UNEVALUATED INFORMATION PROVIDED BY THE FACILITY
On this page:
Region 1
| Unit |
Power |
Down |
Reason or Comment |
Change in Report (*) |
Scrams (#) |
| Beaver Valley 1 |
60 |
|
HOLDING POWER AT THIS LEVEL TO PERFORM PLANNED MAINTENANCE ON A FEEDWATER PUMP |
* |
|
| Beaver Valley 2 |
100 |
|
|
|
|
| Calvert Cliffs 1 |
0 |
1999-05-10 |
MAINTENANCE OUTAGE - PREPARING TO ENTER MODE 4 |
* |
|
| Calvert Cliffs 2 |
100 |
|
|
* |
|
| FitzPatrick |
100 |
|
|
|
|
| Ginna |
98 |
|
OPERATING AT REDUCED LOAD DUE TO DELTA-T SETPOINT ISSUES |
|
|
| Hope Creek 1 |
100 |
|
|
|
|
| Indian Point 2 |
99 |
|
MAXIMUM OPERATING POWER DUE TO STEAM FLOW DEMAND - TURBINE THROTTLE VALVES FULLY OPEN |
|
|
| Indian Point 3 |
100 |
|
|
|
|
| Limerick 1 |
100 |
|
|
|
|
| Limerick 2 |
0 |
1999-04-16 |
REFUELING OUTAGE - FUEL MOVES COMPLETE - REACTOR REASSEMBLY IN PROGRESS |
* |
|
| Millstone 2 |
19 |
|
INCREASING POWER TO 29% FOR AN NRC HOLD |
* |
|
| Millstone 3 |
0 |
1999-05-01 |
REFUELING OUTAGE - FUEL OFFLOAD SUSPENDED DUE TO PROBLEMS WITH SIGMA MACHINE |
* |
|
| Nine Mile Point 1 |
0 |
1999-04-11 |
REFUELING OUTAGE - DEFUELED |
|
|
| Nine Mile Point 2 |
100 |
|
|
|
|
| Oyster Creek |
70 |
|
DECREASING TO 65% POWER TO PERFORM PLANNED MAINTENANCE ON A FEEDWATER HEATER |
* |
|
| Peach Bottom 2 |
72 |
|
INCREASING POWER AFTER REDUCING POWER TO THIS LEVEL TO PERFORM MAIN STEAM ISOLATION VALVE SOLENOID VALVE REPLACEMENT |
* |
|
| Peach Bottom 3 |
100 |
|
|
|
|
| Pilgrim 1 |
0 |
1999-05-08 |
REFUELING OUTAGE - FUEL OFFLOAD AND FUEL SHUFFLE IN PROGRESS |
|
|
| Salem 1 |
100 |
|
|
|
|
| Salem 2 |
0 |
1999-04-03 |
REFUELING OUTAGE |
|
|
| Seabrook 1 |
49 |
|
INCREASING POWER AFTER EXITING A REFUELING OUTAGE |
* |
|
| Susquehanna 1 |
100 |
|
|
|
|
| Susquehanna 2 |
100 |
|
|
|
|
| Three Mile Island 1 |
100 |
|
|
|
|
| Vermont Yankee |
100 |
|
|
|
|
Region 2
| Unit |
Power |
Down |
Reason or Comment |
Change in Report (*) |
Scrams (#) |
| Browns Ferry 1 |
0 |
1985-03-03 |
DEFUELED |
|
|
| Browns Ferry 2 |
100 |
|
|
* |
|
| Browns Ferry 3 |
100 |
|
|
|
|
| Brunswick 1 |
100 |
|
|
|
|
| Brunswick 2 |
0 |
1999-04-16 |
REFUELING OUTAGE |
|
|
| Catawba 1 |
0 |
1999-04-21 |
REFUELING OUTAGE |
* |
|
| Catawba 2 |
0 |
1999-05-03 |
MAINTENANCE OUTAGE - TROUBLESHOOTING INTERMEDIATE RANGE DETECTOR PROBLEM |
