NRC-10-0031, Submittal of 2009 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report

Submittal of 2009 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report

ML101180154
Person / Time
Site:	Fermi
Issue date:	04/27/2010
From:	Rachel Johnson Detroit Edison
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-10-0031
Download: ML101180154 (8)

Text

Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Detroit Edison TS 5.6.6 10CFR50.46 April 27, 2010 NRC-10-0031 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Wasington D C 20555

Reference:

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

Subject:

Submittal of 2009 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report The Fermi 2 Technical Specifications (TS) contains a requirement for submitting an annual report for safety relief valve challenges (TS 5.6.6). Enclosure 1 provides the Safety Relief Valve Challenge Report for 2009. provides the annual Service Life of the Main Steam Bypass Lines Report for 2009. This satisfies the commitment stated in Detroit Edison's letter to the NRC dated November 7, 1986 (VP-86-0154). provides the annual Emergency Core Cooling System (ECCS) Cooling Performance Evaluation Model Changes or Errors Report for 2009. This report is provided in accordance with 10 CFR 50.46(a)(3)(ii).

Should you have any questions or require additional information, please contact me at (734) 586-5076.

Sincerely, Rodney W. Johnson Manager, Nuclear Licensing A DTE Energy Company

USNRC NRC-10-0031 Page 2

Enclosures:

1. Safety Relief Valve Challenge Report

2. Service Life of Main Steam Bypass Lines Report

3. ECCS Cooling Performance Evaluation Model Changes or Errors Report cc: NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 4, Region III Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission

Enclosure 1 To NRC-10-0031 Fermi 2 Safety Relief Valve Challenge Report January 1 to December 31, 2009 Detroit Edison Company NRC Docket No. 50-341 Facility Operating License No. NPF-43 to NRC-10-0031 Page 1 Safety Relief Valve Challenges There were no instances in 2009 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation. There were also no instances in 2009 where an SRV actuation was demanded by an automatic logic system.

Enclosure 2 To NRC-10-0031 Fermi 2 Service Life of Main Steam Bypass Lines Report January 1 to December 31, 2009 Detroit Edison Company NRC Docket No. 50-341 Facility Operating License No. NPF-43 to NRC-10-0031 Page 1 Service Life of Main Steam Bypass Lines In accordance with Detroit Edison's letter to the NRC dated November 7, 1986 (VP-86-0154),

the cumulative time the main steam bypass lines are operated with the bypass valves between 30 and 45 percent open will be reported annually. A cumulative value of 100 days is not to be exceeded without prior NRC notification.

Evaluations performed by Detroit Edison contractors concluded that the bypass lines are acceptable for safe operation when operated within the 100 day constraint. Based on these evaluations, the main steam bypass piping that was installed in 1985 has a service life that will allow it to function for the life of the plant under anticipated operating conditions.

As of December 31, 2009, the main steam bypass lines cumulative usage was 41.93 days.

Enclosure 3 To NRC-10-0031 Fermi 2 ECCS Cooling Performance Evaluation Model Changes or Errors Report January 1 to December 31, 2009 Detroit Edison Company NRC Docket No. 50-341 Facility Operating License No. NPF-43 to NRC-10-0031 Page 1 ECCS Cooling Performance Evaluation Model Changes or Errors There have been no errors identified since last year's annual report.

The current licensing basis Peak Cladding Temperature (PCT) for Fermi 2 is 1830 degrees Fahrenheit for GEl 1 fuel and 1995 degrees Fahrenheit for GE14 fuel. Fermi 2 currently maintains two LOCA analyses, one for each of 'Global Nuclear Fuel - Americas' GEl 1 and GE14 fuel types. There is a minimum of 205 degree Fahrenheit margin to the 2200 degree Fahrenheit PCT limit given in 10 CFR 50.46.