Event Notification Report for June 13, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/12/2011 - 06/13/2011
Power Reactor
Event Number: 46951
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEN HILL
HQ OPS Officer: CHARLES TEAL
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEN HILL
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/13/2011
Notification Time: 10:17 [ET]
Event Date: 06/13/2011
Event Time: 05:10 [CDT]
Last Update Date: 06/13/2011
Notification Time: 10:17 [ET]
Event Date: 06/13/2011
Event Time: 05:10 [CDT]
Last Update Date: 06/13/2011
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):
JULIO LARA (R3DO)
LAURA KOZAK (R3DO)
JULIO LARA (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M | Y | 34 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO STEAM LEAK IN TURBINE BUILDING
"On June 13, 2011 at 0510 CDT, a manual scram was inserted on Unit 1 following discovery of a steam leak in the turbine building downstream of the Main Turbine Stop Valves. Following the reactor scram, reactor water level decreased to approximately -19 inches, which resulted in automatic Group II and Group III isolations (expected response). The steam leak was isolated by closure of the Main Turbine Stop Valves. All systems responded properly to the event. Unit 1 remains in Mode 3 [hot shutdown], maintaining reactor pressure with the Main Turbine Bypass Valves; reactor water level is in the normal level band. The cause of the event is still under investigation."
"Unit 2 was unaffected by the event and remains at 100% power."
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
The licensee has notified the NRC Resident Inspector.
"On June 13, 2011 at 0510 CDT, a manual scram was inserted on Unit 1 following discovery of a steam leak in the turbine building downstream of the Main Turbine Stop Valves. Following the reactor scram, reactor water level decreased to approximately -19 inches, which resulted in automatic Group II and Group III isolations (expected response). The steam leak was isolated by closure of the Main Turbine Stop Valves. All systems responded properly to the event. Unit 1 remains in Mode 3 [hot shutdown], maintaining reactor pressure with the Main Turbine Bypass Valves; reactor water level is in the normal level band. The cause of the event is still under investigation."
"Unit 2 was unaffected by the event and remains at 100% power."
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 46953
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/13/2011
Notification Time: 14:30 [ET]
Event Date: 06/13/2011
Event Time: 12:00 [CDT]
Last Update Date: 06/13/2011
Notification Time: 14:30 [ET]
Event Date: 06/13/2011
Event Time: 12:00 [CDT]
Last Update Date: 06/13/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GREG WERNER (R4DO)
GREG WERNER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
OFFSITE NOTIFICATION DUE TO SEWAGE SYSTEM RELEASE
"At 0500 CDT, the lift station #4 sewage system, South of the Fort Calhoun Station Administration building, was released to the Missouri River. The release was a mixture of ground water and sewage; samples were taken by chemistry but dilution concentration is unknown. Approximately 105 gpm release started around 0500 on 6/13/2011. This condition is being reported pursuant to 10 CFR 50.72(b)(2)(xi) for an event related to the protection of the environment for which a notification of governmental agencies is required. Applicable governmental agencies have been notified per plant procedures."
The licensee notified the State of Nebraska at 1200 CDT. The licensee also notified the NRC Resident Inspector.
"At 0500 CDT, the lift station #4 sewage system, South of the Fort Calhoun Station Administration building, was released to the Missouri River. The release was a mixture of ground water and sewage; samples were taken by chemistry but dilution concentration is unknown. Approximately 105 gpm release started around 0500 on 6/13/2011. This condition is being reported pursuant to 10 CFR 50.72(b)(2)(xi) for an event related to the protection of the environment for which a notification of governmental agencies is required. Applicable governmental agencies have been notified per plant procedures."
The licensee notified the State of Nebraska at 1200 CDT. The licensee also notified the NRC Resident Inspector.
Power Reactor
Event Number: 46957
Facility: POINT BEACH
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DAVID PLESSAS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DAVID PLESSAS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/13/2011
Notification Time: 23:29 [ET]
Event Date: 06/13/2011
Event Time: 19:24 [CDT]
Last Update Date: 10/12/2011
Notification Time: 23:29 [ET]
Event Date: 06/13/2011
Event Time: 19:24 [CDT]
Last Update Date: 10/12/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 0 | Startup | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DURING STARTUP PHYSICS TESTING
"On June 13, 2011 at 1924 CDT, an automatic reactor trip was actuated during Shutdown Bank Insertion for Beginning of Life Physics Testing. Neutron flux lowered from the intermediate range to the point of automatic energization of the Source Range Nuclear Instruments. Energization of the Source Range Nuclear Instruments during this step is anticipated and permissible per the test procedure. When it energized, the N-31 Source Range Nuclear Instrument (Red Channel) failed high which initiated an automatic reactor trip.
