Event Notification Report for August 21, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/20/2004 - 08/21/2004
EVENT NUMBERS
40973
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40973
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: WILLIAM DALTON
HQ OPS Officer: GERRY WAIG
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: WILLIAM DALTON
HQ OPS Officer: GERRY WAIG
Notification Date: 08/22/2004
Notification Time: 01:12 [ET]
Event Date: 08/21/2004
Event Time: 20:00 [EDT]
Last Update Date: 10/12/2004
Notification Time: 01:12 [ET]
Event Date: 08/21/2004
Event Time: 20:00 [EDT]
Last Update Date: 10/12/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN WHITE (R1)
JOHN WHITE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 90 | Power Operation | 90 | Power Operation |
ACCIDENT MITIGATION - HIGH PRESSURE COOLANT INJECTION SYSTEM FLOW CONTROLLER MALFUNCTION
The following information was provided by the licensee via facsimile:
"[The] High Pressure Coolant Injection (HPCI) flow controller malfunctioned resulting in the inability of the HPCI to perform its safety function as a single train system under 10 CFR 50.72 (b)(3)(v). The failure mode for the flow controller is suspected to be a power supply issue, however, the cause has not been confirmed at this time. Unit 2 is in a 14 day technical specification [T.S.] limitation which if exceed results in a unit shutdown ( T.S. 3.5.1 Condition C)."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 10/12/04 @ 0835 BY FOSS TO GOULD * * * RETRACTION
The purpose of this notification is to retract a previous report made on 8/22/04 at 0112 hours (EN# 40973).
Notification of the event to the NRC on 8/22/04 was initially made as a result of declaring the Unit 2 High Pressure
Coolant Injection (HPCI) system inoperable when unexpected conditions were found during performance of routine
control board checks of HPCI. Specifically, it was observed by the Reactor Operator that the HPCI flow controller
would not properly respond to faceplate manipulations. Initially, it was believed that the flow controller power supply
may have failed and therefore, the flow controller could not perform its intended function. The HPCI system was not
operating at the time of the discovery.
Since the initial report, Engineering has determined that the HPCI system was capable of performing its safety
function. Although it was determined that the HPCI flow controller faceplate was defective, the set point of the flow
controller and the flow controller's ability to automatically control system flow for a design basis event was not
affected. A failure analysis of the faceplate was performed. It was determined that keypad contacts on the faceplate
were the cause of the degraded faceplate function, but these keypad Contacts did not prevent the flow controller from
performing its design function.
The flow controller faceplate was replaced by 1410 hours on 8/22/04 (CR 246290).
The NRC resident has been informed of the retraction.
Notified the Reg 2 RDO (Ogle)
The following information was provided by the licensee via facsimile:
"[The] High Pressure Coolant Injection (HPCI) flow controller malfunctioned resulting in the inability of the HPCI to perform its safety function as a single train system under 10 CFR 50.72 (b)(3)(v). The failure mode for the flow controller is suspected to be a power supply issue, however, the cause has not been confirmed at this time. Unit 2 is in a 14 day technical specification [T.S.] limitation which if exceed results in a unit shutdown ( T.S. 3.5.1 Condition C)."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 10/12/04 @ 0835 BY FOSS TO GOULD * * * RETRACTION
The purpose of this notification is to retract a previous report made on 8/22/04 at 0112 hours (EN# 40973).
Notification of the event to the NRC on 8/22/04 was initially made as a result of declaring the Unit 2 High Pressure
Coolant Injection (HPCI) system inoperable when unexpected conditions were found during performance of routine
control board checks of HPCI. Specifically, it was observed by the Reactor Operator that the HPCI flow controller
would not properly respond to faceplate manipulations. Initially, it was believed that the flow controller power supply
may have failed and therefore, the flow controller could not perform its intended function. The HPCI system was not
operating at the time of the discovery.
Since the initial report, Engineering has determined that the HPCI system was capable of performing its safety
function. Although it was determined that the HPCI flow controller faceplate was defective, the set point of the flow
controller and the flow controller's ability to automatically control system flow for a design basis event was not
affected. A failure analysis of the faceplate was performed. It was determined that keypad contacts on the faceplate
were the cause of the degraded faceplate function, but these keypad Contacts did not prevent the flow controller from
performing its design function.
The flow controller faceplate was replaced by 1410 hours on 8/22/04 (CR 246290).
The NRC resident has been informed of the retraction.
Notified the Reg 2 RDO (Ogle)