ML23277A169

GE-Hitachi Nuclear Energy Americas, LLC, ABWR Design Certification Annual 10 CFR 50.46 Report for 2023

ML23277A169
Person / Time
Site:	05200001, PROJ0710, 99902024, 05200045
Issue date:	10/04/2023
From:	Halac K GE-Hitachi Nuclear Energy Americas
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
M230131
Download: ML23277A169 (1)

Text

GE Hitachi Nuclear Energy Kent Halac, PE Senior Engineer, Regulatory Affairs P.O. Box 780, M/C A60 Wilmington, NC 28401 USA T 910 819-5307 Kent.Halac@ge.com M230131 Dockets52-001 and 52-045 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix A October 4, 2023 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

ABWR Design Certification Annual 10 CFR 50.46 Report for 2023 GE Hitachi Nuclear Energy (GEH), as the applicant for the ABWR Design Certification (10 CFR Part 52, Appendix A) and its renewal, submits this annual report under 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Reactors."

Specifically, Enclosure 1 is the 2023 annual report for the ABWR Design Certification for emergency core cooling system (ECCS) evaluation model changes or errors that affect the peak cladding temperature (PCT) calculation.

This annual report identifies changes, errors, and errors in the application of the ECCS-Loss-of-Coolant Accident (LOCA) evaluation model from the date of issuance of the ABWR design certification in 1997 (per 10 CFR Part 52 Appendix A) to October 4, 2023.

Please contact me if you have any questions regarding this information.

Sincerely, Kent Halac Project 710 / Docket No. 99902024

M230131 Page 2 of 2 October 4, 2023 Commitments: No additional commitments are made.

Enclosure:

1. ABWR Design Certification 10 CFR 50.46 Annual Report - 2023 cc: E. Lenning, NRC A. Muniz, NRC DBR-0033158 R7

Enclosure 1 M230131 ABWR Design Certification 10 CFR 50.46 Annual Report - 2023

M230131 Page 1 of 1 Advanced Boiling Water Reactor Design Certification 2023 Annual Report Under 10 CFR 50.46(a)(3)(iii)

Emergency Core Cooling System Model Plant Name: Advanced Boiling Water Reactor (ABWR) Design Certification (Docket 52-001; 10 CFR Part 52, Appendix A) and Renewal Application (Docket 52-045)

Utility Name: GE Hitachi (as holder of the final ABWR Design Certification)

Reporting Year: 2023 This ABWR 2023 annual report identifies changes, errors, and errors in the application of the ECCS-LOCA evaluation model from the date of issuance of the ABWR design certification in 1997 (per 10 CFR Part 52 Appendix A) to October 4, 2023.

Evaluation Model: SAFER/GESTR (SAFER03)

Net PCT Absolute LBPCT Effect PCT Effect Analysis of Record Licensing Basis PCT 1,149°F Prior 10 CFR 50.46 Changes or Error Corrections A.

- Previous Years (itemized below)

PCT = + 75°F + 75°F Prior 10 CFR 50.46 Changes or Error Corrections B.

- Recent Year (itemized below):

None PCT = + 0°F + 0°F Cumulative and Absolute Sum of 10 CFR 50.46 C. PCT = + 75°F + 75°F Changes Projected Licensing Basis PCT Based on These 1,224°F Changes The sum of the peak cladding temperature (PCT) from the most recent analysis using an acceptable evaluation model and the estimates of PCT effect for changes and errors identified since this analysis is less than 2,200°F.

Most Recent Previous Report (2022): Letter, M. P. Catts (GEH) to Document Control Desk (NRC), ABWR Design Certification Annual 10 CFR 50.46 Report for 2022, M220128, October 4, 2022.