ML25014A182
| ML25014A182 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 01/29/2025 |
| From: | Tony Brown NRC/NRR/DANU/UNPO |
| To: | Joel Jenkins Texas A&M Univ |
| References | |
| IR 2024201 | |
| Download: ML25014A182 (1) | |
Text
Mr. Jere Jenkins, Director Texas Engineering Experiment Station Texas A&M University System Nuclear Science Center 1095 Nuclear Science Road, MS 3575 College Station, TX 77843
SUBJECT:
TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000128/2024201 AND NOTICE OF VIOLATION
Dear Mr. Jenkins:
From December 16-20, 2024, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center. The results of this inspection are documented in the enclosed report.
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, the NRC has determined that one Severity Level IV violation of NRC requirements has 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 enclosed inspection report. The violation is 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 review of your response to the Notice will also determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
January 29, 2025
During this inspection, the NRC has determined that another Severity Level IV violation of NRC requirements occurred. This violation is being treated as a non-cited violation (NCV), consistent with section 2.3.2.a of the Enforcement Policy. The NCV is described in the subject inspection report. If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001, with copies to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public inspections, exemptions, requests for withholding, a copy of this letter, its enclosures, 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). 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.
If you have any questions concerning this inspection, please contact Juan Arellano at 301-415-0477, or by email at Juan.Arellano@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. 50-128 License No. R-83
Enclosures:
As stated cc w/enclosures: GovDelivery Subscribers Signed by Brown, Tony on 01/29/25
ML25014A182 NRC-002 OFFICE NRR/DANU/UNPO NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME JArellano NParker TBrown DATE 01/15/2025 01/15/2025 01/20/2025 NOTICE OF VIOLATION Texas Engineering Experiment Station Docket No. 50-128 Texas A&M University System License No. R-83 During a U.S. Nuclear Regulatory Commission (NRC) inspection conducted December 16-20, 2024, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
Texas Engineering Experiment Station (TEES) Texas A&M University System (TAMU) Facility Operating License No. R-83, Amendment No. 19, dated July 22, 2021, section 2.C.2.,
Technical Specifications, states that, The Technical Specifications contained in Appendix A, as revised by license Amendment No. 19, are hereby incorporated in their entirety in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
Technical specification (TS) 6.2.4, RSB Audit Function, states, in part, The audit function shall include selective (but comprehensive) examination of operating records, logs, and other documents. Audits shall include but are not limited to the following:.
TS 6.2.4(1.) states, Facility operations, including radiation protection, for conformance to the Technical Specifications, applicable license conditions, and standard operating procedures: at least once per calendar year (interval between audits not to exceed 15 months). TS 6.2.4(2.)
states, The results of action taken to correct those deficiencies that may occur in the reactor facility equipment systems, structures, or methods of operations that affect reactor safety: at least once per calendar year (interval between audits not to exceed 15 months). TS 6.2.4(5.)
states, The reactor facility security plan and implementing procedures: at least once every other calendar year (interval between audits not to exceed 30 months).
Contrary to TS 6.2.4(1.) and TS 6.2.4(2.), the inspectors identified that the licensee failed to perform an audit to include facility operations and an audit to include the results of action taken to correct those deficiencies that may occur in the reactor facility equipment systems, structures, or methods of operations that affect reactor safety at least once per calendar year. Specifically, the licensee performed an audit, that included TS 6.2.4(1.) and TS 6.2.4(2.), on August 28, 2022, and performed the subsequent audit on April 2, 2024, which exceeded the allowable 15-month frequency.
Contrary to TS 6.2.4(5.), the inspectors identified that the licensee failed to perform an audit to include the reactor facility security plan and implementing procedures at least once every other calendar year. Specifically, the licensee performed an audit, that included TS 6.2.4(5.), on June 28, 2022, and had not performed a subsequent audit, which exceeded the 30-month requirement.
TS 6.2.5, Audit of ALARA Program, states, in part, The Chair of the RSB or designated alternate (excluding anyone whose normal job function is within the NSC) shall conduct an audit of the reactor facility ALARA program annually.
Contrary to TS 6.2.5, the inspectors identified that the licensee failed to conduct an audit of the reactor facility as low as is reasonably achievable (ALARA) program annually. Specifically, the licensee performed an audit, that included TS 6.2.5, on June 28, 2022, and performed the subsequent audit on April 3, 2024, which exceeded the annual requirement.
