Event Notification Report for February 05, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/04/2007 - 02/05/2007
EVENT NUMBERS
43141431424314343144
Power Reactor
Event Number: 43141
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JERRY SHEPP
HQ OPS Officer: JEFF ROTTON
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JERRY SHEPP
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/05/2007
Notification Time: 06:38 [ET]
Event Date: 02/05/2007
Event Time: 03:07 [EST]
Last Update Date: 02/05/2007
Notification Time: 06:38 [ET]
Event Date: 02/05/2007
Event Time: 03:07 [EST]
Last Update Date: 02/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MIKE ERNSTES (R2)
MIKE ERNSTES (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 95 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO STEAM LEAK DURING MAIN FEED BOOSTER PUMP STARTUP
"While starting D Feedwater Booster pump, a steam leak developed in the Turbine building. The Reactor was manually tripped at 0307 on 02/05/07. Investigation revealed that an orifice (XPS0006D) in the D Feedwater Booster pump recirculation header was the source of the leak. The steam/water leak was isolated at 0500 on 02/05/07. All systems responded normally on the Reactor trip. Emergency Feedwater (AFW) system started on LoLo Steam Generator level. Steam Generator level recovered quickly."
All control rods fully inserted on the manual Reactor trip signal. No relief valves or PORVs lifted as a result of the transient. Decay heat is being removed by the main condenser via the steam dump valves.
The licensee notified the NRC Resident Inspector.
"While starting D Feedwater Booster pump, a steam leak developed in the Turbine building. The Reactor was manually tripped at 0307 on 02/05/07. Investigation revealed that an orifice (XPS0006D) in the D Feedwater Booster pump recirculation header was the source of the leak. The steam/water leak was isolated at 0500 on 02/05/07. All systems responded normally on the Reactor trip. Emergency Feedwater (AFW) system started on LoLo Steam Generator level. Steam Generator level recovered quickly."
All control rods fully inserted on the manual Reactor trip signal. No relief valves or PORVs lifted as a result of the transient. Decay heat is being removed by the main condenser via the steam dump valves.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43142
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN GRAHAM
HQ OPS Officer: JEFF ROTTON
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN GRAHAM
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/05/2007
Notification Time: 07:24 [ET]
Event Date: 02/05/2007
Event Time: 07:07 [EST]
Last Update Date: 02/05/2007
Notification Time: 07:24 [ET]
Event Date: 02/05/2007
Event Time: 07:07 [EST]
Last Update Date: 02/05/2007
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):
CHRISTOPHER CAHILL (R1)
MARY JANE ROSS-LEE (NRR)
MELVYN LEACH (IRD)
BARNES (DHS)
LIGGETT (FEMA)
CHRISTOPHER CAHILL (R1)
MARY JANE ROSS-LEE (NRR)
MELVYN LEACH (IRD)
BARNES (DHS)
LIGGETT (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNUSUAL EVENT DECLARED DUE TO LOW SERVICE WATER INTAKE LEVEL
Licensee provided the following details via facsimile on 02/05/05 at 1305 EST:
"On February 5, 2007, at approximately 05:30 hours, the control room received an alarm for 'intake structure or traveling screen trouble alarm,' and a nuclear plant operator was dispatched to investigate the condition. At approximately 05:57 hours, the control room was notified that the alarm was due to low screen wash pressure on all traveling water screens as a result of the all screen wash pumps found tripped. Review of the Emergency Plan (EP) determined that Emergency Action Level (EAL) 8.4.3, 'Service Water Level 4 Feet, 5 Inches Below Mean Sea Level, 'was met and entry into an Notification of Unusual Event (NUE) was required. At approximately 07:07 hours, operations entered an NUE for EP EAL 8.4.3. Further investigation and corrective action are in progress. At approximately 07:24 hours, the NRC Emergency Operations Center was notified of the NUE (Jeff Rotton)."
Licensee reported entering EAL 8.4.3 - Service Water Bay Level < 4 feet 5 inches below mean sea level. There are presently no other open LCOs that impact Service Water operability.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1058 EST ON 2/5/07 FROM J. HARVEY TO P. SNYDER * * *
The licensee terminated the Unusual Event at 1014 based on the fact that:
(a) Service Water Bay Levels had increased to 1 ft below mean sea level and were rising,
(b) The licensee initiated cleaning of the trash rack for the intake structure, and
(c) the time for an unusually low tide was now passed.
The licensee notified the NRC Resident Inspector. Notified R1DO (Cahill), IRD Mgr (Leach), NRR EO (Ross-Lee), DHS (T. Barnes), FEMA (C. Liggett), and R4 (L. Howell).
