NRC-03-0051, ECCS Cooling Performance Evaluation Model Report

ECCS Cooling Performance Evaluation Model Report

ML031570404
Person / Time
Site:	Fermi
Issue date:	05/30/2003
From:	O'Connor W DTE Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-03-0051
Download: ML031570404 (2)

Text

William T. O'Connor, Jr.

Vice Presi(lent, Nuclear Generation Fermi 2 6400 North Dixie Hwy., Newport, Mlichigan 48166 Tel: 734-586-5201 Fax: 734-5864172 DTE Energy-1 OCFR50.46 May 30, 2003 NRC-03-0051 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Detroit Edison Letter, Douglas R. Gipson to USNRC, "30-Day OCFR50.46 Special Report Plant Specific ECCS Evaluation Changes",

dated May 28, 1996 (NRC-96-0052)

3) Detroit Edison Letter, W. T. O'Connor, Jr. to USNRC, "ECCS Cooling Performance Evaluation Model Report",

dated December 19, 2000 (NRC-00-0074)

4) Detroit Edison Letter, W. T. O'Connor, Jr. to USNRC, "ECCS Cooling Performance Evaluation Model Report",

dated June 7, 2001 (NRC-01-0046)

5) Detroit Edison Letter, W. T. O'Connor, Jr. to USNRC, "ECCS Cooling Performance Evaluation Model Report",

dated July 10, 2002 (NRC-02-0071)

Subject:

ECCS Cooling Performance Evaluation Model Report In accordance with OCFR50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," this report is being submitted to describe changes to or errors in an acceptable evaluation model used for calculating 4k(M

USNRC NRC-03-0051 Page 2 Emergency Core Cooling Systems (ECCS) performance. References 2, 3, 4, and 5 describe errors in the evaluation model previously reported to the NRC.

On May 6, 2003, Global Nuclear Fuel (GNF) informed Detroit Edison, in General Electric (GE) 1 OCFR50.46 Notification Letter 2003-01 of an additional error found in the GE SAFER/GESTR-LOCA Analysis code. The error consisted of using too low of a value for the Reactor Pressure Vessel (RPV) initial liquid mass. The effect of the error results in a decrease in the peak clad temperature (PCT) by 5 degrees Fahrenheit. With the 5 degrees Fahrenheit decrease in PCT, the current Licensing Basis PCT for Fermi 2 is 1752 degrees Fahrenheit and there is 448 degrees Fahrenheit margin to the 2200 degrees Fahrenheit PCT limit given in 1 OCFR50.46.

Detroit Edison will continue to track future changes and errors in the SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis evaluation models to ensure that the analyzed PCT remains below the 1 OCFR50.46 limits, and to ensure that the 10CFR50.46 reporting requirements are met. Detroit Edison has no immediate plans to reanalyze the SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Fermi 2.

Should you have any questions or require additional information, please contact Mr. Norman K. Peterson of my staff at (734) 586-4258.

Sincerely, cc:

M. A. Ring J. F. Stang, Jr.

NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission