ML26029A100
| ML26029A100 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 02/05/2026 |
| From: | Stamler B NRC/NRR/DANU/UNPL |
| To: | Joel Jenkins Texas A&M Univ |
| References | |
| EPID L-2025-NFA-0008 | |
| Download: ML26029A100 (0) | |
Text
Mr. Jere Jenkins, Director Nuclear Science Center Texas A&M Engineering Experiment Station 1095 Nuclear Science Road, MS 3575 College Station, TX 77843-3575
SUBJECT:
TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM-- ISSUANCE OF AMENDMENT NO. 21 TO FACILITY OPERATING LICENSE NO. R-83 FOR THE TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM NUCLEAR SCIENCE CENTER RE: REVISION TO TECHNICAL SPECIFICATIONS 6.2 AND 6.2.1 (EPID NO. L-2025-NFA-0008)
Dear Mr. Jenkins:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 21 to Facility Operating License No. R-83 for the Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center. The amendment revises technical specifications (TSs) 6.2 Review and Audit and 6.2.1 Reactor Safety Board (RSB) in response to the application dated August 28, 2025 (Agencywide Documents Access and Management System Accession No. ML25241A097). The amendment revises the TSs to adopt the language verbatim from American Nuclear Society/American National Standards Institute-15.1-2007, The Development of Technical Specifications for Research Reactors.
February 5, 2026
J. Jenkins A copy of the related safety evaluation is also enclosed. If you have any questions, please contact Brooke Gallagher at 301-415-5280, or by email at Brooke.Gallagher@nrc.gov.
Sincerely, Bradley M. Stamler, Project Manager Non-Power Production and Utilization Facility Licensing 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:
- 1. Amendment No. 21 to Facility Operating License R-83
- 2. Safety Evaluation cc w/enclosures: GovDelivery Subscribers Signed by Stamler, Bradley on 02/05/26
ML26029A100 NRR-058 OFFICE NRR/DANU/UNPL/PM NRR/DANU/UNPL/LA NRR/DANU/UNPL/BC NRR/DANU/UNPL/PM NAME BStamler NParker JRady BStamler DATE 1/29/2026 2/2/2026 2/5/2026 2/5/2026 TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM DOCKET NO. 50-128 TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM NUCLEAR SCIENCE CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. R-83 1.
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has found that:
A.
The application for amendment to Facility Operating License No. R-83, filed by the Texas Engineering Experiment Station/Texas A&M University System (the licensee) dated August 28, 2025, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions, of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended as described in Attachment 1 to this license amendment and by changes to the Technical Specifications as described in Attachment 2.
Paragraph 2.C.2 of Facility Operating License No. R-83 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised by Amendment No. 21, are hereby incorporated in the license. The licensee shall operate the reactor in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 calendar days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey S. Rady, Chief Non-Power Production and Utilization Facility Licensing Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Attachments:
1.
Changes to Facility Operating License No. R-83 2.
Changes to Appendix A, Technical Specifications Date of Issuance: February 05, 2026 JEFFREY RADY Digitally signed by JEFFREY RADY ATTACHMENT 1 TO LICENSE AMENDMENT NO. 21 FACILITY OPERATING LICENSE NO. R-83 DOCKET NO. 50-128 Replace the following page of Facility Operating License No. R-83 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change.
Facility Operating License No. R-83 Remove Insert Amendment No. 21 February 05, 2026 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised by license Amendment No. 21, are hereby incorporated in their entirety in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Physical Security Plan The licensee shall maintain and fully implement all provisions of the Commission approved physical security plan, including changes made pursuant to the authority of 10 CFR 50.54(p). The approved physical security plan, entitled Texas A&M Engineering Experiment Station, Nuclear Science Center, Physical Security Plan for the Protection of Special Nuclear Material, Facility Operating License R-83, Docket Number 50-128, March 2015, consists of documents withheld from public disclosure pursuant to 10 CFR 73.21.
This license is effective as of the date of its issuance and has no fixed term.
