Event Notification Report for August 03, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/02/2003 - 08/03/2003
EVENT NUMBERS
40045
Power Reactor
Event Number: 40045
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: A. BARTLIK
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: A. BARTLIK
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/03/2003
Notification Time: 11:10 [ET]
Event Date: 08/03/2003
Event Time: 04:30 [EDT]
Last Update Date: 08/03/2003
Notification Time: 11:10 [ET]
Event Date: 08/03/2003
Event Time: 04:30 [EDT]
Last Update Date: 08/03/2003
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 NOGGLE (R1)
WILLIAM BECKNER (NRR)
RICHARD WESSMAN (IRO)
ROY ZIMMERMAN (NSIR)
CARL PAPERIELLO (EDO)
JAMES NOGGLE (R1)
WILLIAM BECKNER (NRR)
RICHARD WESSMAN (IRO)
ROY ZIMMERMAN (NSIR)
CARL PAPERIELLO (EDO)
| 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/REACTOR TRIP
The following information was received from the licensee via facsimile:
"At 04:30 [EDT], Indian Point 2 lost all load due to an Offsite electrical disturbance. The loss of load caused the Turbine-Generator speed to increase above 1800 RPM resulting in a "TURBINE CONTROL OIL AUTO TRIP" which in turn caused a REACTOR TRIP.
"The over frequency condition prevented the FAST TRANSFER of Bus 1, 2, 3 and 4 to the Station Auxiliary Transformer, resulting in a loss of all Reactor Coolant Pumps and power to Safeguards Bus 2A and 3A.
"All Emergency Diesel Generators auto-started as required. Power remained available to Safeguards Buses 5A and 6A from the Station Auxiliary Transformer and the EDGs did not assume load.
"Auxiliary Feedwater (AFW) Pumps 22 and 23 automatically started on low steam generator level condition. AFW pump 21 did not start due to loss of power to bus 3A.
"Power was restored to bus 2A and 3A by manual closure of the output breakers of EDG 22 at approximately 4:40.
Initial core cooling was provided by natural circulation cooling.
"The Condenser remained available as a heat sink and the Steam Generator Atmospheric Relief Valves and Safety Valves remained closed.
"A Pressurizer Power Operated Relief Valve (PORV) actuated, resulting in discharge to the Pressurizer Relief Tank (PRT), which remained intact. The Pressurizer Code Safety Valves remained closed.
"Forced RCS circulation was re-established at 05:30. At present 3 RCPs [Reactor Coolant Pumps] have been restored to service, with actions in progress to restore the fourth RCP.
"Currently, plant conditions [are] Hot Zero Power with preparations for unit recovery in progress."
The electrical disturbance in the switchyard was due to electrical storms in the area. All rods inserted into the core during the trip. The site's other nuclear unit was not affected. All electrical feeders required by Technical Specifications are in service at this time.
Notified Region 1 PAO (Neil Sheehan) & Headquarters PAO (Beth Hayden). & EDO Office (Ho Nieh).
The licensee has notified the NRC Resident Inspector.
The following information was received from the licensee via facsimile:
"At 04:30 [EDT], Indian Point 2 lost all load due to an Offsite electrical disturbance. The loss of load caused the Turbine-Generator speed to increase above 1800 RPM resulting in a "TURBINE CONTROL OIL AUTO TRIP" which in turn caused a REACTOR TRIP.
"The over frequency condition prevented the FAST TRANSFER of Bus 1, 2, 3 and 4 to the Station Auxiliary Transformer, resulting in a loss of all Reactor Coolant Pumps and power to Safeguards Bus 2A and 3A.
"All Emergency Diesel Generators auto-started as required. Power remained available to Safeguards Buses 5A and 6A from the Station Auxiliary Transformer and the EDGs did not assume load.
"Auxiliary Feedwater (AFW) Pumps 22 and 23 automatically started on low steam generator level condition. AFW pump 21 did not start due to loss of power to bus 3A.
"Power was restored to bus 2A and 3A by manual closure of the output breakers of EDG 22 at approximately 4:40.
Initial core cooling was provided by natural circulation cooling.
"The Condenser remained available as a heat sink and the Steam Generator Atmospheric Relief Valves and Safety Valves remained closed.
"A Pressurizer Power Operated Relief Valve (PORV) actuated, resulting in discharge to the Pressurizer Relief Tank (PRT), which remained intact. The Pressurizer Code Safety Valves remained closed.
"Forced RCS circulation was re-established at 05:30. At present 3 RCPs [Reactor Coolant Pumps] have been restored to service, with actions in progress to restore the fourth RCP.
"Currently, plant conditions [are] Hot Zero Power with preparations for unit recovery in progress."
The electrical disturbance in the switchyard was due to electrical storms in the area. All rods inserted into the core during the trip. The site's other nuclear unit was not affected. All electrical feeders required by Technical Specifications are in service at this time.
Notified Region 1 PAO (Neil Sheehan) & Headquarters PAO (Beth Hayden). & EDO Office (Ho Nieh).
The licensee has notified the NRC Resident Inspector.