In accordance with the NRC Enforcement Manual, multiple examples of the same violation during the period covered by an inspection should be included as one citation. This issue involves four examples of the same non-compliance and has been determined to be a Severity Level IV violation (NRC Enforcement Policy section 6.4).
Pursuant to the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 2.201, Notice of violation, TEES/TAMU System 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.
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 https://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 bases 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, Public inspections, exemptions, requests for withholding, paragraph (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 29th day of January 2025.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-128 License No.:
R-83 Report No.:
05000128/2024201 Licensee:
Texas Engineering Experiment Station/Texas A&M University System Facility:
Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center Location:
College Station, Texas Dates:
December 16 - 20, 2024 Inspectors:
Juan A. Arellano Andrew Waugh Jonathan Braisted 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
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an inspection at the Texas Engineering Experiment (TEES) Texas A&M University (TAMU) System, in accordance with the research and test reactor inspection program. This is the NRCs program for overseeing the safe operation of licensed research and test reactors. Refer to https://www.nrc.gov/reactors/non-power.html for more information.
List of Violations Failure to conduct audits as required by the technical specifications (TSs)
Severity Report Section Severity Level IV NOV 2024201-01 Open 69001.09 The inspectors identified a Severity Level IV notice of violation of TS 6.2.4(1.), TS 6.2.4(2.),
TS 6.2.4(5.), and TS 6.2.5 for the licensees failure to perform audits within the required frequency.
Non-Cited Violation (NCV 05000128/2024201-02) 69001.07 The inspectors identified a Severity Level IV violation of TS 6.7.1 for the licensees failure to submit an annual operating report within the required frequency. This violation of very low safety significance was identified by the licensee and has been corrected and is treated as a non-cited violation, consistent with section 2.3.2(b) of the NRC Enforcement Policy.
Additional Tracking Items None.
REPORT DETAILS Facility Status The TEES/TAMU System Nuclear Science Center research reactor was operated in support of training, experiments, and maintenance since the last routine inspection. During this inspection, the reactor was operated for maintenance.
Inspection Scopes Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at https://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
Inspections were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2545, Research and Test Reactor Inspection Program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
69001 - Class II Non-Power Reactors This inspection included a review of selected aspects of the research and test reactor since the last inspection, to verify activities were conducted safely and in accordance with regulatory requirements and licensee commitments.
Organization and Staffing (IP Section 02.01)
This inspection included a review of the licensees organizational changes and shift staffing records to verify compliance with TS requirements and licensee commitments. Specifically, the inspection included a review of the following:
observation of daily control room briefings current staff qualifications staffing requirements for safe operation of the facility reactor logbooks organizational structure for the facility reactor safety board (RSB) meeting minutes, dated 2022-present Procedures (IP Section 02.03)
This inspection included a review of selected licensee procedures to verify: that the administrative controls were in accordance with the TSs, license requirements, and licensee commitments; the procedures in use were current and reviewed and approved, as required by the TSs; procedures could be implemented as intended; and reactor personnel were observing administrative controls and TS requirements relative to procedural adherence. Specifically, the inspection included a review of the following:
select facility procedures observation of a prestart up checklist observation of a reactor startup observation of a reactor shutdown observation of a calibration on the facility air monitors observation of an irradiated experiment removed from the core RSB meeting minutes, dated 2022-present Health Physics (IP Section 02.07)
This inspection included a review of the licensees health physics program to verify that the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 19, Notices, Instructions and Reports to Workers: Inspection and Investigations, and Part 20, Standards for Protection against Radiation, the TSs, and the licensees procedural requirements were met.