For the Nuclear Regulatory Commission
/RA/
William M. Dean, Director Office of Nuclear Reactor Regulation
Attachment:
Appendix A, Technical Specifications Date of Issuance: October 1, 2015 ATTACHMENT 2 TO LICENSE AMENDMENT NO. 21 FACILITY OPERATING LICENSE NO. R-83 DOCKET NO. 50-128 Replace the following page of Appendix A, Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Technical Specifications Remove Insert Page l 56 Texas Engineering Experiment Station NSC Amendment No. 21 February 05, 2026 6.2 Review and Audit A method for the independent review and audit of the safety aspects of reactor facility operations shall be established to advise management. The two functions may be performed by a single group or separate groups. The information in Secs. 6.2.1 through 6.2.4 shall be shown. The review and audit group is called the Reactor Safety Board (RSB).
6.2.1 Reactor Safety Board (RSB) Composition and qualifications The review and audit group shall be composed of a minimum of three members if a single group is used. If separate groups are used, then there shall be a minimum of three persons for review and one for auditing. The members shall collectively represent a broad spectrum of expertise in the appropriate reactor technology. Members and alternates shall be appointed by and report to Level 1 management. Individuals may be either from within or outside the operating organization. Qualified and approved alternates may serve in the absence of regular members.
6.2.2 RSB Charter and Rules The operations of the RSB shall be in accordance with a written charter, including provisions for:
1.
Meeting Frequency: The RSB shall meet annually at intervals not to exceed 15 months. (Note:
The facility license requires a meeting at least once per year and as frequently as circumstances warrant consistent with effective monitoring of facility activities);
2.
Quorum: A quorum is comprised of not less than one-half of the voting membership where the operating staff does not constitute a majority; 3.
Voting Rules: On matters requiring a vote, if only a quorum is present a unanimous vote of the quorum is required; otherwise a majority vote is required; 4.
Subcommittees: The Chair may appoint subcommittees comprised of members of the RSB including ex-officio members to perform certain tasks. Subcommittees or members of the RSB may be authorized to act for the board; and 5.
Meeting Minutes: The Chair will designate one individual to act as recording secretary. It will be the responsibility of the secretary to prepare the minutes which will be distributed to the RSB, including the Director of TEES (Level 1 Management), within three months. The RSB will review and approve the minutes of the previous meetings. A complete file of the meeting minutes will be maintained by the Chair of the RSB and by the Director of the NSC.
6.2.3 RSB Review Function The review responsibilities of the Reactor Safety Board or a designated subcommittee shall include, but are not limited to the following:
1.
Review and evaluation of determinations of whether proposed changes to equipment, systems, tests, experiments, or procedures can be made under 10 CFR 50.59 or would require a change in Technical Specifications or license conditions; 2.
Review of new procedures, major revisions of procedures, and proposed changes in reactor facility equipment or systems which have significant safety impact to reactor operations;
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 21 TO FACILITY OPERATING LICENSE NO. R-83 TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM NUCLEAR SCIENCE CENTER REACTOR DOCKET NO. 50-128
1.0 INTRODUCTION
By letter dated August 28, 2025 (Agencywide Documents Access and Management System Accession No. ML25241A097), the Texas Engineering Experiment Station/Texas A&M University System (the licensee), submitted a license amendment request to Facility Operating License No. R-83 for the Nuclear Science Center Reactor (NSCR) under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.90, Application for amendment of license, construction permit, or early site permit. Specifically, the licensee requested to revise the facilitys technical specifications (TSs) 6.2, Review and Audit and 6.2.1, Reactor Safety Board (RSB) to adopt the language from American National Standards Institute/American Nuclear Society (ANS/ANSI)-15.1-2007, The Development of Technical Specifications for Research Reactors, sections 6.2, Review and Audit, and 6.2.1, Composition and qualifications, verbatim.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC) staff evaluated the proposed changes based on the following regulations and guidance:
Section 50.92, Issuance of amendment, of 10 CFR, which states, in part, that in determining whether an amendment to a license will be issued, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate.
