Event Notification Report for March 18, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/17/2013 - 03/18/2013
Power Reactor
Event Number: 48827
Facility: HATCH
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/18/2013
Notification Time: 16:50 [ET]
Event Date: 03/18/2013
Event Time: 09:10 [EDT]
Last Update Date: 03/18/2013
Notification Time: 16:50 [ET]
Event Date: 03/18/2013
Event Time: 09:10 [EDT]
Last Update Date: 03/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 2 | Startup | 2 | Startup |
HIGH PRESSURE COOLANT INJECTION INOPERABLE FOLLOWING REFUELING OUTAGE
"On 3/18/2013, with the Unit 2 reactor at approximately 165 psig while in Mode 2 (Startup) following a refueling outage, the high pressure coolant injection (HPCI) system was undergoing post-maintenance testing to demonstrate operability of the system following the performance of major system maintenance. The provision allowed by the Technical Specifications was being used to increase reactor pressure above 150 psig for the purpose of performing operability testing and there was reasonable assurance that the HPCI system had been restored to support successful test results. [However, the HPCI system failed to pass operability testing and] as a result of the inability of the HPCI system to function as required during this testing while above 150 psig, HPCI was not capable of performing its safety function. Reactor pressure was decreased below the Technical Specification 3.5.1 LCO Applicability Requirement of 150 psig and work is in progress to make the needed repairs to support returning HPCI to an operable condition."
The licensee notified the NRC Resident Inspector.
"On 3/18/2013, with the Unit 2 reactor at approximately 165 psig while in Mode 2 (Startup) following a refueling outage, the high pressure coolant injection (HPCI) system was undergoing post-maintenance testing to demonstrate operability of the system following the performance of major system maintenance. The provision allowed by the Technical Specifications was being used to increase reactor pressure above 150 psig for the purpose of performing operability testing and there was reasonable assurance that the HPCI system had been restored to support successful test results. [However, the HPCI system failed to pass operability testing and] as a result of the inability of the HPCI system to function as required during this testing while above 150 psig, HPCI was not capable of performing its safety function. Reactor pressure was decreased below the Technical Specification 3.5.1 LCO Applicability Requirement of 150 psig and work is in progress to make the needed repairs to support returning HPCI to an operable condition."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 48828
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/18/2013
Notification Time: 18:00 [ET]
Event Date: 03/18/2013
Event Time: 16:05 [CDT]
Last Update Date: 03/18/2013
Notification Time: 18:00 [ET]
Event Date: 03/18/2013
Event Time: 16:05 [CDT]
Last Update Date: 03/18/2013
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):
GREG WERNER (R4DO)
GREG WERNER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 0 | Startup | 0 | Startup |
OFFSITE NOTIFICATION DUE TO RADIOACTIVE RELEASE ONSITE
"On March 18, 2013, at approximately 1605 CDT, the station commenced notification of the Louisiana Department of Environmental Quality and other offsite governmental agencies that traces of radioactive contaminants were found at the site of an underground pipe leak on station property. This leak could potentially contain tritium and cobalt-60, and is believed to have been contained on the plant site. The leakage path has been isolated. The station is currently starting up following a refueling outage.
"In October 2012, water was found leaking from the ground and accumulating in a ditch near the station's sewage treatment plant. The initial investigation concluded that the source of the leak was domestic water, based on pH sample results, known buried piping in the area, and the fact that the sewage treatment plant operates intermittently. During the recent refueling outage, which started on February 16, it was noted that the leak had stopped. Testing of the potentially affected piping found that the leak was not domestic water, but was actually coming from the sewage treatment plant effluent line. It was determined that the constant leakage seen in October 2012 was due to a failed check valve in the effluent line. This check valve is designed to prevent backflow from the main condenser circulating water system blow-down line. The failed check valve was allowing water from the blow-down line to flow backwards into the sewage plant effluent line and out of the breach. The leak had stopped because the circulating water system blow-down line was shut down at the start of the refueling outage.
"Discharges from the liquid radwaste system also flow into the blow-down line at a point upstream of the connection to the sewage plant effluent line. During planned discharge of liquid radwaste, some of the diluted radioactive water was thus able to leak out on the ground. Samples of the dirt in the area of the leak obtained on March 17 found detectable levels of cobalt 60. No water is available to perform tritium analysis.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as a condition requiring notifications to local and state governmental agencies in accordance with the NEI 07-07 Industry Ground Water Protection Initiative."
The leak path has been isolated.
