IR 05000284/2023201
| ML23229A025 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 01/09/2024 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Dunzik-Gougar M Idaho State University |
| References | |
| 05000284/202301 IR 2023201 | |
| Download: ML23229A025 (18) | |
Text
SUBJECT:
IDAHO STATE UNIVERSITY - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT NO. 05000284/2023201 AND NOTICE OF VIOLATION
Dear Dr. Dunzik-Gougar:
From July 31 - August 3, 2023, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Idaho State University Aerojet General Nucleonics-201M Research Reactor Facility. The enclosed report documents the inspection results, which were discussed on August 3, 2023, with you, Dr. Marty Blair, Vice President for Research, Dr. Chad Pope, Chair, Department of Nuclear Engineering and Radiation Safety, Kermit Bunde, Reactor Safety Committee chair, Mason Jaussi, Campus Radiation Safety Officer, Jonathan Scott, Reactor Supervisor, and Larry Foulkrod, Administrative Reactor Supervisor.
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. The violation was evaluated in accordance with the NRC Enforcement Policy. The current Enforcement Policy is included on the NRCs website at https://www.nrc.gov/about-nrc/regulatory/enforcement/enforce-pol.html. The violation is cited in the enclosed Notice of Violation (Notice) and the circumstances surrounding it are described in detail in the subject inspection report. The violation is being cited in the Notice because it constitutes a failure to meet regulatory requirements that has more than minor safety significance and the licensee failed to identify the violation.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. If you have additional information that you believe the NRC should consider, you may provide it in your response to the Notice. The NRC January 9, 2024
M. Dunzik-Gougar
review of your response to the Notice will also determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
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 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). To the extent possible, your response should not include any personal privacy or proprietary information, so that it can be made available to the public without redaction.
Should 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. 50-284 License No. R-110 Enclosures:
As stated cc: GovDelivery Subscribers Signed by Tate, Travis on 01/09/24
ML23229A025 NRC-002 OFFICE NRR/DANU/UNPO/RI NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME CBassett NParker TTate DATE 8/21/2023 8/22/2023 1/9/2023
NOTICE OF VIOLATION Idaho State University Docket No. 50-284 AGN-201M Research Reactor Facility License No. R-110 During a U.S. Nuclear Regulatory Commission (NRC) inspection conducted from July 31-August 3, 2023, two violations of NRC requirements were identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
Title 10 of the Code of Federal Regulations (10 CFR) 55.53, Conditions of licenses, paragraph (i) requires that, the licensee [reactor operator] shall have a biennial medical examination.
Contrary to the above, during this inspection the NRC inspector found that two senior reactor operators (SROs) (licensees) with active licenses did not have a biennial medical examination.
Specifically, the NRC inspector found one SROs previous medical examination was completed on July 8, 2021, while a subsequent medical examination had not been completed by July 8, 2023, in accordance with 10 CFR 55.53. The NRC inspector also found that a second SROs previous medical examination was completed on July 19, 2021, while a subsequent medical examination had not been completed by July 19, 2023, in accordance with 10 CFR 55.53.
During the inspection, the two SROs immediately had a medical examination; however, the medical examination intervals for both SROs were found by the NRC inspector to exceed the biennial requirement. The NRC inspector found that the licensee failed to track the status of the medical qualifications for both SROs. The SROs received training by the licensee to emphasize the importance of complying with the regulations. The inspector noted that neither SRO operated the reactor during the period when they were not in compliance with the biennial medical examination requirement.
This is being treated as two examples of the same issue and therefore, is being treated as one violation as stipulated in Enforcement Manual, Part I, Section 2.3. This has been determined to be a Severity Level IV violation (NRC Enforcement Policy section 6.4).
Pursuant to the provisions of 10 CFR 2.201, Notice of violation, Idaho State University is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a Reply to a Notice of Violation, and should include: (1) the reason for the violation, or, if contested, the basis for disputing the violation or severity level, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an Order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
Enclosure 1 Because your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (Agencywide Documents Access and Management System), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html, to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the basis for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21, Protection of Safeguards Information: Performance Requirements.
In accordance with 10 CFR 19.11, Posting of notices to workers, you may be required to post this Notice within two working days of receipt.
