|
|---|
Category:Annual Operating Report
[Table view]
Category:Letter
MONTHYEARML24270A0642024-09-26026 September 2024
GE-Hitachi Nuclear Energy Americas, LLC - ESBWR Design Certification Annual 10 CFR 50.46 Report for 2024
ML24270A0652024-09-26026 September 2024
ABWR Design Certification Annual 10 CFR 50.46 Report for 2024
ML23283A0892023-10-10010 October 2023
ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023
ML23277A1692023-10-0404 October 2023
GE-Hitachi Nuclear Energy Americas, LLC, ABWR Design Certification Annual 10 CFR 50.46 Report for 2023
ML23277A1702023-10-0404 October 2023
GE-Hitachi Nuclear Energy Americas, LLC, ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023
ML22347A2842022-12-0808 December 2022
GE-Hitachi Nuclear Energy Americas, LLC, Accepted Version of NEDO-11209-A Revision 17, GE Hitachi Nuclear Energy Quality Assurance Program Description
ML21320A1902021-11-16016 November 2021
Pre-Application Presentation Slides for Amendment to NEDO-11209-A, Rev. 16, GE Hitachi Nuclear Energy Quality Assurance Program Description
ML21244A3492021-09-0101 September 2021
GE Hitachi Nuclear Energy - ESBWR Design Certification Annual 10 CFR 50.46 Report for 2021
ML20269A1832020-09-25025 September 2020
GE Hitachi Nuclear Energy - ESBWR Design Certification 10 CFR 50.46 Annual Report - 2020, Emergency Core Cooling System Model
ML20197A2692020-07-15015 July 2020
Pre-application Presentation Slides for Amendment to NEDO-11209-A Revision 15, GE Hitachi Nuclear Energy Quality Assurance Program Description
ML20184A1582020-07-14014 July 2020
Verification of Accepted Version of NEDO-11209 Revision 15, GE Hitachi Nuclear Energy Quality Assurance Program Description
ML20093B4532020-04-0202 April 2020
GE-Hitachi Nuclear Energy Americas, LLC - Revision of the GE Model No. 2000 (Docket No. 71-9228) to Clarify Irradiated Hardware Content and Update the Quality Assurance Program References
ML19242D0982019-09-19019 September 2019
General Electric Hitachi Nuclear Energy Americas, LLC, Request for Withholding Information from Public Disclosure
ML19242D6962019-09-19019 September 2019
Verification of NEDC-33173P Supplement 6 Revision 1, Licensing Topical Report Applicability of GE Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Ratio (SLMCPR) Penalty
ML19199A1822019-08-0808 August 2019
Final Safety Evaluation for NEDC-33173P Supplement 6 - Applicability of GE Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Raito (SLMCPR) Penalty
ML19094A9182019-04-25025 April 2019
General Electric Hitachi Nuclear Energy Americas, LLC, Request for Withholding Information from Public Disclosure
ML19094A0582019-04-25025 April 2019
Verification of GE Hitachi Topical Report NEDC-33173 Supplement 5p-A, Revision 1, Applicability of General Electric Methods to Expanded Operating Domains - Supplement for GNF3 Fuel
ML19071A1012019-03-26026 March 2019
Draft Safety Evaluation for NEDC-33173p Supplement 6 - Applicability of General Electric Methods to Expanded Operating Domains - Removal of the Safety Limit Minimum Critical Power Ratio Penalty
ML19074A0542019-03-21021 March 2019
Imltr Supplement 5 Final SE Non-Proprietary
ML19017A0432019-03-0505 March 2019
GE Hitachi Nuclear Energy Americas, Llc, Request for Withholding Information from Public Disclosure
ML19016A4072019-03-0505 March 2019
GE Hitachi Nuclear Energy Americas, LLC, Request for Withholding Information from Public Disclosure
ML19002A3762019-02-0505 February 2019