* |
|
| Crystal River 3 |
100 |
|
|
|
|
| Farley 1 |
100 |
|
|
|
|
| Farley 2 |
100 |
|
|
|
|
| Harris 1 |
100 |
|
|
|
|
| Hatch 1 |
97 |
|
HOLDING POWER AT THIS LEVEL TO PERFORM POWER UPRATE TESTING |
* |
|
| Hatch 2 |
98 |
|
MAXIMUM OPERATING POWER |
|
|
| McGuire 1 |
100 |
|
|
|
|
| McGuire 2 |
100 |
|
|
|
|
| North Anna 1 |
63 |
|
DECREASING TO 60% POWER TO PERFORM BUS DUCT COOLING MAINTENANCE |
* |
|
| North Anna 2 |
100 |
|
|
|
|
| Oconee 1 |
100 |
|
|
|
|
| Oconee 2 |
100 |
|
|
|
|
| Oconee 3 |
0 |
1999-05-15 |
FORCED MAINTENANCE OUTAGE DUE TO LOW REACTOR COOLANT PUMP OIL LEVEL |
* |
|
| Robinson 2 |
100 |
|
|
|
|
| Saint Lucie 1 |
100 |
|
|
|
|
| Saint Lucie 2 |
100 |
|
|
|
|
| Sequoyah 1 |
100 |
|
|
|
|
| Sequoyah 2 |
98 |
|
HOLDING POWER AT THIS LEVEL TO PERFORM NUCLEAR INSTRUMENTATION SYSTEM CALIBRATIONS AFTER EXITING A REFUELING OUTAGE |
* |
|
| Summer |
48 |
|
HOLDING POWER AT THIS LEVEL TO PERFORM FLUX MAPPING AND NUCLEAR INSTRUMENTATION CROSS CALIBRATION AFTER EXITING A REFUELING OUTAGE |
* |
|
| Surry 1 |
100 |
|
|
|
|
| Surry 2 |
0 |
1999-04-18 |
REFUELING OUTAGE |
|
|
| Turkey Point 3 |
100 |
|
|
|
|
| Turkey Point 4 |
100 |
|
|
|
|
| Vogtle 1 |
100 |
|
|
|
|
| Vogtle 2 |
100 |
|
|
|
|
| Watts Bar 1 |
100 |
|
|
|
|
Region 3
| Unit |
Power |
Down |
Reason or Comment |
Change in Report (*) |
Scrams (#) |
| Braidwood 1 |
100 |
|
|
|
|
| Braidwood 2 |
0 |
1999-04-23 |
REFUELING OUTAGE |
|
|
| Byron 1 |
0 |
1999-05-13 |
AUTOMATIC REACTOR TRIP FROM 100% POWER DUE TO AN INADVERTENT POWER RANGE HIGH FLUX SIGNAL DURING SURVEILLANCE TESTING (REFER TO EVENT #35710) - EXACT CAUSE UNDER INVESTIGATION |
* |
|
| Byron 2 |
100 |
|
|
|
|
| Clinton |
0 |
1999-05-14 |
REFUELING OUTAGE - MANUAL REACTOR SCRAM FROM 4% POWER DUE TO A LEVEL TRANSIENT ASSOCIATED WITH A FEED REGULATING VALVE MALFUNCTION (REFER TO EVENT #35715) - CAUSE DETERMINED TO BE BINDING ON PART OF VALVE THAT GIVES FEEDBACK TO CONTROL SYSTEM |
* |
|
| D.C. Cook 1 |
0 |
1997-09-08 |
MAINTENANCE OUTAGE |
|
|
| D.C. Cook 2 |
0 |
1997-09-09 |
REFUELING OUTAGE |
|
|
| Davis-Besse |
100 |
|
|
|
|
| Dresden 2 |
99 |
|
|
* |
|
| Dresden 3 |
99 |
|
|
|
|
| Duane Arnold |
100 |
|
|
|
|
| Fermi 2 |
97 |
|
ADMINISTRATIVE POWER LIMIT |
|
|
| Kewaunee |
97 |
|
