Event Notification Report for March 04, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/03/2013 - 03/04/2013
EVENT NUMBERS
48804488054880648972
Power Reactor
Event Number: 48804
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HUNNICUTT
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HUNNICUTT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/04/2013
Notification Time: 08:59 [ET]
Event Date: 03/04/2013
Event Time: 04:15 [EST]
Last Update Date: 03/06/2013
Notification Time: 08:59 [ET]
Event Date: 03/04/2013
Event Time: 04:15 [EST]
Last Update Date: 03/06/2013
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):
RANDY MUSSER (R2DO)
RANDY MUSSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 99 | Power Operation |
RADIATION MONITOR INOPERABLE FOR PRE-PLANNED MAINTENANCE
"This is a non-emergency notification.
"At 0415 EST on March 4, 2013, REM-01MD-3528, Turbine Building Floor Drain Liquid Effluent Radiation Monitor, was declared inoperable for pre-planned corrective maintenance and surveillance testing. The pre-planned maintenance and surveillance testing is scheduled to take approximately 62 hours. Proceduralized compensatory measures are in place to sample and analyze for radioactivity at a lower limit of detection of no more than 10E-7 microCuries/ml at least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microCuries/gram Dose Equivalent I-131, or at least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microCuries/gram Dose Equivalent I-131. The expected return to service and operability date is March 6, 2013.
"The Liquid Effluent Radiation Monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification 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 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2.
"The NRC Resident has been notified."
* * * UPDATE FROM JOHN CAVES TO VINCE KLCO ON 3/6/13 AT 1703 EST * * *
". . . Radiation Monitor REM-01 MD-3528 would be out of service for preplanned maintenance for approximately 62 hours, and the estimated return to service date was March 6, 2013. The preplanned maintenance is taking longer than expected and the current estimate is approximately 110 hours with return to service on Friday, March 8, 2013. The compensatory measures will continue until the monitor is returned to service."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Nease).
"This is a non-emergency notification.
"At 0415 EST on March 4, 2013, REM-01MD-3528, Turbine Building Floor Drain Liquid Effluent Radiation Monitor, was declared inoperable for pre-planned corrective maintenance and surveillance testing. The pre-planned maintenance and surveillance testing is scheduled to take approximately 62 hours. Proceduralized compensatory measures are in place to sample and analyze for radioactivity at a lower limit of detection of no more than 10E-7 microCuries/ml at least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microCuries/gram Dose Equivalent I-131, or at least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microCuries/gram Dose Equivalent I-131. The expected return to service and operability date is March 6, 2013.
"The Liquid Effluent Radiation Monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification 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 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2.
"The NRC Resident has been notified."
* * * UPDATE FROM JOHN CAVES TO VINCE KLCO ON 3/6/13 AT 1703 EST * * *
". . . Radiation Monitor REM-01 MD-3528 would be out of service for preplanned maintenance for approximately 62 hours, and the estimated return to service date was March 6, 2013. The preplanned maintenance is taking longer than expected and the current estimate is approximately 110 hours with return to service on Friday, March 8, 2013. The compensatory measures will continue until the monitor is returned to service."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Nease).
Power Reactor
Event Number: 48805
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ANGELIQUE BRAY
HQ OPS Officer: VINCE KLCO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: ANGELIQUE BRAY
HQ OPS Officer: VINCE KLCO
Notification Date: 03/04/2013
Notification Time: 11:58 [ET]
Event Date: 03/04/2013
Event Time: 09:27 [CST]
Last Update Date: 03/04/2013
Notification Time: 11:58 [ET]
Event Date: 03/04/2013
Event Time: 09:27 [CST]
Last Update Date: 03/04/2013
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):
NICK VALOS (R3DO)
NICK VALOS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 0 | Cold Shutdown |
OFFSITE NOTIFICATION DUE TO A FISH KILL
"At 0927 CST on March 4, 2012, XCEL Energy Environmental Services made a report to the State of Minnesota regarding 475 fish killed from the discharge canal temperature transient following reactor shutdown on March 2, 2013."
Monticello was in the process of performing a planned shutdown in preparation for a refueling outage.
The NRC Resident Inspector, Wright County Sheriffs Department and Sherburne County Sheriffs Department have been notified by the licensee.
"At 0927 CST on March 4, 2012, XCEL Energy Environmental Services made a report to the State of Minnesota regarding 475 fish killed from the discharge canal temperature transient following reactor shutdown on March 2, 2013."
