ML24270A065

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ABWR Design Certification Annual 10 CFR 50.46 Report for 2024
ML24270A065
Person / Time
Site: 05200001, PROJ0710, 99902024, 05200045
Issue date: 09/26/2024
From: Halac K
GE Hitachi Nuclear Energy
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
M240220
Download: ML24270A065 (1)


Text

GE Hitachi Nuclear Energy

Kent Halac Senior Engineer, Regulatory Affairs

3901 Castle Hayne Road P.O. Box 780 M/C A-18 Wilmington, NC 28402 USA

T 910 819-5307 Kent.Halac@ge.com

M240220 Dockets52-001 and 52-045 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix A September 26, 2024

US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

ABWR Design Certification Annual 10 CFR 50.46 Report for 2024

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 2024 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 September 27, 2024.

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

Sincerely,

Kent Halac Senior Engineer, Regulatory Affairs M240220 Page 2 of 2 September 27, 2024

Project 710 Docket No. 99902024 Commitments: No additional commitments are made.

Enclosure:

1. ABWR Design Certification 10 CFR 50.46 Annual Report - 2024

cc: E. Lenning, NRC A. Muniz, NRC DBR-0033158 R8

Enclosure 1

M240220

ABWR Design Certification 10 CFR 50.46 Annual Report - 2024

M240220 Page 1 of 1 Advanced Boiling Water Reactor Design Certification 2024 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: 2024 This ABWR 2024 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 September 26, 2024.

Evaluation Model: SAFER/GESTR (SAFER03)

LBPCT Net PCT Absolute Effect PCT Effect Analysis of Record Licensing Basis PCT 1,149°F

A. Prior 10 CFR 50.46 Changes or Error Corrections - Previous Years (itemized below)

PCT = + 75°F + 75°F

B. Prior 10 CFR 50.46 Changes or Error Corrections - Recent Year (itemized below):

None PCT = + 0°F + 0°F

C. Cumulative and Absolute Sum of 10 CFR 50.46 Changes PCT = + 75°F + 75°F

Projected Licensing Basis PCT Based on These Changes 1,224°F

Most Recent Previous Report (2023): Letter, K. Halac (GEH) to Document Control Desk (NRC),

ABWR Design Certification Annual 10 CFR 50.46 Report for 2023, M230131, October 4, 2023

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