Event Notification Report for January 04, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/03/2013 - 01/04/2013
Power Reactor
Event Number: 48651
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES AYALA
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES AYALA
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/04/2013
Notification Time: 14:19 [ET]
Event Date: 01/04/2013
Event Time: 09:41 [CST]
Last Update Date: 01/04/2013
Notification Time: 14:19 [ET]
Event Date: 01/04/2013
Event Time: 09:41 [CST]
Last Update Date: 01/04/2013
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):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 2 MANUALLY TRIPPED AFTER TWO SHUTDOWN CONTROL RODS UNEXPECTEDLY DROPPED DURING SURVEILLANCE TESTING
"On January 4, 2013, at 0941 hours [CST], Unit 2 was manually tripped after 2 shutdown rods unexpectedly dropped during monthly control rod surveillance testing. Shutdown Bank C rods were being inserted in accordance with the surveillance procedure, when 2 rods in Shutdown Bank E (D-8 and M-8) unexpectedly dropped. This met the criteria for a manual reactor trip, which was immediately performed.
"The appropriate procedures were entered to mitigate the transient and all systems responded as designed.
"Unit 2 is currently in Mode 3 and the cause of the 2 dropped rods is under investigation."
All three (3) motor-driven and the steam-driven Auxiliary Feedwater Pumps started as required and have since been secured. Decay heat is being removed using normal startup feedwater with steam discharge to the main condenser via the bypass valves. Unit 2 is in a normal post trip electrical lineup.
The licensee informed the NRC Resident Inspector.
"On January 4, 2013, at 0941 hours [CST], Unit 2 was manually tripped after 2 shutdown rods unexpectedly dropped during monthly control rod surveillance testing. Shutdown Bank C rods were being inserted in accordance with the surveillance procedure, when 2 rods in Shutdown Bank E (D-8 and M-8) unexpectedly dropped. This met the criteria for a manual reactor trip, which was immediately performed.
"The appropriate procedures were entered to mitigate the transient and all systems responded as designed.
"Unit 2 is currently in Mode 3 and the cause of the 2 dropped rods is under investigation."
All three (3) motor-driven and the steam-driven Auxiliary Feedwater Pumps started as required and have since been secured. Decay heat is being removed using normal startup feedwater with steam discharge to the main condenser via the bypass valves. Unit 2 is in a normal post trip electrical lineup.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 48652
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: HARDY FARRIS
HQ OPS Officer: CHARLES TEAL
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: HARDY FARRIS
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/05/2013
Notification Time: 03:09 [ET]
Event Date: 01/04/2013
Event Time: 23:37 [CST]
Last Update Date: 01/05/2013
Notification Time: 03:09 [ET]
Event Date: 01/04/2013
Event Time: 23:37 [CST]
Last Update Date: 01/05/2013
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):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 94 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO A TURBINE/GENERATOR TRIP
"Actuation of RPS with reactor critical. Reactor Scram occurred at 2337 CST 01/04/13 from 94% CTP (Core Thermal Power). The cause of the scram appears to be a Generator/Turbine trip.
"Appropriate off normal event procedures were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached and no ECCS or Diesel Generator initiation occurred.
"MSIVs remained open and SRVs lifted and reseated as designed. Currently, reactor water level is being maintained by the Condensate and Feedwater system in normal band and reactor pressure is being controlled via bypass valves to the condenser."
The NRC Resident Inspector has been informed. See similar EN #48637.
"Actuation of RPS with reactor critical. Reactor Scram occurred at 2337 CST 01/04/13 from 94% CTP (Core Thermal Power). The cause of the scram appears to be a Generator/Turbine trip.
"Appropriate off normal event procedures were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached and no ECCS or Diesel Generator initiation occurred.
"MSIVs remained open and SRVs lifted and reseated as designed. Currently, reactor water level is being maintained by the Condensate and Feedwater system in normal band and reactor pressure is being controlled via bypass valves to the condenser."
The NRC Resident Inspector has been informed. See similar EN #48637.