ML25280A007
| ML25280A007 | |
| Person / Time | |
|---|---|
| Site: | PROJ0710, 99902024, 05200010 |
| Issue date: | 10/07/2025 |
| From: | Halac K GE Hitachi Nuclear Energy |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| M250336 | |
| Download: ML25280A007 (1) | |
Text
M250336 Docket 52-010 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix E October 7, 2025 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ESBWR Design Certification Annual 10 CFR 50.46 Report for 2025 GE Hitachi Nuclear Energy (GEH), as the applicant for the ESBWR Design Certification (10 CFR Part 52, Appendix E), submits this annual report under 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Reactors." Specifically, is the 2025 annual report for the ESBWR Design Certification for emergency core cooling system (ECCS) evaluation model changes or errors that affect the peak cladding temperature (PCT) calculation. There is no change to any reported analysis results.
By this letter, GEH also notifies the licensees, DTE Electric Company for Enrico Fermi Nuclear Plant Unit 3, and Dominion Virginia Power for North Anna Unit 3, in accordance with 10 CFR 50.46(a)(3)(iii), because the licenses for these units reference the ESBWR Design Certification.
Please contact me if you have any questions regarding this information.
Sincerely, Kent Halac Project 710 / Docket No. 99902024 Commitments: No additional commitments are made.
GE Vernova Hitachi Nuclear Energy Kent Halac Senior Engineer, Regulatory Affairs P.O. Box 780, M/C A70 Wilmington, NC 28401 USA T 910 819-5307 Kent.Halac@GEVernova.US
M250336 Page 2 of 2 October 7, 2025
Enclosure:
- 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2025 cc:
J. Colaccino, NRC E. Lenning, NRC J. Beste-Walz, DTE E. Frank, DTE S. Franzone, DTE S. Sobas, DTE J. Hough, Dominion S. Sinah, Dominion DBR-0033424 R11
M250336 ESBWR Design Certification 10 CFR 50.46 Annual Report - 2025
M250336 Page 1 of 1 ESBWR Design Certification 2025 Annual Report Under 10 CFR 50.46(a)(3)(iii)
Emergency Core Cooling System Model Plant Name:
Economic Simplified Boiling Water Reactor (ESBWR)
Utility Name:
GE Vernova - Hitachi (as holder of the Final Design Certification for plant)
Reporting Year: 2025*
Evaluation Model: TRACG PCT Net PCT Effect Absolute PCT Effect Analysis of Record Licensing Basis PCT 600°F A.
Prior 10 CFR 50.46 Changes or Error Corrections
- Previous years PCT =
+/- 0°F
+ 0°F B.
Prior 10 CFR 50.46 Changes or Error Corrections
- This year (itemized below):
PCT =
+/- 0°F
+ 0°F (none)
C.
Absolute Sum of 10 CFR 50.46 Changes PCT =
+ 0°F
+ 0°F Projected PCT based on these changes 600°F
- The reporting period is 9/26/2024 through 10/7/2025.
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 (2024): Letter, K. Halac (GEH) to Document Control Desk (NRC),
M240210, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2024,"
September 24, 2024.