The inspection reviewed: licensees dose limits; required radiation surveys, sampling, and monitoring; calibration of radiological instruments; the personnel dosimetry program; effluent releases; posting requirements; training requirements; the implementation of as low as is reasonably achievable (ALARA) principles; and the radiation protection programs review and approval requirements. Specifically, the inspection included a review of the following:
observation of radiation surveys observation of an emergency drill performed inspectors performed radiation surveys observation of selected postings and verified with surveys that they were posted correctly select personnel and environmental dosimetry records, dated 2022-present select ALARA reviews, dated 2022-present select pool water samples, dated 2022-present select liquid and gaseous effluent data, dated 2022-present select calibration records for radiation instrumentation, dated 2022-present select radiation work permits, dated 2024-present select radiation training records, dated 2023-present Design Changes (IP Section 02.08)
This inspection included a review of design changes to determine whether they were reviewed, approved, and implemented in accordance with 10 CFR 50.59, Changes, tests and experiments, the TSs, and the licensees administrative procedures. The inspection also verified that modified equipment would continue to meet regulatory and procedural requirements and licensee commitments. Specifically, the inspection included a review of the following:
10 CFR 50.59 evaluations, dated 2023-present 10 CFR 50.59 screenings, dated 2023-present RSB meeting minutes, dated 2022-present 2023 annual operating report Committees, Audits and Reviews (IP Section 02.09)
This inspection included a review of the licensees committees, audits, and reviews to verify the RSB and independent audits were conducted in accordance with the TSs. The inspection verified issues identified from reviews were resolved in accordance with the TSs requirements and the licensees procedures. Specifically, the inspection included a review of the following:
RSB meeting minutes, dated 2022-present audits required to be performed by TS 6.2.4 event notification 57174 follow up 86740 - Inspection of Transportation Activities This inspection included a review of the licensees transportation activities to verify they have established and are maintaining an effective management-controlled program, to ensure radiological and nuclear safety in the receipt, packaging, and delivery of licensed radioactive materials. Specifically, the inspection included a review of the following:
select transportation procedures select bill of lading documents dated from 2023-present select radioactive shipping label checklist performed from 2023-present select NESC repackaging shipment information performed from 2023-present Inspection Results Minor Violation (VIO 05000128/2024201-03) 69001.01 Minor Violation: On June 14, 2024, the licensee reported event notification57174 to the Headquarters Operation Center for a fuel pin that did not pass the test criteria specified in TS 3.1.5, Reactor Fuel Parameters, during fuel inspection. The licensee responded as required by the TSs to identify a degraded fuel pin and inspected the entire core. While reviewing EN 57174, the inspectors identified a violation of TS 6.7.2, Special Reports. TS 6.7.2 states, in part, There shall be a report not later than the following working day by telephone and confirmed in writing by fax or similar conveyance to the NRC Headquarters Operations Center, and followed by a written report that describes the circumstances of the event and sent within 14 days to the U.S. Nuclear Regulatory Commission.
Contrary to TS 6.7.2, the licensee failed to send a written report that describes the circumstances of the event to the NRC within 14 days after the licensee determined that a reportable event occurred.
Screening: The event report was sent on December 15, 2024. The information in the report would not have changed the NRCs oversight posture and because the licensee performed all required corrective actions after identifying the failed fuel element, the inspectors determined that the failure to meet the requirements of TS 6.7.2 constitutes a violation of minor significance in accordance with section 2.0 of the NRC Enforcement Policy. This minor violation (VIO 05000128-2024201-03) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 6.7.2 constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy.
Non-Cited Violation (NCV 05000128/2024201-02) 69001.07 The inspectors identified a Severity Level IV violation of TS 6.7.1 for the licensee failing to submit an annual operating report within the required frequency. This violation of very low safety significance was identified by the licensee and has been corrected and is treated as a non-cited violation, consistent with section 2.3.2(b) of the NRC Enforcement Policy.
Violation: TS 6.7.1, Annual Operating Report, states, in part, An annual report covering the operation of the reactor facility during the previous calendar year shall be submitted to the NRC before March 31 of each year providing the following information:.
Contrary to TS 6.7.1, the annual report covering the operation of the reactor facility for calendar year 2023 was not submitted to the NRC before March 31, 2024. Specifically, the annual operating report was not submitted until December 19, 2024, 8 months and 19 days after the required time frame.
The inspectors determined that the problem was identified by the licensee and reported to the inspectors. Corrective actions were identified and completed. As a result, this non-willful, non-repetitive, licensee-identified and licensee-corrected violation will be treated as a non-cited violation consistent with section 2.3.2.a of the NRC Enforcement Policy (NCV 05000128/2024201-02).
Minor Violation (VIO 05000128/2024201-04) 69001.07 Minor Violation: TS 4.5, Radiation Monitoring Systems and Effluents, specification 1 states, The area radiation monitoring system (ARM) and the FAM system shall be calibrated annually, shall be channel tested weekly, and shall be channel checked prior to reactor operation.
Contrary to TS 4.5(1.), the licensee identified that the Facility Air Monitoring (FAM) system was not calibrated annually. Specifically, the licensee identified that the calibrations were revised in 2018 to not require a full calibration of the entire FAM system. The last correct calibration was performed on November 19, 2018.
Screening: The licensee performed a complete FAM system calibration in January 2024, prior to reactor operations, and determined that the FAM system was never out of calibration since the last calibration on November 19, 2018. As a result, the inspectors determined that failure to meet the requirements of TS 4.5(1.) constitutes a violation of minor significance in accordance with section 2.0 of the NRC Enforcement Policy. This minor violation (VIO 05000128/2024201-04) was corrected by the licensee and this issue is closed.