NUREG-1537, Part 1, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and Content (ML042430055), which provides guidance on the format and content of non-power reactor licensing applications.
NUREG-1537, Part 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance Criteria (ML042430048), which provides guidance on the conduct of NRC licensing reviews of non-power reactor licensing applications.
American National Standards Institute/American Nuclear Society-15.1-2007, The Development of Technical Specifications for Research Reactors.
3.0 TECHNICAL EVALUATION
3.1 Evaluation of Technical Justification for TS Change The NSCR is a non-power research reactor licensed under 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. The NRC guidance for research reactor licensing, including format and content of TSs, is provided in NUREG-1537, Part 1, Appendix 14.1, Format and Content of Technical Specifications for Non-Power Reactors, section 6, Administrative Controls, which endorses portions of ANS/ANSI-15.1-2007. This amendment modifies TSs 6.2 and 6.2.1 to match sections 6.2 and 6.2.1 of ANS/ANSI-15.1-2007 for both the section titles and content verbatim.
3.2 Proposed Technical Specification Changes For this section, deletions will be represented as text in strikethrough and additions will be represented as underlined text.
The proposed changes to TS 6.2 are:
6.2 Review and Audit A method for the independent review and audit of the safety aspects of reactor facility operations shall be established to advise management. The two functions may be performed by a single group or separate groups. The information in Secs. 6.2.1 through 6.2.4 shall be shown. The review and audit group is called the Reactor Safety Board (RSB).
The proposed change to TS 6.2 adds the introductory language for the section. The language in this proposed change is consistent with NUREG-1537, Part 1, Appendix 14.1, section 6.2 which endorses portions of ANS/ANSI-15.1-2007. The NRC staff finds that this proposed change is consistent with the guidance in NUREG-1537, Part 1, Appendix 14.1, section 6.2, and ANS/ANSI-15.1-2007, section 6.2, therefore, the NRC staff concludes that this proposed change is acceptable.
The proposed changes to TS 6.2.1 are:
6.2.1 Reactor Safety Board (RSB) Composition and qualifications The review and audit group shall be composed of a minimum of three members if a single group is used. If separate groups are used, then there shall be a minimum of three persons for review and one for auditing. The members shall collectively represent a broad spectrum of expertise in the appropriate reactor technology. Members and alternates shall be appointed by and report to Level 1 management. Individuals may be either from within or outside the operating organization. Qualified and approved alternates may serve in the absence of regular members.
The Reactor Safety Board shall be comprised of at least 3 voting members knowledgeable in fields which relate to Nuclear Safety. One of these members, the Director of TEES (Level 1 Management), will serve as the Chair. If the Chair is unable to attend one or a number of committee meetings, then the chair may designate a committee member as Chair pro tem.
The members are appointed by the Director of TEES (Level 1 Management) to serve one year terms. It is expected that the members will be reappointed each year as long as they are willing to serve so that their experience and familiarity with the past history of the NSC will not be lost to the committee. The Director of the NSC, TAMU Radiological Officer, Head of the Department of Nuclear Engineering, and a senior member of the NSC Radiation Safety Staff shall be ex officio members of the RSB.
The proposed change to TS 6.2.1 Reactor Safety Board (RSB) modifies the title to Reactor Safety Board (RSB) Composition and qualifications and the language within to match that of section 6.2.1, Composition and qualifications of ANS/ANSI-15.1-2007. The language in this proposed change is consistent with NUREG-1537, Part 1, Appendix 14.1, section 6 and section 6.2.1 which endorses portions of ANS/ANSI-15.1-2007. The NRC staff finds that this proposed change is consistent with the guidance in NUREG-1537, Part 1, Appendix 14.1, section 6.2.1, and ANS/ANSI-15.1-2007, section 6.2.1, therefore, the NRC staff concludes that this proposed change is acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment modifies TSs 6.2 and 6.2.1 to adopt language verbatim from ANS/ANSI-15.1-2007, which is endorsed by the NRC in NUREG-1537, Part 1. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant changes in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. Additionally, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: B. Stamler, NRR Date: February 05, 2026