Event Notification Report for February 28, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/27/2003 - 02/28/2003
EVENT NUMBERS
39627
Power Reactor
Event Number: 39627
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: PETER DONAHUE
HQ OPS Officer: GERRY WAIG
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: PETER DONAHUE
HQ OPS Officer: GERRY WAIG
Notification Date: 02/28/2003
Notification Time: 14:10 [ET]
Event Date: 02/28/2003
Event Time: 08:57 [CST]
Last Update Date: 02/28/2003
Notification Time: 14:10 [ET]
Event Date: 02/28/2003
Event Time: 08:57 [CST]
Last Update Date: 02/28/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID GRAVES (R4)
DAVID GRAVES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
LESS THAN THE REQUIRED NUMBER OF OPERABLE EMERGENCY DIESEL GENERATORS
"While the plant was in cold shutdown, the division number 2 onsite emergency power (diesel generator) was made inoperable when it was discovered that the time delay relay, which energizes to cause the associated room cooling system to start when the diesel generator automatically initiates or the temperature in the room reaches 104 degrees F, was not replaced before exceeding it's analyzed service life. The division number 1 onsite emergency power (diesel generator) was already inoperable when the fuel oil transfer pump flow was found to be less than required while performing a technical specification surveillance test.
"Technical Specification Limiting Condition of Operation (LCO) [3.8.2] for AC Sources during shutdown was entered. This LCO is required to be entered when one diesel generator is not capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) to support equipment required to be operable. The following actions were immediately taken in accordance with this LCO and will remain in place until the LCO can be met:
1. Core alterations are not allowed.
2. Movement of irradiated fuel assemblies in secondary containment is not allowed.
3. Operations with the potential to drain the reactor vessel are not allowed.
4. Replacement of the subject relay was initiated.
"No fuel movement, core alterations or operations with the potential to drain the reactor vessel were in progress.
"All offsite power sources are available and operable. No maintenance will be conducted which could potentially affect the availability of these offsite sources or the associated distribution systems."
The licensee has notified the NRC Resident Inspector.
"While the plant was in cold shutdown, the division number 2 onsite emergency power (diesel generator) was made inoperable when it was discovered that the time delay relay, which energizes to cause the associated room cooling system to start when the diesel generator automatically initiates or the temperature in the room reaches 104 degrees F, was not replaced before exceeding it's analyzed service life. The division number 1 onsite emergency power (diesel generator) was already inoperable when the fuel oil transfer pump flow was found to be less than required while performing a technical specification surveillance test.
"Technical Specification Limiting Condition of Operation (LCO) [3.8.2] for AC Sources during shutdown was entered. This LCO is required to be entered when one diesel generator is not capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) to support equipment required to be operable. The following actions were immediately taken in accordance with this LCO and will remain in place until the LCO can be met:
1. Core alterations are not allowed.
2. Movement of irradiated fuel assemblies in secondary containment is not allowed.
3. Operations with the potential to drain the reactor vessel are not allowed.
4. Replacement of the subject relay was initiated.
"No fuel movement, core alterations or operations with the potential to drain the reactor vessel were in progress.
"All offsite power sources are available and operable. No maintenance will be conducted which could potentially affect the availability of these offsite sources or the associated distribution systems."
The licensee has notified the NRC Resident Inspector.