Event Notification Report for November 14, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/13/2012 - 11/14/2012
Power Reactor
Event Number: 48507
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/14/2012
Notification Time: 15:43 [ET]
Event Date: 11/14/2012
Event Time: 10:00 [EST]
Last Update Date: 11/14/2012
Notification Time: 15:43 [ET]
Event Date: 11/14/2012
Event Time: 10:00 [EST]
Last Update Date: 11/14/2012
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):
MALCOLM WIDMANN (R2DO)
MALCOLM WIDMANN (R2DO)
| 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 ASSESSMENT CAPABILITY - GROSS FAILED FUEL DETECTOR
"This is a non-emergency notification. At approximately 10:00 am on November 14, 2012, it was identified that on June 14, 2012 at 4:04 am, the Gross Failed Fuel Detector was not controlling flow as required and therefore would not be able to perform its function. Further investigation revealed that the monitor has been in and out of service since that time. The last time the monitor was taken out of service was November 2, 2012 at 08:40 am and currently remains out of service. This condition has not impacted the health and safety of the public as this condition is not impacting the operation of the facility.
"This radiation monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification for an Unusual Event in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. Actions are in place to restore the monitor to functional status."
The licensee can obtain chemistry grab samples to determine if there is failed fuel though this is not as responsive. The Gross Failed Fuel Detector is planned for repair on 11/16/2012.
The licensee notified the NRC Resident Inspector.
"This is a non-emergency notification. At approximately 10:00 am on November 14, 2012, it was identified that on June 14, 2012 at 4:04 am, the Gross Failed Fuel Detector was not controlling flow as required and therefore would not be able to perform its function. Further investigation revealed that the monitor has been in and out of service since that time. The last time the monitor was taken out of service was November 2, 2012 at 08:40 am and currently remains out of service. This condition has not impacted the health and safety of the public as this condition is not impacting the operation of the facility.
"This radiation monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification for an Unusual Event in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. Actions are in place to restore the monitor to functional status."
The licensee can obtain chemistry grab samples to determine if there is failed fuel though this is not as responsive. The Gross Failed Fuel Detector is planned for repair on 11/16/2012.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 48508
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: WARREN WONKA
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: WARREN WONKA
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/14/2012
Notification Time: 16:13 [ET]
Event Date: 11/14/2012
Event Time: 09:27 [EST]
Last Update Date: 11/17/2012
Notification Time: 16:13 [ET]
Event Date: 11/14/2012
Event Time: 09:27 [EST]
Last Update Date: 11/17/2012
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):
MALCOLM WIDMANN (R2DO)
MALCOLM WIDMANN (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
RADIATION MONITOR OUT OF SERVICE
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability.
"On November 14, 2012, Radiation Monitor R-9, Letdown Line Radiation Monitor was removed from service at 0927 [EST] hours following failure of the internal and external source checks during performance of radiation monitor source checks. Both source checks failed high.
"This radiation monitor is used for accident assessment and is credited for Emergency Action Level (EAL) classification for an Unusual Event in the Robinson Nuclear Plant Emergency Plan. Additionally, this monitor is one of multiple indicators used to detect the loss of a fission product barrier. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. Actions are in place to restore the monitor to functional status.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 11/17/12 AT 0812 EST FROM GEORGE CURTIS TO DONG PARK * * *
At 1717 EST on 11/16/12, the Letdown Line Radiation Monitor was placed back in service and is functional.
The licensee has notified the NRC Resident Inspector. Notified R2DO (Widmann).
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability.
"On November 14, 2012, Radiation Monitor R-9, Letdown Line Radiation Monitor was removed from service at 0927 [EST] hours following failure of the internal and external source checks during performance of radiation monitor source checks. Both source checks failed high.
"This radiation monitor is used for accident assessment and is credited for Emergency Action Level (EAL) classification for an Unusual Event in the Robinson Nuclear Plant Emergency Plan. Additionally, this monitor is one of multiple indicators used to detect the loss of a fission product barrier. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. Actions are in place to restore the monitor to functional status.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 11/17/12 AT 0812 EST FROM GEORGE CURTIS TO DONG PARK * * *
At 1717 EST on 11/16/12, the Letdown Line Radiation Monitor was placed back in service and is functional.
The licensee has notified the NRC Resident Inspector. Notified R2DO (Widmann).
Power Reactor
Event Number: 48667
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/11/2013
Notification Time: 16:45 [ET]
Event Date: 11/14/2012
Event Time: 15:58 [EST]
Last Update Date: 01/11/2013
Notification Time: 16:45 [ET]
Event Date: 11/14/2012
Event Time: 15:58 [EST]
Last Update Date: 01/11/2013
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):
CHRISTOPHER NEWPORT (R1DO)
CHRISTOPHER NEWPORT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
60 DAY TELEPHONE NOTIFICATION OF AN INVALID REACTOR TRIP ACTUATION IN MODE 4
"This 60-day telephone notification is being made in accordance with the reporting requirements of 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of a reactor trip while subcritical.
"On November 14, 2012 Salem Unit 2 was in Mode 4 performing unit startup activities during its 2012 Refueling outage. Rod Control system and Individual Rod Position Indication testing was in progress with the Reactor Trip breakers closed. Control Rod Banks were being withdrawn from the core in accordance with a testing procedure.
"At 1558 hours [EST], an Instrument and Controls technician removed control power fuses from the Nuclear Instrumentation System Intermediate Range Drawer 2N36, generating an invalid reactor trip. Affected equipment responded as designed. Both reactor trip breakers opened and all control rods dropped into the core.
"2N36 troubleshooting had been in progress. Repair or replacement options for a broken connector had been discussed between the technician and his supervisor. Concerned for his personal safety, the technician pulled the 2N36 control power fuses in order to perform a wiring inspection. The technician failed to apply human performance standards including written directions, pre-job briefing, and notifying control room personnel and supervision prior to work. The technician failed to recognize that he was working outside of the expectations of normal work processes and failed to properly evaluate the full consequences of his actions.
"There were no safety consequences or impact to the health and safety of the public as a result of this event."
The licensee will notify the NRC Resident Inspector.
"This 60-day telephone notification is being made in accordance with the reporting requirements of 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of a reactor trip while subcritical.
"On November 14, 2012 Salem Unit 2 was in Mode 4 performing unit startup activities during its 2012 Refueling outage. Rod Control system and Individual Rod Position Indication testing was in progress with the Reactor Trip breakers closed. Control Rod Banks were being withdrawn from the core in accordance with a testing procedure.
"At 1558 hours [EST], an Instrument and Controls technician removed control power fuses from the Nuclear Instrumentation System Intermediate Range Drawer 2N36, generating an invalid reactor trip. Affected equipment responded as designed. Both reactor trip breakers opened and all control rods dropped into the core.
"2N36 troubleshooting had been in progress. Repair or replacement options for a broken connector had been discussed between the technician and his supervisor. Concerned for his personal safety, the technician pulled the 2N36 control power fuses in order to perform a wiring inspection. The technician failed to apply human performance standards including written directions, pre-job briefing, and notifying control room personnel and supervision prior to work. The technician failed to recognize that he was working outside of the expectations of normal work processes and failed to properly evaluate the full consequences of his actions.
"There were no safety consequences or impact to the health and safety of the public as a result of this event."
The licensee will notify the NRC Resident Inspector.