Dated this 9th day of January 2024
Enclosure 2 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-284 License No.:
R-110 Report No.:
05000284/2023201 Licensee:
Idaho State University Facility:
Aerojet General Nucleonics-201M Research Reactor Facility Location:
Pocatello, Idaho Dates:
July 31 - August 3, 2023 Inspector:
Craig H. 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-201M Research Reactor Facility Inspection Report No. 05000284/2023201 The primary focus of this routine, announced inspection included onsite review of selected aspects of Idaho State Universitys (ISU, the licensees) 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) experiments; (7) design changes; (8) committees, audits and reviews; (9) maintenance logs and records; and, (10) 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 was in compliance with NRC requirements, with one exception noted below.
Organization and Staffing
The licensees organization and staffing remain in compliance with the requirement specified in the technical specifications (TSs).
Operations Logs and Records
Operational logs and records were consistent with applicable TS and procedural requirements and indicated that reactor operations were conducted in accordance with TSs and applicable procedure requirements.
Procedures
Facility procedural review, revision, control, and implementation satisfied TS requirements.
Requalification Training
The requirements in the reactor operator (RO) requalification program were completed with one exception.
- One violation of the NRC requirement to receive a biennial medical examination was noted for two SROs.
Surveillance and Limiting Conditions for Operation
The program for tracking and completing surveillance verifications and calibrations and for complying with LCOs was implemented in accordance with TS requirements.
Experiments
Experiments were completed in accordance with licensee procedures and the irradiated material produced was controlled in accordance with the radiation protection program.
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Design Changes
Various changes were initiated and/or completed at the facility during the past 2 years and were processed according to their change process in accordance with 10 CFR 50.59.
Committees, Audits and Reviews
Review and audit functions required by TS Section 6.4 were completed by the Reactor Safety Committee (RSC) or designated individuals.
- The composition of the RSC and the committee meeting frequency satisfied requirements stipulated in the TSs.
Maintenance Logs and Records
Maintenance was completed in accordance with TSs and procedural requirements.
Fuel Handling
The licensee performed limited fuel handling operations annually, in accordance with procedure.
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REPORT DETAILS Summary of Facility Status The ISU Aerojet General Nucleonics-201M (AGN-201M) Research Reactor Facility, licensed to operate at a maximum steady-state thermal power of 5 watts, continued to be operated in support of operator training, surveillance, experiments, and laboratory work. During the inspection, the NRC inspector observed the reactor being operated.
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, General Operating Rules, Revision (Rev.) 4
ISU AGN-201M Reactor Facility Master Log and Reactor Operations Log (ROL)
ROL-101 forms for July 2021 to the present
ISU reactor facility annual operating report for 2021, dated August 26, 2022, and the annual operating report for 2022, dated June 23, 2023 b.
Observations and Findings Through interviews with licensee personnel and document review the inspector noted that the organization had not changed since the last operations inspection in 2021.
However, the inspector noted that a new person was hired to become the Reactor Supervisor (RS) upon receiving an SRO license at the facility. The TSs require that the RS hold an SRO license. The Reactor Administrator (RA) will continue to act as the interim official RS until the new person is a licensed SRO at the facility. The inspector verified that the RA is a qualified licensed SRO at the facility. The inspector confirmed that staffing at the facility was acceptable to support the current workload and ongoing activities.
c.
Conclusion The inspector determined that the organization and staffing at the facility met the requirements specified in the TSs.
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2.
Operations Logs and Records a.
Inspection Scope (IP 69001, Section 02.02)
The inspector reviewed selected aspects of the following to ensure that the operations program was implemented as required in TS Sections 2.0, 3.0, and 6.0:
ISU AGN-201M Reactor Facility Master Log and ROL-101 forms for July 2021 to the present
ISU AGN-201M operations procedures including Operating Procedure-1 (OP-1)
AGN-201 Operating Procedure #1, Rev. 7 and OP-2, AGN-201 Operating Procedure #2, Rev. 7 b.
Observations and Findings The inspector verified that reactor operating characteristics, and other TSs and procedurally required entries were recorded on the appropriate forms and logs.
The inspector confirmed that individuals required by TSs were present during reactor operations. In addition, the inspector verified that reactor scrams were identified on the ROL-101 forms and in the log and were reported and resolved as required before the resumption of operations. The inspector observed a routine reactor startup and shutdown and noted that the reactor was operated in accordance with approved procedures.
c.
Conclusion The inspector determined that operational logs and records were consistent with applicable TS and procedural requirements and confirmed that reactor operations were conducted in accordance with TSs and applicable procedure requirements.
