W3F1-2021-0019, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2020

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2020

ML21089A397
Person / Time
Site:	Waterford
Issue date:	03/30/2021
From:	Wood P Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2021-0019
Download: ML21089A397 (4)

Text

Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 464-3786 Paul Wood Manager, Regulatory Assurance Waterford 3 10 CFR 50.46 W3F1-2021-0019 March 30, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2020 Waterford Steam Electric Station Unit 3 Docket No. 50-382 Renewed Facility Operating License No. NPF-38 This letter provides the Waterford Steam Electric Station Unit 3 (Waterford 3) 10 CFR 50.46(a)(3)(ii) reporting information pertaining to the Westinghouse Electric Company Emergency Core Cooling System (ECCS) performance Evaluation Models (EMs) for calendar year 2020.

There were no changes, error corrections, or enhancements to the 1999 Evaluation Model (EM) which is used in the Large Break Loss-of-Coolant Accident (LBLOCA)

Emergency Core Cooling Systems (ECCS) performance analysis. In addition, there were no changes, error corrections, or enhancements to the Supplement 2 Evaluation Model (S2M) which is the EM used in the Small Break Loss-of-Coolant Accident (SBLOCA) ECCS performance analysis.

This letter contains no new commitments.

Please contact Paul Wood, Regulatory Assurance Manager, at 504-464-3786 should you have any questions regarding this submittal.

Respectfully, Paul Wood Digitally signed by Paul Wood Date: 2021.03.30 15:22:07 -05'00' PW/llb

W3F1-2021-0019 Page 2

Attachment:

Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2020 cc:

NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford 3 NRC Project Manager - Waterford 3

Attachment to W3F1-2021-0019 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2020

Attachment to W3F1-2021-0019 Page 1 of 1 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2020 There were no changes, error corrections, or enhancements to the 1999 Evaluation Model (EM), which is the EM used in Waterford 3 Large Break Loss-of-Coolant Accident (LBLOCA)

Emergency Core Cooling System (ECCS) performance analysis in calendar year 2020. In addition, there were no changes, error corrections or enhancements to the Supplement 2 Evaluation Model (S2M), which is the EM used in Waterford 3 Small Break Loss-of-Coolant Accident (SBLOCA) ECCS performance analysis in calendar year 2020.

The limiting PCT results for the large and small break LOCAs continue to meet the criteria of 10 CFR 50.46, paragraph (b) for calendar year 2020.

A summary of the information related to peak clad temperatures (PCT) and adjustment to peak clad temperatures is provided in the following table:

Summary of Information for Waterford 3 10 CFR 50.46 Annual Report for 2020 Analysis of Record Adjustment Net PCT (AOR) Peak Cladding as of End-of-Year at the EOY 2020, Temperature (PCT), oF (EOY) 2020, (oF)

(oF)

Evaluation Model (EM)

Used AOR Date Small-Break 1925 -27 1898 Loss-of-Coolant S2M Accident (SBLOCA) 6/19/2009 Large-Break 2092 -8.4 2083.6 Loss-of-Coolant 1999EM Accident (LBLOCA) 7/16/2009