ML25055A168

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Report of 10 CFR 50.46 Emergency Core Cooling System (ECCS) Model Changes
ML25055A168
Person / Time
Site: 05200017
Issue date: 02/24/2025
From: James Holloway
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
NA3-25-001
Download: ML25055A168 (1)


Text

VIRGINIA ELECTRIC AND POWER COMPANY RIC HMOND, VIRGINIA 23261 February 24, 2025 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3 Serial No.:

NA3-25-001 NRA/JH RO Docket No.: 52-017 License No.: N PF-103 REPORT OF 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM

{ECCS) MODEL CHANGES In reference 1, General Electric Hitachi Nuclear Energy (GEH) reported no changes to the ECCS model for the Certified Economic Simplified Boiling Water Reactor (ESBWR)

Design. The ECCS evaluation model change conclusion provided 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 report is being submitted on the NA3 docket. provides the Report of Changes in the GEH ECCS Evaluation Model. provides the 2024 Annual Reporting of 10 CFR 50.46 Margin Utilization for NA3.

If you have any questions regarding this submittal, please contact Julie Hough at (804) 273-3586.

Very truly yours, c,,~~ )(m~~;

James E. Holloway

(}

Vice President - Nuclear Engineering and Fleet Support Commitments made in this letter: None

Reference:

Attachments:

1.

Letter M240210, from GEH (Kent Halac) to U. S. Nuclear Regulatory Commission, "ESBWR Design Certification Annual 10 CFR 50.46 Report for 2024," dated September 26, 2024

1. Report of Changes in GEH ECCS Evaluation Model
2. 2024 Annual Reporting of 10 CFR 50.46 Margin Utilization - NA3

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 Serial No. NA3-25-001 Docket No.52-017 Page 2 of 2 Serial No. NA3-25-001 Docket No.52-017 2024 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. NA3-25-001 Docket No.52-017, Page 1 of 1 General Electric Hitachi Nuclear Energy (GEH) identified no changes or errors applicable to the ECCS Loss of Coolant Accident (LOCA) TRACG Evaluation Model for North Anna Unit 3 during 2024.

Serial No. NA3-25-001 Docket No.52-017 2024 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS)

MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2024 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNIT 3

Serial No. NA3-25-001 Docket No.52-017, Page 1 of 1 Report of Changes in GEH ECCS Evaluation Model Plant Name I

North Anna Unit 3 (Docket 52-017)

Utility Name I

Virginia Electric and Power Company Reporting Year: 2024*

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 b..PCT =

+ 0°F

+ 0°F SubcoolinQ Calculation 2019 TRACG Radiation Heat b..PCT =

+ 0°F

+ 0°F Transfer Calculation 2017 Fuel Rod Plenum b..PCT =

+ 0°F

+ 0°F Temperature Update 2021 Non-condensable Gas b..PCT =

+ 0°F

+ 0°F Error in Zero Cell Side Branch

11.

10 CFR 50.46 Changes or Error Corrections for 2024 None b..PCT =

+ 0°F

+ 0°F Sum of 1 O CFR 50.46 Changes b..PCT =

+ 0°F

+ 0°F Projected LBPCT based on these 600°F changes

  • The reporting period is 10/4/2023 through 9/26/2024.