Event Notification Report for June 15, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/14/2006 - 06/15/2006
EVENT NUMBERS
42649426474264242643
General Information or Other
Event Number: 42649
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: KLEINFELDER, INC
Region: 4
City: BELLEVUE State: WA
County:
License #: WN-I0475-1
Agreement: Y
Docket:
NRC Notified By: ARDEN SCROGGS
HQ OPS Officer: BILL GOTT
Licensee: KLEINFELDER, INC
Region: 4
City: BELLEVUE State: WA
County:
License #: WN-I0475-1
Agreement: Y
Docket:
NRC Notified By: ARDEN SCROGGS
HQ OPS Officer: BILL GOTT
Notification Date: 06/16/2006
Notification Time: 12:44 [ET]
Event Date: 06/15/2006
Event Time: 00:00 [PDT]
Last Update Date: 06/16/2006
Notification Time: 12:44 [ET]
Event Date: 06/15/2006
Event Time: 00:00 [PDT]
Last Update Date: 06/16/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANTHONY GODY (R4)
TIM HARRIS (NMSS)
ANTHONY GODY (R4)
TIM HARRIS (NMSS)
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The State provided the following information via email:
"A Troxler 3440 portable gauge serial number 37319 (8 millicuries Cs-137, 40 millicuries Am-241:Be) was damaged when a large earth moving piece of equipment backed over it. The operator was taking density readings about 20 feet behind the equipment when the equipment backed up. The operator ran to safety as the gauge was struck. The operator roped off a 50 foot radius around the gauge and called the RSO. When the RSO arrived at the site, the RSO and the operator took the buried gauge out of the soil and inspected it. The fire department was called and took readings in the area with a Geiger count-rate meter. Radiation levels were determined to be in the normal range. The top outer portion of the gauge was damaged and the source rod bent slightly, but the source areas were intact. The source rod was put back into the gauge by pounding the handle up with a mallet. The gauge was transported back to the licensed storage location and will be sent back to the manufacture for repair or disposal."
Location of Event: SeaTac Airport, Port of Seattle, City of SeaTac.
Washington State report number: WA-06-044
The State provided the following information via email:
"A Troxler 3440 portable gauge serial number 37319 (8 millicuries Cs-137, 40 millicuries Am-241:Be) was damaged when a large earth moving piece of equipment backed over it. The operator was taking density readings about 20 feet behind the equipment when the equipment backed up. The operator ran to safety as the gauge was struck. The operator roped off a 50 foot radius around the gauge and called the RSO. When the RSO arrived at the site, the RSO and the operator took the buried gauge out of the soil and inspected it. The fire department was called and took readings in the area with a Geiger count-rate meter. Radiation levels were determined to be in the normal range. The top outer portion of the gauge was damaged and the source rod bent slightly, but the source areas were intact. The source rod was put back into the gauge by pounding the handle up with a mallet. The gauge was transported back to the licensed storage location and will be sent back to the manufacture for repair or disposal."
Location of Event: SeaTac Airport, Port of Seattle, City of SeaTac.
Washington State report number: WA-06-044
Power Reactor
Event Number: 42647
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: SHAWN ELLIOTT
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: SHAWN ELLIOTT
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/16/2006
Notification Time: 02:18 [ET]
Event Date: 06/15/2006
Event Time: 22:23 [EDT]
Last Update Date: 06/16/2006
Notification Time: 02:18 [ET]
Event Date: 06/15/2006
Event Time: 22:23 [EDT]
Last Update Date: 06/16/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 45 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO DIGITAL ELECTRO-HYDRAULIC LEAK
"On 6/15/06 at 2223 hrs an unplanned manual reactor trip was initiated on St. Lucie Unit 2 from 45% power due to severe DEH Leak on the #1 Throttle Valve. DEH Leak ceased upon Turbine Trip. Following the reactor trip, EOP-1, Standard Post Trip Actions, and EOP-2, Reactor Trip Recovery procedures were completed without contingencies and Unit 2 was stabilized in Mode 3. All control rods fully inserted and no S/G Safety Valves Lifted. Feedwater to the S/G was supplied by the main FW Pumps. All safe shutdown equipment operated as expected. There were no major equipment failures."
Decay heat is being removed with main feedwater and dumping steam to the condenser. The grid is stable. The fire brigade was activated following the trip and set a fire watch (no fire).
The NRC Resident Inspector was notified of this event by the licensee.
"On 6/15/06 at 2223 hrs an unplanned manual reactor trip was initiated on St. Lucie Unit 2 from 45% power due to severe DEH Leak on the #1 Throttle Valve. DEH Leak ceased upon Turbine Trip. Following the reactor trip, EOP-1, Standard Post Trip Actions, and EOP-2, Reactor Trip Recovery procedures were completed without contingencies and Unit 2 was stabilized in Mode 3. All control rods fully inserted and no S/G Safety Valves Lifted. Feedwater to the S/G was supplied by the main FW Pumps. All safe shutdown equipment operated as expected. There were no major equipment failures."
