ML17206A034: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:W3F1-2017-0059 Page 2 | ||
W3F1-2017-0059 Page 2 | |||
==Attachment:== | ==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 (AOR) Peak Cladding Temperature (PCT), oF Evaluation Model (EM) Used AOR Date Adjustment as of End-of-Year (EOY) 2016, (oF) Net PCT at the EOY 2016, (oF) Small-Break Loss-of-Coolant Accident (SBLOCA) 1925 S2M 6/19/2009 -27 1898 Large-Break Loss-of-Coolant Accident (LBLOCA) 2092 1999EM 7/16/2009 0 2092 | 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 (AOR) Peak Cladding Temperature (PCT), oF Evaluation Model (EM) Used AOR Date Adjustment as of End-of-Year (EOY) 2016, (oF) Net PCT at the EOY 2016, (oF) Small-Break Loss-of-Coolant Accident (SBLOCA) 1925 S2M 6/19/2009 -27 1898 Large-Break Loss-of-Coolant Accident (LBLOCA) 2092 1999EM 7/16/2009 0 2092}} | ||
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Revision as of 18:20, 18 May 2018
| ML17206A034 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/24/2017 |
| From: | Jarrell J P Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| W3F1 -2017-0059 | |
| Download: ML17206A034 (4) | |
Text
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 (AOR) Peak Cladding Temperature (PCT), oF Evaluation Model (EM) Used AOR Date Adjustment as of End-of-Year (EOY) 2016, (oF) Net PCT at the EOY 2016, (oF) Small-Break Loss-of-Coolant Accident (SBLOCA) 1925 S2M 6/19/2009 -27 1898 Large-Break Loss-of-Coolant Accident (LBLOCA) 2092 1999EM 7/16/2009 0 2092