W3F1-2024-0020, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:John Twarog Manager Regulatory Assurance 504-739-6747 Entergy Operations, Inc., 17265 River Road, Killona, LA 70057 W3F1-2024-0020 10 CFR 50.46 April 11, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | ||
Manager Regulatory Assurance 504-739-6747 | |||
W3F1-2024-0020 10 CFR 50.46 | |||
April 11, 2024 | |||
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | |||
==Subject:== | ==Subject:== | ||
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 | Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 Waterford Steam Electric Station, Unit 3 NRC 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 2023. | ||
This letter contains no new regulatory commitments. | |||
Waterford Steam Electric Station, Unit 3 NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38 | |||
This letter provides the Waterford Steam Electric Station Unit 3 (Waterford 3) | |||
This letter contains no | |||
Should you have any questions or require additional information, please contact John Twarog, Manager, Regulatory Assurance, at 504-739-6747. | Should you have any questions or require additional information, please contact John Twarog, Manager, Regulatory Assurance, at 504-739-6747. | ||
Respectfully, John Twarog JT/llb Digitally signed by John Twarog DN: cn=John Twarog, c=US, o=Waterford 3 Nuclear Independent Oversight, ou=Nuclear Independent Oversight, email=jtwarog@entrgy.com Date: 2024.04.11 15:35:47 -05'00' John Twarog | |||
~ entergy | |||
W3F1-2024-0020 Page 2 of 2 | |||
==Enclosure:== | ==Enclosure:== | ||
Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2023 | Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2023 cc: | ||
NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford 3 NRC Project Manager - Waterford 3 | |||
cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford 3 NRC Project Manager - Waterford 3 | |||
Enclosure W3F1-2024-0020 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2023 | |||
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) | W3F1-2024-0020 Enclosure Page 1 of 1 WATERFORD STEAM ELECTRIC STATION UNIT 3 10 CFR 50.46 ANNUAL NOTIFICATION AND REPORTING FOR 2023 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 2023. 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 2023. | Emergency Core Cooling System (ECCS) performance analysis in calendar year 2023. 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 2023. | ||
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 2023. | 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 2023. | ||
A summary of the information related to peak clad temperatures (PCT) and adjustment to peak clad temperatures is provided in the following table: | 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 2023 Analysis of Record (AOR) | |||
Summary of Information for Waterford 3 10 CFR 50.46 Annual Report for 2023 | Peak Clad Temperature (PCT), (°F) | ||
Evaluation Model (EM) Used AOR Date Adjustment as of End-of-Year (EOY) 2023, | |||
Analysis of Record (AOR) | (°F) | ||
Net PCT at the EOY 2023, (°F) | |||
Small-Break Loss-of-Coolant Accident (SBLOCA) 1925 S2M 6/19/2009 | |||
-27 1898 Large-Break Loss-of-Coolant Accident (LBLOCA) 2092 1999 EM 7/16/2009 | |||
-6.1 2085.9}} | |||
Latest revision as of 18:41, 24 November 2024
| ML24102A286 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/11/2024 |
| From: | Twarog J Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| W3F1-2024-0020 | |
| Download: ML24102A286 (1) | |
Text
John Twarog Manager Regulatory Assurance 504-739-6747 Entergy Operations, Inc., 17265 River Road, Killona, LA 70057 W3F1-2024-0020 10 CFR 50.46 April 11, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 Waterford Steam Electric Station, Unit 3 NRC 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 2023.
This letter contains no new regulatory commitments.
Should you have any questions or require additional information, please contact John Twarog, Manager, Regulatory Assurance, at 504-739-6747.
Respectfully, John Twarog JT/llb Digitally signed by John Twarog DN: cn=John Twarog, c=US, o=Waterford 3 Nuclear Independent Oversight, ou=Nuclear Independent Oversight, email=jtwarog@entrgy.com Date: 2024.04.11 15:35:47 -05'00' John Twarog
~ entergy
W3F1-2024-0020 Page 2 of 2
Enclosure:
Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2023 cc:
NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford 3 NRC Project Manager - Waterford 3
Enclosure W3F1-2024-0020 Waterford Steam Electric Station Unit 3 10 CFR 50.46 Annual Notification and Reporting for 2023
W3F1-2024-0020 Enclosure Page 1 of 1 WATERFORD STEAM ELECTRIC STATION UNIT 3 10 CFR 50.46 ANNUAL NOTIFICATION AND REPORTING FOR 2023 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 2023. 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 2023.
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 2023.
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 2023 Analysis of Record (AOR)
Peak Clad Temperature (PCT), (°F)
Evaluation Model (EM) Used AOR Date Adjustment as of End-of-Year (EOY) 2023,
(°F)
Net PCT at the EOY 2023, (°F)
Small-Break Loss-of-Coolant Accident (SBLOCA) 1925 S2M 6/19/2009
-27 1898 Large-Break Loss-of-Coolant Accident (LBLOCA) 2092 1999 EM 7/16/2009
-6.1 2085.9