3.
Procedures a.
Inspection Scope (IP 69001, Section 02.03)
To ensure that the requirements of TS Section 6.6 was met, the inspector reviewed the following:
selected AGN-201M experiment plans/procedures, maintenance procedures (MPs), and surveillance procedures (SPs)
ISU Nuclear Engineering Laboratory Administrative Procedure, AP-ISU-NEL-001, [Title 10 of the Code of Federal Regulations] 10 CFR 50.59 Evaluations, Rev. 1
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b.
Observations and Findings The inspector confirmed that procedures were established for those activities outlined in TS Section 6.6 and were appropriate for current facility operations. The inspector verified that various existing procedures were revised, updated, and rewritten as needed/required. The inspector noted that the licensee submitted any new, updated, or revised procedures to the RSC for review and approval as required by TS.
c.
Conclusion The inspector determined that procedural review, revision, control, and implementation satisfied TS requirements.
4.
Requalification Training a.
Inspection Scope (IP 69001, Section 02.04)
To determine that operator requalification activities and training were conducted and that medical examinations were completed as required by the licensees operator requalification program, TS Section 6.3 and 10 CFR Part 55, Operators Licenses, the inspector reviewed:
medical examination records for selected operators
active license status for selected licensed operators
ISU AGN-201M Reactor Facility Master Log and ROL-101 forms for July 2021 to the present
documentation of training lectures, records of reactivity manipulations, console evaluations, and written examinations
Reactor Operator Requalification Program for the Idaho State University Reactor, Rev. 4 b.
Observations and Findings (1) Operators The inspector noted that there were four SROs and one RO licensed to operate the reactor at the facility. The inspector found there were two licensed SROs who were full-time university employees working at the facility while the other operators were part-time student operators. The RA and RS are full-time employees. The inspector confirmed that all active licensed operators were current with the requalification plan requirements.
(2) Biennial Medical Examination Section 55.53, Conditions of licenses, paragraph (i) of 10 CFR requires that the licensee [reactor operator] shall have a biennial medical examination.
Through discussions with the RS and a review of records, the inspector found that the biennial medical examination requirement of 10 CFR 55.53 was not met for two SROs.
Records reviewed by the inspector showed that one SROs previous medical
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examination was completed July 8, 2021, but that individual was not reminded to get another exam and no subsequent medical examination was completed by July 8, 2023, as required. Another SROs previous medical examination was completed July 19, 2021, but again, the individual was not reminded to get another exam and no subsequent medical examination was completed by July 19, 2023, as required. Those time frames exceed the biennial requirement. The inspector found that the licensee failed to track the status of the required medical examinations. The SROs each immediately had a medical examination to bring them into compliance with the regulations. The inspector also found that neither SRO operated the reactor during the period when they were not in compliance with the medical examination requirement. As stipulated in the Enforcement Manual, Part I, Section 2.3, these issues of the same problem of failure to have a biennial medical examination are cited as two examples of one violation. The licensee was informed that the failure of two SROs to receive a biennial medical examination was a violation (VIO) of 10 CFR 55.53(i) (VIO 05000284/2023201-01).
c.
Conclusion The inspector determined that the requirements stated in the Reactor Operator Requalification Program were completed except for two licensed operators who failed to receive a biennial medical examination as required by 10 CFR 55.33.
5.
Surveillance and Limiting Conditions for Operation a.
Inspection Scope (IP 69001, Section 02.05)
To determine that reactor surveillance activities and LCO checks, calibrations, and verifications were completed as required by TS Sections 3.0 and 4.0, the inspector reviewed:
selected ISU AGN-201M SPs for calibrations and LCO verifications
ISU AGN-201M Reactor Facility Master Log and ROL-101 forms for July 2021 to the present b.
Observations and Findings The inspector confirmed that selected daily, annual, biennial, and other periodic checks, tests, and/or calibrations for required surveillance and LCO activities and verifications were completed as stipulated in TSs. Surveillance and LCO verifications reviewed by the inspector were completed on schedule and in accordance with the applicable procedures. The inspector confirmed that all recorded results were within the TSs and procedurally prescribed parameters.
c.
Conclusion The inspector determined that the program for surveillance and LCO verifications was completed in accordance with the TS requirements in Sections 3.0 and 4.0 6.
Experiments
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a.
Inspection Scope (IP 69001, Section 02.06)
To ensure that the requirements of TS Section 6.7 were met, the inspector reviewed the following.