Enforcement: The failure to comply with TS 4.5(1.) constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy.
This closes Unresolved Item 05000128/2023201-04.
Failure to conduct audits as required by the TSs Severity Report Section Severity Level IV NOV 2024201-01 Open 69001.09 The inspectors identified a Severity Level IV notice of violation of TS 6.2.4(1.), TS 6.2.4(2.),
TS 6.2.4(5.), and TS 6.2.5 for the licensees failure to perform audits within the required frequency.
==
Description:==
TS 6.2.4 and TS 6.2.5 requires the licensee to perform audits. While the licensee failed to perform the audits required by TS 6.2.4(1.), TS 6.2.4(2.), and TS 6.2.5 within the required time frame, the audits were eventually performed. However, during an NRC security inspection performed December 11-14, 2023, the inspector noted TS 6.2.4(5.) was not performed since June 2021 and was due December 2023. The inspector noted that the audit was scheduled for the month of December, but the auditor changed plans to conduct the audit in January 2024. During this inspection, the inspectors confirmed no audit was conducted in January 2024. The licensee has currently not performed an audit required by TS 6.2.4(5.)
since June 2021.
Corrective Actions: The inspectors confirmed that the licensee placed the issue in their spreadsheet tracking all issues that need to be completed. The licensee informed the inspectors that an individual that works for the Nuclear Science Center and is not immediately responsible for the area would perform the audit this calendar year.
Analysis: The violation was evaluated in accordance with the NRC Enforcement Policy. The violation is cited as a Notice of Violation because it constitutes a failure to meet regulatory requirements that has a more than minor safety significance and the licensee failed to identify the violation.
Enforcement:
Severity: The violation is categorized at Severity Level IV in accordance with section 6.9.d of the NRC Enforcement Policy.
Violation: TS 6.2.4, RSB Audit Function, states, in part, The audit function shall include selective (but comprehensive) examination of operating records, logs, and other documents.
Audits shall include but are not limited to the following:.
TS 6.2.4(1.) states, Facility operations, including radiation protection, for conformance to the Technical Specifications, applicable license conditions, and standard operating procedures:
at least once per calendar year (interval between audits not to exceed 15 months).
TS 6.2.4(2.) states, The results of action taken to correct those deficiencies that may occur in the reactor facility equipment systems, structures, or methods of operations that affect reactor safety: at least once per calendar year (interval between audits not to exceed 15 months).
TS 6.2.4(5.) states, The reactor facility security plan and implementing procedures: at least once every other calendar year (interval between audits not to exceed 30 months).
Contrary to TS 6.2.4(1.) and TS 6.2.4(2.), the inspectors identified that the licensee failed to perform an audit to include facility operations and an audit to include the results of action taken to correct those deficiencies that may occur in the reactor facility equipment systems, structures, or methods of operations that affect reactor safety at least once per calendar year.
Specifically, the licensee performed an audit, that included TS 6.2.4(1.) and TS 6.2.4(2.), on August 28, 2022, and performed the subsequent audit on April 2, 2024, which exceeded the allowable 15-month frequency.
Contrary to TS 6.2.4(5.), the inspectors identified that the licensee failed to perform an audit to include the reactor facility security plan and implementing procedures at least once every other calendar year. Specifically, the licensee performed an audit, that included TS 6.2.4(5.),
on June 28, 2022, and had not performed a subsequent audit, which exceeded the 30-month requirement.
TS 6.2.5, Audit of ALARA Program, states, in part, The Chair of the RSB or designated alternate (excluding anyone whose normal job function is within the NSC) shall conduct an audit of the reactor facility ALARA program annually.
Contrary to TS 6.2.5, the inspectors identified that the licensee failed to conduct an audit of the reactor facility as low as is reasonably achievable (ALARA) program annually.
Specifically, the licensee performed an audit, that included TS 6.2.5, on June 28, 2022, and performed the subsequent audit on April 3, 2024, which exceeded the annual requirement.
Enforcement Action: This violation is being cited as a Notice of Violation, consistent with sections 2.3.2 and 2.3.3 of the NRC Enforcement Policy.
This closes Inspector Follow Up Item 05000128/2023202-01.
Exit Meeting and Debriefs The inspectors verified no proprietary information was retained or documented in this report.
On December 20, 2024, the inspectors presented the NRC inspection results to members of licensee management and staff.
