IR 05000407/2024201
| ML25157A128 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 06/10/2025 |
| From: | Tony Brown NRC/NRR/DANU/UNPO |
| To: | Allison A Univ of Utah |
| References | |
| IR 2024201 | |
| Download: ML25157A128 (1) | |
Text
SUBJECT:
UNIVERSITY OF UTAH - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 05000407/2024201 (REVISED)
Dear Mr. Allison:
From July 8-11, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at your University of Utah TRIGA Nuclear Reactor Facility. On July 11, 2024, the inspection results were discussed with Dr. Glenn Sjoden, Director, Utah Nuclear Engineering Program, Dr. Tong Qiu, Chair, Department of Civil & Environmental Engineering, and Edward Goodell, Senior Reactor Operator. The results of the inspection were discussed further on September 4, 2024. The results of this inspection were originally documented in NRC Inspection Report No. 05000407/2024201, issued January 21, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24261B239). On February 18, 2025, you provided a response (ML25050A611) in which you contested that the violation should be withdrawn. Consequently, the NRC conducted a review of your response and determined that the violation should be rescinded (ML25154A356). Accordingly, the enclosed inspection report is being re-issued to reflect the removal of the violation (VIO)05000407/2024201-01.
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. The original inspection report documented one Severity Level IV violation of NRC requirements. In accordance with the result of the contested violation review referenced above, the Severity Level IV violation is being rescinded. The revised inspection report is enclosed with no findings of significance identified.
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 ADAMS. ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
June 10, 2025 Should you have any questions concerning this inspection, please contact Craig Bassett at (240) 535-1842, or via email at Craig.Bassett@nrc.gov.
Sincerely, Tony Brown, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-407 License No. R-126 Enclosure:
As stated cc: GovDelivery Subscribers Signed by Brown, Tony on 06/10/25
ML25157A128 NRC-002 OFFICE NRR/DANU/UNPO/RI NRR/DANU/UNPO/RI NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME CBassett JBraisted NParker TBrown DATE 6/6/2025 6/6/2025 6/9/202 6/10/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-407 License No.:
R-126 Report No.:
05000407/2024201 Licensee:
University of Utah Facility:
University of Utah TRIGA Reactor Location:
Salt Lake City, Utah Dates:
July 8-11, 2024 Inspector:
Craig Bassett Accompanied by:
Jonathan Braisted, RTR Inspector Trainee Approved by:
Tony Brown, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
- 2 -
EXECUTIVE SUMMARY University of Utah University of Utah TRIGA Nuclear Reactor Facility Inspection Report No. 05000407/2024201 The primary focus of this routine announced inspection was the onsite review of selected aspects of the University of Utah (the licensees) 100-kilowatt 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. 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 the NRCs requirements.
Organization and Staffing
The licensees organizational structure complied with requirements outlined in the technical specifications (TSs).
Procedures
The facility procedural review, revision, control, and implementation satisfied the TS requirements.
Health Physics
- The radiation safety program was conducted in compliance with Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Standards for Protection against Radiation, requirements, TSs, and licensee procedures.
Design Changes
Changes made at the facility during the past 2 years were completed in accordance with 10 CFR 50.59, Changes, tests and experiments, and applicable licensee procedures.
Committees, Audits and Reviews
The Reactor Safety Committee (RSC) met and conducted audits and reviews in accordance with the requirements specified in TS section 6.2.
Emergency Planning
The emergency preparedness program was conducted in accordance with the Emergency Plan (E-Plan) and implementing procedures.
Transportation Activities
The licensee transferred radioactive waste material to the campus Radiation Safety (Rad Safety) Office for disposal as needed and the Rad Safety Office handled any shipments of radioactive material from the facility.
- 3 -
REPORT DETAILS Summary of the Facility Status The University of Utah continued to operate the 100-kilowatt Training, Research, Isotope, General Atomics (TRIGA) Mark I research reactor (UUTR) as needed for sample irradiation, reactor operator training, educational demonstrations, preventive maintenance, and operational surveillance testing required by the TSs. During this inspection, the reactor was not operated due to planned maintenance to repair a reactor tank leak.
