Event Notification Report for September 20, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/19/2010 - 09/20/2010
Power Reactor
Event Number: 46262
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEVIN LUESHEN
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEVIN LUESHEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/20/2010
Notification Time: 19:37 [ET]
Event Date: 09/20/2010
Event Time: 17:04 [CDT]
Last Update Date: 09/20/2010
Notification Time: 19:37 [ET]
Event Date: 09/20/2010
Event Time: 17:04 [CDT]
Last Update Date: 09/20/2010
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):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (R3DO)
| 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 |
AUTOMATIC REACTOR TRIP
"At 1704 CDT, Braidwood Unit 1 experienced an automatic reactor trip. The reactor trip red first out was Over Temperature Delta Temperature (OTDT). At the time of the reactor trip, the Instrument Maintenance Department was performing a calibration of Power Range Channel N-43 and a calibration of the 1C S/G Narrow Range Level Channel 1L-0538. The cause of the trip is unknown at this time.
"After the reactor trip occurred, all four Steam Generators reached their Low-2 reactor trip setpoint and Pressurizer pressure reached its low pressure reactor trip setpoint which is an expected response on a trip from full power. Steam Generator levels and Pressurizer pressure have been restored. Both the 1A and 1B Auxiliary Feedwater pumps auto started on the Low-2 Steam Generator levels as expected. All control rods fully inserted into the core.
"Train B Main Control Room Filtration system shifted to makeup mode and the Train B Fuel Handling Building ventilation shifted to Emergency Mode due to a spurious actuation signal.
"No secondary relief valves lifted and no secondary steam [was] released as a result of the reactor trip. The Main Steam Dumps are in service to the Main Condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. This report is being made per 10CFR50.72(b)(2)(iv)(B) for RPS actuation, 4-hr. notification, and per 10CFR50.72(b)(3)(iv)(A) for automatic actuation of the Auxiliary Feedwater system, 8-hr. notification.
"AC power is being provided by offsite power with the Diesel Generators in standby and all safety systems available. There is no Unit 2 impact."
The licensee notified the NRC Resident Inspector. The licensee also anticipates that there will be a press release issued regarding this event.
"At 1704 CDT, Braidwood Unit 1 experienced an automatic reactor trip. The reactor trip red first out was Over Temperature Delta Temperature (OTDT). At the time of the reactor trip, the Instrument Maintenance Department was performing a calibration of Power Range Channel N-43 and a calibration of the 1C S/G Narrow Range Level Channel 1L-0538. The cause of the trip is unknown at this time.
"After the reactor trip occurred, all four Steam Generators reached their Low-2 reactor trip setpoint and Pressurizer pressure reached its low pressure reactor trip setpoint which is an expected response on a trip from full power. Steam Generator levels and Pressurizer pressure have been restored. Both the 1A and 1B Auxiliary Feedwater pumps auto started on the Low-2 Steam Generator levels as expected. All control rods fully inserted into the core.
"Train B Main Control Room Filtration system shifted to makeup mode and the Train B Fuel Handling Building ventilation shifted to Emergency Mode due to a spurious actuation signal.
"No secondary relief valves lifted and no secondary steam [was] released as a result of the reactor trip. The Main Steam Dumps are in service to the Main Condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. This report is being made per 10CFR50.72(b)(2)(iv)(B) for RPS actuation, 4-hr. notification, and per 10CFR50.72(b)(3)(iv)(A) for automatic actuation of the Auxiliary Feedwater system, 8-hr. notification.
"AC power is being provided by offsite power with the Diesel Generators in standby and all safety systems available. There is no Unit 2 impact."
The licensee notified the NRC Resident Inspector. The licensee also anticipates that there will be a press release issued regarding this event.
Hospital
Event Number: 46264
Rep Org: SOUTHEAST MISSOURI HOSPITAL
Licensee: SOUTHEAST MISSOURI HOSPITAL
Region: 3
City: CAPE GIRARDEAU State: MO
County:
License #: 24-00128-03
Agreement: N
Docket:
NRC Notified By: SAM HANCOCK
HQ OPS Officer: DONALD NORWOOD
Licensee: SOUTHEAST MISSOURI HOSPITAL
Region: 3
City: CAPE GIRARDEAU State: MO
County:
License #: 24-00128-03
Agreement: N
Docket:
NRC Notified By: SAM HANCOCK
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/21/2010
Notification Time: 18:22 [ET]
Event Date: 09/20/2010
Event Time: 21:00 [CDT]
Last Update Date: 09/21/2010
Notification Time: 18:22 [ET]
Event Date: 09/20/2010
Event Time: 21:00 [CDT]
Last Update Date: 09/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
DUNCAN WHITE (FSME)
RICHARD SKOKOWSKI (R3DO)
DUNCAN WHITE (FSME)
HIGH DOSE RATE AFTERLOADER STUCK / EXPOSED SOURCE
On 9/20/10, the licensee was having scheduled maintenance work performed on a Varian High Dose Rate (HDR) afterloader. A source exchange was also scheduled to be performed. During the source exchange, the source became "stuck, partially exposed, not fully shielded in the shield" of the HDR machine and became inoperable. The licensee believes this to be due to personnel error on the part of the service technician. The service technician then vacated the room.
