W3F1-2016-0044, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2015

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2015

ML16161A819
Person / Time
Site:	Waterford
Issue date:	06/09/2016
From:	Jarrell J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2016-0044
Download: ML16161A819 (4)

Text

Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 504 739 6698 jjarrel@entergy.com John P. Jarrell, III Manager, Regulatory Assurance Waterford 3 10 CFR 50.46 W3F1-2016-0044 June 9, 2016 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 2015 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) 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 2015.

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.

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

Attachment:

Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2015

W3F1-2016-0044 Page 2 cc: Mr. Mark L. Dapas, 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 W3F1-2016-0044 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2015

Attachment to W3F1-2016-0044 Page 1 of 1 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2015 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 2015. 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 2015.

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 2015.

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 2015 Analysis of Record Adjustment Net PCT (AOR) Peak Cladding as of End-of-Year at the EOY 2015, Temperature (PCT), oF (EOY) 2015, (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