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{{#Wiki_filter: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 M230132 | {{#Wiki_filter: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 | |||
M230132 Docket 52-010 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix E October 4, 2023 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 | |||
==Subject:== | ==Subject:== | ||
ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023 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, | ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023 | ||
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 2022 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. | 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. | Please contact me if you have any questions regarding this information. | ||
M230132 | Sincerely, | ||
Kent Halac | |||
Project 710 / Docket No. 99902024 | |||
M230132 Page 2 of 2 October 4, 2023 | |||
Commitments: No additional commitments are made. | |||
==Enclosure:== | ==Enclosure:== | ||
: 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2023 cc: | : 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2023 | ||
cc: E. Lenning, NRC J. Colaccino, NRC M. Brandon, DTE R. Westmoreland, DTE D. Aitken, Dominion C. Sly, Dominion S. Sinah DBR-0033424 R8 | |||
Enclosure 1 | |||
M230132 | |||
ESBWR Design Certification 10 CFR 50.46 Annual Report - 2023 | |||
M230132 Page 1 of 1 | |||
ESBWR Design Certification | |||
2023 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: 2023* | Reporting Year: 2023* | ||
Evaluation Model: TRACG Net PCT | |||
Evaluation Model: TRACG LBPCT Net PCT Absolute Effect PCT Effect | |||
2021-09 -TRACG04P Version 4.2.76.1 | 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 | |||
2021-09 -TRACG04P Version 4.2.76.1 0 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 10/4/2022 through 10/4/2023. | * The reporting period is 10/4/2022 through 10/4/2023. | ||
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. | 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), | Most Recent Previous Report (2022): Letter, M. P. Catts (GEH) to Document Control Desk (NRC), | ||
M220129, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2022," October 4, 2022.}} | M220129, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2022," October 4, 2022.}} |
Revision as of 10:50, 13 November 2024
ML23277A170 | |
Person / Time | |
---|---|
Site: | PROJ0710, 99902024, 05200010 |
Issue date: | 10/04/2023 |
From: | Halac K GE-Hitachi Nuclear Energy Americas |
To: | Office of Nuclear Reactor Regulation, Document Control Desk |
References | |
M230132 | |
Download: ML23277A170 (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
M230132 Docket 52-010 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix E October 4, 2023 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023
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 2022 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
M230132 Page 2 of 2 October 4, 2023
Commitments: No additional commitments are made.
Enclosure:
- 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2023
cc: E. Lenning, NRC J. Colaccino, NRC M. Brandon, DTE R. Westmoreland, DTE D. Aitken, Dominion C. Sly, Dominion S. Sinah DBR-0033424 R8
Enclosure 1
M230132
ESBWR Design Certification 10 CFR 50.46 Annual Report - 2023
M230132 Page 1 of 1
ESBWR Design Certification
2023 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: 2023*
Evaluation Model: TRACG LBPCT Net PCT Absolute Effect 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
2021-09 -TRACG04P Version 4.2.76.1 0 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 10/4/2022 through 10/4/2023.
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),
M220129, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2022," October 4, 2022.