Varian was called and said they would dispatch personnel to the hospital on 9/21/10. Security was notified of the radiation safety problem. The door to the room was secured. The door to the room was posted with hazard warning tape, with a do not enter sign, and with a high radiation area sign. The department was also locked down.
Varian personnel arrived on-site on 9/21/10. Varian service personnel secured the source back in the machine. Radiation levels in the room then returned to normal background readings. The source wire was found kinked and shipped out today. The hospital is scheduled to receive a new source and have it installed tomorrow.
Service personnel were wearing "active monitors" and received only a few milli-rem during the repair operation. It is not known at this time how much dose the first service technician received.
On 9/20/10, the licensee was having scheduled maintenance work performed on a Varian High Dose Rate (HDR) afterloader. A source exchange was also scheduled to be performed. During the source exchange, the source became "stuck, partially exposed, not fully shielded in the shield" of the HDR machine and became inoperable. The licensee believes this to be due to personnel error on the part of the service technician. The service technician then vacated the room.
Varian was called and said they would dispatch personnel to the hospital on 9/21/10. Security was notified of the radiation safety problem. The door to the room was secured. The door to the room was posted with hazard warning tape, with a do not enter sign, and with a high radiation area sign. The department was also locked down.
Varian personnel arrived on-site on 9/21/10. Varian service personnel secured the source back in the machine. Radiation levels in the room then returned to normal background readings. The source wire was found kinked and shipped out today. The hospital is scheduled to receive a new source and have it installed tomorrow.
Service personnel were wearing "active monitors" and received only a few milli-rem during the repair operation. It is not known at this time how much dose the first service technician received.
Power Reactor
Event Number: 46259
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JIM PRIEST
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JIM PRIEST
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/20/2010
Notification Time: 00:10 [ET]
Event Date: 09/20/2010
Event Time: 07:00 [EDT]
Last Update Date: 10/06/2010
Notification Time: 00:10 [ET]
Event Date: 09/20/2010
Event Time: 07:00 [EDT]
Last Update Date: 10/06/2010
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):
GLENN DENTEL (R1DO)
GLENN DENTEL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
ERDS AND SPDS OUT OF SERVICE FOR COMPUTER UPGRADE
"On 9/20/2010 at approximately 0700 EDT, the Hope Creek Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) will be taken out of service for approximately nine days to support a planned modification which will install a new (upgraded) computer system. During this timeframe, ERDS and SPDS will be unavailable. Should the need arise, plant status information will be communicated to the NRC, State and local responders using other available communication systems. SPDS and ERDS are expected to be restored on 9/29/2010. This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a 'Major Loss of Assessment Capability'."
The licensee has notified Lower Alloways Creek Township and the NRC Resident Inspector of the planned outage.
* * * UPDATE AT 1540 ON 9/29/2010 FROM DAVID HALL TO ERIC SIMPSON * * *
"SPDS and ERDS systems were removed from service to support planned computer upgrade. Planned work which resulted in the removal from service of the SPDS and ERDS has been completed. The SPDS system has been returned to service. During the ERDS testing, a problem was discovered with the NRC's communication link supplied by Verizon. An update will be provided when ERDS testing is completed."
Notified R1DO (Gray).
* * * UPDATE AT 1306 ON 10/6/2010 FROM DAVID HALL TO MARK ABRAMOVITZ * * *
"The ERDS communication problem was repaired and successfully tested. SPDS and ERDS are now fully functional and all work is complete."
The licensee notified the NRC Resident Inspector.
Notified the R1DO (Joustra)
"On 9/20/2010 at approximately 0700 EDT, the Hope Creek Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) will be taken out of service for approximately nine days to support a planned modification which will install a new (upgraded) computer system. During this timeframe, ERDS and SPDS will be unavailable. Should the need arise, plant status information will be communicated to the NRC, State and local responders using other available communication systems. SPDS and ERDS are expected to be restored on 9/29/2010. This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a 'Major Loss of Assessment Capability'."
The licensee has notified Lower Alloways Creek Township and the NRC Resident Inspector of the planned outage.
* * * UPDATE AT 1540 ON 9/29/2010 FROM DAVID HALL TO ERIC SIMPSON * * *
"SPDS and ERDS systems were removed from service to support planned computer upgrade. Planned work which resulted in the removal from service of the SPDS and ERDS has been completed. The SPDS system has been returned to service. During the ERDS testing, a problem was discovered with the NRC's communication link supplied by Verizon. An update will be provided when ERDS testing is completed."
Notified R1DO (Gray).
* * * UPDATE AT 1306 ON 10/6/2010 FROM DAVID HALL TO MARK ABRAMOVITZ * * *
"The ERDS communication problem was repaired and successfully tested. SPDS and ERDS are now fully functional and all work is complete."
The licensee notified the NRC Resident Inspector.
Notified the R1DO (Joustra)