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DTE Energy One Energy Plaza, Detroit, Ml 48226-1279 DTE 10 CFR 52.3 10 CFR 50.46 (a)(3)(ii)
November "18, 2019 N RC3-19-0003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001-
Reference:
- 1) Fermi 3 NRC Docket No.52-033 NRC License No. NPF-95
- 2) Letter from Michelle P. Catts (GE Hitachi Nuclear Energy) to USN RC, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2019," dated October 9, 2019
Subject:
DTE Electric Company 10 CFR 50.46 Annual Report of Fenni 3 Emergency Core Cooling System (ECCS) Model Changes By reference 2, GE Hitachi reported 2 errors in the ECCS model for the Certified ESBWR design; however, the correction of these errors had no impact on the calculated Peak Clad Temperature (PCT). The ECCS evaluation model changes are applicable to the Fermi 3 COL.
Therefore, in accordance with 10 CFR 50.46 (a)(3)(ii), DTE is reporting these changes on the Fermi 3 docket. contains the 2019 10 CFR 50.46 report GE Hitachi submitted in reference 2.
If you have any questions, or need additional infom1ation, please contact me at (313) 235-0443.
Sincerely, Michael K. Brandon, Manager Nuclear Development - Licensing DTE Electric Company
USNRC NRC3-19-0003 Page2 Cc: George Wunder, NRC Fenni 3 Project Manager Fanni 2 Resident Inspector Ho Nieh, Director, NRC Office of Nuclear Reactor Regulation NRC Region Ill Regional Administrator NRC Region II Regional Administrator Supervisor, Electric Operators, Michigan Public Service Commission Michigan Department of Environmental Quality OWMRP, Radiological Protection Section Craig D. Sly, Dominion Energy, Inc.
Lisa Schichlein, General Electric Art Zaremba, Duke Energy Steve Franzone, Florida Power and Light to NRC3-19-0003 Page 1 Enclosure 1 to NRCJ-19-0003 ESBWR Design Certification Annual 10 CFR 50.46 Report for 2019 (4 pages)
GE Hitachi Nuclear Energy
- HITACHI Michelle P. Catts
~nlor Vice President Regulatory Affairs 3901 Castle Hayne Road P.O. Box 780 M/C_A-18 .
Wilmington, NC 28402 USA T 910 200-9836 M\chefle,Catts@ae.com M190171 Docket 52-010 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix E October 9, 2019 US Nuclear Regulatory Commission Document Control Desk
- - . Washfngton, DC 20555-0001
Subject:
ESBWR Design Certification Annual 10 CFR 60.46 Report for 2019
Reference:
- 1. Letter, M. P. Catts (GEH)-to Document Control Desk (NRC), M190165, ESBWR Design
_Certificati_on Annual 10 CFR 50.46 Report for 2019*, October 8, 2019.
Enclo.sure 1 is the 2019 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. This is an upd.ate to the previous report (Reference 1), due to th~
omission of two error notifications_ that were submitted during the last reporting perio_d. Th~
notifications. were zero-degree effects on the PCT calculation, *so, ajthough these evaluation model errors are corrected, there will be no change to, any reported analysis results.
- By this. letter, GEH. also nottfies 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 lice'nses for these units reference the _ESBWR Design Certification. ._ -
Please contact me if you have any questions regarding this information.
M190171 Page 2 of 2 October 9, 2019 Sincerely, Michelle P. Catts Senior Vice President, Regulatory Affairs Commitments: No additional commitments are made.
Enclosure:
- 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2019 cc: J. Colaccino, NRC M. Brandon, DTE R. Westmoreland, DTE D. Aitken, Dominion C. Sly, Dominion DBR-0033424 R4
Enclosure 1 M190171 ESBWR Design Certification 10 CFR 50.46 Annual Report- 2019
M190171 Page 1 of 1 ESBWR Design Certification 2019 Annual Report Under 10 CFR 50.46(a)(3)(111)
Emergency Core Cooling System Model Plant Name: ESBWR Design Certification (Docket 52-010; 10 CFR Part 52, Appendix E)
Utility Name: GE Hitachi (as applicant for the ESBWR Design Certification)
Reporting Year. 2019*
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
- Previous years LiPCT = +/- 0°F + 0°F Prior 10 CFR 50.46 Changes or Error Corrections B.
- This year (itemized below):
LiPCT = +/- 0°F + 0°F 2019 TRACG Channel Inlet Subcooling Calculation 0 2019 TRACG Radiation Heat Transfer Calculation 0 C. Absolute Sum of 10 CFR 50.46 Changes LiPCT = + 0°F + 0°F Projected LBPCT based on these changes 600°F
- The reporting period is 10/29/2018 through 09/30/2019. 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 because this analysis is less than 2,200°F.
Most Recent Previous Report (2019): Letter, M. P. Catts (GEH) to Document Control Desk (NRC),
M190165, ESBWR Design Certification Annual 10 CFR 50.46 Report for 2019, October 8, 2019.