the audits and reviews required by TS 6.4.
The inspector noted that various audits and reviews were conducted by the RSC in the areas of reactor operations, radiation protection, security, and requalification of operators. The inspector confirmed that the licensee took corrective actions for findings as needed.
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c.
Conclusion The inspector determined that the RSC met at least annually and conducted the audits and reviews required by the TSs.
6.
Emergency Planning a.
Inspection Scope (IP 69001, Section 02.10)
To ensure that the licensee was implementing the various aspects of their emergency preparedness program, as stipulated in the E-Plan for ISU dated August 5, 2016, the inspector reviewed selected aspects of:
documentation of emergency drills and critiques
E-Plan implementing procedures, audits, and audit responses
reactor facility emergency notification roster dated June 11, 2024
emergency locker inventory sheets documenting maintenance of emergency response supplies, equipment, and instrumentation
memoranda of understanding (MOUs) with offsite support agencies including the City of Pocatello (for Fire and Police support), Portneuf Medical Center, and Idaho State Police b.
Observations and Findings The inspector found that the current version of the E-Plan and the implementing procedures were audited and reviewed biennially as required by the TS. The inspector noted that, following the audits, the licensee addressed any problems identified. The inspector confirmed that the MOUs with off-site response organizations were maintained and updated as required.
The inspector confirmed that the emergency supplies, instrumentation, and equipment were maintained as required in the E-Plan and that annual inspections and inventories were completed and documented as well. The inspector also confirmed that emergency drills were conducted annually as required by the E-Plan and critiques were held following the drills. The inspector noted that every 2 years the drills often included participants from the reactor staff, City of Pocatello Police and Fire Departments, Portneuf Medical Center staff, and ISU Public Safety officers as required by the E-Plan.
The inspector noted that the emergency training for the reactor staff and for response organization personnel was conducted. The inspector found that training for off-site support personnel was typically done in conjunction with the annual drills. Through interviews with various personnel, the inspector confirmed that the emergency responders were knowledgeable of the actions to take in case of an emergency.
The inspector, accompanied by the Reactor Supervisor, met with a training supervisor from the City of Pocatello Fire Department at Fire Station #1. Various topics were discussed including training, participation in drills, and support of the research reactor facility. From the visit, the inspector noted that there was a good working relationship between reactor staff and Fire Department personnel.
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c.
Conclusion The inspector determined that the emergency preparedness program was carried out in accordance with the E-Plan.
7.
Transportation Activities a.
Inspection Scope (IP 86740)
The inspector reviewed the following to ensure compliance with the NRC regulatory and licensee procedural requirements for shipping or transferring licensed material were met:
radioactive material transfer records for the last 2 years documented on form RPR 14 - Request for Shipment of Radioactive Material
shipper training and certification records b.
Observations and Findings Through records review and discussions with licensee personnel and the campus RSO, the inspector verified that the licensee did not ship any radioactive material from the facility under the reactor license in the past 2 years. The inspector confirmed that any reactor-produced radioactive material was transferred to the campus broadscope license and shipped under that license, transferred to other authorized users on campus, or maintained at the reactor facility for use in laboratories in accordance with procedure.
The inspector also noted that no reactor staff members were authorized to ship radioactive material. If material needed to be shipped, a qualified shipper from the radiation safety department would process the shipment. The inspector confirmed that there were various Rad Safety personnel who were qualified to ship radioactive materials.
c.
Conclusion The inspector determined no radioactive material was shipped from the reactor facility under the reactor license during the past several years.
8.
Exit Meeting Summary The inspection scope and results were summarized by the inspector on August 15, 2024, with licensee representatives. The inspector discussed the findings for each area reviewed.
The licensee acknowledged the results of the inspection and did not identify any information as proprietary.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel M. Dunzik-Gougar Reactor Administrator L. Foulkrod Reactor Supervisor C. Pope Professor and Program Director, Nuclear Engineering Department Other Personnel K. Bunde Chair, Reactor Safety Committee M. Jaussi Radiation Safety Officer, Radiation Safety Department, ISU M. Mendez Training Supervisor, Fire Station 1, City of Pocatello Fire Department INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors IP 86740 Inspection of Transportation Activities ITEMS OPENED, CLOSED, AND DISCUSSED OPENED:
None CLOSED:
None