- various ISU AGN-201M ROL-101 forms
various approved experiment procedures (EPs) including EP-1 through EP-22
ISU AGN-201M Reactor, Isotope Production and Disposition Log and the associated Isotope Production and Disposition forms b.
Observations and Findings The inspector noted that 20 experiments were approved for use at the facility, however, only about 10 of those were routinely used. The inspector found that experiments were generally conducted for classwork and training. The inspector reviewed the EPs and no issues were identified.
The inspector noted that the operations log and forms were annotated to record which experiments were performed and to indicate that the irradiated material produced was controlled and maintained. A review of the isotope production and disposition forms by the inspector showed that irradiated material was not transferred to another license, but the material was analyzed and then placed in a storage vault at the facility as required by the radiation protection plan. The inspector confirmed that material was often re-irradiated for other experiments.
c.
Conclusion The inspector determined that experiments were completed in accordance with licensee procedures and the irradiated material produced was controlled in accordance with the radiation protection plan.
7.
Design Changes a.
Inspection Scope (IP 69001, Section 02.08)
In order to verify whether modifications to the facility, procedures, and experiments were consistent with 10 CFR 50.59 and TS Section 6.5, the inspector reviewed:
various 10 CFR 50.59 reviews and screenings
RSC meeting minutes for 2021 through the present
reviews and audits completed by the RSC or a designee for 2021 - 2023
The two most recent ISU AGN-201M reactor annual operating reports b.
Observations and Findings The inspector noted that various facility changes were made or initiated since the last inspection. A review of the modification proposals and the 10 CFR 50.59 screenings by the inspector indicated that none required an evaluation nor the submission of an
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amendment to the NRC for approval.
c.
Conclusion The inspector determined that various changes were initiated and/or completed at the facility during the past 2 years and were processed according to their process in accordance with 10 CFR 50.59.
8.
Committees, Audits and Reviews a.
Inspection Scope (IP 69001, Section 02.09)
In order to verify that the licensee conducted reviews and audits as required by TS Section 6.4, the inspector reviewed:
RSC meeting minutes for 2021 through the present
reviews and audits completed by the RSC or a designee for 2021 through 2023
The two most recent ISU AGN-201M reactor annual operating reports b.
Observations and Findings The inspector found the meeting minutes showed that the RSC met as required and reviewed the types of topics outlined by the TSs. Review of the committee meeting minutes by the inspector also indicated that the RSC provided guidance and direction for safe reactor operations and ensured suitable use and oversight of the reactor.
The inspector noted that the RSC, or individuals designated by the committee, completed audits of the facility operations, programs, and procedures. Since the last NRC inspection, audits were completed annually in those areas outlined in the TSs. The inspector also found that the security plan and the emergency plan were reviewed every 2 years as required by the TSs.
c.
Conclusion The inspector determined that the review, audit, and oversight functions required by TS Section 6.4 were completed by the RSC.
9.
Maintenance Logs and Records a.
Inspection Scope (IP 69001, Section 02.11)
To determine that reactor maintenance activities were completed as required by TS Sections 3.0 and 4.0, the inspector reviewed:
selected maintenance forms, data sheets, and records
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ISU AGN-201M MP-1, AGN-201 Rod Maintenance, and MP-2, Procedure To Open The AGN-201M Core Tank
ISU AGN-201M Reactor Facility Master Log and ROL-101 forms for July 2021 to the present b.
Observations and Findings The inspector confirmed that preventive maintenance activities were conducted as scheduled and emergent items were addressed and completed. The inspector noted that the Reactor Facility Master Log was now used as the primary maintenance log.
The inspector found that any problems noted were addressed in accordance with the applicable facility procedures or equipment manuals. The inspector noted that, in the past, many maintenance activities involved reactor electronics as documented in the Reactor Facility Master Log; these issues were investigated and resolved by the licensee.
c.
Conclusion The inspector determined that the maintenance program satisfied TS requirements.
10. Fuel Handling Logs and Records a.
Inspection Scope (IP 69001, Section 02.12)
The inspector reviewed the following to ensure that TS Sections 4.0 and 5.0 and procedural requirements were met:
AGN-201M fuel inventory sheets for 2022 and 2023
ISU AGN-201M MP-1, AGN-201M Rod Maintenance
ISU AGN-201M Reactor Facility Master Log and ROL-101 forms for July 2021 to the present.
b.
