Event Notification Report for August 25, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/24/2005 - 08/25/2005
Power Reactor
Event Number: 41946
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICK GUERRA
HQ OPS Officer: PETE SNYDER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICK GUERRA
HQ OPS Officer: PETE SNYDER
Notification Date: 08/25/2005
Notification Time: 12:07 [ET]
Event Date: 08/25/2005
Event Time: 11:41 [EDT]
Last Update Date: 08/25/2005
Notification Time: 12:07 [ET]
Event Date: 08/25/2005
Event Time: 11:41 [EDT]
Last Update Date: 08/25/2005
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
DAVID AYRES (R2)
PETER WILSON (IRD)
IAN JUNG (NRR)
KEN SWEETSER (FEMA)
KRAUSE (DHS)
DAVID AYRES (R2)
PETER WILSON (IRD)
IAN JUNG (NRR)
KEN SWEETSER (FEMA)
KRAUSE (DHS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNUSUAL EVENT DECLARED DUE TO FIRE IN PROTECTED AREA
"At 1125 on 8/25/05, the 'B' condensate pump tripped. Upon investigation, the turbine building operator noticed smoke coming from the pump motor. There was no visible flame at this time. In response, the 'A' condensate pump was started. Due to a suspected malfunction of the 'A' condensate pump discharge valve, a low water level condition developed in the deaerator storage tank. The order was then given to manually trip the reactor. However, before the operator could complete this action, the low level condition automatically tripped the feedwater pumps and the main turbine which by design tripped the reactor at 1133.
"A Notification of Unusual Event (NUE) was declared at 1141 due to a fire in the protected area lasting for more than 15 minutes. The fire was initially extinguished at 1200. Subsequently, a small flame was noted within the pump motor housing upon removal of an inspection cover at 1253. The fire was ultimately extinguished at 1317.
"The plant is currently stable in mode 3. According to current indications, all safety systems operated as required. The fire was fully contained within the pump motor housing and did not cause any collateral damage. No radioactivity was released to the environment and there were no injuries."
The licensee requested offsite assistance from the Fairfield Fire Department.
All control rods fully inserted from the automatic trip. Decay heat was being removed via emergency feedwater into the steam generators through the steam dumps into the main condenser. Normal offsite power was available and electrical power was in normal alignment.
The licensee notified the NRC Resident Inspector. The licensee notified state and local government agencies.
* * * UPDATE ON 8/25/05 AT 1346 EDT FROM R. SWEET TO SNYDER * * *
At 1327 the licensee terminated the Unusual Event. The licensee was continuing to investigate the cause of the automatic reactor trip and the fire.
Notified R2DO (D. Ayers), NRR EO (I. Jung), IRD Manager (P. Wilson), FEMA (K. Sweetser), and DHS (Krause).
"At 1125 on 8/25/05, the 'B' condensate pump tripped. Upon investigation, the turbine building operator noticed smoke coming from the pump motor. There was no visible flame at this time. In response, the 'A' condensate pump was started. Due to a suspected malfunction of the 'A' condensate pump discharge valve, a low water level condition developed in the deaerator storage tank. The order was then given to manually trip the reactor. However, before the operator could complete this action, the low level condition automatically tripped the feedwater pumps and the main turbine which by design tripped the reactor at 1133.
"A Notification of Unusual Event (NUE) was declared at 1141 due to a fire in the protected area lasting for more than 15 minutes. The fire was initially extinguished at 1200. Subsequently, a small flame was noted within the pump motor housing upon removal of an inspection cover at 1253. The fire was ultimately extinguished at 1317.
"The plant is currently stable in mode 3. According to current indications, all safety systems operated as required. The fire was fully contained within the pump motor housing and did not cause any collateral damage. No radioactivity was released to the environment and there were no injuries."
The licensee requested offsite assistance from the Fairfield Fire Department.
All control rods fully inserted from the automatic trip. Decay heat was being removed via emergency feedwater into the steam generators through the steam dumps into the main condenser. Normal offsite power was available and electrical power was in normal alignment.
The licensee notified the NRC Resident Inspector. The licensee notified state and local government agencies.
* * * UPDATE ON 8/25/05 AT 1346 EDT FROM R. SWEET TO SNYDER * * *
At 1327 the licensee terminated the Unusual Event. The licensee was continuing to investigate the cause of the automatic reactor trip and the fire.
Notified R2DO (D. Ayers), NRR EO (I. Jung), IRD Manager (P. Wilson), FEMA (K. Sweetser), and DHS (Krause).
