NRC-06-0016, Fermi 2, 2005 Annual Reports

Fermi 2, 2005 Annual Reports

ML060870405
Person / Time
Site:	Fermi
Issue date:	03/16/2006
From:	Gaston R W Detroit Edison
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-06-0016
Download: ML060870405 (8)

Text

Fermi 2 6400 North Dixie Hwy., Newport, Al 48166 Detroit Edison March 16,2006 NRC-06-0016 U. S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington D C 20555

Reference:

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

Subject:

2005 Annual Reports for Fermi 2 The Fermi 2 Technical Specifications (TS) contains a requirement for submitting a report for safety relief Valve challenges (Technical Specification 5.6.6). Enclosure A is provided in accordance with Technical Specification 5.6.6 to meet this requirement.

Enclosure B is attached and contains a report on service life of the main steam bypass lines. This satisfies the commitment stated in Detroit Edison letter to the NRC dated November 7, 1986 (VP-86-0154).

Enclosure C is attached in accordance with 10 CFR 50.46(a)(3)(ii) and contains a report of Emergency Core Cooling System (ECCS) cooling performance-evaluation model changes or errors.Should you have any questions or require additional information, please contact me at (734) 586-5197.Sincerely, Ronald W. Gaston Manager, Nuclear Licensing* iDC)A DTE Energy Company USNRC NRC-06-00 16 March 16, 2006 Page 2 Enclosure A: Safety Relief Valve Challenge Report Enclosure B: Service Life of Main Steam Bypass Lines Enclosure C: ECCS Cooling Performance Evaluation Model Changes or Errors cc: w/Enclosures D. H. Jaffe T. J. Kozak NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission

-4 Enclosure A to NRC-06-0016 March I16, 2006 Page 1 of 2 ENCLOSURE A FERMI 2 SAFETY RELIEF VALVE CHALLENGE REPORT JANUARY 1 -DECEMBER 31,2005 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 Enclosuire A to NRC-06-001 6 March 16, 2006 Page 2 of 2 Safety Relief Valve Challenges There were no instances in 2005 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation.

There were no instances in 2005 where an SRV actuation was demanded by an automatic logic system or the valves were cycled for surveillance testing.

a Enclosure B to NRC-06-0016 March 16, 2006 Page 1 of 2 ENCLOSURE B FERMI 2 SERVICE LIFE OF MAIN STEAM BYPASS LINES JANUARY 1 -DECEMBER 31,2005 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 I Enclosure B to NRC-06-0016 March 16,2006 Page 2 of 2 Service Life of Main Steam Bypass Lines In accordance with Detroit Edison 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 percent and 45 percent open will be reported annually.

A cumulative value of 100 days is riot to be exceeded without prior NRC notification.

Evaluations performed by Stone and Webster and by Hopper and Associates concluded that the bypass lines are acceptable for safe operation when operated within the 100 day constraint.

Based on these evaluations, the new 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.

The main steam bypass lines cumulative usage was 40.66 days as of December 31, 2005.

Enclosure C to NRC-06-0016 March 16, 2006 Page 1 of 2 ENCLOSURE C FERMI 2 ECC'S COOLING PERFORMANCE EVALUATION MODEL CHANGES OR ERRORS JANUARY I -DECEMBER 31,2005 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 Enclosure C to NRC-06-0016 March 16, 2006 Page 2 of 2 ECCS Cooling Performance Evaluation Model Changes or Errors There have been no errors identified since last year's annual report.The current license basis Peak Clad Temperature (PCT) for Fermi 2 is 1650 degrees Fahrenheit.

This is a change from the previous reporting period. Fermi 2 re-analyzed the Loss of CoDlant Accident (LOCA) for all fuel currently in the Reactor Pressure Vessel. Two LOCA analyses were performed for General Electric (GE) 11 and GE 14 fuel which also incorporated all error reports. No new error reports have been issued against Fermi 2 since completing the LOCA analysis.

There is a 550 degrees Fahrenheit margin to the 2200 degrees Fahrenheit PCT limit given in 10 CFR 50.46.