ML25043A112

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February 2025 Advisory Committee on Reactor Safeguards Full Committee Meeting Topical Reports
ML25043A112
Person / Time
Issue date: 02/13/2025
From: Marissa Bailey
Advisory Committee on Reactor Safeguards
To: Mirela Gavrilas
NRC/EDO
Burkhart L
References
Download: ML25043A112 (1)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 MEMORANDUM TO: Dr. Mirela Gavrilas Executive Director for Operations FROM:

Marissa G. Bailey, Executive Director Advisory Committee on Reactor Safeguards

SUBJECT:

FEBRUARY 2025 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS During the 722nd meeting of the Advisory Committee on Reactor Safeguards (ACRS), February 5 through 7, 2025, the Committee considered the following topical reports. No response to this memorandum is requested.

GENERIC TOPICAL REPORTS 1.

ANP-10350P, Revision 0, Framatome Methodology for Boiling Water Reactors:

Evaluation and Validation of AP0LL02-A/ARTEMIS-B. The Committee requests to review this document.

2.

Westinghouse - WCAP-18904-P/NP, Revision 0, Critical Power Experiments and D6 CPR Correlation for TRITON11 Fuel. The Committee does not request to review this document.

DESIGN-CENTERED TOPICAL REPORTS 3.

Xe-100 Licensing Topical Report, Transient and Safety Analysis Methodology, Revision 1. The Committee requests to review this document.

4.

Xe-100 Licensing Topical Report, Gothic and Flownex Analysis Code Qualification, Revision 2. The Committee requests to review this document.

5.

Xe-100 Licensing Topical Report, Mechanistic Source Term Approach, Revision 2.

The Committee requests to review this document.

CONTACT:

L. Burkhart, ACRS 301-287-3775 February 13, 2025 Signed by Bailey, Marissa on 02/13/25

6.

Xe-100 Licensing Topical Report, Reactor Core Design Methods and Analysis, Revision 1. The Committee does not request to review this document at this time due to the topical reports preliminary nature and lack of a verification, validation, and uncertainty quantification assessment. The Committee may request to review this document when additional safety-relevant information becomes available.

7.

Xe-100 Licensing Topical Report, Training Programs Methodology, Revision 3. The Committee does not request to review this document.

cc:

T. Herrera, SECY D. Lewis, OEDO J. Martin, OEDO C. Araguas, RES M. Rahimi, RES M. Eudy, RES

SUBJECT:

FEBRUARY 2025 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS) FULL COMMITTEE MEETING - TOPICAL REPORTS Accession No: ML25043A112 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 2/12/2025 2/12/2025 2/13/2025 OFFICIAL RECORD COPY February 13, 2025