ML19281C461
| ML19281C461 | |
| Person / Time | |
|---|---|
| Site: | 05200001, 05200045 |
| Issue date: | 10/08/2019 |
| From: | Michelle Catts GE Hitachi Nuclear Energy |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| M190164 | |
| Download: ML19281C461 (5) | |
Text
M190164 Dockets52-001 and 52-045 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix A October 8, 2019 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ABWR Design Certification Annual 10 CFR 50.46 Report for 2019
Reference:
- 1. Letter, M.P. Catts (GEH) to Document Control Desk (NRC), M180187, ABWR Design Certification Annual 10 CFR 50.46 Report for 2018, October 29, 2018 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 2019 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 October 1, 2019.
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
M190164 Page 2 of 2 October 8, 2019
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 - 2019 cc:
A. Muniz, NRC S. Head, STP DBR-0033158 R3
M190164 ABWR Design Certification 10 CFR 50.46 Annual Report - 2019
M190164 Page 1 of 2
Advanced Boiling Water Reactor Design Certification 2019 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: 2019 This ABWR 2019 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, 2019.
Evaluation Model: SAFER/GESTR (SAFER03)
LBPCT Net PCT Effect Absolute PCT Effect Analysis of Record Licensing Basis PCT 1,149°F A.
Prior 10 CFR 50.46 Changes or Error Corrections
- 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 Changes of Neutral Impact 0
2014-02: SAFER04A E4 Revision - Mass Non-Conservatism 0
2014-04: SAFER04A E4 Revision - Lower Plenum CCFL Restriction 0
PCT =
+ 75°F
+ 75°F B.
Prior 10 CFR 50.46 Changes or Error Corrections
- This Year (itemized below):
None 0
PCT =
+ 0°F
+ 0°F C.
Cumulative and Absolute Sum of 10 CFR 50.46 Changes PCT =
+ 75°F
+ 75°F Projected Licensing Basis PCT Based on These Changes 1,224°F
M190164 Page 2 of 2
Most Recent Previous Report (2018): Letter, M. P. Catts (GEH) to Document Control Desk (NRC), ABWR Design Certification Annual 10 CFR 50.46 Report for 2018, M180187, October 29, 2018.