Event Notification Report for February 21, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/20/2013 - 02/21/2013
Power Reactor
Event Number: 48775
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TONY COOK
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TONY COOK
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/21/2013
Notification Time: 12:49 [ET]
Event Date: 02/21/2013
Event Time: 09:57 [EST]
Last Update Date: 02/21/2013
Notification Time: 12:49 [ET]
Event Date: 02/21/2013
Event Time: 09:57 [EST]
Last Update Date: 02/21/2013
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):
GERALD MCCOY (R2DO)
GERALD MCCOY (R2DO)
| 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 DUE TO TURBINE TRIP ON LOSS OF BOTH MAIN FEED PUMPS
At 0957 EST on 02/21/13, Unit 1 Reactor automatically tripped from 100% power, due to a turbine trip. The turbine trip was caused by a loss of both main feedwater (MFW) pumps. The 1A motor driven auxiliary feedwater (AFW) pump auto started to feed the "A" and "B" Steam Generators (S/G). The 1B motor driven AFW pump was unavailable due to planned maintenance, so the turbine driven AFW pump was manually started to feed the "C" and "D" S/Gs.
The reactor trip was uncomplicated. All control rods fully inserted. Decay heat removal is to the main condenser via the turbine bypass valves. There was no primary to secondary leakage. Electrical buses are being supplied via offsite power. Steam generator levels are being returned to normal and MFW has been reset and is available. All other plant systems functioned as designed during and after the reactor trip. There is no impact on Unit 2. There is no impact on the health and safety of the public. The loss of the MFW pumps is still under investigation.
The licensee has informed the NRC Resident Inspector.
At 0957 EST on 02/21/13, Unit 1 Reactor automatically tripped from 100% power, due to a turbine trip. The turbine trip was caused by a loss of both main feedwater (MFW) pumps. The 1A motor driven auxiliary feedwater (AFW) pump auto started to feed the "A" and "B" Steam Generators (S/G). The 1B motor driven AFW pump was unavailable due to planned maintenance, so the turbine driven AFW pump was manually started to feed the "C" and "D" S/Gs.
The reactor trip was uncomplicated. All control rods fully inserted. Decay heat removal is to the main condenser via the turbine bypass valves. There was no primary to secondary leakage. Electrical buses are being supplied via offsite power. Steam generator levels are being returned to normal and MFW has been reset and is available. All other plant systems functioned as designed during and after the reactor trip. There is no impact on Unit 2. There is no impact on the health and safety of the public. The loss of the MFW pumps is still under investigation.
The licensee has informed the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Agreement State
Event Number: 48975
Rep Org: BEAUMONT HEALTH SYSTEMS
Licensee: BEAUMONT HEALTH SYSTEMS
Region: 3
City: ROYAL OAK State: MI
County:
License #: 21-01333-01
Agreement: N
Docket:
NRC Notified By: CHERYL SCHULTZ
HQ OPS Officer: BILL HUFFMAN
Licensee: BEAUMONT HEALTH SYSTEMS
Region: 3
City: ROYAL OAK State: MI
County:
License #: 21-01333-01
Agreement: N
Docket:
NRC Notified By: CHERYL SCHULTZ
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/26/2013
Notification Time: 13:45 [ET]
Event Date: 02/21/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/29/2013
Notification Time: 13:45 [ET]
Event Date: 02/21/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/29/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
DAVID HILLS (R3DO)
FSME EVENTS RESOURCE (E-MA)
DAVID HILLS (R3DO)
FSME EVENTS RESOURCE (E-MA)
SURFACE CONTAMINATION OF RADIOACTIVE MATERIAL SHIPMENT EXCEEDED LIMITS
During an audit of a satellite facility associated with Beaumont Health Systems, the Radiation Safety Officer (RSO) determined that a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits had been received but not reported to the NRC as required per 10 CFR 20.1906(d)(1).
The package was received on February 21, 2013 and wipe tests performed on the external surface of the package. Removable contamination levels were found on the package of 19,070 dpm/300 cm2. This level exceeds the reportable limits specified in 10 CFR 71.87(i).
The package contained Technetium-99m that had been shipped and delivered by Beaumont's Troy Hospital facility. The receiving facility did not find any damage or contamination on the Tech-99m vial or inside the ammo case used to transport the vial. The audited receipt inspection report revealed the external package contamination event was documented but not reported to the company's RSO. Troy Hospital was notified at the time of the event and contamination surveys were performed at the packaging location, on the transport vehicle, and on the driver. The only contamination found was a wipe used to wipe the area where the package had been stored in the truck (wipe-down of radioactive material lay-down area is routine protocol for the licensee).
