Event Notification Report for April 04, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/03/2013 - 04/04/2013
Part 21
Event Number: 48893
Rep Org: FLOWSERVE CONTROL - LIMITORQUE
Licensee: FLOWSERVE CONTROL - LIMITORQUE
Region: 1
City: LYNCHBURG State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFF McCONKEY
HQ OPS Officer: BILL HUFFMAN
Licensee: FLOWSERVE CONTROL - LIMITORQUE
Region: 1
City: LYNCHBURG State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFF McCONKEY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/05/2013
Notification Time: 14:36 [ET]
Event Date: 04/04/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/05/2013
Notification Time: 14:36 [ET]
Event Date: 04/04/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
DANIEL RICH (R2DO)
RAY KELLAR (R4DO)
PART 21 REPORTS (E-MA)
DANIEL RICH (R2DO)
RAY KELLAR (R4DO)
PART 21 REPORTS (E-MA)
PART 21 REPORT OF LIMITORQUE VALVES WITH INCORRECT MOTOR NAMEPLATES INSTALLED
The following information is a synopsis of a report received from Flowserve - Limitorque via facsimile:
"During routine Motor Operated Valve testing of a Limitorque SMB-000 actuator prior to being placed into operation, Duke Energy, Catawba Nuclear Station measured motor current readings higher than expected. This actuator was equipped with a 2 ft-lb motor. This motor was returned to Limitorque and subsequently to the motor Original Equipment Manufacturer (OEM). Investigation revealed that this motor was a 5 ft-lb motor mislabeled with the nameplate from a 2 ft-lb motor which explains the measured current draw.
"This notification is limited to a quantity of two motors for Limitorque SMB-000 actuators. Both affected licensees have been notified of this occurrence and both motors have been returned to Flowserve - Limitorque for replacement. [Catawba and Arkansas Nuclear One]
"The defect which occurred is that the 2 ft - lb motor was identified on the nameplate as a 5 ft - lb motor. Similarly the 5 ft - lb motor was identified on the nameplate as a 2 ft - lb motor. Had these motors been placed into service, this defect has the potential to affect safety related operation due to a possible reduction of MOV capability.
"The cause of the defect was due to two motor nameplates being inadvertently interchanged by Flowserve personnel during the painting process prior to shipment. The two motors which are both 48 frame, SMB-000 flanged, Baldor Reliance AC motors were being painted in the same timeframe. The painting process requires the OEM supplied nameplate to be temporarily separated from the motor. Upon the completion of the painting process, Flowserve personnel inadvertently interchanged the nameplates resulting in the 2 ft-lb motor being incorrectly identified as a 5 ft-lb motor. Similarly the 5 ft-lb motor was incorrectly identified on the nameplate as a 2 ft-lb motor. Inspections of the returned motors by Flowserve and the motor OEM confirmed the problem.
"To prevent recurrence of this issue, Flowserve has reviewed and strengthened the relevant procedures regarding verification of motor identification during the installation of the OEM supplied motor nameplate. All personnel associated with this process have been trained by Flowserve QA to the latest revision of the procedures."
The following information is a synopsis of a report received from Flowserve - Limitorque via facsimile:
"During routine Motor Operated Valve testing of a Limitorque SMB-000 actuator prior to being placed into operation, Duke Energy, Catawba Nuclear Station measured motor current readings higher than expected. This actuator was equipped with a 2 ft-lb motor. This motor was returned to Limitorque and subsequently to the motor Original Equipment Manufacturer (OEM). Investigation revealed that this motor was a 5 ft-lb motor mislabeled with the nameplate from a 2 ft-lb motor which explains the measured current draw.
"This notification is limited to a quantity of two motors for Limitorque SMB-000 actuators. Both affected licensees have been notified of this occurrence and both motors have been returned to Flowserve - Limitorque for replacement. [Catawba and Arkansas Nuclear One]
"The defect which occurred is that the 2 ft - lb motor was identified on the nameplate as a 5 ft - lb motor. Similarly the 5 ft - lb motor was identified on the nameplate as a 2 ft - lb motor. Had these motors been placed into service, this defect has the potential to affect safety related operation due to a possible reduction of MOV capability.
"The cause of the defect was due to two motor nameplates being inadvertently interchanged by Flowserve personnel during the painting process prior to shipment. The two motors which are both 48 frame, SMB-000 flanged, Baldor Reliance AC motors were being painted in the same timeframe. The painting process requires the OEM supplied nameplate to be temporarily separated from the motor. Upon the completion of the painting process, Flowserve personnel inadvertently interchanged the nameplates resulting in the 2 ft-lb motor being incorrectly identified as a 5 ft-lb motor. Similarly the 5 ft-lb motor was incorrectly identified on the nameplate as a 2 ft-lb motor. Inspections of the returned motors by Flowserve and the motor OEM confirmed the problem.
"To prevent recurrence of this issue, Flowserve has reviewed and strengthened the relevant procedures regarding verification of motor identification during the installation of the OEM supplied motor nameplate. All personnel associated with this process have been trained by Flowserve QA to the latest revision of the procedures."
Power Reactor
Event Number: 48887
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/04/2013
Notification Time: 08:35 [ET]
Event Date: 04/04/2013
Event Time: 04:06 [EDT]
Last Update Date: 04/05/2013
Notification Time: 08:35 [ET]
Event Date: 04/04/2013
Event Time: 04:06 [EDT]
Last Update Date: 04/05/2013
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 65 | Power Operation | 65 | Power Operation |
FAILURE OF THE INTEGRATED PLANT COMPUTER SYSTEM
"At 0406 [EDT] on April 4, 2013, the Fermi 2 Integrated Plant Computer System (IPCS) failed. This resulted in a loss of approximately 60 percent of data on the Safety Parameters Display System (SPDS).
"While IPCS and SPDS are not fully functional, the Emergency Plan can still be implemented if a plant emergency does occur, as assessment capabilities are available under alternate means.
"Investigation is in progress. A follow up message will be made when IPCS and SPDS are restored to fully functional status.
"This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM GREG MILLER TO VINCE KLCO AT 1636 EDT ON 4/5/2013 * * *
"At 1627 [EDT] on April 4, 2013, plant personnel were able to restore full functionality of IPCS and SPDS. This restored full assessment capabilities to all onsite emergency response faculties."
The licensee notified the NRC Resident Inspector.
Notified the R3DO (Daley).
"At 0406 [EDT] on April 4, 2013, the Fermi 2 Integrated Plant Computer System (IPCS) failed. This resulted in a loss of approximately 60 percent of data on the Safety Parameters Display System (SPDS).
"While IPCS and SPDS are not fully functional, the Emergency Plan can still be implemented if a plant emergency does occur, as assessment capabilities are available under alternate means.
"Investigation is in progress. A follow up message will be made when IPCS and SPDS are restored to fully functional status.
"This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM GREG MILLER TO VINCE KLCO AT 1636 EDT ON 4/5/2013 * * *
"At 1627 [EDT] on April 4, 2013, plant personnel were able to restore full functionality of IPCS and SPDS. This restored full assessment capabilities to all onsite emergency response faculties."
The licensee notified the NRC Resident Inspector.
Notified the R3DO (Daley).