Observations and Findings The inspector confirmed that no reactor fuel inspection or movement was required or completed in the period since the last inspection. The inspector verified that the control and safety rods, which contain a small amount of fuel, were inspected every year in accordance with licensee procedure.
c.
Conclusion The inspector determined that the safety and control rods were inspected annually in accordance with licensee procedure.
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11. Follow-up On Previously Identified Items a.
Inspection Scope (IP 92701)
The inspector reviewed the licensees actions taken in response to a previously identified VIO - 05000284/2021201-01, and a letter from the licensee to the NRC regarding and abnormal occurrence that occurred April 17, 2023.
b.
Observation and Findings (1)05000284/2021201-01 - VIO - Failure of two operators to receive a biennial medical examination as required by 10 CFR 55.53(i).
During an inspection in 2021, the NRC identified a violation of 10 CFR 50.53(i) had occurred and issued VIO - 05000284/2021201-01 for the failure of two licensed operators to receive a biennial medical examination.
During this inspection, the inspector found that the same two licensed operators failed to receive biennial medical examinations as required by 10 CFR 55.53(i) and as noted in Section 4 of this report. As corrective actions in the 2021 instances, the operators each received a medical examination and the licensee held training for the operators. The licensee also indicated that they would update their Operator Requalification Plan to help operators be aware of the due dates for medical examinations. The inspector determined that the previous corrective actions to ensure that licensed operators receive a biennial medical examination were inadequate. Therefore, this issue remains open.
(2) Occurrence at ISU and subsequent notification of the NRC By letter dated May 24, 2023, the licensee notified the NRC of an occurrence at the facility. The report stated that on April 17, 2023, a slow drip of water from underneath the reactor tank inside the reactor skirt was discovered. After an investigation, the licensee determined that the drip was coming from between the lead shield and the steel reactor tank. The control rod drive mechanisms were removed to prevent damage from the leaking water. Following an extensive search for the location of the leak, the licensee could not find the exact source. As a result, a method was developed to divert the water away from the control rods for safe collection and monitoring. The licensee determined that the leak rate was insignificant in comparison to the water volume in the tank and there was no safety concern. A restart plan was developed and approved by the RSC and implemented. The NRC reviewed this issue and determined that it would be reviewed during the next facility inspection.
The inspector reviewed the event and the licensees corrective actions. As noted, the licensee developed and installed a device to divert the water away from the control rods.
The liquid is collected, monitored, and the leakage amount is tracked. A threshold drip rate was established which, if exceeded, would require further restrictive actions.
Calculations were performed to predict any effect of water-soaked graphite on reactivity and no problems were noted. Various long-term actions are being considered to correct the problem including obtaining a replacement water tank from the University of Utah or replacing the water in the shield tank with polyethylene pellets that have shielding properties similar to water. Because a long-term solution was not implemented to date and no immediate safety issue exists, the licensee was informed that this issue will be
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identified as a follow-up item and will be reviewed during a future inspection (IFI 05000284/2023201-01).
c.
Conclusion The inspector determined that the issue of ensuring that ROs receive a medical examination every 2 years was not properly addressed and the reactor shield tank leak was minimal but ongoing.
12. Exit Meeting Summary The inspection scope and results were summarized on August 3, 2023, with licensee representatives. The inspector discussed the findings for each area reviewed. The licensee acknowledged the results of the inspection and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee M. Dunzik-Gougar Reactor Administrator L. Foulkrod Administrative Reactor Operator J. Scott Reactor Supervisor Other Personnel M. Blair Vice President for Research, Idaho State University K. Bunde Professional Engineer and Chairman of the Reactor Safety Committee M. Jaussi Campus Radiation Safety Officer, Idaho State University C. Pope Chair, Department of Nuclear Engineering and Radiation Safety, Idaho State University INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors IP 92701 Follow-up on Previously Identified Issues ITEMS OPENED, CLOSED, AND DISCUSSED Opened:
05000284/2023201-01 VIO - Failure of two operators to receive a medical examination every 2 years as required by 10 CFR 55.53(i).05000284/2023201-02 IFI - Follow-up the issue of finding and implementing a permanent solution to the shield tank water leak.
Discussed:
05000284/2021201-01 VIO - Failure of two operators to receive a medical examination every 2 years as required by 10 CFR 55.53(i).
Closed:
None