1.
Organization and Staffing a.
Inspection Scope (Inspection Procedure (IP) 69001, Section 02.01)
The inspectors reviewed the following regarding the licensees organization and staffing to ensure that the requirements of TS section 6.1, were met:
current facility TSs
qualifications and responsibilities of the facility personnel
UUTR Annual Operating Reports for the periods of July 1, 2021, through June 30, 2022, and July 1, 2022, through June 30, 2023, submitted to the NRC on July 29, 2022, and June 30, 2023, respectively
American National Standards Institute/American Nuclear Society (ANSI/ANS)-15.4-2007, Selection and Training of Personnel for Research Reactors b.
Observations and Findings Through discussions with licensee representatives, the inspectors confirmed that there were no changes to management responsibilities or the organizational structure since the last NRC inspection of this area conducted in July 2022 (NRC Inspection Report No. 50-407/2022-201). The inspectors noted that the previous Director for the Utah Nuclear Engineering Program (designated by the licensee as the reactor administration Level 2) took another position at the university since the last inspection and another individual was assigned as the Facility Director. The inspectors noted that the licensee notified the NRC staff of this change as required by the TS via letter dated October 6, 2023 (ML23313A09), and that the person met the requirements of ANSI/ANS-15.4-2007.
c.
Conclusion The inspectors determined that the organizational structure was consistent with the TS requirements.
2.
Procedures a.
Inspection Scope (IP 69001, Section 02.03)
The inspectors reviewed the selected aspects of the following to verify that the licensee complied with the requirements of TS section 6.4:
records and logs of procedure changes and implementation
- 4 -
various administrative and radiation protection procedures
RSC meeting minutes from March 2022 to the present b.
Observations and Findings The inspectors noted that the licensee conducted operations in accordance with approved procedures and the procedures were available for tasks and items required by the TSs. The inspectors confirmed that substantive changes to the procedures were reviewed and approved by the RSC. The inspectors found that reactor personnel also made use of the procedures maintained by the Rad Safety Office which were contained in the Radiological Procedures and Records [RPR]
manual. Those procedures were reviewed and approved by the Rad Safety Committee.
c.
Conclusion The inspectors determined that the procedural review, revision, control, and implementation has satisfied TS requirements.
3.
Health Physics a.
Inspection Scope (IP 69001, Section 02.07)
To verify compliance with TS sections 3.4, 3.7, 4.3, 4.7, 5.4, 6.3, and 6.7, as well as 10 CFR Part 19, Notices, Instructions and Reports to Workers: Inspection and Investigations, and 10 CFR Part 20 requirements, the inspectors reviewed the following selected aspects of:
radiological signs and postings in various areas of the facility
RSC meeting minutes from March 2022 to the present
various facility and Rad Safety Office RPR procedures and forms
personnel dosimetry records for 2022, 2023, and to date in 2024
environmental dosimetry records for 2022, 2023, and to date in 2024
selected radiation and contamination surveys conducted by licensee and Rad Safety Office personnel for the past 2 years
Assessment of Radiation Dose from Air Emissions of Radioactive Material, Calendar Year 2023, which was completed by Rad Safety Office personnel
UUTR annual operating reports for the last two reporting periods
calibration records b.
Observations and Findings (1)
Surveys, Postings and Notices The inspectors noted that the results of radiation and contamination surveys were documented, reviewed, and evaluated, as required by facility procedures, and corrective actions were taken when radiation readings or contamination results exceeded set action levels.
During tours of the facility, the inspectors confirmed that the caution signs, postings, and controls established for the controlled areas were in
- 5 -
place as required by 10 CFR Part 20, Subpart J, Precautionary Procedures. The inspectors also found that copies of NRC Form 3, Notice to Employees, were posted at the facility as required by 10 CFR 19.11 and were the current version.
(2)
Dosimetry and Radiation Monitoring Equipment Use and Calibration The inspectors verified that the licensee used thermoluminescent dosimeters (TLDs) for whole body radiation monitoring and finger ring TLDs for monitoring radiation exposure of the extremities. The inspectors confirmed that individual dosimetry results for the past 2 years since the last inspection of this area showed all occupational doses were within regulatory limits.