Licensee provided the following details via facsimile on 02/05/05 at 1305 EST:
"On February 5, 2007, at approximately 05:30 hours, the control room received an alarm for 'intake structure or traveling screen trouble alarm,' and a nuclear plant operator was dispatched to investigate the condition. At approximately 05:57 hours, the control room was notified that the alarm was due to low screen wash pressure on all traveling water screens as a result of the all screen wash pumps found tripped. Review of the Emergency Plan (EP) determined that Emergency Action Level (EAL) 8.4.3, 'Service Water Level 4 Feet, 5 Inches Below Mean Sea Level, 'was met and entry into an Notification of Unusual Event (NUE) was required. At approximately 07:07 hours, operations entered an NUE for EP EAL 8.4.3. Further investigation and corrective action are in progress. At approximately 07:24 hours, the NRC Emergency Operations Center was notified of the NUE (Jeff Rotton)."
Licensee reported entering EAL 8.4.3 - Service Water Bay Level < 4 feet 5 inches below mean sea level. There are presently no other open LCOs that impact Service Water operability.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1058 EST ON 2/5/07 FROM J. HARVEY TO P. SNYDER * * *
The licensee terminated the Unusual Event at 1014 based on the fact that:
(a) Service Water Bay Levels had increased to 1 ft below mean sea level and were rising,
(b) The licensee initiated cleaning of the trash rack for the intake structure, and
(c) the time for an unusually low tide was now passed.
The licensee notified the NRC Resident Inspector. Notified R1DO (Cahill), IRD Mgr (Leach), NRR EO (Ross-Lee), DHS (T. Barnes), FEMA (C. Liggett), and R4 (L. Howell).
Power Reactor
Event Number: 43143
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: DONALD DETTMAN
HQ OPS Officer: PETE SNYDER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: DONALD DETTMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 02/05/2007
Notification Time: 08:28 [ET]
Event Date: 02/05/2007
Event Time: 05:25 [EST]
Last Update Date: 02/05/2007
Notification Time: 08:28 [ET]
Event Date: 02/05/2007
Event Time: 05:25 [EST]
Last Update Date: 02/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTOPHER CAHILL (R1)
NADER MAMISH (DDEP)
CHRISTOPHER CAHILL (R1)
NADER MAMISH (DDEP)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
BLOCKED EMERGENCY VEHICLE ACCESS
"Ginna Station Site access for emergency vehicles has been unavailable since 0525 this morning due to the inability to lower both the North and South Active Vehicle Barriers."
The licensee notified the NRC Resident Inspector.
"Ginna Station Site access for emergency vehicles has been unavailable since 0525 this morning due to the inability to lower both the North and South Active Vehicle Barriers."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43144
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN FINCH
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: BRIAN FINCH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/05/2007
Notification Time: 12:25 [ET]
Event Date: 02/05/2007
Event Time: 04:30 [EST]
Last Update Date: 02/06/2007
Notification Time: 12:25 [ET]
Event Date: 02/05/2007
Event Time: 04:30 [EST]
Last Update Date: 02/06/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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 | 98 | Power Operation | 98 | Power Operation |
LOSS OF STACK EFFLUENT MONITORING CAPABILITY
"At 0430 on 2/5/07, Nine Mile Point Unit 1 determined that the capability to determine effluent radioactivity going out the stack has been lost. It is postulated that this is likely due to moisture in the primary and auxiliary sampling line which has frozen and blocking the flow of effluent to the sample analysis equipment.
"Compensatory actions include monitoring alternate indications of increased radioactivity in the plant effluent steams. A method has been proceduralized to sum systems that input to the stack. Portions of the systems required for monitoring plant effluents are currently out of service for preventive maintenance. It is expected that they will be returned to service by 1700 hours today." The State of New York will be notified of this event.
The NRC Resident Inspector was notified of this event by the licensee.
See similar event # 43125 reported by Nine Mile Point Unit 1 on 01/26/07
* * * UPDATE ON 02/06/07 AT 1615 EST BY BRIAN FINCH TO MACKINNON * * *
"The systems required for compensatory actions using alternate indications for monitoring plant effluents for the backup methodology previously reported out of service for preventative maintenance were returned to service as of 12:00 EST 2/05/07" R1DO (Bill Cook) notified.
The NRC Resident Inspector was notified of this update by the licensee.
"At 0430 on 2/5/07, Nine Mile Point Unit 1 determined that the capability to determine effluent radioactivity going out the stack has been lost. It is postulated that this is likely due to moisture in the primary and auxiliary sampling line which has frozen and blocking the flow of effluent to the sample analysis equipment.
"Compensatory actions include monitoring alternate indications of increased radioactivity in the plant effluent steams. A method has been proceduralized to sum systems that input to the stack. Portions of the systems required for monitoring plant effluents are currently out of service for preventive maintenance. It is expected that they will be returned to service by 1700 hours today." The State of New York will be notified of this event.
The NRC Resident Inspector was notified of this event by the licensee.
See similar event # 43125 reported by Nine Mile Point Unit 1 on 01/26/07
* * * UPDATE ON 02/06/07 AT 1615 EST BY BRIAN FINCH TO MACKINNON * * *
"The systems required for compensatory actions using alternate indications for monitoring plant effluents for the backup methodology previously reported out of service for preventative maintenance were returned to service as of 12:00 EST 2/05/07" R1DO (Bill Cook) notified.
The NRC Resident Inspector was notified of this update by the licensee.