W3F1-2014-0040, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2013

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2013

ML14188B067
Person / Time
Site:	Waterford
Issue date:	07/03/2014
From:	Jarrell J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2014-0040
Download: ML14188B067 (4)

Text

Entergy Operations, Inc.

17265 RiverRoad Kiflona, LA 70057-3093 Tel 5047396685 Fax 504 739 6698

EnteJgy jjarre14enterqy. corn John Jarrell Manager, Regulatory Assurance Waterford 3 10 CFR 50.46 W3FI -2014-0040 July 3, 2014 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 2013 Waterford Steam Electric Station Unit 3 Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

This letter provides the Waterlord 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 2013.

There were no changes, error corrections, or enhancements to the I 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 (52M) 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.

Scer JPJ/LE Attac aterlord Nuclear Generating Station Unit 3 1 0 CFR 50.46 Annual Notification and Reporting for 2013

July 3, 2014 W3F1-2014-0040 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 Michael.Orenak@nrc.gov

Attachment to W3F1-2014-0040 Waterford Nuclear Generating Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2013

Attachment to W3F1-2014-0040 Page 1 of 1 Waterford Nuclear Generating Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2013 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 2013. 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 2013.

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 2013.

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 2013 Analysis of Record (AOR) Peak Cladding Temperature (PCT), oF Evaluation Model (EM) Adjustment Used as of End-of-Year Net PCT (EOY) 2013, at the EOY 2013, AOR Date (oF) (oF)

Small-Break 1925 -27 1898 Loss-of-Coolant S2M Accident (SBLOCA) 6/19/2009 Large-Break 2092 None 2092 Loss-of-Coolant 1999EM Accident (LBLOCA) 7/16/2009