The inspectors confirmed that calibration frequencies met the requirements established in the TSs. The inspectors noted that the monitoring equipment was used in accordance with the procedural guidelines.
(3)
Radiation Protection Program and ALARA Policy The inspectors confirmed that the licensees Radiation Protection Program and the as low as is reasonably achievable (ALARA) Policy were established through various University of Utah campus documents including: (1) the Rad Safety Office RPRs, (2) The University of Utah Radiation Safety Policy Manual; and, (3) The University of Utah Radiation Protection Program. The inspectors also confirmed that the Radiation Protection Program was reviewed annually. The inspectors found that the ALARA Policy provided guidance for keeping doses as low as possible and was consistent with the requirements in 10 CFR Part 20.
(4)
Radiation Worker Training The inspectors noted that all university personnel who worked in radiation areas or handled radioactive material, including licensee staff, were required to receive training in radiation protection. The inspectors confirmed that the reactor staff members completed the required training and were then issued a dosimeter. The inspectors noted that the personnel training program satisfied requirements in 10 CFR 19.12, Instruction to workers, and that the content and periodicity of the training were in accordance with the regulations.
(5)
Environmental and Effluent Monitoring The inspectors confirmed that gaseous releases continued to be monitored as required. The inspectors noted that the doses resulting from the releases were calculated by the Rad Safety Office according to established procedures, using the Environmental Protection Agency COMPLY code. The dose rate to the public was well below the dose constraint of 10 millirem per year specified in 10 CFR 20.1101, Radiation protection programs, paragraph (d). The inspectors found that the concentrations of airborne gaseous releases were also calculated by the
- 6 -
Rad Safety Office. The inspectors confirmed that the concentrations of gaseous releases were well within those stipulated in 10 CFR Part 20, Appendix B, Table 2, and TS limits. The results were documented in the facility annual reports, as required by the TSs.
The inspectors found that there were no liquid releases from the facility to the sanitary sewer within the past 2 years since the last inspection of this area and no solid waste was transferred from the facility to the campus Rad Safety Office during that period.
The inspectors confirmed that onsite and off-site gamma radiation monitoring was completed using environmental TLDs in accordance with university procedures. The inspectors found that the data indicated no measurable doses above any regulatory limits in the areas surrounding the UUTR facility. These results were also reported in the facilitys annual reports.
c.
Conclusion The inspectors determined that the Radiation Protection Program, as implemented by the licensee, satisfied the regulatory requirements.
4.
Design Changes a.
Inspection Scope (IP 69001, Section 02.08)
The inspectors reviewed the following to verify compliance with 10 CFR 50.59 and TS section 6.2:
RSC meeting minutes from March 2022 to the present
Utah Nuclear Engineering Program (UNEP) Job-Aid 002 R1, 10 CFR 50.59 Screening
UNEP Job-Aid 003 R1, 10 CFR 50.59 Evaluation
UNEP Procedure AP-001 R1, Guidelines for 10 CFR 50.59 Evaluations
various forms designated as form UNEP-022 R4, Maintenance Log which were used in conjunction with the design change process
UUTR Annual Operating Reports for the last two reporting periods b.
Observations and Findings The inspectors noted that various 10 CFR 50.59 reviews were conducted since the last inspection. The inspectors found that the design changes were reviewed and approved as required by 10 CFR 50.59. The inspectors also found that the performance of modified equipment and the procedures related to that equipment met regulatory, TS, and procedural requirements.
c.
Conclusion The inspectors concluded that changes made at the facility during the past 2 years were completed in accordance with 10 CFR 50.59 and applicable licensee procedures.
- 7 -
5.
Committees, Audits and Reviews a.
Inspection Scope (IP 69001, Section 02.09)
The inspectors reviewed the following to ensure that the review and audit requirements in TS section 6.2 were met:
RSC meeting minutes from March 2022 to the present
radiation safety and ALARA reviews and audits completed during the past 2 years and licensee responses to the reviews and audits
UUTR annual operating reports for the last two reporting periods b.
