Event Notification Report for May 09, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/08/2011 - 05/09/2011
Power Reactor
Event Number: 46830
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/09/2011
Notification Time: 08:44 [ET]
Event Date: 05/09/2011
Event Time: 07:22 [CDT]
Last Update Date: 05/09/2011
Notification Time: 08:44 [ET]
Event Date: 05/09/2011
Event Time: 07:22 [CDT]
Last Update Date: 05/09/2011
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):
MARK RING (R3DO)
MARK RING (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP UPON TURBINE TRIP DUE TO MAIN GENERATOR LOCKOUT
"With Unit 2 at 100% power and Unit 1 in Mode 6 and severe weather in the vicinity, [a] Unit 2 Main Generator Lockout trip occurred at 0722 [CDT]. The reactor trip was 'Turbine Trip'. Procedure 2E-0, 'Reactor Trip or Safety Injection' was completed at 0725 hrs. [with] no Safety Injection required. [Procedure] 2ES-0.1, 'Reactor Trip Recovery' is in progress. Offsite power remains on all safeguards buses for both units. [The] 21 and 22 AFW [Auxiliary Feed Water] pumps automatically started on steam generator low level and are supplying Unit 2 steam generators. Unit 1 shutdown cooling was not affected.
"Reportable actuations are: Unit 2 Reactor Protection (scram), Unit 2 AFW pumps automatic start."
The licensee has notified the State of Wisconsin, the State of Minnesota, the Prairie Island Indian Nation and the NRC Resident Inspector. They will be issuing a press release.
"With Unit 2 at 100% power and Unit 1 in Mode 6 and severe weather in the vicinity, [a] Unit 2 Main Generator Lockout trip occurred at 0722 [CDT]. The reactor trip was 'Turbine Trip'. Procedure 2E-0, 'Reactor Trip or Safety Injection' was completed at 0725 hrs. [with] no Safety Injection required. [Procedure] 2ES-0.1, 'Reactor Trip Recovery' is in progress. Offsite power remains on all safeguards buses for both units. [The] 21 and 22 AFW [Auxiliary Feed Water] pumps automatically started on steam generator low level and are supplying Unit 2 steam generators. Unit 1 shutdown cooling was not affected.
"Reportable actuations are: Unit 2 Reactor Protection (scram), Unit 2 AFW pumps automatic start."
The licensee has notified the State of Wisconsin, the State of Minnesota, the Prairie Island Indian Nation and the NRC Resident Inspector. They will be issuing a press release.
Non-Agreement State
Event Number: 46832
Rep Org: ESCANABA PAPER COMPANY
Licensee: ESCANABA PAPER COMPANY
Region: 3
City: ESCANABA State: MI
County:
License #: 21-17630-01
Agreement: N
Docket:
NRC Notified By: JAMES HATTEN
HQ OPS Officer: DONALD NORWOOD
Licensee: ESCANABA PAPER COMPANY
Region: 3
City: ESCANABA State: MI
County:
License #: 21-17630-01
Agreement: N
Docket:
NRC Notified By: JAMES HATTEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/09/2011
Notification Time: 17:07 [ET]
Event Date: 05/09/2011
Event Time: 11:00 [EDT]
Last Update Date: 05/09/2011
Notification Time: 17:07 [ET]
Event Date: 05/09/2011
Event Time: 11:00 [EDT]
Last Update Date: 05/09/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
DAVE PASSEHL (R3DO)
DIANA DIAZ-TORO (FSME)
DAVE PASSEHL (R3DO)
DIANA DIAZ-TORO (FSME)
BROKEN SHUTTER HANDLE ON LEVEL GAUGE
While performing a shutter check on a Kay Ray Model 7050, serial number 1019, level gauge, the shutter handle broke. The gauge is still in service at this time. No personnel exposures occurred as a result of this event. The gauge manufacturer will be contacted for repair guidance.
While performing a shutter check on a Kay Ray Model 7050, serial number 1019, level gauge, the shutter handle broke. The gauge is still in service at this time. No personnel exposures occurred as a result of this event. The gauge manufacturer will be contacted for repair guidance.
Power Reactor
Event Number: 46839
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL SPRINKLE
HQ OPS Officer: JOE O'HARA
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL SPRINKLE
HQ OPS Officer: JOE O'HARA
Notification Date: 05/11/2011
Notification Time: 01:21 [ET]
Event Date: 05/09/2011
Event Time: 15:18 [EDT]
Last Update Date: 05/11/2011
Notification Time: 01:21 [ET]
Event Date: 05/09/2011
Event Time: 15:18 [EDT]
Last Update Date: 05/11/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
EUGENE GUTHRIE (R2DO)
EUGENE GUTHRIE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
POTENTIAL VALVE MISPOSITIONING LED TO A CONDITION PROHIBITED BY TECHNICAL SPECIFICATIONS
"On May 9, 2011, at 1518 Eastern Daylight Saving Time (EDT), WBN [Watts Bar Nuclear] started a Safety Injection Pump and began to inject into the Reactor Coolant System contrary to Technical Specification Limiting Condition for Operation 3.4.12, which requires in part for Mode 5 that a Cold Overpressure Mitigation System (COMS) shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated.
"The RCS pressure rise was recognized immediately, and the pump was secured within 27 seconds. The pressure reached a maximum of 328 psig. which is below the relief valve setpoint, so no structure, system, or component pressure limit was exceeded at any time. LCO 3.4.12 Condition A was entered immediately. At 1521, the pump breaker was directed to be racked out, and the breaker was reported racked out and verified by 1600, at which time LCO 3.4.12 was exited.
"This event was determined to be reportable as a condition prohibited by Technical Specifications in accordance with 10 CFR 50.73(a) (2)(i)(b). This notification is made in accordance with Watts Bar License condition 2.G.
"The NRC Resident Inspector has been notified of this event and event notification."
The licensee is investigating the likelihood of a valve mispositioning.
"On May 9, 2011, at 1518 Eastern Daylight Saving Time (EDT), WBN [Watts Bar Nuclear] started a Safety Injection Pump and began to inject into the Reactor Coolant System contrary to Technical Specification Limiting Condition for Operation 3.4.12, which requires in part for Mode 5 that a Cold Overpressure Mitigation System (COMS) shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated.
"The RCS pressure rise was recognized immediately, and the pump was secured within 27 seconds. The pressure reached a maximum of 328 psig. which is below the relief valve setpoint, so no structure, system, or component pressure limit was exceeded at any time. LCO 3.4.12 Condition A was entered immediately. At 1521, the pump breaker was directed to be racked out, and the breaker was reported racked out and verified by 1600, at which time LCO 3.4.12 was exited.
"This event was determined to be reportable as a condition prohibited by Technical Specifications in accordance with 10 CFR 50.73(a) (2)(i)(b). This notification is made in accordance with Watts Bar License condition 2.G.
"The NRC Resident Inspector has been notified of this event and event notification."
The licensee is investigating the likelihood of a valve mispositioning.