Event Notification Report for May 31, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/30/2015 - 05/31/2015
Power Reactor
Event Number: 51106
Facility: COOK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD HARRIS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD HARRIS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/31/2015
Notification Time: 16:32 [ET]
Event Date: 05/31/2015
Event Time: 16:00 [EDT]
Last Update Date: 06/02/2015
Notification Time: 16:32 [ET]
Event Date: 05/31/2015
Event Time: 16:00 [EDT]
Last Update Date: 06/02/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 99 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO FAILURE OF AN EMERGENCY DIESEL GENERATOR
"At 1600 [EDT] on May 31, 2015, [DC Cook] operations commenced a shutdown of DC Cook Unit 1 to comply with LCO 3.8.1 Condition G, when the 14 day limit to complete Condition B Required Action could not be met.
"At 0010 [EDT] on May 18, 2015, Unit 1 AB Emergency Diesel Generator was removed from service for planned maintenance. LCO 3.8.1 Condition B was entered which allows 14 days to restore diesel to operable.
"At 1049 [EDT] on May 21, 2015, Unit 1 AB Emergency Diesel Generator tripped during post maintenance testing due to high bearing temperatures. Subsequent actions to repair and restore the diesel to operable status have been unsuccessful.
"This event is reportable under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications, as a four (4) hour report. The DC Cook Sr. Resident NRC Inspector has been notified."
Unit 1 is expected to be in Mode 5 by 2030 EDT on June 1, 2015. There is no impact on Unit 2.
* * * UPDATE FROM CHRIS PEAK TO JOHN SHOEMAKER ON 6/1/15 AT 1704 EDT * * *
"This update is to correct the information contained in the block titled 'Power/Mode After'. The power and mode after the event requiring notification (TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INABILITY TO RESTORE UNIT 1 AB EDG WITHIN THE COMPLETION TIME PRESCRIBED IN LCO 3.8.1 CONDITION B) was 99% power and mode 1.
"The licensee has notified the NRC Resident Inspector."
D.C. Cook Unit 1 is currently in Mode 3 and conducting a normal cooldown to Mode 4.
Notified R3DO (Passehl).
* * * UPDATE FROM CHRIS PEAK TO HOWIE CROUCH AT 0734 EDT ON 6/2/15 * * *
"DC Cook Unit 1 reactor was shut down (Mode 3) at 0231 hours [EDT] June 01, 2015 and achieved Mode 5 at 0410 hours [EDT] June 02, 2015 to comply with LCO 3.8.1 Condition G with all systems operating normally.
"The licensee has notified the NRC Resident Inspector."
Notified R3DO (Passehl).
"At 1600 [EDT] on May 31, 2015, [DC Cook] operations commenced a shutdown of DC Cook Unit 1 to comply with LCO 3.8.1 Condition G, when the 14 day limit to complete Condition B Required Action could not be met.
"At 0010 [EDT] on May 18, 2015, Unit 1 AB Emergency Diesel Generator was removed from service for planned maintenance. LCO 3.8.1 Condition B was entered which allows 14 days to restore diesel to operable.
"At 1049 [EDT] on May 21, 2015, Unit 1 AB Emergency Diesel Generator tripped during post maintenance testing due to high bearing temperatures. Subsequent actions to repair and restore the diesel to operable status have been unsuccessful.
"This event is reportable under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications, as a four (4) hour report. The DC Cook Sr. Resident NRC Inspector has been notified."
Unit 1 is expected to be in Mode 5 by 2030 EDT on June 1, 2015. There is no impact on Unit 2.
* * * UPDATE FROM CHRIS PEAK TO JOHN SHOEMAKER ON 6/1/15 AT 1704 EDT * * *
"This update is to correct the information contained in the block titled 'Power/Mode After'. The power and mode after the event requiring notification (TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INABILITY TO RESTORE UNIT 1 AB EDG WITHIN THE COMPLETION TIME PRESCRIBED IN LCO 3.8.1 CONDITION B) was 99% power and mode 1.
"The licensee has notified the NRC Resident Inspector."
