ML24043A227
| ML24043A227 | |
| Person / Time | |
|---|---|
| Site: | 05200017 |
| Issue date: | 02/12/2024 |
| From: | James Holloway Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NA3-24-001 | |
| Download: ML24043A227 (1) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGTI'HA 23261 February 12, 2024 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3 Serial No.:
NA3-24-001 NRA/JH RO Docket No.: 52-017 License No.: NPF-103 REPORT OF 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES In reference 1, General Electric Hitachi Nuclear Energy (GEH) submitted one error notification to the ECCS model for the Certified Economic Simplified Boiling Water Reactor (ESBWR) Design. The evaluation model error was corrected, and because the notification had a zero-degree effect on the peak cladding temperature calculation, there was no change to any previously reported analysis results.
The ECCS evaluation model change conclusion provided by GEH is applicable to the North Anna Unit 3 Combined Operating License. Therefore, in accordance with 10 CFR 50.46 (a)(3)(ii), this report is being submitted on the North Anna Unit 3 docket. provides the Report of Changes in the GEH ECCS Evaluation Model. provides the 2023 Annual Reporting of 10 CFR 50.46 Margin Utilization for North Anna Unit 3.
If you have any questions regarding this submittal, please contact Julie Hough at (804) 273-3586.
Very truly yours, James E. Holloway Vice President - Nuclear Engineering and Fleet Support Commitments made in this letter: None
Reference:
- 1.
Letter M230132, Rev. 1, from GEH (Kent Halac) to U.S. Nuclear Regulatory Commission, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2023," dated October 10, 2023 Attachments:
- 1.
Report of Changes in GEH ECCS Evaluation Model
- 2.
2023 Annual Reporting of 10 CFR 50.46 Margin Utilization
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. Rolband, VDEQ M. Nichol, NEI M. K. Brandon, DTE R. Westmoreland, DTE Serial No. NA3-24-001 Docket No.52-017 Page 2 of 2 Serial No. NA3-24-001 Docket No.52-017 2023 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS)
MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 REPORT OF CHANGES IN GEH ECCS EVALUATION MODEL VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3
North Anna Unit 3 REPORT OF CHANGES IN GEH ECCS EVALUATION MODEL Serial No. NA3-24-001 Docket No.52-017, Page 1 of 1 General Electric Hitachi Nuclear Energy (GEH) identified the following change and error applicable to the ECCS Loss of Coolant Accident (LOCA) TRACG Evaluation Model for North Anna Unit 3 during 2023.
2023-03: Error in TRACG Default Inputs for 3-Stage Steam Separator Two TRACG04P default values for the 3-stage steam separator are not consistent with actual 3-stage steam separator geometry. Specifically, the two values are the axial distance between the exit of the first discharge passage and the swirl vane exit, and the length of the separating barrel. The ESBWR ECCS-LOCA analyses are affected. The ESBWR ECCS-LOCA analysis shows there is no fuel heat up during LOCA. Therefore, the error in modeling is estimated to have a O °F impact.
Serial No. NA3-24-001 Docket No.52-017 2023 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS)
MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2023 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3
Serial No. NA3-24-001 Docket No.52-017, Page 1 of 1 Report of Changes in GEH ECCS Evaluation Model Plant Name North Anna Unit 3 (Docket 52-017)
Utility Name VirQinia Electric and Power Company ReportinQ Year: 2023*
Evaluation Model: TRACG Vendor: GE Hitachi LBPCT Net PCT Absolute Effect PCT Effect Analysis of Record Licensing Basis PCT 600°F
{LBPCT), with prior updates I.
Prior 10 CFR 50.46 Changes or Error Corrections 2019 TRACG Channel Inlet
~PCT=
+ 0°F
+ 0°F Subcooling Calculation 2019 TRACG Radiation Heat
~PCT=
+ 0°F
+ 0°F Transfer Calculation 2017 Fuel Rod Plenum
~PCT=
+ 0°F
+ 0°F Temperature Update 2021 Non-condensable Gas
~PCT=
+ 0°F
+ 0°F Error in Zero Cell Side Branch
- 11.
10 CFR 50.46 Changes or Error Corrections for 2023 2023 Error in TRACG
~PCT=
+ 0°F
+ 0°F Default Inputs for 3-Stage Steam Separator Sum of 10 CFR 50.46 Changes
~PCT=
+ 0°F
+ 0°F Projected LBPCT based on these 600°F chanQes
- The reporting period is 10/4/2022 through 10/10/2023.