ML25273A169

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University of New Mexico - NRC Safety Inspection Report No. 05000252/2025201
ML25273A169
Person / Time
Site: University of New Mexico
Issue date: 11/17/2025
From: Tony Brown
NRC/NRR/DANU/UNPO
To: Willis C
Univ of New Mexico
Waugh A
References
IR 2025201
Download: ML25273A169 (9)


Text

Mr. Carl Willis, Chief Reactor Supervisor Nuclear Engineering Department 1 University of New Mexico, MSC-01-1120 Albuquerque, NM 87131-0001

SUBJECT:

UNIVERSITY OF NEW MEXICO - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000252/2025201

Dear Mr. Willis:

From September 22-25, 2025, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at the University of New Mexico AGN-201M Reactor facility. The enclosed report presents the results of that inspection, which were discussed on September 25, 2025, with you and members of your staff.

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, no findings of significance were identified. No response to this letter is required.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public inspections, exemptions, requests for withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (Agencywide Documents Access and Management System (ADAMS)). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

November 17, 2025

If you have any questions concerning this inspection, please contact Andrew Waugh at (301) 415-0230, or via email at Andrew.Waugh@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. 50-252 License No. R-102

Enclosure:

As stated cc w/enclosure: GovDelivery Subscribers Signed by Brown, Tony on 11/17/25

ML25273A169 NRC-002 OFFICE NRR/DANU/UNPO NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME AWaugh NParker TBrown DATE 9/30/2025 11/17/2025 11/17/2025

Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:

50-252 License No.:

R-102 Report No.:

05000252/2025201 Licensee:

University of New Mexico Facility:

University of New Mexico AGN-201M Reactor Location:

Albuquerque, New Mexico Dates:

September 22-25, 2025 Inspector:

Andrew Waugh 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 University of New Mexico (UNM) Aerojet General Nucleonics-201 Modified (AGN-201M) Reactor, 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 No violations of more than minor significance were identified.

Additional Tracking Items None.

REPORT DETAILS Facility Status The UNM AGN-201M research reactor continued to operate in support of teaching, classroom experiments/demonstrations, surveillances, and operator training. During the inspection, the reactor was started up, operated, and shutdown to support these ongoing activities.

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 inspector 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 technical specification (TS) requirements and licensee commitments. Specifically, the inspection included a review of the following:

select reactor operation logs, dated 2023-present memorandums to the NRC concerning management changes, dated 2023-present 2024 and 2025 annual operating reports Operations Logs and Records (IP Section 02.02)

This inspection included a review of the licensees operation logs and records to verify they were maintained and that significant issues were reported and resolved as required by the TSs and the licensees administrative procedures. Specifically, the inspection included a review of the following:

the inspector observed completion of a pre-critical startup checkout, a reactor startup, operation, and shutdown select reactor operation logs, dated 2023-present select pre-critical startup checkouts, dated 2023-present This inspection included review of event notifications (ENs) 57248 and 57948. No violations of NRC requirements were identified for these ENs.

Requalification Training (IP Section 02.04)

This inspection included a review of selected documents pertaining to operator requalification training to verify requirements of the licensees approved requalification plan and Title 10 of the Code of Federal Regulations Part 55, Operators Licenses were met. Specifically, the inspection included a review of the following:

select reactor operation logs, dated 2023-present medical examination records for licensed operators select requalification records, dated 2023-present requalification exam records, dated 2023-present Surveillance and Limiting Conditions for Operation (IP Section 02.05)

This inspection included a review of surveillances listed in the TSs to verify requirements were met. Limiting conditions for operation were also reviewed to verify that operating conditions were maintained in accordance with the licensees procedural requirements. Specifically, the inspection included a review of the following:

select monthly reactor inspection records, dated 2023-present annual reactor maintenance records, dated 2023-present Emergency Planning (IP Section 02.10)

This inspection included a review of the licensees emergency procedures, exercises and drills, training, and equipment to verify compliance with the licensees emergency plan and applicable regulatory requirements. Specifically, the inspection included a review of the following:

emergency drill records, dated 2023-present annual reactor maintenance records, dated 2023-present Maintenance Logs and Records (IP Section 02.11)

This inspection included a review of the licensees maintenance logs and records to verify that operational and maintenance activities were conducted and maintained in accordance with regulatory and TS requirements. Specifically, the inspection included a review of the following:

select reactor maintenance log sheets, dated 2023-present Fuel Handling Logs and Records (IP Section 02.12)

This inspection included a review of the licensees fuel handling logs and records to verify TS and procedural requirements were met. Specifically, the inspection included a review of the following:

select reactor operation logs, dated 2023-present select fuel addition data sheets, dated 2023-present select reactor operation logs, dated 2023-present Inspection Results No violations of more than minor significance were identified.

Exit Meeting and Debriefs The inspector verified no proprietary information was retained or documented in this report.

On September 25, 2025, the inspector presented the NRC inspection results to members of licensee management and staff.

Documents Reviewed Inspection Procedure Type Description or Title Revision or Date Procedure Reactor Operation and Training Manual January 2024 Event Notification#57248 July 26, 2024 69001.02 Miscellaneous Event Notification#57948 September 24, 2025 Operator and Senior Operator Requalification Program for UNM AGN-201M Reactor Facility January 2019 69001.04 Procedure Operator and Senior Operator Requalification Implementing Procedure 1 June 29, 2022 Procedure for Excess Reactivity Measurements May 23, 2019 Procedure for Fine Control Rod Worth Measurement May 2019 69001.05 Procedure Procedure for Safety Rod 1, Safety Rod 2, and Coarse Control Rod Worth Measurements February 25, 2019 69001.10 Miscellaneous Emergency Plan for the University of New Mexico AGN-201M Reactor Facility August 15, 2024 AGN-201 Fuel Removal Procedure for Approach to Critical January 29.

2018 AGN-201 Fuel Removal Procedure for Disassembly of Core Tank June 27, 2025 69001.12 Procedure AGN-201 Fuel Insertion and Procedure for Re-Assembly of Core Tank May 17, 2019