M180187, GE-Hitachi Nuclear Energy Americas, LLC - ABWR Design Certification Annual 10 CFR 50.46 Report for 2018
| ML18302A023 | |
| Person / Time | |
|---|---|
| Site: | 05200001, 05200045 |
| Issue date: | 10/29/2018 |
| From: | Michelle Catts GE-Hitachi Nuclear Energy Americas |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| M180187 | |
| Download: ML18302A023 (4) | |
Text
GE Hitachi Nuclear Energy Michelle P. Catts Senior Vice President Regulatory Affairs 3901 Castle Hayne Road P.O. Box 780 M/C A-18 Wilmington, NC 28402 USA T 910 200-9836 Michelle.Catts@ge.com M180187 Dockets52-001 and 52-045 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix A October 29, 2018 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ABWR Design Certification Annual 10 CFR 50.46 Report for 2018
Reference:
- 1. Letter, J. G. Head (GEH) to Document Control Desk (NRC), M170240, ABWR Design Certification Annual 10 CFR 50.46 Report for 2017, October 10, 2017 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 2018 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.
Unlike the report for 2017 (Reference 1), 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 October 1, 2018. This was done in response to an NRC audit conducted at the GEH site August 13-16, 2018.
By this letter, GEH also notifies the licensee, Nuclear Innovation North America LLC, for the South Texas Project (STP), Units 3 and 4, in accordance with 10 CFR 50.46(a)(3)(iii), because the STP Unit 3 and 4 licenses reference the ABWR Design Certification.
M180187 Page 2 of 2 October 29, 2018 Please contact me if you have any questions regarding this information.
Sincerely, Michelle P. Catts Senior Vice President, Regulatory Affairs Commitments: No additional commitments are made.
Enclosure:
- 1. ABWR Design Certification 10 CFR 50.46 Annual Report - 2018 cc: A. Muniz, NRC S. Head, STP DBR-0033158 R2
Enclosure 1 M180187 ABWR Design Certification 10 CFR 50.46 Annual Report - 2018
M180187 Page 1 of 1 Advanced Boiling Water Reactor Design Certification 2018 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: 2018 In response to the NRC audit conducted at the GEH site August 13-16, 2018, the ABWR 2018 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 October 1, 2018.
Evaluation Model: SAFER/GESTR (SAFER03)
Net PCT Absolute LBPCT Effect PCT Effect Analysis of Record Licensing Basis PCT 1,149°F Prior 10 CFR 50.46 Changes or Error Corrections A.
- Previous Years (itemized below) 1999-02 CCFL in Upper Tie Plate, Pre-GE11 + 25 2001-02 Time Step Change for Convergence + 25 2001-04 Steam Condensed by ECCS Injection + 10 2002-03 GESTR Input File Interpolation 0 2003-01 SAFER Level/Volume Table + 10 2003-03 Steam Separator Pressure Drop +5 2014-01: SAFER04A E4 Revision - Code 0
Changes of Neutral Impact 2014-02: SAFER04A E4 Revision - Mass 0
Non-Conservatism 2014-04: SAFER04A E4 Revision - Lower 0
Plenum CCFL Restriction PCT = + 75°F + 75°F Prior 10 CFR 50.46 Changes or Error Corrections B.
- This Year (itemized below):
None 0 PCT = + 0°F + 0°F Cumulative and Absolute Sum of 10 CFR 50.46 C. PCT = + 75°F + 75°F Changes Projected Licensing Basis PCT Based on These 1,224°F Changes Most Recent Previous Report (2017): Letter, J. G. Head (GEH) to Document Control Desk (NRC),
ABWR Design Certification Annual 10 CFR 50.46 Report for 2017, M170240, October 10, 2017.