Event Notification Report for May 10, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/09/2011 - 05/10/2011
EVENT NUMBERS
46837468334683547035
Power Reactor
Event Number: 46837
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN MACDONALD
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN MACDONALD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/10/2011
Notification Time: 16:15 [ET]
Event Date: 05/10/2011
Event Time: 13:15 [EDT]
Last Update Date: 05/10/2011
Notification Time: 16:15 [ET]
Event Date: 05/10/2011
Event Time: 13:15 [EDT]
Last Update Date: 05/10/2011
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):
ANNE DEFRANCISCO (R1DO)
ANNE DEFRANCISCO (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 4 | Startup | 0 | Hot Shutdown |
REACTOR PROTECTION SYSTEM ACTUATION DURING START-UP
"At 1315 hours on Tuesday, May 10, 2011, with the Reactor Mode Select Switch in Startup, the Reactor Protection System (RPS) actuated due to a valid Hi-Hi trip signal from the Intermediate Range Monitors (IRMs) of the Neutron Monitoring System. At the time of the RPS actuation, reactor thermal power was four (4)% and control rods were being withdrawn as part of a planned reactor startup from a refueling outage. The RPS actuation signal resulted in a reactor scram. The IRMs were in range 7 when the scram occurred.
"All control rods automatically inserted in accordance with design. No other ESF actuation signals were generated. The reactor scram was not part of pre-planned test or reactor operation. The cause of the Hi-Hi IRM trip signal is under investigation.
"This event had no impact on the health and/or safety of the public.
"The licensee has notified the NRC Senior Resident Inspector.
"This 4-hour notification is being made in accordance with 10CFR50.72(b)(2)(iv)(B)."
The unit is in a normal post trip electrical alignment. Decay heat is being removed via the main steam line drains to the main condenser.
The licensee will notify the Massachusetts Emergency Management Agency.
"At 1315 hours on Tuesday, May 10, 2011, with the Reactor Mode Select Switch in Startup, the Reactor Protection System (RPS) actuated due to a valid Hi-Hi trip signal from the Intermediate Range Monitors (IRMs) of the Neutron Monitoring System. At the time of the RPS actuation, reactor thermal power was four (4)% and control rods were being withdrawn as part of a planned reactor startup from a refueling outage. The RPS actuation signal resulted in a reactor scram. The IRMs were in range 7 when the scram occurred.
"All control rods automatically inserted in accordance with design. No other ESF actuation signals were generated. The reactor scram was not part of pre-planned test or reactor operation. The cause of the Hi-Hi IRM trip signal is under investigation.
"This event had no impact on the health and/or safety of the public.
"The licensee has notified the NRC Senior Resident Inspector.
"This 4-hour notification is being made in accordance with 10CFR50.72(b)(2)(iv)(B)."
The unit is in a normal post trip electrical alignment. Decay heat is being removed via the main steam line drains to the main condenser.
The licensee will notify the Massachusetts Emergency Management Agency.
Power Reactor
Event Number: 46833
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DUANE BISTODEAU
HQ OPS Officer: JOE O'HARA
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DUANE BISTODEAU
HQ OPS Officer: JOE O'HARA
Notification Date: 05/10/2011
Notification Time: 09:10 [ET]
Event Date: 05/10/2011
Event Time: 09:15 [CDT]
Last Update Date: 05/10/2011
Notification Time: 09:10 [ET]
Event Date: 05/10/2011
Event Time: 09:15 [CDT]
Last Update Date: 05/10/2011
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):
DAVE PASSEHL (R3DO)
DAVE PASSEHL (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 |
LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"Dose assessment cannot be performed onsite.
"Pursuant to 10CFR50.72 (b)(3)(xiii), Monticello Nuclear Generating Plant is reporting a planned loss of emergency assessment capability scheduled for 0915 hours on May 10, 2011 for system maintenance. Dose assessment in the control room, TSC, and EOF are non-functional. Main meteorological tower data is unavailable. Projected outage duration is approximately 7 hours. Control room and local instrumentation/annunciation remain available for accident assessment. Telephone lines remain available between site emergency response facilities and offsite agencies for communication of plant status information. Dose assessment capabilities will exist at the backup EOF. Backup meteorological data will be available in the control room, TSC, and EOF. "
The licensee will not be in any Technical Specification action statements as a result of this evolution.
The NRC Resident Inspector has been notified.
* * * UPDATE FROM JEFF OLSON TO PETE SNYDER ON 5/10/11 AT 1650 EDT * * *
The licensee has restored their dose assessment capability.
Notified R3DO (Passehl).
"Dose assessment cannot be performed onsite.