Draft Safety Evaluation for NEDC-33173p Supplement 5 and Applicability of GE Methods to Expanded Operating Domains and Supplement for GNF3 Fuel
ML18155A2102018-06-22022 June 2018
Verification of GE Hitachi Topical Report NEDE-33005P-A, Revision 2 Tracg Application for Emergency Core Cooling Systems/Loss-of Coolant Accident Analysis for BWR/2-6
ML18129A0242018-05-11011 May 2018
Final Safety Evaluation for Licensing Topical Report Nede 33005P-A / NEDO-33005-A, Tracg Application for Emergency Core Cooling Systems / Loss-Of-Coolant-Accident Analysis for BWR/2-6 Satisfaction of Limitation 10.7
ML18117A3112018-04-27027 April 2018
Draft Safety Evaluation for Licensing Topical Report NEDE-33005P-A / NEDO-33005-A, Tracg Application for Emergency Core Cooling Systems / Loss-of-Coolant-Accident Analysis for BWR/2-6 Satisfaction of Limitation 10.7
ML18078A5872018-04-10010 April 2018
Satisfaction of TRACG-LOCA Limitation 10.7 Draft SE Cover Letter
ML18046A6392018-03-0606 March 2018
Proprietary Determination Letter for TRACG-LOCA Satisfaction of Limitation 10.7 RAI Response
ML18016A1142018-01-30030 January 2018
Approval of Proposed Alternate Reviewing Officials for the General Electric Vallecitos Nuclear Center
ML18002A4322018-01-10010 January 2018
Final SE for Amendment to NEDO-11209 Revision 13 GE QAPD
ML17347B1992018-01-0909 January 2018
GNF2 Compliance Report Proprietary Determination Letter
ML17342A1012018-01-0909 January 2018
Proprietary Determination Letter for Nsf Annual Experience Summary Report
ML17332A6012018-01-0909 January 2018
Proprietary Determination Letter for NEDC-33840P-A, Prime Model for Transient Analysis
ML17332A2962018-01-0505 January 2018
Final Safety Evaluation for Global Nuclear Fuel - Americas, LLC, Proposed Amendment 44 to NEDE-24011-P-A-24
ML17341A9432018-01-0505 January 2018
Verification Letter for the Approved Version of NEDC-33840P (Prime)
ML14062A0442014-03-0303 March 2014
Additional Utility Support for NEDE-33766P, GEH Simplified Stability Solution (GS3)
ML1032704642010-12-28028 December 2010
Letter Transmitting Final Safety Evaluation of GE Hitachi Nuclear Energy (GEH) Topical Report NEDC-33173P, Supplement 3, Applicability of GE Methods to Expanded Operating Domains - Supplement for GNF2 Fuel
ML1036305742010-12-22022 December 2010
Response to Us NRC Regulatory Issue Summary 2010-10 Process for Scheduling Acceptance Reviews of New Reactor Licensing Applications and Process for Determining Budget Needs for Fiscal Year 2013
ML0717106152007-07-18018 July 2007
Potential Adverse Flow Effects in Nuclear Power Plants
ML0610803382006-04-14014 April 2006
Withholding Letter to G Strambach, GE, GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point Nuclear Station 2 and Perry Nuclear Power Plant (Mfn 06-089)
ML0608804422006-03-24024 March 2006
GE Evaluation of OPRM Performance During Instability Events at Nine Mile Point, Unit 2 and Perry Nuclear Power Plant
ML0500600862004-11-12012 November 2004
Content of VY Steam Dryer Audit Report, Non-Proprietary
ML0416204602004-05-0707 May 2004
Supporting Lattice Information - Mellla+ RAI AOO 6
2024-09-26
[Table view] |
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 Net PCT Absolute LBPCT Effect PCT Effect Analysis of Record Licensing Basis PCT 600°F (LBPCT), with prior updates Prior 10 CFR 50.46 Changes or Error Corrections A. PCT = +/- 0°F + 0°F
- Previous years Prior 10 CFR 50.46 Changes or Error Corrections B. PCT = +/- 0°F + 0°F
- This year (itemized below):
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.