Event Notification Report for April 12, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/11/2003 - 04/12/2003
Power Reactor
Event Number: 39787
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: M. HOWARD
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: M. HOWARD
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/23/2003
Notification Time: 12:46 [ET]
Event Date: 04/12/2003
Event Time: 12:54 [EDT]
Last Update Date: 04/23/2003
Notification Time: 12:46 [ET]
Event Date: 04/12/2003
Event Time: 12:54 [EDT]
Last Update Date: 04/23/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MIKE ERNSTES (R2)
MIKE ERNSTES (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID START OF THE FOUR EMERGENCY DIESEL GENERATORS.
On 04/12/03 at 1254 an invalid start of the four emergency diesel generators occurred. The actuation was caused by a loss of DC power to the 1BB emergency diesel start circuit and a auto start signal to the remaining 3 emergency diesel generators. Power loss was caused by poor terminal lug contact on a space breaker during testing of a Vital Battery breaker.
The specific train actuated were both Train "A" and "B" for both Units 1 and 2. The system actuated was emergency AC electrical power (emergency diesel generators).
Complete train actuation occurred.
The Emergency Diesel Generator start was successful.
The NRC Resident Inspector was notified of this event by the licensee.
On 04/12/03 at 1254 an invalid start of the four emergency diesel generators occurred. The actuation was caused by a loss of DC power to the 1BB emergency diesel start circuit and a auto start signal to the remaining 3 emergency diesel generators. Power loss was caused by poor terminal lug contact on a space breaker during testing of a Vital Battery breaker.
The specific train actuated were both Train "A" and "B" for both Units 1 and 2. The system actuated was emergency AC electrical power (emergency diesel generators).
Complete train actuation occurred.
The Emergency Diesel Generator start was successful.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 39752
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: STEVEN SULLIVAN
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: STEVEN SULLIVAN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 04/12/2003
Notification Time: 20:55 [ET]
Event Date: 04/12/2003
Event Time: 18:47 [EDT]
Last Update Date: 04/12/2003
Notification Time: 20:55 [ET]
Event Date: 04/12/2003
Event Time: 18:47 [EDT]
Last Update Date: 04/12/2003
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):
JAMES TRAPP (R1)
JAMES TRAPP (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM- ALL RODS FULLY INSERTED
At 1847 hours on 04/12/03 the Peach Bottom Atomic Power Station Unit 2 experienced an automatic reactor scram and shutdown following an air line failure which resulted in the closure of the "D" outboard main steam line isolation valve. The closure of this valve resulted in a Reactor High Pressure Automatic Scram Signal. This caused a actuation of the Alternate Rod Insertion system on reactor high pressure of 1106 psi. All rods fully inserted. Additionally reactor vessel water level lowered to approximately negative 10 inches which resulted in a RPS and PCIS Group 2 & 3 isolations. All systems activated as required. The outage control center is currently staffed and repair/planning and restart preparation activities are in progress. Peach Bottom Atomic Power Station Unit 2 plant conditions are currently stable.
A copper air line going to the solenoid valve which operated the "D" outboard main steam isolation valve failed. Cause of the line failure is unknown at this time. The offsite electrical grid is stable and all emergency core cooling systems are fully operable if needed.
The NRC Resident Inspector was notified of this event by the licensee.
At 1847 hours on 04/12/03 the Peach Bottom Atomic Power Station Unit 2 experienced an automatic reactor scram and shutdown following an air line failure which resulted in the closure of the "D" outboard main steam line isolation valve. The closure of this valve resulted in a Reactor High Pressure Automatic Scram Signal. This caused a actuation of the Alternate Rod Insertion system on reactor high pressure of 1106 psi. All rods fully inserted. Additionally reactor vessel water level lowered to approximately negative 10 inches which resulted in a RPS and PCIS Group 2 & 3 isolations. All systems activated as required. The outage control center is currently staffed and repair/planning and restart preparation activities are in progress. Peach Bottom Atomic Power Station Unit 2 plant conditions are currently stable.
A copper air line going to the solenoid valve which operated the "D" outboard main steam isolation valve failed. Cause of the line failure is unknown at this time. The offsite electrical grid is stable and all emergency core cooling systems are fully operable if needed.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 39753
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MITCHEL TAGGART
HQ OPS Officer: RICH LAURA
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MITCHEL TAGGART
HQ OPS Officer: RICH LAURA
Notification Date: 04/12/2003
Notification Time: 23:50 [ET]
Event Date: 04/12/2003
Event Time: 22:21 [EDT]
Last Update Date: 04/13/2003
Notification Time: 23:50 [ET]
Event Date: 04/12/2003
Event Time: 22:21 [EDT]
Last Update Date: 04/13/2003
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):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| 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 |
TURBINE TRIP CAUSES REACTOR TRIP AT SEQOUYAH UNIT 2
"While resetting a turbine trip supervisory module, the unit 2 turbine tripped from "Turbine High Vibration Turbine Trip" at 22:21. The reactor tripped as a result of the turbine trip. Investigation is pending concerning the turbine vibration equipment.
"Auxiliary feed water system initiated as designed. All secondary plant equipment performed as expected.
"The plant is being maintained in Mode 3 at NOT/NOP, 547 degrees F and 2235 psig, with auxiliary feed water supplying the Steam Generators and steam dumps removing the decay heat."
All control rods inserted into the core with no problems. The NRC Resident Inspector was notified.
"While resetting a turbine trip supervisory module, the unit 2 turbine tripped from "Turbine High Vibration Turbine Trip" at 22:21. The reactor tripped as a result of the turbine trip. Investigation is pending concerning the turbine vibration equipment.
"Auxiliary feed water system initiated as designed. All secondary plant equipment performed as expected.
"The plant is being maintained in Mode 3 at NOT/NOP, 547 degrees F and 2235 psig, with auxiliary feed water supplying the Steam Generators and steam dumps removing the decay heat."
All control rods inserted into the core with no problems. The NRC Resident Inspector was notified.