ML020600132
| ML020600132 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/26/2002 |
| From: | Greenlee S Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:2691-02 | |
| Download: ML020600132 (6) | |
Text
Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1373 INDIANA MICHIGAN POWER February 26, 2002 AEP:NRC:2691-02 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 2001 ANNUAL OPERATING REPORT Technical Specifications 6.9.1.4 and 6.9.1.5 of Appendix A to the Donald C. Cook Nuclear Plant Unit 1 and Unit 2 operating licenses require that an annual report be submitted to address personnel exposure, steam generator in-service inspection results, challenges to power-operated relief and safety valves, and information regarding any instances when the 1-131 specific activity limit was exceeded.
Consistent with these requirements, a copy of the 2001 annual operating report is attached.
There are no new commitments in this submittal.
Should you have any questions, please contact Mr. Gordon P. Arent, Manager of Regulatory Affairs, at (616) 697-5553.
Sincerely, S. A. Greenlee Director of Nuclear Technical Services
/bjb Attachment N
U.S. Nuclear Regulatory Commission Page 2 c:
K. D. Curry, w/o attachment J. E. Dyer MDEQ - DW & RPD, w/o attachment NRC Resident Inspector R. Whale, w/o attachment AEP:NRC:2691-02
U.S. Nuclear Regulatory Commission AEP:NRC:2691-02 Page 3 bc:
G. P. Arent, w/o attachment A. C. Bakken P. B. Cowan, w/o attachment M. J. Finissi, w/o attachment R. W. Gaston, w/o attachment S. A. Greenlee, w/o attachment S. B. Haggerty D. W. Jenkins, w/o attachment J. E. Pollock, w/o attachment M. W. Rencheck, w/o attachment J. F. Stang, Jr., NRC - Washington, D.C.
T. R. Stephens
ATTACHMENT TO AEP:NRC:2691-02 2001 Annual Operating Report
1.0 INTRODUCTION
Plant Description Indiana Michigan Power Company is the licensee for Donald C. Cook Nuclear Plant. The plant is located north of Bridgman, Michigan. The plant consists of two nuclear units, each employing a Westinghouse pressurized water reactor nuclear steam supply system.
Each reactor unit employs an ice condenser reactor containment system. The American Electric Power Service Corporation was the architect-engineer and constructor.
Units 1 and 2 reactor licensed power levels are 3250 Mwt and 3411 Mwt, respectively.
The main condenser cooling method is open cycle using Lake Michigan water as the cooling source for each unit.
2.0 PERSONNEL RADIATION EXPOSURE
SUMMARY
Page 2 of this attachment provides a summary of the number of station, utility, and contractor/other personnel receiving exposures greater than 100 millirem (mr) in 2001.
This estimated dose is based on electronic dosimetry and reported in the format specified by Regulatory Guide 1.16.
The values shown in the individual categories (routine maintenance, etc.) represent the number of people who received greater than 100 mr in that particular category.
The grand total figure represents the total number of people who received 100 mr, whether in one of the categories or multiple categories. A specific person could receive dose in two or more categories, but they would be counted only once in the grand total.
As a result, the sum of the individual category totals does not necessarily equal the grand total.
Attachment to AEP:NRC:2691-02 Page 2 Reg. Guide 1.16 Report INDIANA MICHIGAN POWER / COOK NUCLEAR PLANT Prepared for Year 2001 Number of Personnel and Man-Rem by Work and Job Function Number of Personnel > 100 mrem Total Person-Rem Station Utility Contractors and Station Utility Contractors and Employees Employees Others Employees Employees Others Reactor Operation & Surveillance
-Maintenance 1
0 0
0.453 0.005 0.353
-Operations 0
0 0
1.640 0.001 0.165
-Health Physics 0
0 0
0.347 0.002 0.002
-Supervisory 0
0 0
0.015 0.000 0.021
-Engineering 0
0 0
0.160 0.023 0.079 Routine Maintenance
-Maintenance 10 0
4 5.089 0.065 2.283
-Operations 1
0 0
2.348 0.043 0.226
-Health Physics 19 0
1 5.000 0.000 0.230
-Supervisory 0
0 0
0.029 0.000 0.067
-Engineering 0
0 0
0.277 0.006 0.229 Inservice Inspection
-Maintenance 0
0 0
0.045 0.000 0.100
-Operations 0
0 0
0.034 0.001 0.002
-Health Physics 0
0 0
0.005 0.000 0.000
-Supervisory 0
0 0
0.000 0.000 0.000
-Engineering 0
0 0
0.005 0.000 0.051 Special Maintenance
-Maintenance 1
0 23 0.342 0.000 6.554
-Operations 0
0 2
0.117 0.000 0.762
-Health Physics 2
0 0
0.811 0.000 0.073
-Supervisory 0
0 0
0.000 0.000 0.060
-Engineering 0
0 0
0.004 0.000 0.028 Waste Processing
-Maintenance 0
0 0
0.081 0.001 0.130
-Operations 0
0 0
0.019 0.000 0.049
-Health Physics 3
0 0
1.243 0.000 0.110
-Supervisory 0
0 0
0.001 0.000 0.000
-Engineering 0
0 0
0.015 0.000 0.004 Refueling
-Maintenance 0
0 0
0.173 0.000 0.169
-Operations 0
0 0
0.058 0.000 0.023
-Health Physics 0
0 0
0.040 0.000 0.000
-Supervisory 0
0 0
0.009 0.000 0.006
-Engineering 0
0 0
0.007 0.000 0.002 Totals
-Maintenance 15 0
31 6.183 0.071 9.589
-Operations 4
0 2
4.216 0.044 1.227
-Health Physics 27 0
1 7.445 0.002 0.414
-Supervisory 0
0 0
0.054 0.000 0.153
-Engineering 0
0 0
0.467 0.029 0.394 Grand Totals 46 0
34 18.366 0.147 11.778
Attachment to AEP:NRC:2691-02 3.0 STEAM GENERATOR INSPECTIONS No steam generator tube in-service inspections were performed on either Unit 1 or Unit 2 4.0 CHALLENGES TO PRESSURIZER POWER OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES There were no challenges to the pressurizer PORVs or the pressurizer safety valves on either Unit 1 or Unit 2.
5.0 REACTOR COOLANT SPECIFIC ACTIVITY There were no instances in which the reactor coolant dose equivalent 1-131 specific activity exceeded the limits of Technical Specification 3.4.8 (greater than or equal to 1 ptCi/g) in either Unit 1 or Unit 2.
Compliance was determined by routine gamma spectrometry analysis of reactor coolant.
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