"All plant systems functioned as required, including the Reactor Protection System. All control rods fully inserted into the core. There was no Emergency Core Cooling System or Auxiliary Feedwater System actuation. No Emergency Diesel Generators were started and power continues to be supplied from off site. The reactor coolant system has forced circulation and the atmospheric steam dumps are currently being used for decay heat removal from the steam generators.
"There was no radiological release and emergency plan implementation was not required.
"An investigation of the failure of the N-31 Source Range Nuclear Instrument is in progress"
There is no known primary to secondary leakage. The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM RUSS PARKER TO DONALD NORWOOD AT 2155 EDT ON 6/14/11 * * *
"At the time of the trip, the reactor was subcritical. This notification is updated to reflect reporting in accordance with 10CFR50.72(b)(3)(iv)(A).
"An investigation of the failure of the N-31 source range nuclear instrument continues."
This event was initially reported by the licensee as a four-hour report in accordance with 10CFR50.72(b)(2)(iv)(B).
The licensee notified the NRC Resident Inspector.
Notified R3DO (Kozak).
* * * UPDATE FROM ALEX RIVAS TO HUFFMAN ON 10/12/11 AT 1502 EDT * * *
'On June 14, 2011 at 2055 EDT, EN 46957 was amended to state the reactor was subcritical at the time of the trip. Subsequent review of this situation by the licensee resulted in a determination that at the time the test sequence was initiated, the reactor was critical and in MODE 2. Accordingly, this non-emergency report is amended to reflect EN 46957 as originally submitted on 06/13/11 at 2229 CDT. LER 301/2011-004-01 [submitted on July 25, 2011] will be revised accordingly.'
The licensee has notified the NRC Resident Inspector. R3DO (Peterson) notified.
"On June 13, 2011 at 1924 CDT, an automatic reactor trip was actuated during Shutdown Bank Insertion for Beginning of Life Physics Testing. Neutron flux lowered from the intermediate range to the point of automatic energization of the Source Range Nuclear Instruments. Energization of the Source Range Nuclear Instruments during this step is anticipated and permissible per the test procedure. When it energized, the N-31 Source Range Nuclear Instrument (Red Channel) failed high which initiated an automatic reactor trip.
"All plant systems functioned as required, including the Reactor Protection System. All control rods fully inserted into the core. There was no Emergency Core Cooling System or Auxiliary Feedwater System actuation. No Emergency Diesel Generators were started and power continues to be supplied from off site. The reactor coolant system has forced circulation and the atmospheric steam dumps are currently being used for decay heat removal from the steam generators.
"There was no radiological release and emergency plan implementation was not required.
"An investigation of the failure of the N-31 Source Range Nuclear Instrument is in progress"
There is no known primary to secondary leakage. The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM RUSS PARKER TO DONALD NORWOOD AT 2155 EDT ON 6/14/11 * * *
"At the time of the trip, the reactor was subcritical. This notification is updated to reflect reporting in accordance with 10CFR50.72(b)(3)(iv)(A).
"An investigation of the failure of the N-31 source range nuclear instrument continues."
This event was initially reported by the licensee as a four-hour report in accordance with 10CFR50.72(b)(2)(iv)(B).
The licensee notified the NRC Resident Inspector.
Notified R3DO (Kozak).
* * * UPDATE FROM ALEX RIVAS TO HUFFMAN ON 10/12/11 AT 1502 EDT * * *
'On June 14, 2011 at 2055 EDT, EN 46957 was amended to state the reactor was subcritical at the time of the trip. Subsequent review of this situation by the licensee resulted in a determination that at the time the test sequence was initiated, the reactor was critical and in MODE 2. Accordingly, this non-emergency report is amended to reflect EN 46957 as originally submitted on 06/13/11 at 2229 CDT. LER 301/2011-004-01 [submitted on July 25, 2011] will be revised accordingly.'
The licensee has notified the NRC Resident Inspector. R3DO (Peterson) notified.