ML25196A201
| ML25196A201 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/2025 |
| From: | Marissa Bailey Advisory Committee on Reactor Safeguards |
| To: | Mark King NRC/EDO |
| Burkhart L | |
| References | |
| Download: ML25196A201 (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:
JULY 2025 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS During the 727th meeting of the Advisory Committee on Reactor Safeguards (ACRS), July 9 through 10, 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.
NEDC-34270P, Revision 0, March 2025, GEH Proprietary Information - Non-Public BWRX-300 Stability Analysis. The Committee requests to review this document, focusing on the applicability and use of those tools and methods for evaluation of an exclusively natural circulation plant design. This document supports the Clinch River construction permit application currently under review by the Nuclear Regulatory Commission (NRC) and, given the limited design and operational experience with natural circulation in boiling water reactors, the stability analysis is novel and noteworthy.
2.
NEDC-33926P, Revision 3, BWRX-300 Steel-Plate Composite Containment Vessel and Reactor Building Structural Design - Proprietary Information. The Committee does not request to review of this document at this time and instead considers reviewing this report as appropriate during the expected Clinch River construction permit application review.
3.
GEH Licensing Topical Report NEDC 33934, Revision 1, BWRX-300 Safety Strategy Topical Report. The Committee requests to review this document. This document supports the Clinch River construction permit application currently under review by the NRC. The safety strategy for this design is foundational to the safety case for this reactor, making this topical report unique, novel and noteworthy.
CONTACT:
L. Burkhart, ACRS 301-287-3775 July 17, 2025 Signed by Bailey, Marissa on 07/17/25
Generic Topical Reports Related to Reactor Safety Standards 4.
Westinghouse Topical Report Full Spectrum LOCA (FSLOCA) for High Burnup Fuel.
The Committee requests to review this document. The FSLOCA WCAP-18850 report is a first-of-its-kind application of the approved methodology to high burnup fuel, incorporating new modeling of cladding rupture, fission gas release, and fuel relocation. 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.
5.
ALS-v2 Surveillance Elimination Topical Report. The Committee does not request to review this document because it does not represent a unique, novel or noteworthy methodology.
6.
Qualification of Fiber-Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Production and Utilization Facilities, Draft Guide-1427 (Proposed Revision 0 to Regulatory Guide 1.257). The Committee does not request to review this document because it does not represent a unique, novel or noteworthy methodology.
7.
Updated Review of EPRI High Energy Line Break Topical Report. The Committee does not request to review this document because it does not represent a unique, novel or noteworthy methodology.
cc:
T. Herrera, SECY D. Lewis, OEDO J. Martin, OEDO C. Araguas, RES M. Rahimi, RES M. Eudy, RES
SUBJECT:
JULY 2025 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS Accession No: ML25196A201 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 7/15/2025 7/15/2025 7/17/2025 OFFICIAL RECORD COPY July 17, 2025