Event Notification Report for March 29, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/28/2014 - 03/29/2014
Power Reactor
Event Number: 49972
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROGER BUTLER
HQ OPS Officer: DONG HWA PARK
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROGER BUTLER
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/29/2014
Notification Time: 14:09 [ET]
Event Date: 03/29/2014
Event Time: 10:08 [CDT]
Last Update Date: 03/29/2014
Notification Time: 14:09 [ET]
Event Date: 03/29/2014
Event Time: 10:08 [CDT]
Last Update Date: 03/29/2014
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):
DAVID PROULX (R4DO)
DAVID PROULX (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 87 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO A TURBINE TRIP
"Actuation of RPS with reactor critical. Reactor Scram occurred at 1008 [CDT] on 03/29/2014 from 87% CTP [core thermal power]. The cause of the Scram appears to be a Turbine Generator Trip.
"05-S-01-EP-2 RPV Control, 05-1-02-I-1 Reactor Scram ONEP and 05-1-02-l-2 Turbine Generator Trip ONEP were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF [engineered safety feature] power occurred. No ECCS [emergency core cooling systems] initiation signals were reached and no ESF or Diesel Generator initiations occurred.
"All control rods are fully inserted. MSIVs [main steam isolation valve] remained open and no SRVs [safety relief valves] lifted. Currently, reactor water level is being maintained by the Condensate and Feedwater system in normal band and reactor pressure is being controlled via Main Turbine Bypass Valves to the main condenser. There are no challenges to Primary or Secondary Containment at this time."
The licensee has notified the NRC Resident Inspector.
"Actuation of RPS with reactor critical. Reactor Scram occurred at 1008 [CDT] on 03/29/2014 from 87% CTP [core thermal power]. The cause of the Scram appears to be a Turbine Generator Trip.
"05-S-01-EP-2 RPV Control, 05-1-02-I-1 Reactor Scram ONEP and 05-1-02-l-2 Turbine Generator Trip ONEP were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF [engineered safety feature] power occurred. No ECCS [emergency core cooling systems] initiation signals were reached and no ESF or Diesel Generator initiations occurred.
"All control rods are fully inserted. MSIVs [main steam isolation valve] remained open and no SRVs [safety relief valves] lifted. Currently, reactor water level is being maintained by the Condensate and Feedwater system in normal band and reactor pressure is being controlled via Main Turbine Bypass Valves to the main condenser. There are no challenges to Primary or Secondary Containment at this time."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 49973
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: RUDY CAPUTO
HQ OPS Officer: CHARLES TEAL
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: RUDY CAPUTO
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/29/2014
Notification Time: 23:49 [ET]
Event Date: 03/29/2014
Event Time: 16:20 [CDT]
Last Update Date: 03/30/2014
Notification Time: 23:49 [ET]
Event Date: 03/29/2014
Event Time: 16:20 [CDT]
Last Update Date: 03/30/2014
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):
BILLY DICKSON (R3DO)
BILLY DICKSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
DIVISION 3 CORE STANDBY COOLING SYSTEM VENTILATION FAILED
"This report is being made pursuant to SAF 1.8, 10 CFR 50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. During steady state operations on Unit 1 at 1620 [CDT] hrs. on 3/29/14, the Division 3 Core Standby Cooling System (CSCS) Pump Room, SWGR Room, and Battery Room Ventilation failed in such a manner that heat could not be removed from the rooms. These Division 3 systems supply power and cooling water to the High Pressure Core Spray system (HPCS), which is a single-train system. The HPCS system and its associated power supplies were declared inoperable based on long-term temperature considerations. The system remains available due to manual damper adjustments that than can be made per an approved procedure."
The licensee will notify the NRC Resident Inspector.
"This report is being made pursuant to SAF 1.8, 10 CFR 50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. During steady state operations on Unit 1 at 1620 [CDT] hrs. on 3/29/14, the Division 3 Core Standby Cooling System (CSCS) Pump Room, SWGR Room, and Battery Room Ventilation failed in such a manner that heat could not be removed from the rooms. These Division 3 systems supply power and cooling water to the High Pressure Core Spray system (HPCS), which is a single-train system. The HPCS system and its associated power supplies were declared inoperable based on long-term temperature considerations. The system remains available due to manual damper adjustments that than can be made per an approved procedure."
The licensee will notify the NRC Resident Inspector.