NRC-04-0025, 2003 Annual Reports for Fermi 2

2003 Annual Reports for Fermi 2

ML041260497
Person / Time
Site:	Fermi
Issue date:	04/29/2004
From:	Peterson N Detroit Edison
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-04-0025, VP-86-0154
Download: ML041260497 (10)

Text

Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Detroit Edison April 29,2004 NRC-04-0025 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555

Reference:

Fermi 2 NRC Docket No. 50-341 NRC License No. NPF43

Subject:

2003 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) 586-4258.

Sincerely, Norman K. Peterson Manager - Nuclear Licensing AI)TE Energy Company

USNRC NRC-04-0025 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 D. P. Beaulieu E. R. Duncan NRC Resident Office Regional Administrator, Region m Supervisor, Electric Operators, Michigan Public Service Commission

, - .- e :; as Enclosure A to NRC-04-0025 Page 1 of 2 ENCLOSURE A FERMI 2 OCCUPATIONAL RADIATION EXPOSURE REPORT JANUARY 1- DECEMBER 31, 2003 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure A to NRC-04-0025 - J.

Page 2 of 2 Detroit Edison Fermi 2 2003 Regulatory Guide 1.16 Secondary Dosimeter Deep Dose Equivalent (DDE) Dose Report

. _ Personnel Receiving Exposure 1 DDE Manrem Function Department Station . -Utility l Contract Station Utility Contract Employees Emplo0ees Workers J Emplo ees Employees Workers Reactor Operations

& Surveillance Maintenance Operations Health Physics j 147 155 50 48 2

6 1322 74 63 10.348 18.769 7.691 0.613 0.000 0.005 17.573 8.863 6.076

_ _Supervisory 235 60 217 5.384 0.248 1.036 Engineeng 108 3 110 1.646 0.000 1.136 Routine Maintenance 49 36 339 7.239 0.892 27.425 Maintenance Operations 1 11 0 0.067 0.000 0.000 Health Physics 1 0 1 0 0.005 0.000 0.000 Supervisory 5 3 4 0.256 0.173 0.036 Engineering 6 0 l 13 0.474 0.000 l 1.372 Inservice l Maintenance 0 0 44 l 0.000 0.000 7.812 Inspection

_ Operations - 0 0 0.000 0.000 0.000 p oHealth Phjsics lt 0 l _r__r _°° 0 0.000 0.000 0.000 T Supervisory 0 _ 1 1 ij 1 0.000 0.167 0.018 Engineering 0 1 1 18 0.000 0.031 3.690 Special Maintenance 1 41 117 0.0001 0.033 l 16.744 Maintenance Operations 0 0 1 0.000 I 0.0001 0.060 l_Health Physics 0 0 r 101 0.000 0.000 2.349

_ _Supervisory 1 4 r 12 0.002 0.109 1 1.338 Engineering 0 2 0.000 0.000 0.006 Waste [Maintenance 0 0 20' 0.000 0.000 0.000 Processing Operations ll2 0 20 11 0.279 1 0.000 1.492

_ Health Physics 0 0 t0 0.000 0.000 0.000

_ Supervisory 0 0 j 01 0.000 1 0.000 0.000 l_Engineering __ 0 0 0 0.000 l 0.000 0.000 Refueling Maintenance 0 0 45 0.000 0.000 7.405 ROperationstnc 0 0 2 0.000 0.000 0.111 T Health Physics 0 0 3 0.000 0.000 0.153

_ Supervisory 0 0 1 11 0.000 1 0.000 1 0.007

_ _Engineering 0 0 10 0.000 l 0.000 l 1.189 Total l Maintenance 197 88 867 17.587 l 1.538 76.959 I Operations 158 3 97 19.115 0.00 l 10.526 T Health Physics 51 6 76 7.696 0.005 8.578 Supervisory 241 68 j 235 1 5.642 0.697 1 2.435 l Engineering 114 4 153 l 2.120 1 0.031 7.393 Grand Total _ Personnel 2358 Manrem 160.322 NOTE: This report was produced using only secondary external dosimetry - it does not include any internal exposure.