The licensee notified the NRC Resident Inspector.
"On March 18, 2013, at approximately 1605 CDT, the station commenced notification of the Louisiana Department of Environmental Quality and other offsite governmental agencies that traces of radioactive contaminants were found at the site of an underground pipe leak on station property. This leak could potentially contain tritium and cobalt-60, and is believed to have been contained on the plant site. The leakage path has been isolated. The station is currently starting up following a refueling outage.
"In October 2012, water was found leaking from the ground and accumulating in a ditch near the station's sewage treatment plant. The initial investigation concluded that the source of the leak was domestic water, based on pH sample results, known buried piping in the area, and the fact that the sewage treatment plant operates intermittently. During the recent refueling outage, which started on February 16, it was noted that the leak had stopped. Testing of the potentially affected piping found that the leak was not domestic water, but was actually coming from the sewage treatment plant effluent line. It was determined that the constant leakage seen in October 2012 was due to a failed check valve in the effluent line. This check valve is designed to prevent backflow from the main condenser circulating water system blow-down line. The failed check valve was allowing water from the blow-down line to flow backwards into the sewage plant effluent line and out of the breach. The leak had stopped because the circulating water system blow-down line was shut down at the start of the refueling outage.
"Discharges from the liquid radwaste system also flow into the blow-down line at a point upstream of the connection to the sewage plant effluent line. During planned discharge of liquid radwaste, some of the diluted radioactive water was thus able to leak out on the ground. Samples of the dirt in the area of the leak obtained on March 17 found detectable levels of cobalt 60. No water is available to perform tritium analysis.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as a condition requiring notifications to local and state governmental agencies in accordance with the NEI 07-07 Industry Ground Water Protection Initiative."
The leak path has been isolated.
The licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 48888
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: PEKINS ELMER
Region: 4
City: RICHLAND State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KRISTEN SCHWAB
HQ OPS Officer: VINCE KLCO
Licensee: PEKINS ELMER
Region: 4
City: RICHLAND State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KRISTEN SCHWAB
HQ OPS Officer: VINCE KLCO
Notification Date: 04/04/2013
Notification Time: 16:08 [ET]
Event Date: 03/18/2013
Event Time: 00:00 [PDT]
Last Update Date: 04/04/2013
Notification Time: 16:08 [ET]
Event Date: 03/18/2013
Event Time: 00:00 [PDT]
Last Update Date: 04/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY KELLAR (R4DO)
FSME RESOURCES (EMAI)
RAY KELLAR (R4DO)
FSME RESOURCES (EMAI)
AGREEMENT STATE REPORT - SHIPMENT EXCEEDED SURFACE CONTAMINATION LIMITS
The following information was received from the Washington State Division of Radiation Protection by email:
"PermaFix Northwest received a shipment from Perkin Elmer, Inc. that consisted of 32 packages, 4 plastic drums and 28 metal drums, and was shipped as an exclusive use shipment. Upon receipt, the drums were surveyed and 2 plastic drums were found to exceed the 49 CFR 173.443 non-removable contamination limit of 2,200 dpm/cm2 for an exclusive use shipment. The drum survey results were reported as 44,391 dpm/100 cm2 H-3 and 18,080 dpm/100 cm2 C-14; 20,127 dpm/100 cm2 H-3 and 18,508 dpm/100 cm2 C-14, and 13,323 dpm/100 cm2 H-3 and 10,019 dpm/100 cm2 C-14. This most contaminated drum was manifested with only H-3 and C-14, the other 2 drums were manifested with only C-14."
Washington Incident Number: WA-13-021
The following information was received from the Washington State Division of Radiation Protection by email:
"PermaFix Northwest received a shipment from Perkin Elmer, Inc. that consisted of 32 packages, 4 plastic drums and 28 metal drums, and was shipped as an exclusive use shipment. Upon receipt, the drums were surveyed and 2 plastic drums were found to exceed the 49 CFR 173.443 non-removable contamination limit of 2,200 dpm/cm2 for an exclusive use shipment. The drum survey results were reported as 44,391 dpm/100 cm2 H-3 and 18,080 dpm/100 cm2 C-14; 20,127 dpm/100 cm2 H-3 and 18,508 dpm/100 cm2 C-14, and 13,323 dpm/100 cm2 H-3 and 10,019 dpm/100 cm2 C-14. This most contaminated drum was manifested with only H-3 and C-14, the other 2 drums were manifested with only C-14."
Washington Incident Number: WA-13-021