Event Notification Report for December 02, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/01/2011 - 12/02/2011
Power Reactor
Event Number: 47494
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: RUSSELL SEARS
HQ OPS Officer: VINCE KLCO
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: RUSSELL SEARS
HQ OPS Officer: VINCE KLCO
Notification Date: 12/02/2011
Notification Time: 13:21 [ET]
Event Date: 12/02/2011
Event Time: 08:29 [CST]
Last Update Date: 12/02/2011
Notification Time: 13:21 [ET]
Event Date: 12/02/2011
Event Time: 08:29 [CST]
Last Update Date: 12/02/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
THOMAS FARNHOLTZ (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 87 | Power Operation | 87 | Power Operation |
FITNESS FOR DUTY REPORT INVOLVING A NON-LICENSED EMPLOYEE SUPERVISOR
A non-licensed employee supervisor had a confirmed positive drug test during random testing. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
A non-licensed employee supervisor had a confirmed positive drug test during random testing. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 47495
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JIM BROOKS
HQ OPS Officer: PETE SNYDER
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JIM BROOKS
HQ OPS Officer: PETE SNYDER
Notification Date: 12/02/2011
Notification Time: 13:28 [ET]
Event Date: 12/02/2011
Event Time: 09:45 [EST]
Last Update Date: 12/02/2011
Notification Time: 13:28 [ET]
Event Date: 12/02/2011
Event Time: 09:45 [EST]
Last Update Date: 12/02/2011
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):
WAYNE SCHMIDT (R1DO)
WAYNE SCHMIDT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
WRONG TRAIN EMERGENCY DIESEL FUEL RACK TRIP
"While hanging tags on the 'B' Diesel Generator, which was tagged out for maintenance, the operator mistakenly entered the 'A' Diesel Generator Room and tripped the 'A' Diesel Generator fuel rack, making it inoperable. At this time both diesels were inoperable placing the plant in a 24 Hour LCO.
"When the fuel rack was tripped alarms were received in the control room, the operator was immediately contacted and the problem was identified and corrected. Total LCO time was approximately 2 minutes."
The licensee notified the NRC Resident Inspector.
"While hanging tags on the 'B' Diesel Generator, which was tagged out for maintenance, the operator mistakenly entered the 'A' Diesel Generator Room and tripped the 'A' Diesel Generator fuel rack, making it inoperable. At this time both diesels were inoperable placing the plant in a 24 Hour LCO.
"When the fuel rack was tripped alarms were received in the control room, the operator was immediately contacted and the problem was identified and corrected. Total LCO time was approximately 2 minutes."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 47511
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: JOHN SHOEMAKER
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/08/2011
Notification Time: 14:33 [ET]
Event Date: 12/02/2011
Event Time: 13:11 [CST]
Last Update Date: 12/08/2011
Notification Time: 14:33 [ET]
Event Date: 12/02/2011
Event Time: 13:11 [CST]
Last Update Date: 12/08/2011
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):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (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 |
LOW PRESSURE COOLANT INJECTION INOPERABLE
"This condition is being reported in accordance with 10CFR50.72(b)(3)(v) as a condition that could have prevented fulfillment of a safety function.
"On 12/02/2011 at 1311 CST, the Low Pressure Coolant Injection (LPCI) was declared inoperable when voiding was discovered in the 'B' Residual Heat Removal (RHR) inject vent line.
"Initial review of this condition for immediate reportability under 50.72(b)(3)(v), event or condition that could have prevented fulfillment of a safety function, concluded the condition was not reportable based on the availability of other Emergency Core Cooling Systems (ECCS). Specifically, Core Spray and HPCI were both available to perform the function of emergency core cooling. On 12/03/2011 at 1650 CST, LPCI was declared operable based on further examinations to determine extent of voiding, system filling and venting and completion of supporting engineering evaluations. Subsequent reviews determined that the reportability decision under 50.72(b)(3)(v) as a event or condition that could have prevented fulfillment of a safety function should be based on safety function at the system level, rather than at the ECCS function level. The decision to report the inoperability of LPCI under 50.72(b)(3)(v) was made at 1319 CST on 12/08/2011.
"The licensee has notified the NRC Resident Inspector."
"This condition is being reported in accordance with 10CFR50.72(b)(3)(v) as a condition that could have prevented fulfillment of a safety function.
"On 12/02/2011 at 1311 CST, the Low Pressure Coolant Injection (LPCI) was declared inoperable when voiding was discovered in the 'B' Residual Heat Removal (RHR) inject vent line.
"Initial review of this condition for immediate reportability under 50.72(b)(3)(v), event or condition that could have prevented fulfillment of a safety function, concluded the condition was not reportable based on the availability of other Emergency Core Cooling Systems (ECCS). Specifically, Core Spray and HPCI were both available to perform the function of emergency core cooling. On 12/03/2011 at 1650 CST, LPCI was declared operable based on further examinations to determine extent of voiding, system filling and venting and completion of supporting engineering evaluations. Subsequent reviews determined that the reportability decision under 50.72(b)(3)(v) as a event or condition that could have prevented fulfillment of a safety function should be based on safety function at the system level, rather than at the ECCS function level. The decision to report the inoperability of LPCI under 50.72(b)(3)(v) was made at 1319 CST on 12/08/2011.
"The licensee has notified the NRC Resident Inspector."