Observations and Findings The inspectors found that the RSC met at least annually as required by the TSs.
The inspectors confirmed that all required audits of reactor facility activities and reviews of programs, procedures, equipment, and proposed tests or experiments were completed and documented. The inspectors noted that the audits and the associated findings were detailed, and the licensee responded and took corrective actions when needed. Additionally, the annual reviews of the Radiation Protection Program and the E-Plan were conducted and documented.
c.
Conclusion The inspectors determined that the RSC met at the required frequency and that audits and reviews were conducted as required and in accordance TS section 6.2.
6.
Emergency Planning a.
Inspection Scope (IP 69001, Section 02.10)
To verify that the licensee complied with the University of Utah, Utah Nuclear Engineering Program (UNEP) Emergency Plan for NRC License R-126: TRIGA Nuclear Reactor, Revision 8, dated July 20, 2011, the inspectors reviewed the following selected aspects of:
selected emergency (implementing) procedures
emergency response supplies, equipment, and instrumentation
documentation of emergency drills and critiques for calendar years 2022, 2023, and 2024
UNEP Annual Emergency Training Attendance Record forms and related records for staff and support personnel for calendar years 2022 and 2023
various UNEP forms including UNEP-015R4, Emergency Kit Check; UNEP-021R28, UNEP Emergency Call List; and, UNEP-037, Radiological Emergency Classification Checklist
letter of agreement with Gold Cross Services, Inc., dated October 22, 2021, for ambulance transport
- 8 -
b.
Observations and Findings The inspectors noted that the RSC audited the E-Plan annually, and the last audit was completed on September 28, 2023. Implementing procedures were reviewed and revised as needed.
The inspectors found that semiannual inventories of the various first aid kits and other equipment were conducted and that the supplies, instrumentation, and equipment were maintained as required in the E-Plan. The inspectors confirmed that training for the reactor staff and the off-site support personnel was conducted and documented. The inspectors also noted that the UNEP Emergency Call List was up to date with the current revision dated February 12, 2024.
The inspectors confirmed that emergency drills were conducted annually, and critiques were held following each drill documenting strengths and areas for improvement. The inspectors found drills to be challenging and the critiques appropriate. The inspectors also reviewed the agreement between the licensee and a local company to provide transportation services for a person or persons injured at the facility and verified that it was maintained. The inspectors also noted that communications capabilities with the various support groups were in place and were tested periodically.
c.
Conclusion The inspectors determined that the emergency preparedness program was implemented as required by the E-Plan.
7.
Transportation Activities a.
Inspection Scope (IP 86740)
The inspectors reviewed selected aspects of:
RPR Procedures including No. 13, Radioisotope Acquisition and Disposition; No. 14, Shipment of Limited Quantity of Radioisotopes; and No. 55, Transportation of Radioactive Materials
various forms including form RPR 13A, Radioisotope Package Arrival Report; form RPR 13B, Radioisotope Receipt and Verification; and, form RPR 13C, Radioisotope Disposition Record b.
Observations and Findings The inspectors noted that the shipping records indicated that UUTR radioactive waste designated for disposal was transferred from the reactor facility to the University of Utahs broad scope license, Utah Department of Environmental Quality, License No. 1800001, in accordance with Rad Safety Office requirements.
The inspectors found that this shipping process was followed.
The inspectors noted that none of the licensee personnel has the current training required to ship radioactive material as required by the Department of Transportation. Therefore, in any instance involving the shipment of radioactive material, the paperwork and shipments would be completed by qualified Rad Safety Office personnel.
- 9 -
c.
Conclusion The inspectors determined that the licensee transferred radioactive waste material to the campus Rad Safety Office as needed and the Rad Safety Office handled any shipments of radioactive material from the facility.
8.
Follow-up on Previous Items a.
Inspection Scope (IP 92702)
The inspectors reviewed the following licensees actions taken in response to previously identified items.
b.
Observation and Findings (1)
Inspector Follow-up Item (IFI) 50-407/2019-202-01 - (Open) - Follow-up on the licensees actions to complete the revision of the E-Plan and have it reviewed and approved by the RSC.