Power Reactor
Event Number: 41947
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: GERRY WAIG
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: GERRY WAIG
Notification Date: 08/25/2005
Notification Time: 15:58 [ET]
Event Date: 08/25/2005
Event Time: 10:59 [CDT]
Last Update Date: 08/25/2005
Notification Time: 15:58 [ET]
Event Date: 08/25/2005
Event Time: 10:59 [CDT]
Last Update Date: 08/25/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
WILLIAM JONES (R4)
WILLIAM JONES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
POSITIVE RANDOM FITNESS FOR DUTY TEST - ALCOHOL
A licensed employee was determined to be under the influence of alcohol during a random fitness-for-duty test. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.
A licensed employee was determined to be under the influence of alcohol during a random fitness-for-duty test. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 41948
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: FRANCIS CLIFFORD
HQ OPS Officer: PETE SNYDER
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: FRANCIS CLIFFORD
HQ OPS Officer: PETE SNYDER
Notification Date: 08/25/2005
Notification Time: 20:39 [ET]
Event Date: 08/25/2005
Event Time: 16:30 [EDT]
Last Update Date: 09/27/2005
Notification Time: 20:39 [ET]
Event Date: 08/25/2005
Event Time: 16:30 [EDT]
Last Update Date: 09/27/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WILLIAM COOK (R1)
WILLIAM COOK (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE COOLANT INJECTION INOPERABLE DUE TO FLOW OSCILLATIONS
"This report is being made in accordance with 10CFR50.72 (b) (3) (v) due to the High Pressure Coolant Injection (HPCI) system being declared inoperable. HPCI was declared inoperable on 8/25/05 at 1630 EST due to oscillations at below rated flow during the scheduled operability testing. HPCI was restored to standby line-up when testing was completed and remains available for use. This event is an eight hour notification. Efforts are on going to determine the cause of the oscillations on the Flow Controller. This event had no adverse effect to the health and safety of the public.
"The resident NRC inspector has been notified of this event."
* * * RETRACTION FROM D. NOYES TO W. GOTT AT 1711 ON 09/27/05 * * *
"This follow-up notification is being made to retract the notification made to the NRC Operations Center on 8/25/05 at 2039 hours (notification #41948).
"The initial report was made in accordance with 10 CFR 50.72(b)(3) due to the HPCI system being declared inoperable. The system was declared inoperable due to oscillations in turbine speed, pump discharge pressure, and pump flow during a quarterly surveillance test of the HPCI pump.
"Further investigation and evaluation of this has been performed. The cause of the noted oscillations was the position of a hand operated valve that is located in the HPCI system full flow test line. The hand operated valve is located downstream of an in-series motor operated valve that automatically closes if an automatic HPCI system initiation signal occurs. The full flow test line is not part of the HPCI injection pathway to the reactor vessel. As a result, the position of this valve would not have impacted the ability of the system to perform its design function. After adjusting the position of the hand operated valve, the surveillance test of the HPCI pump was completed with satisfactory results.
"The evaluation has determined that the HPCI system was capable of performing the designed safety function. Therefore, the HPCI system was not inoperable and event notification #41948 is retracted."
The licensee notified the NRC Resident Inspector.
Notified R1DO (C. Cahill)
"This report is being made in accordance with 10CFR50.72 (b) (3) (v) due to the High Pressure Coolant Injection (HPCI) system being declared inoperable. HPCI was declared inoperable on 8/25/05 at 1630 EST due to oscillations at below rated flow during the scheduled operability testing. HPCI was restored to standby line-up when testing was completed and remains available for use. This event is an eight hour notification. Efforts are on going to determine the cause of the oscillations on the Flow Controller. This event had no adverse effect to the health and safety of the public.
"The resident NRC inspector has been notified of this event."
* * * RETRACTION FROM D. NOYES TO W. GOTT AT 1711 ON 09/27/05 * * *
"This follow-up notification is being made to retract the notification made to the NRC Operations Center on 8/25/05 at 2039 hours (notification #41948).
"The initial report was made in accordance with 10 CFR 50.72(b)(3) due to the HPCI system being declared inoperable. The system was declared inoperable due to oscillations in turbine speed, pump discharge pressure, and pump flow during a quarterly surveillance test of the HPCI pump.
"Further investigation and evaluation of this has been performed. The cause of the noted oscillations was the position of a hand operated valve that is located in the HPCI system full flow test line. The hand operated valve is located downstream of an in-series motor operated valve that automatically closes if an automatic HPCI system initiation signal occurs. The full flow test line is not part of the HPCI injection pathway to the reactor vessel. As a result, the position of this valve would not have impacted the ability of the system to perform its design function. After adjusting the position of the hand operated valve, the surveillance test of the HPCI pump was completed with satisfactory results.
"The evaluation has determined that the HPCI system was capable of performing the designed safety function. Therefore, the HPCI system was not inoperable and event notification #41948 is retracted."
The licensee notified the NRC Resident Inspector.
Notified R1DO (C. Cahill)