Event Notification Report for July 10, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/09/2005 - 07/10/2005
EVENT NUMBERS
41832
Power Reactor
Event Number: 41832
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ALAN RAUSH
HQ OPS Officer: JOHN KNOKE
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: ALAN RAUSH
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/10/2005
Notification Time: 06:42 [ET]
Event Date: 07/10/2005
Event Time: 03:18 [EDT]
Last Update Date: 07/10/2005
Notification Time: 06:42 [ET]
Event Date: 07/10/2005
Event Time: 03:18 [EDT]
Last Update Date: 07/10/2005
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):
GREG BOWMAN (R1)
GREG BOWMAN (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 |
TURBINE TRIP RESULTING IN RPS ACTUATION AND AUTOMATIC REACTOR SCRAM
"This non-emergency 4-hour and 8-hour report is pursuant to 10CFR50.72(b)(2) and 10CFR50.72(b)(3). On 7/10/05 at 0318 hours, Unit 2 experienced a turbine trip and subsequent reactor scram. An RPS actuation occurred, as expected, following the turbine trip. RPS responded normally and reactor power is 0%. Reactor water level went below 1 inch, as expected, following a reactor scram from 100% power. At a reactor level of less than 1 inch, PCIS Group 2 and 3 isolations occurred. Reactor water level has been restored above 1 inch to the normal level using the normal reactor feedwater system. All safety systems responded as designed.
"An investigation is in progress to determine the cause of the turbine trip and to initiate appropriate corrective actions."
During the scram the RCS experienced a high pressure condition which caused both recirculation pumps to trip and 3 SRVs to lift and reseat. The licensee is presently depressurizing primary system in order to restart one of the recirculation pumps. Current RCS parameters: Pressure - 320 psig; Temperature - 428 F; and Level - +23 inches. All rods fully inserted.
Prior to the turbine trip the licensee was conducting a routine weekly "Mechanical Trip Valve Test."
The licensee notified the NRC Resident Inspector.
"This non-emergency 4-hour and 8-hour report is pursuant to 10CFR50.72(b)(2) and 10CFR50.72(b)(3). On 7/10/05 at 0318 hours, Unit 2 experienced a turbine trip and subsequent reactor scram. An RPS actuation occurred, as expected, following the turbine trip. RPS responded normally and reactor power is 0%. Reactor water level went below 1 inch, as expected, following a reactor scram from 100% power. At a reactor level of less than 1 inch, PCIS Group 2 and 3 isolations occurred. Reactor water level has been restored above 1 inch to the normal level using the normal reactor feedwater system. All safety systems responded as designed.
"An investigation is in progress to determine the cause of the turbine trip and to initiate appropriate corrective actions."
During the scram the RCS experienced a high pressure condition which caused both recirculation pumps to trip and 3 SRVs to lift and reseat. The licensee is presently depressurizing primary system in order to restart one of the recirculation pumps. Current RCS parameters: Pressure - 320 psig; Temperature - 428 F; and Level - +23 inches. All rods fully inserted.
Prior to the turbine trip the licensee was conducting a routine weekly "Mechanical Trip Valve Test."
The licensee notified the NRC Resident Inspector.