10 CFR 50.34, Contents of Applications, Technical Information, requires in Section (b)(6)(v) that each application for an operating license shall include a final safety analysis report. The final safety analysis shall include plans for coping with emergencies.
The University of Utah, Utah Nuclear Engineering Program (UNEP)
Emergency Plan, dated June 2011, requires in Section 10.4, Emergency Plan Review and Update, requires that the RS (Reactor Supervisor)
shall periodically revise and update the Emergency Plan and the RSC (Reactor Safety Committee) shall review and approve the overall UNEP Emergency Plan to ensure that the Plan is adequate and current, and shall specifically review and approve any revisions to the Emergency Plan that affect implementation procedures.
In August 2019, an inspector noted that the RSC did not complete a biennial review of the E-Plan. This was because a revision of the E-Plan to incorporate suggested changes was not finished. The licensee indicated that the revision was in progress and would be ready for review by the December meeting of the RSC. The licensee was informed that the revision of the E-Plan, and review and approval by the RSC, would be designated as an IFI. During subsequent inspections it was noted that the E-Plan was still being revised and, because of the ongoing revisions, the RSC had not reviewed the plan.
During this inspection, the inspectors reviewed the issue and found that the E-Plan was revised various times since 2019 and a review by the RSC was still pending. Because there have been numerous changes in the Facility Director and Reactor Supervisor positions since the issue was first noted, the licensee has not followed this issue properly and no review by the RSC has occurred as required. This issue is noted as a violation of an administrative requirement in the Emergency Plan and does not adversely affect the public health and safety. This failure to comply with the University of Utah Emergency Plan, Section 10.4 constitutes a minor violation that is not subject to enforcement action in accordance with the
- 10 -
NRC Enforcement Policy. However, this issue remains open.
(2)
IFI 05000407/2021201-02 - (Open) - Follow-up on the licensees actions to revise procedure UNEP-002R4, Biennial Fuel/Tank/Control Rod/Reflector Element Inspection, to include maintenance actions needed during control rod inspection.
In 2021, the inspector reviewed the circumstances surrounding a Special Report issued by the licensee, dated April 2, 2020, documenting a component malfunction.
On March 30, 2020, facility personnel completed the routine monthly inspection of various reactor components and systems and initiated a standard reactor startup and termination checklist to test all systems. The licensee staff noted that the safety rod did not drop as expected.
Troubleshooting showed that the safety rod was not responding as required and the Reactor Supervisor (RS) terminated the operation. The safety rod was disassembled, and rust and calcium deposits were noted and subsequently removed. Following these corrective actions, the safety rod was inspected, reassembled, and reinstalled in the core. Testing and calibration of the safety rod indicated that the malfunction was resolved, and the rod functioned properly.
The licensee submitted a letter to the NRC concerning the component malfunction in which the licensee indicated that the procedure involving the inspection of the control rods, UNEP-002R4, Biennial Fuel/Tank/
Control Rod/Reflector Element Inspection, would be revised to include checking for debris, binding, rubbing, or misalignment of the control rod drives that might prevent the control rods from dropping. The licensee was informed that the issue would be considered an IFI. During an inspection in July 2023, this issue was reviewed, and the inspector found that no action was taken on the procedure to that point.
During this inspection, the inspectors found that, since the inspection in 2020, changes occurred in the RS position at the facility and operators who were aware of the situation. Consequently, the current RS and operators have not completed the revision to the procedure. This issue remains open.
(3)
IFI 05000407/2023201-02 - (Open) - Follow-up on the reactor tank repair and the complete stoppage of tank water loss due to leakage.
The inspector reviewed the circumstances surrounding the notification made by the licensee on March 31, 2023, to the NRC regarding a reactor pool leak at the UUTR. The UUTR staff personnel noted the reactor tank developed a leak of approximately 24 gallons per day (gals/day). The licensee noted that there was no indication of leakage to the environment and the leakage did not reach or exceed any reporting criteria. However, a few days later the licensee noted that the leak rate increased to about 50 gallons a day. Water samples taken when the leak rate increased continued to show there were no activity levels that reached any reporting criteria or above any regulatory limit.
