NRC-03-0051, 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