POWER LIMITED DUE TO STEAM GENERATOR TUBE PLUGGING |
|
|
| La Salle 1 |
100 |
|
|
|
|
| La Salle 2 |
100 |
|
|
|
|
| Monticello |
0 |
1999-05-08 |
MAINTENANCE OUTAGE |
|
|
| Palisades |
0 |
1999-05-07 |
MAINTENANCE OUTAGE - REACTOR COOLANT SYSTEM SOLID - HEATUP IN PROGRESS |
* |
|
| Perry 1 |
100 |
|
|
|
|
| Point Beach 1 |
0 |
1999-05-14 |
MANUAL REACTOR TRIP FROM 100% POWER AND MANUAL SAFETY INJECTION DUE TO A STEAM LEAK ON THE 4B FEEDWATER HEATER STEAM SIDE (REFER TO EVENT #35714) - BREAK REPORTED TO BE 27" LONG AND APPROXIMATELY ½" WIDE |
* |
|
| Point Beach 2 |
52 |
|
HOLDING POWER AT THIS LEVEL TO PERFORM INSPECTION ON THE #4 FEEDWATER HEATERS |
* |
|
| Prairie Island 1 |
0 |
1999-04-16 |
REFUELING OUTAGE - FUEL RELOAD COMPLETE |
|
|
| Prairie Island 2 |
100 |
|
|
|
|
| Quad Cities 1 |
100 |
|
|
|
|
| Quad Cities 2 |
100 |
|
|
|
|
Region 4
| Unit |
Power |
Down |
Reason or Comment |
Change in Report (*) |
Scrams (#) |
| Arkansas Nuclear 1 |
100 |
|
|
|
|
| Arkansas Nuclear 2 |
100 |
|
|
|
|
| Callaway |
100 |
|
|
|
|
| Columbia Generating Station |
0 |
1999-04-17 |
MAINTENANCE OUTAGE |
|
|
| Comanche Peak 1 |
100 |
|
|
|
|
| Comanche Peak 2 |
100 |
|
|
|
|
| Cooper |
100 |
|
|
|
|
| Diablo Canyon 1 |
100 |
|
|
|
|
| Diablo Canyon 2 |
100 |
|
|
|
|
| Fort Calhoun |
100 |
|
|
|
|
| Grand Gulf 1 |
100 |
|
|
|
|
| Palo Verde 1 |
100 |
|
|
|
|
| Palo Verde 2 |
99 |
|
HOLDING POWER AT THIS LEVEL TO PERFORM TURBINE BYPASS VALVE TESTING |
* |
|
| Palo Verde 3 |
100 |
|
|
|
|
| River Bend 1 |
0 |
1999-04-03 |
REFUELING OUTAGE - FUEL SHUFFLE TEMPORARILY STOPPED |
* |
|
| San Onofre 2 |
100 |
|
|
|
|
| San Onofre 3 |
0 |
1999-05-13 |
MANUAL REACTOR TRIP FROM 97% POWER DUE TO LOSS OF BOTH FEEDWATER PUMPS (REFER TO EVENT #35713) - CAUSE DETERMINED TO BE A FAILED RELAY IN THE FEEDWATER REGULATING VALVE CONTROL SYSTEM WHICH CAUSE VALVE CLOSURE AND HIGH DISCHARGE PRESSURE ON BOTH PUMPS |
* |
|
| South Texas 1 |
100 |
|
|
|
|
| South Texas 2 |
100 |
|
|
|
|
| Waterford 3 |
100 |
|
|
|
|
| Wolf Creek 1 |
100 |
|
|
* |
|
* - Power Reactor Status Report change within past 24 hours
# - Number of reactor scrams or trips within past 24 hours
Notes:
- Reactor status data collected between 4 a.m. and 8 a.m. each day.
- All times are based on eastern time.