ML040230328
| ML040230328 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/12/2004 |
| From: | George Gellrich AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 5928-04-20020, GL-97-002 | |
| Download: ML040230328 (4) | |
Text
AmerGen]SM AmerGen Energy Company, LLC Telephone: 717-944-7621 An Exelon/British Energy Company Three Mile Island Unit 1 Route 44i South, P.O. Box 480 Middletown, PA 17057 January 12, 2004 5928-04-20020 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 DECEMBER 2003 Enclosed are two copies of the December 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 9Z02.
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 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 04001
Document Control Desk 5928-04-20020 Page 2 of 4 APPENDIX A OPERATING DATA REPORT DOCKET NO. 50-289 DATE January 12, 2004 COMPLETED BY A. W. MILLER TELEPHONE (717) 948-8128 REPORTING PERIOD: December 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.
667.1 7,631.6 174,877.9.
The total number of hours during the gross hours of the reporting period that the reactor was critical.
- 4.
HOURS GENERATOR ON LINE.
643.0 7,602.2 173,263.2 (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).
418,815.0 6,205,073.0 137,727,999.4 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 KYear to Date" or"Cumulative" significance.
Document Control Desk 5928-04-20020 Page 3 of 4 APPENDIX B UNIT SHUTDOWNS DOCKET NO. 50-289 DATE January 12, 2004
. COMPLETED BY A. W. MILLER TELEPHONE (717) 948-8128 REPORTING PERIOD: December 2003 Generator Off Line Method of Cause & Corrective No Date Type' Duration Reason2 Shutting Action to (Hours)
Down Prevent Recurrence Reactor' 12/04/03 F
6.3 A
4 Main generator was synchronized to the grid following refueling outage T1 R1 5, on 12/4/03 at l
22:40. Both output breakers were opened at 22:47 on 12/4/03, based on main turbine bearing high vibrations. The reactor remained on-line. The unit was re-synchronized to the grid on 1215/03 at 05:04.
I F Forced S Scheduled 2
Reason.
A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain) 3 Method 1-Manual 2-Manual Scram 3-Automatic Scram 4-Other (Explain)
SUMMARY
- On 12/4/03, at 04:52, the reactor reached criticality following refueling outage T1 R15. On 12/4103, at 22:40, main generator output breakers were r, losed. At 22:47, main generator output breakers were opened due to high vibrations on the main turbine bearings. The main generator output breakers were again tclosed on 12/5/03 at 05:04, and power ascension began. On 12/7/03, at approximately 01:50, with the unit at approximately 98% power, main feedwater pump 1A (FW-P-1A) failed. This resulted in an unplanned power reduction to approximately 63% power. Following evaluation, power was raised from 63% to approximately
'75% on 12/13/03 at 15:30. Following repairs to FW-P-1A, power was increased to 100% on 12/21/03 at 17:21. The unit ended the month at 100% power.
Document Control Desk 5928-03-20239 Page 4 of 4
SUMMARY
(continued)
On January 23, 2003, an inspection in the basement area of the Reactor Building (inside the "BB D-Ring) identified a RCS leak on the line associated with the Reactor Vessel Water Level Instrumentation System. The leak, at a % inch to % 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 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 remained 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 if at 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 were inoperable because isolation valves were closed to mitigate a RCS leak on the instrumentation line associated with the Reactor Vessel Water Level Instrumentation System. The repair activities were completed and the system was returned to operable status on December 3, 2003, following post-maintenance inspection.