ML20143A090

Korea Hydro & Nuclear Power Co, Ltd., 10 CFR 50.46 Annual Report for the APR1400 Standard Plant Design

ML20143A090
Person / Time
Site:	05200046
Issue date:	05/13/2020
From:	Yeon Kim Korea Hydro & Nuclear Power Co, Ltd
To:	William Ward Document Control Desk, Office of Nuclear Reactor Regulation
References
MKD/NW-20-0004L
Download: ML20143A090 (3)

Text

- 15;!:t~~ NUCLEAR POWER CO.* LTD 70-1312-gil, Yuseong-daero, Yuseong-gu, Daejeon, 305-343, KOREA Tel: +82-42-870-5000 / Fax: +82-42-870-5449 http://www.khnp.co.kr May 13, 2020 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention:* Mr. William Ward Docket No.52-046 Division of New Reactor Licensing MKD/NW-20-0004L

Subject:

10 CFR 50.46 Annual Report for the APR1400 Standard Plant Design

References:

APRl 400 Standard Design Certification Application Design Control Document, Revision 3, Tier 1 and Tier 2, dated August 18, 2018

• Pursuant to 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Reactors," Korea Hydro and Nuclear Power (KHNP) is submitting the attached report to document any emergency core cooling system (ECCS) evaluation model changes or errors that affect the temperature calculation for the APR1400 Standard Plant Design. There have been no changes or errors that have occurred for the ECCS model for the APR1400 Standard Plant Design since submitted in letter MKD/NW-18-0119L, dated August 13, 2018.

The information included in this letter is generic and is expected to apply to all COL applications referencing the APR1400 Design Certification Application. By copy of this letter, prospective COL Applicants are hereby notified of any changes or errors in the APRl 400 Standard Design PCT as required by 10 CFR 50.46(a)(3)(iii).

If additional information or clarification is required, please contact Lee Jong-Sul, Director of KHNP Washington DC Center at surry0123@khnp.co.kr or 703-790-4625.

Sincerely, Yun-ho Kim Project Manager, Central Research Institute Korea Hydro & Nuclear Power Co., Ltd.

Enclosure:

APR1400 Design Certification 10 CFR 50.46 Annual Report - 2019 (Non-Proprietary)

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- E;H~~ NUCLEAR POWER co.. LTD Enclosure APR1400 Design Certification 10 CPR 50.46 Annual Report - 2019 (Non-Proprietary)

May 13, 2020

10CFR50.46 Annual Report for the APRI 400 Design Certification Plant Name: APRl 400 Design Certification (Docket 52-046; 10 CFR Part 52, Appendix F)

Reporting Year: 2020 Evaluation Model: CAREM Net PCT Absolute LBPCT Effect PCT Effect Analysis of Record Licensing Basis 1,886 °F PCT (LBPCT), with prior updates (l,030°C)

Prior 10 CFT 50.46 Changes or Error oop A. .6.PCT= +/-0°F Corrections - This year Absolute Sum of 10 CFR 50.46 +/- oop B. .6.PCT= +/-0°F Changes Projected LBPCT based on these 1,886 °F changes The sum of the .6.PCT from the most recent analysis using an acceptable evaluation model and the estimates of .6.PCT impact for changes and errors identified since this analysis is less than 2200

°F (1204 °C).