ML24270A064
| ML24270A064 | |
| Person / Time | |
|---|---|
| Site: | 05200010 |
| Issue date: | 09/26/2024 |
| From: | Halac K GE-Hitachi Nuclear Energy Americas |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| M240210 | |
| Download: ML24270A064 (1) | |
Text
M240210 Docket 52-010 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix E September 26, 2024 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ESBWR Design Certification Annual 10 CFR 50.46 Report for 2024 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 2024 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 Hitachi Nuclear Energy Kent Halac Senior Engineer, Regulatory Affairs P.O. Box 780, M/C A60 Wilmington, NC 28401 USA T 910 819-5307 Kent.Halac@ge.com
M240210 Revision 0 Page 2 of 2 September 27, 2024
Enclosure:
- 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2024 cc:
E. Lenning, NRC J. Colaccino, NRC M. Brandon, DTE R. Westmoreland, DTE D. Aitken, Dominion C. Sly, Dominion S. Sinah DBR-0033424 R10
M240210, Revision 0 ESBWR Design Certification 10 CFR 50.46 Annual Report - 2024
M240210, Revision 0 Page 1 of 1
ESBWR Design Certification 2024 Annual Report Under 10 CFR 50.46(a)(3)(iii)
Emergency Core Cooling System Model Plant Name:
ESBWR Design Certification (Docket 52-010; 10 CFR Part 52, Appendix E)
Utility Name:
GE Hitachi (as holder for the ESBWR Final Design Certification)
Reporting Year: 2024*
Evaluation Model: TRACG LBPCT Net PCT Effect Absolute PCT Effect Analysis of Record Licensing Basis PCT (LBPCT), with prior updates 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 2023 Error in TRACG Default Inputs for 3-Stage Steam Separator 0°F C.
Absolute Sum of 10 CFR 50.46 Changes PCT =
+ 0°F
+ 0°F Projected LBPCT based on these changes 600°F
- The reporting period is 10/4/2023 through 9/26/2024.
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 (2023): Letter, K. Halac (GEH) to Document Control Desk (NRC),
M230132, Revision 1, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023,"
October 4, 2023.