ML17206A034

Annual Report on Westinghouse Electric Company LLC, Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2016

ML17206A034
Person / Time
Site:	Waterford
Issue date:	07/24/2017
From:	Jarrell J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1 -2017-0059
Download: ML17206A034 (4)

Text

Entergy Operations, Inc.

I 7265 R ver Road Killona, LA 70057-3093

.::;:_JT 1-i ei:gy Tel 5047395685 Fax 504 739 6698 jjarrekenterciy.corn John P. Jarrell, III Manager, Regulatory Assurance Waterford 3 10 CFR 50.46 W3FI -2017-0059 July 24, 2017 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 2016 Waterford Steam Electric Station Unit 3 Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

This letter provides the Waterford Steam Electric Station Unit 3 (Waterford 3)

I 0 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 2016.

There were no changes, error corrections, or enhancements to the 1 999 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.

If you have any questions, or require additional information, please contact John Jarrell at 504-739-6685.

W3F1-2017-0059 Page 2

Attachment:

Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2016 cc: Mr. Kriss Kennedy, Regional Administrator RidsRgn4MailCenter@nrc.gov NRC Senior Resident Inspector Frances.Ramirez@nrc.gov Chris.Speer@nrc.gov NRC Project Manager for Waterford 3 April.Pulvirenti@nrc.gov

Attachment to W3F1-2017-0059 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2016

Attachment to W3F1-2017-0059 Page 1 of 1 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2016 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 2016. 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 2016.

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 2016.

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 2016 Analysis of Record Adjustment Net PCT (AOR) Peak Cladding as of End-of-Year at the EOY 2016, Temperature (PCT), oF (EOY) 2016, (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 0 2092 Loss-of-Coolant 1999EM Accident (LBLOCA) 7/16/2009