W3F1-2019-0043, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2018

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2018

ML19182A363
Person / Time
Site:	Waterford
Issue date:	07/01/2019
From:	Wood P Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2019-0043
Download: ML19182A363 (4)

Text

• ~ Entergy Entergy Operations, Inc.

Paul Wood 10 CFR 50.46 W3F1-2019-0043 July 1, 2019 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 2018 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 2018.

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.

PW/llb

W3F1-2019-0043 Page 2

Attachment:

Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2018 cc:

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

Attachment to W3F1-2019-0043 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2018

Attachment to W3F1-2019-0043 Page 1 of 1 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2018 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 2018. 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 2018.

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 2018.

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 2018 Analysis of Record Adjustment Net PCT (AOR) Peak Cladding as of End-of-Year at the EOY 2018, Temperature (PCT), oF (EOY) 2018, (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 -3 2089 Loss-of-Coolant 1999EM Accident (LBLOCA) 7/16/2009