Event Notification Report for October 17, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/16/2010 - 10/17/2010
Power Reactor
Event Number: 46337
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACK OSBORNE
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JACK OSBORNE
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/17/2010
Notification Time: 06:38 [ET]
Event Date: 10/17/2010
Event Time: 05:12 [EDT]
Last Update Date: 10/18/2010
Notification Time: 06:38 [ET]
Event Date: 10/17/2010
Event Time: 05:12 [EDT]
Last Update Date: 10/18/2010
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):
WILLIAM COOK (R1DO)
WILLIAM COOK (R1DO)
| 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 DUE TO 4 KV GROUP BUS UNDERVOLTAGE CONDITION
"On 10/17/10 at 0512 [EDT], Unit 2 experienced an [automatic] reactor trip due to 4 kV group bus under voltage. While restoring the voltage regulator to automatic, following a swap to manual at 0123 [EDT] on 10/17/10 while 500 kV line 5014 was being restored to service, the reactor tripped after placing the voltage regulator in automatic.
"The crew entered EOP [Emergency Operating Procedure] Trip 1, and then EOP Trip 2 as required. The plant was stabilized at no load conditions. All rods fully inserted on the trip, and all systems responded as designed with RCS [Reactor Coolant System] temperature being controlled via 21 RCP [Reactor Coolant Pump] and the steam dump system. 22, 23, and 24 RCP's tripped on group bus under voltage. The AFW [Auxiliary Feed Water] Pumps started in response to low steam generator levels. 23 AFW was subsequently tripped per procedure since 21 and 22 AFW pumps were in service feeding 21-24 steam generators.
"Salem Unit 2 is currently in Mode 3. RCS temperature is 547 degrees. RCS pressure is 2235 pounds. All Emergency Core Cooling Systems and Engineered Safety Function Systems are available. No personnel injuries occurred as a result of the trip. No radiological release is in progress due to this event."
At 0123 EDT, following the restoration of a 500 kV line, perturbation in the line caused an over current condition which shifted the voltage regulator to manual. After engineering's recommendation, the voltage regulator was placed in automatic shortly prior to the reactor trip. The plant is in a normal shutdown electrical lineup. There was no impact on Salem Unit 1 as a result of this event.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM BILL MUFFLEY TO JOHN SHOEMAKER 1138 EDT ON 10/18/10 * * *
Notified by the licensee that the AFW Pumps started on loss of Steam Generator Feed Pumps which had tripped on low suction pressure.
The licensee has notified the NRC Resident Inspector.
"On 10/17/10 at 0512 [EDT], Unit 2 experienced an [automatic] reactor trip due to 4 kV group bus under voltage. While restoring the voltage regulator to automatic, following a swap to manual at 0123 [EDT] on 10/17/10 while 500 kV line 5014 was being restored to service, the reactor tripped after placing the voltage regulator in automatic.
"The crew entered EOP [Emergency Operating Procedure] Trip 1, and then EOP Trip 2 as required. The plant was stabilized at no load conditions. All rods fully inserted on the trip, and all systems responded as designed with RCS [Reactor Coolant System] temperature being controlled via 21 RCP [Reactor Coolant Pump] and the steam dump system. 22, 23, and 24 RCP's tripped on group bus under voltage. The AFW [Auxiliary Feed Water] Pumps started in response to low steam generator levels. 23 AFW was subsequently tripped per procedure since 21 and 22 AFW pumps were in service feeding 21-24 steam generators.
"Salem Unit 2 is currently in Mode 3. RCS temperature is 547 degrees. RCS pressure is 2235 pounds. All Emergency Core Cooling Systems and Engineered Safety Function Systems are available. No personnel injuries occurred as a result of the trip. No radiological release is in progress due to this event."
At 0123 EDT, following the restoration of a 500 kV line, perturbation in the line caused an over current condition which shifted the voltage regulator to manual. After engineering's recommendation, the voltage regulator was placed in automatic shortly prior to the reactor trip. The plant is in a normal shutdown electrical lineup. There was no impact on Salem Unit 1 as a result of this event.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM BILL MUFFLEY TO JOHN SHOEMAKER 1138 EDT ON 10/18/10 * * *
Notified by the licensee that the AFW Pumps started on loss of Steam Generator Feed Pumps which had tripped on low suction pressure.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 46338
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVE DEES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/17/2010
Notification Time: 14:35 [ET]
Event Date: 10/17/2010
Event Time: 09:53 [CDT]
Last Update Date: 10/17/2010
Notification Time: 14:35 [ET]
Event Date: 10/17/2010
Event Time: 09:53 [CDT]
Last Update Date: 10/17/2010
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 HAIRE (R4DO)
MARK HAIRE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 16 | Power Operation | 0 | Hot Standby |
REACTOR TRIP ON LOW STEAM GENERATOR LEVEL DURING PLANT STARTUP
"At 0953 CDT, Wolf Creek experienced a reactor trip due to low steam generator level. At the time of the trip the plant was in Mode 1 approximately 16% power following a forced outage. A feedwater isolation signal [FWIS] was generated due to high S/G level (P-14) in 'B' S/G [steam generator]. The FWIS resulted in a low S/G level. Although a manual reactor trip was ordered by the duty Shift Manager, the manual trip signal was not inserted before the reactor automatically tripped on low steam generator level.
"Auxiliary Feed Water systems actuated as expected due to low steam generator levels.
"The plant is presently in Mode 3 at normal operating temperature and pressure.
"The Senior Resident Inspector has been notified."
All control rods fully inserted during the trip. All three Auxiliary Feedwater Pumps started to maintain S/G levels.
The plant was stabilized with the motor driven startup feedwater pump maintaining S/G level. Decay heat is being removed using the atmospheric steam dumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup.
A press release will be issued.
"At 0953 CDT, Wolf Creek experienced a reactor trip due to low steam generator level. At the time of the trip the plant was in Mode 1 approximately 16% power following a forced outage. A feedwater isolation signal [FWIS] was generated due to high S/G level (P-14) in 'B' S/G [steam generator]. The FWIS resulted in a low S/G level. Although a manual reactor trip was ordered by the duty Shift Manager, the manual trip signal was not inserted before the reactor automatically tripped on low steam generator level.
"Auxiliary Feed Water systems actuated as expected due to low steam generator levels.
"The plant is presently in Mode 3 at normal operating temperature and pressure.
"The Senior Resident Inspector has been notified."
All control rods fully inserted during the trip. All three Auxiliary Feedwater Pumps started to maintain S/G levels.
The plant was stabilized with the motor driven startup feedwater pump maintaining S/G level. Decay heat is being removed using the atmospheric steam dumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup.
A press release will be issued.