View source for M200132, ABWR Design Certification Annual 10 CFR 50.46 Report for 2020

{{Adams
| number = ML20269A184
| issue date = 09/25/2020
| title = ABWR Design Certification Annual 10 CFR 50.46 Report for 2020
| author name = Catts M
| author affiliation = GE Hitachi Nuclear Energy
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05200001, 05200045
| license number = 
| contact person = 
| case reference number = M200132
| document type = Annual Operating Report, Letter type:M
| page count = 4
}}

=Text=
{{#Wiki_filter:GE Hitachi Nuclear Energy Michelle P. Catts Senior Vice President Nuclear Programs 3901 Castle Hayne Road P.O. Box 780 M/C A-18 Wilmington, NC 28402 USA T 910 200-9836 Michelle.Catts@ge.com M200132                                                            Dockets 52-001 and 52-045 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix A September 25, 2020 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

==Subject:==
ABWR Design Certification Annual 10 CFR 50.46 Report for 2020 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 2020 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 September 17, 2020.
Please contact me if you have any questions regarding this information.
Sincerely, Michelle P. Catts Senior Vice President, Nuclear Programs

M200132                                                            Page 2 of 2 September 25, 2020 Commitments: No additional commitments are made.

==Enclosure:==
: 1. ABWR Design Certification 10 CFR 50.46 Annual Report - 2020 cc:      N. Otto, NRC A. Muniz, NRC DBR-0033158 R4

Enclosure 1 M200132 ABWR Design Certification 10 CFR 50.46 Annual Report - 2020

M200132                                                                               Page 1 of 2 Advanced Boiling Water Reactor Design Certification 2020 Annual Report Under 10 CFR 50.46(a)(3)(iii)
Emergency Core Cooling System Model Plant Name:              Advanced Boiling Water Reactor (ABWR) Design Certification (Docket 52-001; 10 CFR Part 52, Appendix A) and Renewal Application (Docket 52-045)
Utility Name:            GE Hitachi (as holder of the final ABWR Design Certification)
Reporting Year: 2020 This ABWR 2020 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 September 17, 2020.
Evaluation Model: SAFER/GESTR (SAFER03)
Net PCT        Absolute LBPCT Effect       PCT Effect Analysis of Record Licensing Basis PCT                1,149&deg;F Prior 10 CFR 50.46 Changes or Error Corrections A.
        - Previous Years (itemized below)
PCT =    + 75&deg;F         + 75&deg;F Prior 10 CFR 50.46 Changes or Error Corrections B.
        - Recent Year (itemized below):
2019-05 SAFER Lower Limit on Differential
                                                                         + 0&deg;F          + 0&deg;F Pressure for Bypass Leakage PCT =     + 0&deg;F          + 0&deg;F Cumulative and Absolute Sum of 10 CFR 50.46 C.                                                           PCT =    + 75&deg;F         + 75&deg;F Changes Projected Licensing Basis PCT Based on These 1,224&deg;F Changes Most Recent Previous Report (2019): Letter, M. P. Catts (GEH) to Document Control Desk (NRC), ABWR Design Certification Annual 10 CFR 50.46 Report for 2019, M190164, October 8, 2019.}}