ML25254A240
| ML25254A240 | |
| Person / Time | |
|---|---|
| Issue date: | 09/16/2025 |
| From: | Marissa Bailey Advisory Committee on Reactor Safeguards |
| To: | Mark King NRC/EDO |
| Burkhart L | |
| References | |
| Download: ML25254A240 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 MEMORANDUM TO: Mike King Executive Director for Operations (Acting)
FROM:
Marissa G. Bailey, Executive Director Advisory Committee on Reactor Safeguards
SUBJECT:
SEPTEMBER 2025 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS During the 728th meeting of the Advisory Committee on Reactor Safeguards (ACRS),
September 3 through 5, 2025, 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-Center Topical Report Reviews 1.
Terrestrial Energy (TEUSA) Postulated Initiating Events (PIE) Topical Report (TR). The Committee has changed its position on this document and now does not request to review this document. The unique, novel, and noteworthy parts of this topical report will be explored during the subsequent license application review.
2.
Kairos Topical Report Revision 1, Safety Analysis Methodology for the Kairos Power Fluoride Salt-Cooled High-Temperature Test Reactor. The Committee does not request to review this document at this time. The Committee will review relevant parts of this report as they are implemented in subsequent license applications.
3.
Kairos Topical Report on Operator Training and Testing Program for the Non-Power Kairos Power Fluoride Salt-Cooled High-Temperature Reactors. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic.
4.
SMR-300 Design Basis Analysis Radiological Consequences 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.
CONTACT:
L. Burkhart, ACRS 301-287-3775 September 16, 2025 Signed by Bailey, Marissa on 09/16/25
5.
SOLO Micro Modular Nuclear Reactor Principal Design Criteria, SOLO-TR-2025-1. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic.
6.
Blue Energy Topical Report, BE-BOPTR-02-P, Rev. 0, Resequencing Balance-of-Plant and Nuclear Island Construction for Blue Energy Deployments. The Committee does not request to review this document because it does not address a unique, novel, or noteworthy technical topic.
Generic Topical Reports Related to Reactor Safety Standards 7.
Framatome ANP-10358P, Revision 0, Increased Burnup for PWRs. The Committee requests to review this document. It supports rulemaking on increased enrichment and burnup, making it both novel and regulatory-relevant. In addition, first of a kind power uprate license amendment requests will rely on this important topical report.
8.
AMS-Cable TR-R0, Condition Monitoring Methodology for Life Extension and Aging Management of Electrical Cable. The Committee does not request to review this document because it does not represent a unique, novel or noteworthy methodology.
9.
WCAP-16747, Revision 2 - POLCA-T Evaluation Model. The Committee requests to review this report. Although most of the methodology (in Appendices C and D) has been previously reviewed and approved, the combination of 3D spatial kinetics, explicit tolerance of fuel cladding failure during fast transients and ATWS, and the anticipated application under high burnup and power uprate conditions represents a novel and safety-significant departure.
Accordingly, the Committee review will focus on the technical and regulatory basis for accepting fuel failure in high-consequence transients.
- 10. Framatome Topical Report, ANP-10354P, Revision 0 - Single-Phase CFD for Fuel Assembly Characterization. The Committee does not request to review this document because it does not represent a unique, novel or noteworthy methodology.
- 11. EPRI Alternative Licensing Strategy (ALS) for Loss-of-Coolant (LOCA)-induced Fuel Fragmentation, Redistribution and Disbursal (FFRD) with Lead Before Break (LBB) Credit:
Alternative Licensing Strategy. Because this report touches on unique, novel, and noteworthy topics related to fuel fragmentation, redistribution and dispersal, the Committee requests to review this document.
- 12. Materials Reliability Program: xLPR Estimation of PWR Loss-of-Coolant Accident Frequencies (MRP-480). The Committee does not request to review this document because it does not address a unique, novel, or noteworthy topic.
- 13. EPRI 3002028674, Revision 0, LOCA Analysis of FFRD for WEC 2-, 3-, and 4-Loop Plants. 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 J. Martin, OEDO C. Araguas, RES M. Rahimi, RES M. Eudy, RES
SUBJECT:
SEPTEMBER 2025 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS Accession No: ML25254A240 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 9/15/2025 9/15/2025 9/16/2025 OFFICIAL RECORD COPY September 16, 2025