"Pursuant to 10CFR50.72 (b)(3)(xiii), Monticello Nuclear Generating Plant is reporting a planned loss of emergency assessment capability scheduled for 0915 hours on May 10, 2011 for system maintenance. Dose assessment in the control room, TSC, and EOF are non-functional. Main meteorological tower data is unavailable. Projected outage duration is approximately 7 hours. Control room and local instrumentation/annunciation remain available for accident assessment. Telephone lines remain available between site emergency response facilities and offsite agencies for communication of plant status information. Dose assessment capabilities will exist at the backup EOF. Backup meteorological data will be available in the control room, TSC, and EOF. "
The licensee will not be in any Technical Specification action statements as a result of this evolution.
The NRC Resident Inspector has been notified.
* * * UPDATE FROM JEFF OLSON TO PETE SNYDER ON 5/10/11 AT 1650 EDT * * *
The licensee has restored their dose assessment capability.
Notified R3DO (Passehl).
Agreement State
Event Number: 46835
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TEAM INDUSTRIAL SERVICE INC.
Region: 4
City: ALVIN State: TX
County:
License #: L00087
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: PETE SNYDER
Licensee: TEAM INDUSTRIAL SERVICE INC.
Region: 4
City: ALVIN State: TX
County:
License #: L00087
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: PETE SNYDER
Notification Date: 05/10/2011
Notification Time: 12:43 [ET]
Event Date: 05/10/2011
Event Time: 00:00 [CDT]
Last Update Date: 05/10/2011
Notification Time: 12:43 [ET]
Event Date: 05/10/2011
Event Time: 00:00 [CDT]
Last Update Date: 05/10/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WAYNE WALKER (R4DO)
GLENDA VILLAMAR (FSME)
WAYNE WALKER (R4DO)
GLENDA VILLAMAR (FSME)
AGREEMENT STATE REPORT - STUCK RADIOGRAPHY CAMERA SOURCE
"On May 10, 2011, the Agency [Texas Department of Health] was notified by a licensee that while conducting radiography operations at a temporary job site, a pipe fell on the guide tube of a QSA Model 880D camera. The pipe damaged the guide tube preventing the radiographer from retracting the 34.1 curie Iridium (Ir) -192 source into the camera. The radiographer contacted his supervisor and a source recovery team was sent to the location.
"The recovery team was able to repair the guide tube enough to retract the source into the camera. The camera was returned to the licensee's facility for inspection. There was no exposure to a member of the general public and the highest exposure to a member of the recovery team was 28 millirem for the event.
"The investigation into this event is ongoing. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident No. I-8844
"On May 10, 2011, the Agency [Texas Department of Health] was notified by a licensee that while conducting radiography operations at a temporary job site, a pipe fell on the guide tube of a QSA Model 880D camera. The pipe damaged the guide tube preventing the radiographer from retracting the 34.1 curie Iridium (Ir) -192 source into the camera. The radiographer contacted his supervisor and a source recovery team was sent to the location.
"The recovery team was able to repair the guide tube enough to retract the source into the camera. The camera was returned to the licensee's facility for inspection. There was no exposure to a member of the general public and the highest exposure to a member of the recovery team was 28 millirem for the event.
"The investigation into this event is ongoing. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident No. I-8844
Power Reactor
Event Number: 47035
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOHN KNOKE
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/08/2011
Notification Time: 13:48 [ET]
Event Date: 05/10/2011
Event Time: 04:30 [CDT]
Last Update Date: 07/08/2011
Notification Time: 13:48 [ET]
Event Date: 05/10/2011
Event Time: 04:30 [CDT]
Last Update Date: 07/08/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BOB HAGAR (R4DO)
BOB HAGAR (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 |
60 DAY REPORT - EMERGENCY DIESEL GENERATOR STARTED DUE TO INVALID SIGNAL
"This 10CFR50.73(a)(1) report is a 60-day telephone notification in lieu of a written licensee event report being made under 10CFR50.73(a)(2)(iv)(A). On May 10, 2011 at 0430 CDT, during installation of the new loss of offsite power relay, Emergency Diesel Generator 2, started (a complete start) due to an invalid signal but remained operable while running as a backup power supply to its bus. The unit was in a refueling outage at the time. Offsite power was not lost and the diesel bus remained energized from offsite power and was operable. The diesel was subsequently secured."
The licensee has notified the NRC Resident Inspector.
"This 10CFR50.73(a)(1) report is a 60-day telephone notification in lieu of a written licensee event report being made under 10CFR50.73(a)(2)(iv)(A). On May 10, 2011 at 0430 CDT, during installation of the new loss of offsite power relay, Emergency Diesel Generator 2, started (a complete start) due to an invalid signal but remained operable while running as a backup power supply to its bus. The unit was in a refueling outage at the time. Offsite power was not lost and the diesel bus remained energized from offsite power and was operable. The diesel was subsequently secured."
The licensee has notified the NRC Resident Inspector.