- 11 -
The licensee determined the most probable leak site would be a degraded weld presumably toward the bottom of the circumference of the tank (the point of highest pressure). To resolve the leak problem, the licensee hired a contractor to apply two-part epoxy sealant material to the weld areas around the bottom three sections of the tank. During an inspection in July 2023, the inspector observed the repair work on the tank. At the completion of the inspection, the inspector noted that leak appeared to have stopped but that the success of the repair project would need to be evaluated further during a future inspection. The licensee was informed that the issue of the reactor tank repair and the complete stoppage of tank water loss due to leakage would be considered an IFI.
During this inspection the inspectors noted that the original problem with a leak at a weld seam was resolved. However, following approximately one month, a new leak developed, and the licensee is currently taking action to repair the reactor tank a second time. This will involve removing the reactor fuel from the tank and draining the tank so that an epoxy coating can be applied to the entire interior surface of the tank. As a result, this IFI will remain open.
(4)
URI 05000407/2023201-03 - (Closed) - Follow-up on the possible impact the tank leak may have had on the facility and/or the surrounding.
environment and any potential violations that may have occurred as a result.
As a result of the tank leak mentioned above, the NRC determined that an Unresolved Item (URI) was warranted to follow up on the possible impact the tank leak may have had on the facility and/or the surrounding environment and any potential violations that may have occurred as a result (URI 05000407/2023201-03).
During this inspection the inspectors discussed the reactor tank leak with personnel from the Rad Safety Office and reviewed the extensive documentation of sampling that they conducted following the initial reactor tank leak. The inspectors noted that Rad Safety personnel sampled numerous locations around the reactor facility and down-stream from the reactor. None of the samples indicated radioisotopes in concentrations that would be reportable to the NRC. Also, the sampling showed that the concentration of tritium in the water in the area was below the levels considered safe for drinking by the Environmental Protection Agency (EPA). The sampling is continuing. The Rad Safety Office is also coordinating their efforts with the State of Utah EPA and keeping that office informed of all their findings. Based upon the findings during this inspection discussed above, this issue is closed.
c.
Conclusion The inspectors determined that one URI was closed and three IFIs remain open.
9.
Exit Meeting Summary The inspection scope and results were summarized on July 11, 2024, with university management and facility staff. The inspectors discussed the findings for each area
- 12 -
reviewed. The licensee did not identify any of the material provided to or reviewed by the inspectors as proprietary. The inspectors presented the re-exit meeting inspection results through a video conference call on September 4, 2024, to Mr. Andrew Allison.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel Reactor Supervisor and Interim Facility Director T. Goodell Senior Reactor Operator G. Sjoden Director, Utah Nuclear Engineering Program Other Personnel M. Beitollahi Health Physicist and Adjunct Associate Professor, Radiation Safety Office, Environmental Health and Safety Department, University of Utah J. Cunningham Specialist, Hazardous Materials Team, Station No. 14, Salt Lake City Fire Department F. Monette Radiation Safety Officer and Director of Environmental Health and Safety Department, University of Utah C. Olson Health Physicist, Radiation Safety Office, Environmental Health and Safety Department, University of Utah T. Qiu Chair, Department of Civil & Environmental Engineering, University of Utah INSPECTION PROCEDURE (IP) USED IP 69001:
Class II Non-Power Reactors IP 86740:
Inspection of Transportation Activities IP 92702 Follow-up on Previously Identified Items ITEMS OPENED, CLOSED, AND DISCUSSED Opened Closed 05000407/2023201-03 URI Follow-up on the possible impact the tank leak may have had on the facility and/or the surrounding environment.
Discussed 50-407/2019-202-01 IFI Follow-up on the licensees actions to complete the revision of the Emergency Plan and have it reviewed and approved by the RSC.05000407/2021201-02 IFI Follow-up on the licensees actions to revise procedure UNEP-002R4, Biennial Fuel/Tank/Control Rod/Reflector Element Inspection, to include maintenance actions needed during control rod inspection.05000407/2023201-02 IFI Follow-up on the reactor tank repair and the complete stoppage of tank water loss due to leakage.