NRC-03-0042, 2002 Annual Reports for Fermi 2
| ML031270156 | |
| Person / Time | |
|---|---|
| Site: | Fermi  (NPF-043) |
| Issue date: | 04/28/2003 |
| From: | Peterson N Detroit Edison |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-03-0042 | |
| Download: ML031270156 (10) | |
Text
Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Detroit Edison April 28, 2003 NRC-03-0042 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:
2002 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 a 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,
/f
/ A Norman K. Peterson Manager - Nuclear Licensing A DTE Energy Company
USNRC NRC-03-0042 Page 2 Enclosure A:
Enclosure B:
Enclosure C:
Enclosure D:
Occupational Radiation Exposure Report Safety Relief Valve Challenge Report Service Life of Main Steam Bypass Lines ECCS Cooling Performance Evaluation Model Changes or Errors cc: Enclosures M. A. Ring J. F. Stang, Jr.
NRC Resident Office Regional Administrator, Region m Supervisor, Electric Operators, Michigan Public Service Commission
Enclosure A to NRC-03-0042 Page 1 of 2 ENCLOSURE A FERMI 2 OCCUPATIONAL RADIATION EXPOSURE REPORT JANUARY 1 - DECEMBER 31, 2002 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43
Enclosure A to NRC-03-0042 Page 2 of 2 Detroit Edison Fermi 2 2002 Regulatory Guide 1.16 Secondary Dosimeter Deep Dose Equivalent (DDE) Dose Report Personnel Receiving Exposure DDE Manrem Function Department Station Utility Contract Station Utility Contract Employees Employees Workers Employees Employees Workers Reactor Operations Maintenance 126 15 40 5.549 0 000 1.412
& Surveillance Operabons 128 2
24 6 866 0 007 2 094 Health Physics 58 3
7 4.652 0 002 0 024 Supervisory 180 31 231 1.389 0 006 1.631 Engineenng 131 7
17 0 833 0.025 0 006 Routine Maintenance 44 0
15 5 254 0.000 0 525 Maintenance Operations 2
0 0
0 217 0.000 0 000 Health Physics 0
0 0
0 000 0 000 0 000 Supervisory 4
2 8
0322 0 061 0 089 Engineenng 2
1 1
0 010 0.002 0 064 Inservice Maintenance 0
0 0
0 000 0 000 0.000 Inspection Operations 0
0 0
0 000 0.000 0 000 Health Physics 0
0 0
0000 0 000 0 000 Supervisory 0
0 0
0000 0 000 0 000 Enaineenna 0
O 0
0 000 0.000 0 000 Special Maintenance 0
1 0
0000 0 002 0 000 Maintenance Operations 0
0 0
0 000 0 000 0.000 Health Physics 0
0 0
0 000 0 000 0 000 Supervisory 1
4 1 1 0 000 0.025 0.133 Engineenng 0
0 0
0 000 0.000 0 000 Waste Maintenance 0
0 0
0000 0.000 000 Processing Operabons 0
0 1
0 000 0.000 0 318 Health Physics 0
0 0
0 000 0.000 0.000 Supervisory 0
0 0
0000 0.000 0.000 Engineenng 0
0 0
0 000 0.000 0.000 Refueling Maintenance 0
0 0
0000 0.000 0.000 Operations 0
0 0
0.000 0.000 0.000 Health Physics 0
0 0
0 000 0 000 0.000 Supervisory 0
0 0
0l000 0 000 0.0°0 Engineenng 0
0 0
0000 0.000 0.000 Total Maintenance 170 16 55 10.803 0.002 1.937 Operations 130 2
25 7.083 l 0.007 2.412 Health Physics 58 3
7 4.652 0.002 0.024 Supervisory 185 37 250 1.711 0.092 1.853 Engineerlng 133 8
18 0.843 0.027 0.070 GrandTotal Personnel 1097 Manrem 31.518 NOTE: This report was produced using only secondary external dosimetry - it does not include any internal exposure.
Enclosure B to NRC-03-0042 Page 1 of 2 ENCLOSURE B FERMI 2 SAFETY RELIEF VALVE CHALLENGE REPORT JANUARY 1-DECEMBER 31,2002 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43
Enclosure B to NRC-03-0042 Page 2 of 2 Safety Relief Valve Challenges There were no instances in 2002 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation. There were no instances in 2002 where an SRV actuation was demanded by an automatic logic system.
Enclosure C to NRC-03-0042 Page 1 of 2 ENCLOSURE C FERMI 2 SERVICE LIFE OF MAIN STEAM BYPASS LINES JANUARY 1-DECEMBER 31,2002 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43
Enclosure C to NRC-03-0042 Page 2 of 2 Service Life of Main Steam Bypass Line In accordance with a 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 38.60 days as of December 31, 2002.
Enclosure D to NRC-03-0042 Page 1 of 2 ENCLOSURE D FERMI 2 ECCS COOLING PERFORMANCE EVALUATION MODEL CHANGES OR ERRORS JANUARY 1-DECEMBER 31,2002 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43
Enclosure D to NRC-03-0042 Page 2 of 2 ECCS Cooling Performance Evaluation Model Changes or Errors Five errors have been identified since last year's annual report. Two of these errors affect peak clad temperature (PCT) results by 45 degrees Fahrenheit and were therefore reported to the NRC in Detroit Edison Letter NRC-02-0071 dated July 10, 2002. The remaining three errors have no impact on PCT results. A description of the five errors is provided below:
On June 13, 2002 Global Nuclear Fuel (GNF) informed Detroit Edison, in General Electric (GE) 10CFR50.46 Notification Letters 2002-01 and 2002-02, of two errors found in the GE SAFER/GESTR-LOCA code. The first error resulted in too low a value being calculated for the core spray injection elevation. The second error resulted in too high a value used for the reactor pressure vessel initial liquid inventory because the steam dryer pressure drop was not properly accounted for. The total effect of these two errors results in an increase in the PCT by 45 degrees Fahrenheit.
On August 26, 2002 GNF informed Detroit Edison, in GE 10CFR50.46 Notification Letters 2002-03, 2002-04, and 2002-05, of three additional errors in the GE SAFER/GESTR-LOCA code. The first of these three errors resulted in the use of an initial gap conductance slightly lower than it should have been. The second error involved a change in computer platform (from VAX to Alpha platform). The third error resulted in a small miscalculation of the vessel downcomer volume. None of these three errors have any impact on PCT results.
The total effect of these five errors results in an increase in the PCT by 45 degrees Fahrenheit.
With the 45 degree Fahrenheit increase in PCT, the current Licensing Basis PCT for Fermi 2 is 1757 degrees Fahrenheit and there still is 443 degrees Fahrenheit margin to the 2200 degrees Fahrenheit PCT limit given in 10CFR50.46.