NRC-05-0032, 2004 Annual Reports for Fermi 2

2004 Annual Reports for Fermi 2

ML051220114
Person / Time
Site:	Fermi
Issue date:	04/22/2005
From:	Peterson N Detroit Edison
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-05-0032
Download: ML051220114 (10)

Text

Fermi 2 6400 North Dixie Hwy., NeTwport, MI 48166 Detroit Edison April 22, 2005 NRC-05-0032 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:

2004 Annual Reports for Fermi 2 The Fermi 2 Technical Specifications (TS) contain requirements for submitting a report for occupational radiation exposure (Technical Specification 5.6.1) and safety relief valve challenges (Technical Specification 5.6.6). Enclosures A and B are provided in accordance with Technical Specifications 5.6.1 and 5.6.6 to meet these requirements.

Enclosure C 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 D 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) 5864258.

Sincerely, Norman K. Peterson Manager - Nuclear Licensing ADTE Energy Company

USNRC NRC-05-0032 Page 2 Enclosure A: Occupational Radiation Exposure Report Enclosure B: Safety Relief Valve Challenge Report Enclosure C: Service Life of Main Steam Bypass Lines Enclosure D: ECCS Cooling Performance Evaluation Model Changes or Errors cc: w/Enclosures E. R. Duncan N. K. Ray NRC Resident Office Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission

Enclosure A to NRC-05-0032 Page I of 2 ENCLOSURE A FERMI 2 OCCUPATIONAL RADIATION EXPOSURE REPORT JANUARY 1 - DECEMBER 31, 2004 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure A to NRC-05-0032 Page 2 of 2 Detroit Edison Fermi 2 2004 Regulatory Guide 1.16 Secondary Dosimeter Deep Dose Equivalent (DDE) Dose Report Personnel Receiving Exposure DDE Manrem Function Department Station Utility Contract Station UUlity Contract Em poyees Employees Workers Employees Employees Workers Reactor Operations Maintenance 136 37 222 11.268 0.557 7.104

& Surveillance Operations 151 3 89 15.344 0.000 10.238 Health Physics 46 6 65 8.152 0.022 4.049 Supervisory 249 38 193 3.557 0.157 1.174 i Engineering 93 3 103 1.327 0.058 0.128 Routine Maintenance 43 29 627 4.770 0.537 35.697 Maintenance Operations 0 0 1 0.000 0.000 0.183 Health Physics 0 0 4 .0.000 0.000 0.415 Supervisory 1 5 34 0.000 0.000 1.805 Engineering 2 1 9 0.271 0.099 1.002 Inservice Maintenance 0 0 l 49 0.000 0.000 l 5.609 Inspection Operations 0 0 J 0 0.000 .0.000 0.000 l Health Physics l Supervisory _ _

0 I

0 l 0 I 14 0 0.000 0.058 0.000 l 0.000 l 0.000 2.519 l lEngineering ll 1 j 0 l 9 0.073 0.000 l 1.294 l _Special lMaintenance 1 1 104 0.014 0.000 14.897 Maintenance Operations 0 0 l 0 0.000 0.000 0.000

_ Health Physics 0 0 10 0.000 0.000 1.776

_ Supervisory 0 4 r 5 0.000 0.068 0.03 1 l Engineering 3 0 l 2 0.150 0.000 0.040 Waste [Maintenance 0 0 l 0 0.000 0.000 0.000 Processing Operations 2 0 1 18 0.081 1 0.000 0.935

_ Health Physics 0 0 l 0 0.000 0.000 l 0.000

_ T Supervisory 0 0 0 0.000 0.000 0.000

_ Engineering 0 0 0 0.000 0.000 T 0.000 Refueling T l _Maintenance_ _ _2 l _0 l 52_ll 0.205 0.000 6.102 l Operations 0 0 l 0.0000 0.000 0.000

_ Health Physics 0 0 8 0.000 0.000 0.806 Supervisory 1 0 l 3 0.000 0.000 0.087 l

Engineering 1 °0 3 - 0.005 0.000 1 0.013 Total l Maintenance ll 182 l 67 1054 ll 16.257 1.0941 69.409 l Operations 153 3 108 15.425 0.000 11.356 Health Physics 46 6 17 8.152 0.0221 7.046 l Supervisory 252 47 249 3.615 0.2251 5.616

_ Engineering 100 4 126 J 1.826 0.157 2.477 Grand Total Personnel 2484 l Manrem 142.677 NOTE: This report was produced using only secondary external dosimetry - It does not include any internal exposure.

Enclosure B to NRC-05-0032 Page 1 of 2 ENCLOSURE B FERMI 2 SAFETY RELIEF VALVE CHALLENGE REPORT JANUARY 1 - DECEMBER 31,2004 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF43

Enclosure B to NRC-05-0032 Page 2 of 2 Safety Relief Valve Challenges There were no instances in 2004 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation. There were no instances in 2004 where an SRV actuation was demanded by an automatic logic system. On December 2,2004, following completion of the Tenth Refueling Outage (RFl0), Surveillance Procedure 24.137.11, "Safety Relief Valve Operability Test," was satisfactorily performed, which cycled all 15 Safety Relief Valves (SRVs).

Enclosure C to NRC-05-0032 Page 1 of 2 ENCLOSURE C FERMI 2 SERVICE LIFE OF MAIN STEAM BYPASS LINES JANUARY 1- DECEMBER 31, 2004 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF43

Enclosure C to NRC-05-0032 Page 2 of 2 Service Life of Main Steam Bypass Line 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 40.57 days as of December 31, 2004.

Enclosure D to NRC-05-0032 Page 1 of 2 ENCLOSURE D FERMI 2 ECCS COOLING PERFORMANCE EVALUATION MODEL CHANGES OR ERRORS JANUARY 1- DECEMBER 31, 2004 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure D to NRC-05-0032 Page 2 of 2 ECCS Cooling Performance Evaluation Model Changes or Errors One error has been identified since last year's annual report. The error has no impact on Fermi 2 peak clad temperature (PCT) results and therefore, was not reported. A description of the error is provided below:

On May 13, 2004, Global Nuclear Fuel (GNF) informed Detroit Edison, in General Electric (GE) 10 CFR 50.46 Notification Letter 2003-05, of an error found in the GE SAFER/GESTR-LOCA code. This letter describes a new heat source, which has been postulated during a Loss of Coolant Accident (LOCA). This heat source involves the recombination of hydrogen and oxygen within a fuel bundle during core heatup. The error only contributes to increasing peak clad temperature (PCT) results for non-jet pump plants. This is due to the fact that oxygen from the containment enters the vessel late in the LOCA event, after the core has reflooded for jet pump plants. Therefore, this error has no impact on Fermi 2.

The current Licensing Basis PCT for Fermi 2 remains at 1752 degrees Fahrenheit and there is still 448 degrees Fahrenheit margin to the 2200 degrees Fahrenheit PCT limit given in 10 CFR 50.46.