Monticello was in the process of performing a planned shutdown in preparation for a refueling outage.
The NRC Resident Inspector, Wright County Sheriffs Department and Sherburne County Sheriffs Department have been notified by the licensee.
Power Reactor
Event Number: 48806
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: VINCE KLCO
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: VINCE KLCO
Notification Date: 03/04/2013
Notification Time: 18:32 [ET]
Event Date: 03/04/2013
Event Time: 14:00 [CST]
Last Update Date: 03/04/2013
Notification Time: 18:32 [ET]
Event Date: 03/04/2013
Event Time: 14:00 [CST]
Last Update Date: 03/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RYAN LANTZ (R4DO)
RYAN LANTZ (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 |
UNANALYZED CONDITION DUE TO MECHANICAL SEAL MATERIAL DESIGN
"It has been determined that the mechanical seals used in two Low Pressure Safety Injection Pumps and three Containment Spray Pumps are made of a material that may not maintain the designed integrity of the systems under certain accident conditions. These seals have been installed since original plant construction. This issue was discovered by plant personnel while researching requirements for the replacement parts during scheduled outage activities."
The licensee notified the NRC Resident Inspector.
"It has been determined that the mechanical seals used in two Low Pressure Safety Injection Pumps and three Containment Spray Pumps are made of a material that may not maintain the designed integrity of the systems under certain accident conditions. These seals have been installed since original plant construction. This issue was discovered by plant personnel while researching requirements for the replacement parts during scheduled outage activities."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 48972
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK TURKAL
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK TURKAL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/26/2013
Notification Time: 12:21 [ET]
Event Date: 03/04/2013
Event Time: 08:04 [EST]
Last Update Date: 04/26/2013
Notification Time: 12:21 [ET]
Event Date: 03/04/2013
Event Time: 08:04 [EST]
Last Update Date: 04/26/2013
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):
MARVIN SYKES (R2DO)
MARVIN SYKES (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 |
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
INVALID ACTUATION OF EMERGENCY DIESEL GENERATORS
"This 60-day telephone notification is provided in accordance with 10 CFR 50.73(a)(1) to report an invalid actuation of the Emergency Diesel Generators (EDGs) reportable under 10 CFR 50.73(a)(2)(iv)(A). Due to the shared configuration of the onsite AC Electrical Distribution System, this event is applicable to both Units 1 and 2.
"On March 4, 2013, at approximately 0804 EST, while performing a planned maintenance activity associated with the Unit 2 Start-Up Auxiliary Transformer (SAT), the SAT lock-out relay was inadvertently energized. This occurred when a Transmission Maintenance electrician closed the fault pressure device oil isolation valve without having previously opened the fault pressure cutoff switch. This action resulted in energizing the SAT lock-out relay and, per design, started all four EDGs.
"All four EDGs started and operated as expected. Because electrical power was never lost to the emergency busses and none of the EDGs loaded to their respective emergency busses, the actuations were considered to be partial.
"The EDGs were returned to their standby line-up by 1023 [EST] hours on March 4, 2013. Since no actual bus under voltage condition existed which required the EDGs to start and the start was not in response to actual plant conditions satisfying the requirements for initiation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public."
The licensee has notified the NRC Resident Inspector.
"This 60-day telephone notification is provided in accordance with 10 CFR 50.73(a)(1) to report an invalid actuation of the Emergency Diesel Generators (EDGs) reportable under 10 CFR 50.73(a)(2)(iv)(A). Due to the shared configuration of the onsite AC Electrical Distribution System, this event is applicable to both Units 1 and 2.
"On March 4, 2013, at approximately 0804 EST, while performing a planned maintenance activity associated with the Unit 2 Start-Up Auxiliary Transformer (SAT), the SAT lock-out relay was inadvertently energized. This occurred when a Transmission Maintenance electrician closed the fault pressure device oil isolation valve without having previously opened the fault pressure cutoff switch. This action resulted in energizing the SAT lock-out relay and, per design, started all four EDGs.
"All four EDGs started and operated as expected. Because electrical power was never lost to the emergency busses and none of the EDGs loaded to their respective emergency busses, the actuations were considered to be partial.
"The EDGs were returned to their standby line-up by 1023 [EST] hours on March 4, 2013. Since no actual bus under voltage condition existed which required the EDGs to start and the start was not in response to actual plant conditions satisfying the requirements for initiation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public."
The licensee has notified the NRC Resident Inspector.