Event Notification Report for April 02, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/01/2015 - 04/02/2015
EVENT NUMBERS
50949509465094750948
Power Reactor
Event Number: 50949
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JOHN VESELY
HQ OPS Officer: DANIEL MILLS
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JOHN VESELY
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/03/2015
Notification Time: 01:32 [ET]
Event Date: 04/02/2015
Event Time: 21:33 [CDT]
Last Update Date: 04/03/2015
Notification Time: 01:32 [ET]
Event Date: 04/02/2015
Event Time: 21:33 [CDT]
Last Update Date: 04/03/2015
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 20 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO STEAM LEAK
"On April 2, 2015 at 2133 CDT, a manual scram was inserted on Unit 1 following discovery of a steam leak in the Turbine Building at the D-ring, near the Turbine Bypass valves. Following the reactor scram, reactor water level decreased to approximately -2 inches, which resulted in an automatic Group II and Group III isolation (expected response). The steam leak was isolated by manual closure of the Main Steam Isolation Valves. All systems responded properly to the event. Unit 1 remains in Mode 3, with cooldown in progress. Reactor water level is in the normal level band. The cause and details of the event are under investigation. Unit 2 was unaffected by the event and remains at 100 percent power."
Operators reduced reactor power to 20 percent before initiating a SCRAM. All rods fully inserted and the reactor is shutdown and stable. The electrical supply is in a normal shutdown lineup. The reactor is being supplied by normal feedwater, and decay heat is being controlled by use of the ADS valves. The licensee is currently cooling down and depressurizing the reactor in preparation for repair of the steam leak.
The licensee has notified the NRC Resident Inspector and the State of Illinois Resident Inspector.
"On April 2, 2015 at 2133 CDT, a manual scram was inserted on Unit 1 following discovery of a steam leak in the Turbine Building at the D-ring, near the Turbine Bypass valves. Following the reactor scram, reactor water level decreased to approximately -2 inches, which resulted in an automatic Group II and Group III isolation (expected response). The steam leak was isolated by manual closure of the Main Steam Isolation Valves. All systems responded properly to the event. Unit 1 remains in Mode 3, with cooldown in progress. Reactor water level is in the normal level band. The cause and details of the event are under investigation. Unit 2 was unaffected by the event and remains at 100 percent power."
Operators reduced reactor power to 20 percent before initiating a SCRAM. All rods fully inserted and the reactor is shutdown and stable. The electrical supply is in a normal shutdown lineup. The reactor is being supplied by normal feedwater, and decay heat is being controlled by use of the ADS valves. The licensee is currently cooling down and depressurizing the reactor in preparation for repair of the steam leak.
The licensee has notified the NRC Resident Inspector and the State of Illinois Resident Inspector.
Power Reactor
Event Number: 50946
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/02/2015
Notification Time: 06:55 [ET]
Event Date: 04/02/2015
Event Time: 04:26 [EDT]
Last Update Date: 04/02/2015
Notification Time: 06:55 [ET]
Event Date: 04/02/2015
Event Time: 04:26 [EDT]
Last Update Date: 04/02/2015
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):
SHAKUR WALKER (R2DO)
SHAKUR WALKER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO MAIN GENERATOR VOLTAGE REGULATOR FAILURE
"On April 2, 2015 at 0426 EDT, the Unit 1 reactor was manually tripped while operating at 100 percent power due to a failure of the main generator voltage regulator. This also resulted in a turbine trip. The operations crew entered the reactor trip procedure and stabilized the unit in Mode 3 at normal operating pressure and temperature. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater System actuated as designed and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 1 is in a normal shutdown electrical lineup.
"The NRC Resident Inspectors have been notified. The Louisa County Administrator will be notified."
There was no effect on Unit 2 as a result of this trip.
"On April 2, 2015 at 0426 EDT, the Unit 1 reactor was manually tripped while operating at 100 percent power due to a failure of the main generator voltage regulator. This also resulted in a turbine trip. The operations crew entered the reactor trip procedure and stabilized the unit in Mode 3 at normal operating pressure and temperature. All control rods fully inserted into the core following the reactor trip. This reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater System actuated as designed and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 1 is in a normal shutdown electrical lineup.
"The NRC Resident Inspectors have been notified. The Louisa County Administrator will be notified."
There was no effect on Unit 2 as a result of this trip.