Documents Reviewed Inspection Procedure Type Designation Description or Title Revision or Date Logbook 272 Reactor Operations Logbook N/A N/A License Management Change for the Referenced Reactors May 8, 2024 69001.01 Miscellaneous N/A NSCR Reactor Facilities Org Chart December 1, 2024 AP-03 Procedures Revision 1 CCP-01 Weekly FAM Channel Test November 7, 2023 SOP Section VII Procedure A Primary Coolant Radiological Analysis January 31, 2020 SOP Section VII Procedure B Radiation Monitoring Channels Check January 31, 2020 SOP Section II Procedure E
Reactor Shutdown and Secure February 17, 2016 69001.03 Procedure SOP Section II Procedure B
Reactor Startup February 17, 2016 SOP Section VII Procedure I Stack Gas Monitor Calibration Adjustment January 31, 2020 CCP-04 Stack Gas (Ar-41) Monitor Calibration June 5, 2024 RSP-01 ALARA Procedure March 14, 2023 69001.07 Procedure E-1 Personnel Dosimetry February 13, 1995 RSP-06 Radiation Work Permit Procedure December 12, 2023 C-12 Facility Radiation Survey December 14, 2004 Power Point N/A Radiation Worker 1 Training N/A Logbook 270 Reactor Operations Logbook N/A 845 Radiation Work Permit Sign in/Out Sheet October 30, 2023 825 Channel No.1, Maintenance and Calibration January 4, 2024 826 Channel No. 2 Maintenance and Calibration January 4, 2024 827 Channel No. 3 and 5 Maintenance and Calibration January 11, 2024 828 Channel No. 4, Maintenance and Calibration January 5, 2024 Procedural Form 829 Channel No. 6, Maintenance and Calibration January 23, 2024 Miscellaneous PLN-NESC-RSP NESC Radiation Safety Program November 11, 2021 AP-11 Change Management July 16, 2023 Procedure AP-12 Work Package July 16, 2023 2023-02 TR Drawer Repair April 5, 2023 2023-03 ARM Display Computer April 26, 2023 2023-04 FAM 1, 2 Paper Drive Power Supply May 3, 2023 2023-06 Bayonet Change Out June 1, 2023 69001.08 Design Change 2023-07 Safety Channel 1, 2 Repair June 8, 2023 2023-09 August Fuel Element Swap August 9, 2023 2023-10 July 2023 Transient Rod Damage August 9, 2023 2023-11 July 2023 Transient Drive Component Wear August 15, 2023 2023-13 Pool Walkway Mount November 28, 2023 2023-14 Log Channel Cable Repair September 26, 2023 2023-15 HVAC Controls Reprogramming September 23, 2023 2024-03 Reactor Bridge Jack Replacement February 28, 2024 2024-05 June 2024 Fuel Elements Swap July 15, 2024 2024-08 Log Power Channel Detector Replacement November 20, 2024 2024-09 Safety Channel 1 Inverter IC Replacement November 20, 2024 Miscellaneous NSCR-RPT-2302 2023 Transient Rod Malfunction Analysis August 13, 2023 Drawing 252D205 Transient Rod Assembly-Air Follower N/A 199 Meeting Minutes July 28, 2022 200 Meeting Minutes February 13, 2023 201 Meeting Minutes March 13, 2023 69001.09 Reactor Safety Board 202 Meeting Minutes June 15, 2023 203 Meeting Minutes July 19, 2023 204 Meeting Minutes October 16, 2023 205 Meeting Minutes December 14, 2023 206 Meeting Minutes January 31, 2024 207 Meeting Minutes May 23, 2024 PLN-RSB-CHARTER Charter for the Reactor Safety Board February 21, 2022 N/A Reactor Operations Audit August 26, 2022 N/A NSCR Reactor Staff Response to the Program Audit Conducted in August 2022 February 9, 2023 N/A Health Physics Records Review June 28, 2022 N/A Response to Health Physics Records Review Conducted June 28, 2022 N/A N/A Reactor Operations Audit of the Texas A&M Engineering Station Nuclear Engineering & Science Center Research Reactor April 2, 2024 Audit/Review N/A Technical Specifications Audit November 12, 2024 Event Report 57174 Submission of Technical Specifications Required Report for Event Notification 57174, Identification of Degraded Fuel Elements During 2024 Maintenance December 15, 2024 86740 Procedure SOP Section VII Procedure Q Radioactive Materials Released January 31, 2020 SOP Section VII Procedure R Radioactive Materials Handling December 19, 2024