ML25280A006
| ML25280A006 | |
| Person / Time | |
|---|---|
| Site: | 05200001, PROJ0710, 99902024, 05200046 |
| Issue date: | 10/07/2025 |
| From: | Halac K GE Hitachi Nuclear Energy |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| M250337 | |
| Download: ML25280A006 (1) | |
Text
M250337 Dockets52-001 and 52-045 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix A October 7, 2025 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ABWR Design Certification Annual 10 CFR 50.46 Report for 2025 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 2025 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 7, 2025.
Please contact me if you have any questions regarding this information.
Sincerely, Kent Halac Senior Engineer, Regulatory Affairs Project 710 Docket No. 99902024 GE Vernova - Hitachi Nuclear Energy Kent Halac Senior Engineer, Regulatory Affairs 3901 Castle Hayne Road P.O. Box 780 M/C A70 Wilmington, NC 28402 T 910 819-5307 Kent.Halac@GEVernova.US
M250337 Page 2 of 2 October 7, 2025 Commitments: No additional commitments are made.
Enclosure:
- 1. ABWR Design Certification 10 CFR 50.46 Annual Report - 2025 cc:
E. Lenning, NRC A. Muniz, NRC DBR-0033158 R9
M250337 ABWR Design Certification 10 CFR 50.46 Annual Report - 2025
M250337 Page 1 of 1 Advanced Boiling Water Reactor Design Certification 2025 Annual Report Under 10 CFR 50.46(a)(3)(iii)
Emergency Core Cooling System Model Plant Name:
Advanced Boiling Water Reactor (ABWR)
Utility Name:
GE Vernova - Hitachi (as holder of Final Design Certification for plant)
Reporting Year: 2025 This ABWR 2025 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 7, 2025.
Evaluation Model: SAFER/GESTR (SAFER03)
LBPCT Net PCT Effect Absolute 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 (2024): Letter, K. Halac (GEH) to Document Control Desk (NRC),
ABWR Design Certification Annual 10 CFR 50.46 Report for 2024, M240220, September 24, 2024.