Power Reactor
Event Number: 50947
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVE WHEELER
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVE WHEELER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/02/2015
Notification Time: 10:48 [ET]
Event Date: 04/02/2015
Event Time: 01:49 [CDT]
Last Update Date: 04/02/2015
Notification Time: 10:48 [ET]
Event Date: 04/02/2015
Event Time: 01:49 [CDT]
Last Update Date: 04/02/2015
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):
JACK WHITTEN (R4DO)
JACK WHITTEN (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF METEOROLOGICAL SYSTEM DUE TO LIGHTNING STRIKE
"At 0149 CDT on 4/2/2015, Cooper Nuclear Station received an alarm indication that the primary and backup Meteorological System (MET) had gone off-line as a result of a lightning strike on the MET tower. This resulted in a major loss of emergency assessment capabilities in regard to meteorological conditions. Technicians responded to the plant and restored the system at 0418 CDT. Loss of the MET system is considered a major loss of emergency assessment capability and is reportable under 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
"At 0149 CDT on 4/2/2015, Cooper Nuclear Station received an alarm indication that the primary and backup Meteorological System (MET) had gone off-line as a result of a lightning strike on the MET tower. This resulted in a major loss of emergency assessment capabilities in regard to meteorological conditions. Technicians responded to the plant and restored the system at 0418 CDT. Loss of the MET system is considered a major loss of emergency assessment capability and is reportable under 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 50948
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEPHEN SEILHYMER
HQ OPS Officer: VINCE KLCO
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEPHEN SEILHYMER
HQ OPS Officer: VINCE KLCO
Notification Date: 04/02/2015
Notification Time: 17:29 [ET]
Event Date: 04/02/2015
Event Time: 12:30 [CDT]
Last Update Date: 04/02/2015
Notification Time: 17:29 [ET]
Event Date: 04/02/2015
Event Time: 12:30 [CDT]
Last Update Date: 04/02/2015
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SEISMIC MONITOR NOT AVAILABLE FOR EMERGENCY PLAN ASSESSMENT
"Northern States Power Company - Minnesota (NSPM) has completed a review of seismic monitor performance at the Prairie Island Nuclear Generating Plant (PINGP) over the past 3 years. The emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency action levels (EAL) HA1.1 (Seismic Event Greater Than Operating Basis Earthquake (OBE) as indicated by 'OBE Exceedance' alarm on Seismic Monitoring Panel) or HU1.1 (Earthquake felt in plant as indicated by Valid 'Event' alarm on Seismic Monitoring Panel). Contrary to that requirement, this review identified 6 unplanned instances where the seismic monitor was non-functional that were not previously reported, and 3 planned instances where the seismic monitor was non-functional for greater than 24 hours that were not previously reported. Since there was no compensatory measure that could be credited when the seismic monitor was non-functional, an emergency classification at the ALERT or UNUSUAL EVENT level could not be obtained with site instrumentation for a seismic event.
"The seismic monitor is currently functional, however it was determined to be non-functional on the following dates:
Unplanned out of service:
1. August 14, 2012
2. November 16, 2012
3. November 18 2012
4. November 21, 2012
5. December 5, 2012
6. January 16, 2013
Planned greater than 24 hour out of service:
1. December 14, 2012
2. September 3, 2014
3. September 30, 2014
"The unplanned non-functional conditions of the seismic monitor have been corrected and were entered into the NSPM Corrective Action Program.
"The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery.
"Corrective actions are in progress to address the missed reporting of seismic monitor unavailability."
The licensee notified the NRC Resident Inspector.
"Northern States Power Company - Minnesota (NSPM) has completed a review of seismic monitor performance at the Prairie Island Nuclear Generating Plant (PINGP) over the past 3 years. The emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency action levels (EAL) HA1.1 (Seismic Event Greater Than Operating Basis Earthquake (OBE) as indicated by 'OBE Exceedance' alarm on Seismic Monitoring Panel) or HU1.1 (Earthquake felt in plant as indicated by Valid 'Event' alarm on Seismic Monitoring Panel). Contrary to that requirement, this review identified 6 unplanned instances where the seismic monitor was non-functional that were not previously reported, and 3 planned instances where the seismic monitor was non-functional for greater than 24 hours that were not previously reported. Since there was no compensatory measure that could be credited when the seismic monitor was non-functional, an emergency classification at the ALERT or UNUSUAL EVENT level could not be obtained with site instrumentation for a seismic event.
"The seismic monitor is currently functional, however it was determined to be non-functional on the following dates:
Unplanned out of service:
1. August 14, 2012
2. November 16, 2012
3. November 18 2012
4. November 21, 2012
5. December 5, 2012
6. January 16, 2013
Planned greater than 24 hour out of service:
1. December 14, 2012
2. September 3, 2014
3. September 30, 2014
"The unplanned non-functional conditions of the seismic monitor have been corrected and were entered into the NSPM Corrective Action Program.
"The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery.
"Corrective actions are in progress to address the missed reporting of seismic monitor unavailability."
The licensee notified the NRC Resident Inspector.