ML030580500
| ML030580500 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 02/13/2003 |
| From: | George Gellrich AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 5928-03-20025 | |
| Download: ML030580500 (4) | |
Text
Amerkomi..
An Exelon/Brtish Energy Company AmerGen Energy Company, LLC Telephone 717-944-7621 Three Mile Island Unit 1 Route 441 South, P 0 Box 48o Middletown, PA 17057 February 13, 2003 5928-03-20025 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 THREE MILE ISLAND UNIT I (TMI UNIT 1)
OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
SUBJECT:
MONTHLY OPERATING REPORT FOR JANUARY 2003 Enclosed are two copies of the January 2003 Monthly Operating Report for Three Mile Island Unit 1. The content and format of information submitted in this report is in accordance with the guidance provided by Generic Letter 97-02.
Additionally, as required by Technical Specification 3.24, information is provided on the status of the Reactor Vessel Water Level Instrumentation System. On January 25, 2003, both channels of the Reactor Vessel Water Level Instrumentation System were isolated.
Information on the cause for this isolation, the action being taken and the projected date for return to operable status are contained in the summary section of Appendix B.
Sincerely, George H. Gellrich Plant Manager GHG/awm
Enclosure:
Appendix A, and Appendix B cc: Administrator, Region I TMI-1 Senior Resident Inspector File 03001
Document Control Desk 5928-03-20025 Page 2 of 4 APPENDIX A OPERATING DATA REPORT DOCKET NO. 50-289 DATE February 13, 2003 COMPLETED BY A. W. MILLER TELEPHONE (717) 948-8128 REPORTING PERIOD: January 2003 YEAR TO MONTH DATE CUMULATIVE
- 1. DESIGN ELECTRICAL RATING (MWe NET). 819.0 **
The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.
- 2. MAXIMUM DEPENDABLE CAPACITY (MWe NET). 802.0 **
The gross electrical output as measured at the output terminals of the turbine generator during the most restrictive seasonal conditions minus the normal station service loads.
- 3. NUMBER OF HOURS REACTOR WAS CRITICAL. 744.0 744.0 167,990.3 The total number of hours during the gross hours of the reporting period that the reactor was critical.
- 4. HOURS GENERATOR ON LINE. 744.0 744.0 166,405.0 (Service Hours) The total number of hours during the gross hours of the reporting period that the unit operated with the breakers closed to the station bus. The sum of the hours that the generator was on line plus the total outage hours in the reporting period.
- 5. UNIT RESERVE SHUTDOWN HOURS. 0.0 0.0 0.0 The total number of hours during the gross hours of the reporting period that the unit was removed from service for economic or similar reasons but was available for operation.
- 6. NET ELECTRICAL ENERGY (MWH)., 631,984.0 631,984.0 132,154,910.4 The gross electrical output of the unit measured at the output terminals of the turbine generator minus the normal station service loads during the gross hours of the reporting period, expressed in megawatt hours. Negative quantities should not be used.
- Design values have no "Year to Date" or "Cumulative" significance.
Document Control Desk 5928-03-20025 Page 3 of 4 APPENDIX B UNIT SHUTDOWNS DOCKET NO. 50-289 DATE February 13, 2003 COMPLETED BY A. W. MILLER TELEPHONE (717) 948-8128 REPORTING PERIOD: January 2003 Cause &Corrective Action to Prevent Recurrence None 1 2 3 F Forced Reason Method S Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Explain)
E-Operator Training &Licensing Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
SUMMARY
- The plant entered January at 100% power and remained at nominal full power for the remainder of the month.
On January 23, 2003, an inspection in the basement area of the Reactor Building (inside the "B" D-Ring) identified a RCS leak on the line associated with the Reactor Vessel Water Level Instrumentation System. The leak, at a % inch to 2 inch reducing fitting, was isolated by closing the two Reactor Vessel Water Level
- Instrumentation System isolation valves on January 25, 2003. The closing of these valves results in both channels of the Reactor Vessel Water Level
Document Control Desk 5928-03-20025 Page 4 of 4
SUMMARY
(continued)
Instrumentation System being inoperable. Since it is not feasible to repair this leak during power operation without incurring significant radiological exposure, both channels of the Reactor Vessel Water Level Instrumentation System will remain inoperable till the next scheduled refueling outage.
Continued power operations with both channels of the Reactor Vessel Water Level Instrumentation System inoperable is allowed in accordance with Technical Specification (TS) 3.24. TS 3.24 states that ifat least one channel is not restored within seven days, details are required to be provided in this report. These details must include cause, action being taken, and projected date for return to operable status.
Both channels of the Reactor Vessel Water Level Instrumentation System are inoperable because isolation valves are closed to mitigate a RCS leak on the instrumentation line associated with the Reactor Vessel Water Level Instrumentation System. It is anticipated that the Reactor Vessel Water Level Instrumentation System will remain isolated through the next scheduled refueling outage that will begin in October 2003, when repairs will be accomplished. The repair activities are currently being planned. Following repairs, both channels of the Reactor Vessel Water Level Instrumentation System will be returned to operable status prior to reactor criticality (currently scheduled for November 2003).
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