The RSO stated that corrective actions are being taken related to improving contamination controls while packaging these shipments. In addition, improvements in the process related to reporting events to the RSO and the NRC are being explored.
* * * RETRACTION AT 1415 EDT ON 4/29/2013 FROM CHERYL SCHULTZ TO MARK ABRAMOVITZ * * *
The removable contamination of 19070 dpm/300cm2 equates to 63 dpm/cm2 which is below the reportable limit of 220 dpm/cm2. Therefore, this event is retracted.
Notified the R3DO (Duncan) and FSME Resources (via e-mail).
During an audit of a satellite facility associated with Beaumont Health Systems, the Radiation Safety Officer (RSO) determined that a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits had been received but not reported to the NRC as required per 10 CFR 20.1906(d)(1).
The package was received on February 21, 2013 and wipe tests performed on the external surface of the package. Removable contamination levels were found on the package of 19,070 dpm/300 cm2. This level exceeds the reportable limits specified in 10 CFR 71.87(i).
The package contained Technetium-99m that had been shipped and delivered by Beaumont's Troy Hospital facility. The receiving facility did not find any damage or contamination on the Tech-99m vial or inside the ammo case used to transport the vial. The audited receipt inspection report revealed the external package contamination event was documented but not reported to the company's RSO. Troy Hospital was notified at the time of the event and contamination surveys were performed at the packaging location, on the transport vehicle, and on the driver. The only contamination found was a wipe used to wipe the area where the package had been stored in the truck (wipe-down of radioactive material lay-down area is routine protocol for the licensee).
The RSO stated that corrective actions are being taken related to improving contamination controls while packaging these shipments. In addition, improvements in the process related to reporting events to the RSO and the NRC are being explored.
* * * RETRACTION AT 1415 EDT ON 4/29/2013 FROM CHERYL SCHULTZ TO MARK ABRAMOVITZ * * *
The removable contamination of 19070 dpm/300cm2 equates to 63 dpm/cm2 which is below the reportable limit of 220 dpm/cm2. Therefore, this event is retracted.
Notified the R3DO (Duncan) and FSME Resources (via e-mail).
Power Reactor
Event Number: 48824
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/15/2013
Notification Time: 17:23 [ET]
Event Date: 02/21/2013
Event Time: 10:12 [EDT]
Last Update Date: 03/15/2013
Notification Time: 17:23 [ET]
Event Date: 02/21/2013
Event Time: 10:12 [EDT]
Last Update Date: 03/15/2013
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):
GLENN DENTEL (R1DO)
PART 21 RX GROUP (EMAI)
GLENN DENTEL (R1DO)
PART 21 RX GROUP (EMAI)
| 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 | Y | 100 | Power Operation | 100 | Power Operation |
PART 21 REPORT - INITIAL NOTIFICATION FOR FLOWSERVE MODEL 28KXL PUMP IMPELLER DEFECT
"This Part 21 initial notification addresses a pump impeller defect that resulted in a post maintenance test (PMT) failure. The 0C RHR Service Water Pump was being replaced due to degraded performance which caused an In-Service Test (IST) failure. The replacement pump impeller received from the supplier had not been machined to the purchase order specifications. The IST of the new pump could not be completed since the required test conditions could not be established. The pump was later replaced and the IST was completed successfully. The pump was declared operable on March 2, 2013.
"This Part 21 Initial Notification is being submitted pursuant to the requirements of 10CFR21.21 (d)(3)(i)."
The licensee has notified the NRC Resident Inspector.
"This Part 21 initial notification addresses a pump impeller defect that resulted in a post maintenance test (PMT) failure. The 0C RHR Service Water Pump was being replaced due to degraded performance which caused an In-Service Test (IST) failure. The replacement pump impeller received from the supplier had not been machined to the purchase order specifications. The IST of the new pump could not be completed since the required test conditions could not be established. The pump was later replaced and the IST was completed successfully. The pump was declared operable on March 2, 2013.
"This Part 21 Initial Notification is being submitted pursuant to the requirements of 10CFR21.21 (d)(3)(i)."
The licensee has notified the NRC Resident Inspector.