Enclosure B to NRC-04-0025 Page 1 of 2 ENCLOSURE B FERMI 2 SAFETY RELIEF VALVE CHALLENGE REPORT JANUARY 1- DECEMBER 31, 2003 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure B to NRC-04-0025 Page 2 of 2 Safety Relief Valve Challenges On May 9, 2003, Surveillance Procedure 24.137.11, "Safety Relief Valve Operability Test," was satisfactorily performed, which cycled all 15 Safety Relief Valves (SRVs).

On August 14, 2003, a reactor scram from full power due to the loss of offsite power event caused SRVs B2104F013A, B2104F013B, B2104F013C, B2104F013D, B2104F013E, B2104F013G, B2104F013H, B2104F013J, and B2104F013K to satisfactorily lift and reseat in the Safety/Relief mode of operation.

Additionally, during the August 14, 2003, loss of offsite power event, SRV B2104F013A was operated automatically in Low-Low Set mode of operation and satisfactorily cycled an estimated 197 times between 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> on August 14, 2003, and approximately 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> on August 16, 2003. Details concerning this estimate are as follows:

• SRV B2104F013A cycled 15 times between 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> and 1721 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.548405e-4 months <br /> on August 14, 2003, based upon data from the Integrated Plant Computer System (IPCS).

• The IPCS was taken out of service to limit battery use at 1721 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.548405e-4 months <br /> on August 14, 2003, and was restored at 0422 hours0.00488 days <br />0.117 hours <br />6.977513e-4 weeks <br />1.60571e-4 months <br /> on August 15, 2003. Using Reactor Pressure Vessel (RPV) pressure data and SRV lift rates before and after the time the IPCS was taken out of service, it is estimated that SRV B2104F013A cycled 99 times.

• SRV B2104F013A cycled 83 times between 0422 hours0.00488 days <br />0.117 hours <br />6.977513e-4 weeks <br />1.60571e-4 months <br /> on August 15, 2003, and approximately 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> on August 16, 2003, when the plant was depressurized. This is based upon data from the IPCS.

Enclosure C to NRC-04-0025 Page 1 of 2 ENCLOSURE C FERMI 2 SERVICE LIFE OF MAIN STEAM BYPASS LINES JANUARY 1- DECEMBER 31, 2003 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure C to NRC-04-0025 Page 2 of 2 Service Life of Main Steam Bvpass 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 39.57 days as of December 31, 2003.

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Enclosure D to NRC-04-0025 Page 1 of 2 ENCLOSURE D FERMI 2 ECCS COOLING PERFORMANCE EVALUATION MODEL CHANGES OR ERRORS JANUARY 1- DECEMBER 31, 2003 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43

Enclosure D to NRC-04-0025 Page 2 of 2 ECCS Cooling Performance Evaluation Model Changes or Errors Two errors have been identified since last year's annual report. The effect of one of these errors results in a decrease in the peak clad temperature (PCT) by 5 degrees Fahrenheit and was reported to the NRC in Detroit Edison Letter NRC-03-0051 dated May 3, 2003. The second error had no impact on PCT results and was therefore not previously reported. A description of the two errors is provided below:

On May 6, 2003, Global Nuclear Fuel (GNF) informed Detroit Edison, in General Electric (GE) 10 CFR 50.46 Notification Letters 2003-01 and 2003-03 of two errors found in the GE SAFER/GESTR-LOCA code. The first error consisted of using too low of a value for the RPV initial liquid mass. The effect of this error results in a decrease in the peak clad temperature (PCT) by 5 degrees Fahrenheit. The second error consisted of using a wrong loss coefficient for the steam separator. This error resulted in a higher initial steam separator pressure drop and overly restricted the flow through the separator during the LOCA event. This second error has no impact on PCT results.

The total effect of these two errors results in a decrease in the PCT by 5 degrees Fahrenheit. With the 5 degree Fahrenheit decrease in PCT, the current Licensing Basis PCT for Fermi 2 is 1752 degrees Fahrenheit and there still is 448 degrees Fahrenheit margin to the 2200 degrees Fahrenheit PCT limit given in 10 CFR 50.46.