W3F1-2010-0066, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models: Difference between revisions

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{{#Wiki_filter:Entergy Nuclear South William J. Steelman W3F1-2010-0066 July 27,2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
{{#Wiki_filter:W3F1-2010-0066 July 27,2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear South William J. Steelman


==Subject:==
==Subject:==
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models Waterford Steam Electric Station Unit 3 Docket No. 50-382 License No. NPF-38
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models Waterford Steam Electric Station Unit 3 Docket No. 50-382 License No. NPF-38  


==Dear Sir or Madam:==
==Dear Sir or Madam:==
This letter provides the Waterford Steam Electric Station Unit 3 (Waterford 3) 10CFR50.46(a)(3)(ii) reporting information pertaining to the Westinghouse Electric Company Emergency Core Cooling System (ECCS) performance Evaluation Models (EMs) for calendar year 2009.
This letter provides the Waterford Steam Electric Station Unit 3 (Waterford 3) 10CFR50.46(a)(3)(ii) reporting information pertaining to the Westinghouse Electric Company Emergency Core Cooling System (ECCS) performance Evaluation Models (EMs) for calendar year 2009.
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)
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)
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.
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 William Steelman at 504-739-6685.
This letter contains no new commitments. If you have any questions or require additional information, please contact William Steelman at 504-739-6685.
WJS/ssf
WJS/ssf  


W3F1-2010-0066 Page 2 cc:   Mr. Elmo E. Collins, Jr.
W3F1-2010-0066 Page 2 cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001}}
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001}}

Latest revision as of 03:54, 14 January 2025

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models
ML102080450
Person / Time
Site: Waterford Entergy icon.png
Issue date: 07/27/2010
From: Steelman W
Entergy Nuclear Operations, Entergy Nuclear South
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2010-0066
Download: ML102080450 (2)


Text

W3F1-2010-0066 July 27,2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear South William J. Steelman

Subject:

Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models 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) 10CFR50.46(a)(3)(ii) reporting information pertaining to the Westinghouse Electric Company Emergency Core Cooling System (ECCS) performance Evaluation Models (EMs) for calendar year 2009.

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)

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 William Steelman at 504-739-6685.

WJS/ssf

W3F1-2010-0066 Page 2 cc:

Mr. Elmo E. Collins, Jr.

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001