D.C. Cook Unit 1 is currently in Mode 3 and conducting a normal cooldown to Mode 4.
Notified R3DO (Passehl).
* * * UPDATE FROM CHRIS PEAK TO HOWIE CROUCH AT 0734 EDT ON 6/2/15 * * *
"DC Cook Unit 1 reactor was shut down (Mode 3) at 0231 hours [EDT] June 01, 2015 and achieved Mode 5 at 0410 hours [EDT] June 02, 2015 to comply with LCO 3.8.1 Condition G with all systems operating normally.
"The licensee has notified the NRC Resident Inspector."
Notified R3DO (Passehl).
Power Reactor
Event Number: 51107
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JEFFREY HUMAN
HQ OPS Officer: DANIEL MILLS
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JEFFREY HUMAN
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/01/2015
Notification Time: 02:25 [ET]
Event Date: 05/31/2015
Event Time: 22:20 [CDT]
Last Update Date: 06/01/2015
Notification Time: 02:25 [ET]
Event Date: 05/31/2015
Event Time: 22:20 [CDT]
Last Update Date: 06/01/2015
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):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO TRIP OF CONDENSATE AND MAIN FEEDWATER PUMP
"On May 31, 2015 at 2220 CDT, the Unit 1 reactor was manually tripped while operating at 100 percent power due to a lockout trip of 11 Condensate Pump followed by a lockout trip of 11 Main Feedwater Pump. Manual Reactor Trip is directed by the annunciator response procedure for the lockout alarm, C47010-0101, 11 Feedwater Pump Locked Out. This also resulted in a turbine trip. The crew entered the reactor trip emergency operating procedures and stabilized the unit in Mode 3 at normal operating pressure and temperature. All control rods fully inserted into the core following the trip. The manual trip is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater System actuated to start the auxiliary feedwater pumps as designed on low narrow range steam generator level and provided makeup flow to the steam generators. The auxiliary feedwater actuation is reportable per 10 CFR 50.72(b)(3)(iv)(A). Steam generator levels have been returned to normal. Following the reactor trip, 15A Feedwater Heater relief lifted and failed to reseat. 12 Main Feedwater Pump was subsequently secured resulting in 15A Feedwater Heater relief valve reseating successfully. Steam generators are being supplied by 12 Motor Drive Auxiliary Feedwater Pump and decay heat is being removed by the condenser steam dump system. The cause of 11 Condensate Pump trip remains under investigation. There was no effect on Unit 2 as a result of this trip. The health and safety of the public and site personnel were not at risk at any time during this event. The NRC Senior Resident Inspector has been notified."
Unit 2 is unaffected and remains at 100 percent power.
"On May 31, 2015 at 2220 CDT, the Unit 1 reactor was manually tripped while operating at 100 percent power due to a lockout trip of 11 Condensate Pump followed by a lockout trip of 11 Main Feedwater Pump. Manual Reactor Trip is directed by the annunciator response procedure for the lockout alarm, C47010-0101, 11 Feedwater Pump Locked Out. This also resulted in a turbine trip. The crew entered the reactor trip emergency operating procedures and stabilized the unit in Mode 3 at normal operating pressure and temperature. All control rods fully inserted into the core following the trip. The manual trip is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater System actuated to start the auxiliary feedwater pumps as designed on low narrow range steam generator level and provided makeup flow to the steam generators. The auxiliary feedwater actuation is reportable per 10 CFR 50.72(b)(3)(iv)(A). Steam generator levels have been returned to normal. Following the reactor trip, 15A Feedwater Heater relief lifted and failed to reseat. 12 Main Feedwater Pump was subsequently secured resulting in 15A Feedwater Heater relief valve reseating successfully. Steam generators are being supplied by 12 Motor Drive Auxiliary Feedwater Pump and decay heat is being removed by the condenser steam dump system. The cause of 11 Condensate Pump trip remains under investigation. There was no effect on Unit 2 as a result of this trip. The health and safety of the public and site personnel were not at risk at any time during this event. The NRC Senior Resident Inspector has been notified."
Unit 2 is unaffected and remains at 100 percent power.