Decay heat is being removed with main feedwater and dumping steam to the condenser. The grid is stable. The fire brigade was activated following the trip and set a fire watch (no fire).
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 42642
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/15/2006
Notification Time: 05:05 [ET]
Event Date: 06/15/2006
Event Time: 03:00 [EDT]
Last Update Date: 06/15/2006
Notification Time: 05:05 [ET]
Event Date: 06/15/2006
Event Time: 03:00 [EDT]
Last Update Date: 06/15/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID SILK (R1)
DAVID SILK (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
REACTOR SCRAM WHILE SHIFTING POWER SUPPLIES
"At approximately 0300 hours on 15 June, the Susquehanna Unit One reactor automatically scrammed due to an apparent neutron monitoring trip while transferring Reactor Protection System power supplies. All rods [fully] inserted, and both reactor recirculation pumps tripped. Reactor water level lowered to -38" causing level 3 (+13") and level 2 (-38")isolations, and was restored to normal level (+35") by RCIC and subsequently the feedwater system. All isolations at this level occurred as expected. No steam relief valves opened. Pressure was controlled via turbine bypass valve operation. All safety systems operated as expected.
"A reactor recirculation pump was restarted to re-establish forced core circulation. The reactor is currently stable in condition 3. An investigation into the cause of the shutdown is underway. Unit Two continued power operation.
"The NRC resident inspectors were notified. A press release will occur."
After the scram, HPCI automatically started but was manually shut down with RCIC maintaining vessel level. Decay heat removal is being maintained with main feedwater and the turbine steam dumps. The electrical grid is stable. No major LCOs were in affect at the time of the event.
"At approximately 0300 hours on 15 June, the Susquehanna Unit One reactor automatically scrammed due to an apparent neutron monitoring trip while transferring Reactor Protection System power supplies. All rods [fully] inserted, and both reactor recirculation pumps tripped. Reactor water level lowered to -38" causing level 3 (+13") and level 2 (-38")isolations, and was restored to normal level (+35") by RCIC and subsequently the feedwater system. All isolations at this level occurred as expected. No steam relief valves opened. Pressure was controlled via turbine bypass valve operation. All safety systems operated as expected.
"A reactor recirculation pump was restarted to re-establish forced core circulation. The reactor is currently stable in condition 3. An investigation into the cause of the shutdown is underway. Unit Two continued power operation.
"The NRC resident inspectors were notified. A press release will occur."
After the scram, HPCI automatically started but was manually shut down with RCIC maintaining vessel level. Decay heat removal is being maintained with main feedwater and the turbine steam dumps. The electrical grid is stable. No major LCOs were in affect at the time of the event.
Power Reactor
Event Number: 42643
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: BILL GOTT
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: BILL GOTT
Notification Date: 06/15/2006
Notification Time: 13:38 [ET]
Event Date: 06/15/2006
Event Time: 10:53 [EDT]
Last Update Date: 06/15/2006
Notification Time: 13:38 [ET]
Event Date: 06/15/2006
Event Time: 10:53 [EDT]
Last Update Date: 06/15/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
PATRICK LOUDEN (R3)
PATRICK LOUDEN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO TURBINE TRIP
"At 10:53 on 6/15/06, a reactor scram, occurred due to a Turbine/Generator Trip. All control rods fully inserted into core. The lowest vessel water level reached was 134 inches. Water level is now being controlled in the normal water level band using Condensate/Feedwater system. No SRVs lifted. RPV pressure is being controlled by the Turbine Pressure Regulator.
"At the time of the scram, 2B Main Transformer cleaning was taking place. The initial alarm was 'Main Transformer 2B Oil Temp Hi' followed by Generator Differential Relaying and a Turbine Trip. Transformer Deluge also initiated. An investigation is in progress to determine the specific cause for the initiating event.
"Group 13 'Drywell Sumps' isolated on Level 3 as expected. At the time of the scram, all ECCS systems and Emergency Diesel Generators were Operable."
The licensee notified the NRC Resident Inspector.
"At 10:53 on 6/15/06, a reactor scram, occurred due to a Turbine/Generator Trip. All control rods fully inserted into core. The lowest vessel water level reached was 134 inches. Water level is now being controlled in the normal water level band using Condensate/Feedwater system. No SRVs lifted. RPV pressure is being controlled by the Turbine Pressure Regulator.
"At the time of the scram, 2B Main Transformer cleaning was taking place. The initial alarm was 'Main Transformer 2B Oil Temp Hi' followed by Generator Differential Relaying and a Turbine Trip. Transformer Deluge also initiated. An investigation is in progress to determine the specific cause for the initiating event.
"Group 13 'Drywell Sumps' isolated on Level 3 as expected. At the time of the scram, all ECCS systems and Emergency Diesel Generators were Operable."
The licensee notified the NRC Resident Inspector.