Event Notification Report for November 24, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/23/2015 - 11/24/2015
Power Reactor
Event Number: 51566
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MATTHEW QUICK
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MATTHEW QUICK
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/24/2015
Notification Time: 17:02 [ET]
Event Date: 11/24/2015
Event Time: 12:53 [CST]
Last Update Date: 11/24/2015
Notification Time: 17:02 [ET]
Event Date: 11/24/2015
Event Time: 12:53 [CST]
Last Update Date: 11/24/2015
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):
AARON McCRAW (R3DO)
ENDANGERED SPECIES (EMAI)
AARON McCRAW (R3DO)
ENDANGERED SPECIES (EMAI)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
OFFSITE NOTIFICATION FOR A DISCHARGE CANAL TEMPERATURE CHANGE CAUSING A FISH KILL
"At 1253 CST on 11/24/2015, XCEL Energy Environmental Services made a report to the Minnesota Pollution Control Agency (MPCA) and the Minnesota Department of Natural Resources (DNR) due to the recorded total fish loss (59) as a result of the Monticello Plant's discharge canal temperature change following the reactor scram on 11/23/2015. This notification is being made under 10 CFR 50.72(b)(2)(xi) based on a notification to another government agency.
"This issue has no safety significance and no impact on the health and safety of the general public.
"NRC Resident Inspector has been notified."
"At 1253 CST on 11/24/2015, XCEL Energy Environmental Services made a report to the Minnesota Pollution Control Agency (MPCA) and the Minnesota Department of Natural Resources (DNR) due to the recorded total fish loss (59) as a result of the Monticello Plant's discharge canal temperature change following the reactor scram on 11/23/2015. This notification is being made under 10 CFR 50.72(b)(2)(xi) based on a notification to another government agency.
"This issue has no safety significance and no impact on the health and safety of the general public.
"NRC Resident Inspector has been notified."
Power Reactor
Event Number: 51562
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: BRYAN HEAVILIN
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: BRYAN HEAVILIN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2015
Notification Time: 17:50 [ET]
Event Date: 11/24/2015
Event Time: 13:30 [PST]
Last Update Date: 11/23/2015
Notification Time: 17:50 [ET]
Event Date: 11/24/2015
Event Time: 13:30 [PST]
Last Update Date: 11/23/2015
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):
MARK HAIRE (R4DO)
MARK HAIRE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION OF FUEL DEFECTS
"At approximately 1100 PST, Columbia Generating Station (CGS) planned to make a non-required notification to Energy Facility Site Evaluation Council (EFSEC) regarding indications of two fuel defects. This condition has not affected full power operation at CGS, and there is no impact to the health and safety of the public or to the environment. CGS plans on making this notification to EFSEC on November 24, 2015 at 1330 PST.
"This condition is being reported pursuant to 10 CFR 50.72 (b)(2)(xi).
"The licensee notified the NRC Resident Inspector."
"At approximately 1100 PST, Columbia Generating Station (CGS) planned to make a non-required notification to Energy Facility Site Evaluation Council (EFSEC) regarding indications of two fuel defects. This condition has not affected full power operation at CGS, and there is no impact to the health and safety of the public or to the environment. CGS plans on making this notification to EFSEC on November 24, 2015 at 1330 PST.
"This condition is being reported pursuant to 10 CFR 50.72 (b)(2)(xi).
"The licensee notified the NRC Resident Inspector."
Power Reactor
Event Number: 51564
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RON BLENKER
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RON BLENKER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/24/2015
Notification Time: 14:19 [ET]
Event Date: 11/24/2015
Event Time: 05:34 [CST]
Last Update Date: 11/24/2015
Notification Time: 14:19 [ET]
Event Date: 11/24/2015
Event Time: 05:34 [CST]
Last Update Date: 11/24/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
AARON McCRAW (R3DO)
AARON McCRAW (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
RESIDUAL HEAT REMOVAL PUMP TRIPPED DURING INITIATION OF SHUTDOWN COOLING
"On 11/24/2015 at 0534 hours [CST] the plant was in MODE 3 [hot standby] for a forced outage. While initially placing Shutdown Cooling (SDC) in service, the 12 Residual Heat Removal (RHR) pump tripped approximately 8-10 seconds after start due to the closure of the RHR SDC suction isolation valves. This was determined to be from an invalid signal on the Reactor Pressure Vessel (RPV) suction interlock. This is being reported under 10 CFR 50.72 (b)(3)(v)(B) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat. This event did not challenge the ability to maintain safe shutdown conditions, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident as other methods of decay heat removal were being utilized successfully to establish plant conditions.
"The NRC Resident Inspector has been notified."
This incident places the RHR system in a 24-hour technical specification limiting condition for operations.
"On 11/24/2015 at 0534 hours [CST] the plant was in MODE 3 [hot standby] for a forced outage. While initially placing Shutdown Cooling (SDC) in service, the 12 Residual Heat Removal (RHR) pump tripped approximately 8-10 seconds after start due to the closure of the RHR SDC suction isolation valves. This was determined to be from an invalid signal on the Reactor Pressure Vessel (RPV) suction interlock. This is being reported under 10 CFR 50.72 (b)(3)(v)(B) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat. This event did not challenge the ability to maintain safe shutdown conditions, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident as other methods of decay heat removal were being utilized successfully to establish plant conditions.
"The NRC Resident Inspector has been notified."
This incident places the RHR system in a 24-hour technical specification limiting condition for operations.