ML26040A091
| ML26040A091 | |
| Person / Time | |
|---|---|
| Issue date: | 02/25/2026 |
| From: | Marissa Bailey Advisory Committee on Reactor Safeguards |
| To: | Mark King NRC/EDO |
| Burkhart L | |
| References | |
| Download: ML26040A091 (0) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 MEMORANDUM TO: Michael F. King Executive Director for Operations FROM:
Marissa G. Bailey, Executive Director Advisory Committee on Reactor Safeguards
SUBJECT:
FEBRUARY 2026 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS During the 732nd meeting of the Advisory Committee on Reactor Safeguards (ACRS), February 5, 2026, the Committee considered the following topical reports. The Committee made these decisions in accordance with the direction contained in Executive Order 14300, Ordering the Reform of the Nuclear Regulatory Commission, and with a focus on the statutory requirements contained in the Atomic Energy Act, as amended. No response to this memorandum is requested.
Design-Centered Topical Reports (TRs) 1.
Holtec SMR-300 TR, SMR-300 Time-Domain LS-DYNA Soil Structure Interaction Analysis Methodology Licensing Topical Report. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic.
2.
Holtec SMR-300 TR, SMR-300 Concrete Strengthened Steel Structures Design and Analysis Methodology Licensing Topical Report. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic.
Generic Topical Reports Related to Reactor Safety Standards 3.
Westinghouse TR, WCAP-16747m Appendices C and D, Revision 2, POLCA-T: System Analysis Code with Three-Dimensional Core Model. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic. The Committee revised its decision on this TR due to the issuance of Executive Order 14300.
4.
Westinghouse TR, WCAP-18483-P, Revision 0, EnCore Chromium Coated Cladding for Use in Pressurized Water Reactors. The Committee requests to review this document. This is the first TR presented to NRC on coated LWR fuel cladding and introduces unique, novel, and noteworthy considerations related to accident-tolerant fuel technology.
CONTACT:
L. Burkhart, ACRS 301-287-3775 February 25, 2026 Signed by Bailey, Marissa on 02/25/26
5.
Westinghouse TR, Westinghouse WCAP-18951 -P/NP, Revision 1, TRITON11 Reference Fuel Design. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic.
cc:
T. Herrera, SECY D. Lewis, OEDO D. Curtis, OEDO C. Araguas, RES M. Rahimi, RES M. Eudy, RES
SUBJECT:
FEBRUARY 2026 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS Accession No: ML26040A091 Publicly Available Y
Sensitive N
Viewing Rights:
NRC Users or ACRS Only or See Restricted distribution OFFICE ACRS/TSB SUNSI Review ACRS NAME LBurkhart LBurkhart MBailey DATE 2/9/2026 2/9/2026 2/25/2026 OFFICIAL RECORD COPY February 25, 2026