ML18053A130
| ML18053A130 | |
| Person / Time | |
|---|---|
| Site: | 05200017 |
| Issue date: | 02/12/2018 |
| From: | Mark D. Sartain Dominion Energy Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| NA3-18-001 | |
| Download: ML18053A130 (7) | |
Text
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Dominion Energy Services, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com P Dominion j J Energy February 12, 2018 U. S. Nuclear Regulatory Commission I
Serial No.: NA3-18-001 Attention: Document Control Desk NRA/DEA RO Washington, D. C. 20555 Docket No.: 52-017 License No.:NPF-103 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3 REPORT OF 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES General Electric Hitachi Nuclear Energy (GEH) reported a change to one ECCS model for the Certified Economic Simplified Boiling Water Reactor (ESBWR) Design in letter M170244 from Jerald G. Head (GEH) to U. S. Nuclear Regulatory Commission, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2017," dated October 30, 2017. The ECCS evaluation model change reported by GEH is applicable to the North Anna Unit 3 (NA3) Combined Operating License. Therefore, in accordance with 10 CFR 50.46 (a)(3)(ii), this change is being reported on the NA3 docket.
Attachment 1 provides the 2017 annual 10 CFR 50.46 report submitted by GEH.
If you have any questions regarding this submittal, please contact Ms. Diane E. Aitken at (804) 273-2694.
Very truly yours,
~-
Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support
Attachment:
GEH ESBWR Design Certification Annual 10 CFR 50.46 Report for 2017 Commitments made in this letter: None
Serial No. NA3-18-001 Report of 10 CFR 50.46 ECCS Model Changes Page 2 of 2 cc: (electronic distribution, except where noted)
U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 J. J. Shea, Jr., NRC M. A. Eudy, NRC T. S. Dozier, NRC G. Croon, NRC D. Paylor, VDEQ M. K. Brandon, DTE R. J. Bell, NEI
Serial No. NA3-18-001 Docket No.52-017 Attachment 1 GEH ESBWR DESIGN CERTIFICATION ANNUAL 10 CFR 50.46 REPORT FOR 2017 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3
GE Hitachi Nuclear Energy HITACHI Jerald G. Head Senior Vice Presid~nt, Regulatory Affairs 3901 Castle Hayne Road P.O. Box 780 M/C/ A-18 Wilmington, NC 28402 USA T 910 233 1134 Jerald.Head@ge.com M170244 Docket 52-010 10 CFR 50.46 10 CFR 50.46(a)(3)(iii) 10 CFR Part 52, Appendix E October 30, 2017 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
ESBWR Design Certification Annual 10 CFR 50.46 Report for 2017
Reference:
- 1. Letter, J. G. Head (GEH) to Document Control Desk (NRC), MFN 16-067, ESBWR Standard Plant Design Annual 10 CFR 50.46 Report for 2016, September 23, 2016.
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 2017 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. Since the 2016 report (Reference 1), one evaluation model change has occurred, but it does not result in a change to the PCT values for the ESBWR Design Certification during this period.
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.
M170244 Page 2 of 2 October 30, 2017 Sincerely, Jerald G. Head Senior Vice President, Regulatory Affairs Commitments: No additional commitments are made.
Enclosure:
- 1. ESBWR Design Certification 10 CFR 50.46 Annual Report - 2017 cc: J. Colaccino, NRC M. Brandon, DTE R. Westmoreland, DTE D. Aitken, Dominion C. Sly, Dominion DBR-0033424
Enclosure 1 M170244 ESBWR Design Certification 10 CFR 50.46 Annual Report - 2017
M170244 Page 1 of 1 ESBWR Design Certification 2017 Annual Report Under 10 CFR 50.46(a)(3)(iii)
Emergency Core Cooling System Model Plant Name: ESBWR Design Certification (Docket 52-01 O; 10 CFR Part 52, Appendix E)
Utility Name: LGE Hitachi (as applicant for the ESBWR Design Certification)
Reporting Year: 2017*
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
.1PCT = + 0°F + 0°F Prior 10 CFR 50.46 Changes or Error Corrections B.
- This year (itemized below):
.1PCT = + 0°F + 0°F 2017-02: Fuel Rod Plenum Temperature Update**
L1PCT = + 0°F + 0°F C. Absolute Sum on O CFR 50.46 Changes .1PCT = + 0°F + 0°F Projected LBPCT based on these changes 600°F
- The reporting period is 10/01/2016 through 09/30/2017. The sum of the peak cladding temperature (PCT) from the most recent analysis using an acceptable evaluation model and the estimates of PCT impac; for changes and errors *identified since t~is analysis is less than 2,200°F.
- Removes "getter" as a model commitment going forward for consistency between model and fuel products as installed (0°F impact on PCT).
Most Recent Previous Report (2016): Letter, J. G. Head (GEH) to Document Control Desk (NRC),
MFN 16-067, ESBWR Standard Plant Design Annual 10 CFR 50.46 Report for 2016, September 23, 2016.