| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/15/2009 - 10/16/2009 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 45433 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/15/2009
Notification Time: 09:06 [ET]
Event Date: 10/15/2009
Event Time: 05:37 [CDT]
Last Update Date: 10/15/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 97 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO REACTOR RECIRCULATION PUMP TRIP
"At 0537 hours on October 15, 2009, the 'B' Reactor Recirculation pump tripped. The reactor mode switch was placed in shutdown due to rising reactor water level (approx. 49 inches) prior to the Level 8 automatic scram setpoint (52 inches). All controls rods inserted as a result of the manual scram. All systems performed as expected. Reactor water level is being controlled by the motor driven feedwater pump. Main steam isolation valves were manually closed and decay heat was initially controlled through the main steam line drains to the main condenser via the main turbine bypass valves. Reactor Core Isolation Cooling (RCIC) was manually placed into service (tank-to-tank) to assist in RPV pressure control. RCIC is currently being used for decay heat removal. Investigation is underway to determine the cause of the Reactor Recirculation pump trip."
The licensee will be contacting the state, and issuing a press release.
The NRC Senior Resident Inspector has been notified. |
| Power Reactor | Event Number: 45434 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MICHAEL NEMCEK
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/15/2009
Notification Time: 14:47 [ET]
Event Date: 10/15/2009
Event Time: 12:25 [EDT]
Last Update Date: 10/15/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 75 | Power Operation | Event Text UNIT COMMENCED SHUTDOWN DUE TO INOPERABLE DIVISION 2 EMERGENCY SERVICE WATER SYSTEM
"This event is being reported in accordance with 10CFR50.72(b)(2)(i). On October 15, 2009, at approximately 1225 hours, the Perry Nuclear Power Plant commenced a Technical Specification required plant shutdown.
"On October 14, 2009, At 1747 hours, the Division 2 Emergency Service Water (ESW) system was declared inoperable and unavailable for planned work. The plant entered Technical Specification (TS) 3.7.1 Action A for one inoperable ESW Division. Other supported TSs were also entered (TS 3.8.1 for the Division 2 diesel generator, TS 3.6.1.7 for Containment Spray 'B', TS 3.6.2.3 for Suppression Pool Cooling 'B', TS 3.7.10 for Emergency Closed Cooling 'B', TS 3.5.1 for LPCI 'B' & 'C', among others).
"On October 15, 2009, at 0601 hours, the ESW 'B' pump was started for a planned pump run. At 0718 hours, the ESW 'B' pump tripped for unknown reasons. The determination was made to commence a controlled plant shutdown and power reduction commenced at 1225 hours. This decision was based on the anticipated investigation and repair time of ESW 'B' pump exceeding the TS 3.7.1 Action A 72 hour LCO completion time, and therefore, Action B requires the plant to be in MODE 3 within 12 hours and in MODE 4 in 36 hours. The TS 3.7.1 Action A 72 hour LCO completion time coincides with October 17, 2009, at 1747 hours.
"Currently, the plant is expected to be in MODE 3 at approximately 2300 hours on October 15, 2009.
"The NRC Resident Inspector has been notified. The State and Counties will also be notified." |
| Power Reactor | Event Number: 45437 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRIAN JOHNSON
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/15/2009
Notification Time: 17:13 [ET]
Event Date: 10/15/2009
Event Time: 14:49 [CDT]
Last Update Date: 10/15/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO MINOR OIL SPILL TO THE MISSISSIPPI RIVER
An oil spill of less than 1/2 of a cup to the Mississippi River occurred while preparing for Intake Structure dredging activities. Hydraulic oil leaked out of a fitting for the dredging pump and entered the Mississippi River side of the Intake Screenhouse. A small oil sheen was noticed and collected using the pre-deployed absorbents. The fitting was repaired and no more oil is currently leaking. The Minnesota Pollution Control Agency and the National Response Center were notified.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45438 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DAVID KARST
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/15/2009
Notification Time: 18:11 [ET]
Event Date: 10/15/2009
Event Time: 12:04 [CDT]
Last Update Date: 10/15/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text MOMENTARY LOSS OF SHUTDOWN COOLING WITH AUTOSTART OF EMERGENCY DIESEL GENERATOR
"At 1204 power was lost to Safeguards Bus '5' and Emergency Diesel Generator 'A' started and re-energized Bus '5.'
"Event was caused by starting SI Pump 'A' to fill SI Accumulator 'A' which resulted in a Tertiary Auxiliary Transformer trip and lockout. At the time RHR Pump 'A' was in operation and tripped, RHR Pump 'B' was started within 2 minutes using the Abnormal Operating Procedure and flow restored to the RCS. RCS temperature decreased initially due to an increase in service water cooling and actions were taken to stabilize RCS Temperature.
"All equipment operated as expected for the voltage restoration to Safeguards Bus '5.'
"Both trains of RHR were declared inoperable as of 1204 [CDT] due to the loss of normal power supplies per Technical Specification 3.7. Emergency Busses were energized and both trains of RHR remained available for decay heat removal during this event."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 45440 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: VINCE KLCO | Notification Date: 10/16/2009
Notification Time: 01:48 [ET]
Event Date: 10/16/2009
Event Time: 00:48 [EDT]
Last Update Date: 10/16/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 30 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO REACTOR RECIRCULATION PUMP TRIP
"On October 16, 2009 at 0048 a manual reactor scram was inserted at the Perry Nuclear Plant.
"The plant was conducting a planned shutdown due to the Division 2 Emergency Service Water inoperability. While shifting reactor recirculation pumps to slow speed the 'A' pump failed to transfer and tripped off. Following stabilization from this event a manual reactor scram was inserted from approximately 30% power. This was different from the initial planned shutdown sequence.
"Following the scram all systems operated as expected. The plant is stable in Mode 3. The plant will transition to Mode 4 in accordance with Technical Specification 3.7.1 (Emergency Service Water Inoperability) required actions."
All control rods fully inserted and the plant electrical power is in a normal line-up.
The licensee notified the NRC Resident Inspector. | |