NRC-07-0019, 2006 Annual Reports for Fermi 2

2006 Annual Reports for Fermi 2

ML071200217
Person / Time
Site:	Fermi
Issue date:	04/24/2007
From:	Gaston R Detroit Edison
To:	Document Control Desk, NRC/NRR/ADRO
References
NRC-07-0019
Download: ML071200217 (8)

Text

Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Detroit Edison April 24, 2007 NRC-07-0019 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:

2006 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 A DTE Energy Company

USNRC NRC-07-0019 April 24, 2007 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 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 A to NRC-07-0019 April 24, 2007 Page 1 of 2 ENCLOSURE A FERMI 2 SAFETY RELIEF VALVE CHALLENGE REPORT JANUARY 1 - DECEMBER 31, 2006 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure A to NRC-07-0019 April 24, 2007 Page 2 of 2 Safety Relief Valve Challenges There were no instances in 2006 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation. There were no instances in 2006 where an SRV actuation was demanded by an automatic logic system. On May 5, 2006, following completion of the Eleventh Refueling Outage (RF 11), Surveillance Procedure 24.137.11, "Safety Relief Valve Operability Test," was satisfactorily performed, which cycled all 15 Safety Relief Valves (SRVs).

Enclosure B to NRC-07-0019 April 24, 2007 Page 1 of 2 ENCLOSURE B FERMI 2 SERVICE LIFE OF MAIN STEAM BYPASS LINES JANUARY 1 - DECEMBER 31, 2006 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure B to NRC-07-0019 April 24, 2007 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 not 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 41.14 days as of December 31, 2006.

Enclosure C to NRC-07-0019 April 24, 2007 Page 1 of 2 ENCLOSURE C FERMI 2 ECCS COOLING PERFORMANCE EVALUATION MODEL CHANGES OR ERRORS JANUARY 1 - DECEMBER 31, 2006 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure C to NRC-07-0019 April 24, 2007 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 for General Electric GE 11 fuel and 1620 degrees Fahrenheit for GE 14 fuel. Fermi has two Loss of Coolant Accident (LOCA) analyses, one for each of Global Nuclear Fuel - Americas GEl 1 and GE14 fuel types. Each of these analyses has incorporated the applicable error reports. No new error reports have been issued against Fermi 2 since completing the LOCA analyses. There is at least a 550 degree Fahrenheit margin to the 2200 degree Fahrenheit PCT limit given in 10 CFR 50.46.