Event Notification Report for December 02, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/01/2001 - 12/02/2001
Power Reactor
Event Number: 38531
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RESTUCCIO
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RESTUCCIO
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/02/2001
Notification Time: 18:17 [ET]
Event Date: 12/02/2001
Event Time: 14:48 [EST]
Last Update Date: 12/03/2001
Notification Time: 18:17 [ET]
Event Date: 12/02/2001
Event Time: 14:48 [EST]
Last Update Date: 12/03/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
WILLIAM RULAND (R1)
WILLIAM RULAND (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 75 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM FROM 75% POWER
On December 2, 2001 at 1448, Unit 2 manually scrammed from approximately 75% reactor power due to a low water level trip (159.3" - Level 3). Preliminary indications are an electrical fault/trip on feedwater Pump "A" was the cause of the reactor low level condition. The "A" Recirculation Flow Control Valve (FCV) ran back to minimum position as required on the low level alarm at 178.3" - Level 4. The "B" FCV failed to fully run back as required due to the electrical transient and the subsequent loss of hydraulic control units. The "B" FCV stabilized at 50% open. The Operators were inserting cram rods in an attempt to lower power further when the low water level trip alarm came in for Division 1. The Control Room Supervisor (CRS) ordered the mode switch to shutdown. All Control Rods inserted as required. Reactor water level is being controlled in the normal level band with Condensate Booster pumps. Reactor pressure is being reduced to place the shutdown cooling system in service by the use of the turbine bypass valves.
Additionally, indications show that the Neutron Monitoring System (NMS) scram setpoints were exceeded for the Average Power Range Monitoring (APRM) thermal power trip. This trip signal was in close sequence to the mode switch being placed in the shutdown position.
The NRC Resident Inspector was notified.
HOO NOTE: see event # 38532
* * * UPDATED AT 1734 EST ON 12/3/01 BY TOM RESTUCCIO TO FANGIE JONES * * *
"The purpose of this notification is to provide an update to Event #38531. From reviews of plant computer data and alarm printouts, it was determined that the Average Power Range Monitoring (APRM) Thermal Power trip was NOT exceeded. The only APRM scram signal received was the expected APRM neutron monitoring scram which occurred when the mode switch was taken out of the run position. With the mode switch not in run, the APRM neutron monitoring scram setpoint is 15% which was exceeded due to power being at 75%."
The licensee notified the NRC Resident Inspector. The R1DO (John Rogge) has been notified.
On December 2, 2001 at 1448, Unit 2 manually scrammed from approximately 75% reactor power due to a low water level trip (159.3" - Level 3). Preliminary indications are an electrical fault/trip on feedwater Pump "A" was the cause of the reactor low level condition. The "A" Recirculation Flow Control Valve (FCV) ran back to minimum position as required on the low level alarm at 178.3" - Level 4. The "B" FCV failed to fully run back as required due to the electrical transient and the subsequent loss of hydraulic control units. The "B" FCV stabilized at 50% open. The Operators were inserting cram rods in an attempt to lower power further when the low water level trip alarm came in for Division 1. The Control Room Supervisor (CRS) ordered the mode switch to shutdown. All Control Rods inserted as required. Reactor water level is being controlled in the normal level band with Condensate Booster pumps. Reactor pressure is being reduced to place the shutdown cooling system in service by the use of the turbine bypass valves.
Additionally, indications show that the Neutron Monitoring System (NMS) scram setpoints were exceeded for the Average Power Range Monitoring (APRM) thermal power trip. This trip signal was in close sequence to the mode switch being placed in the shutdown position.
The NRC Resident Inspector was notified.
HOO NOTE: see event # 38532
* * * UPDATED AT 1734 EST ON 12/3/01 BY TOM RESTUCCIO TO FANGIE JONES * * *
"The purpose of this notification is to provide an update to Event #38531. From reviews of plant computer data and alarm printouts, it was determined that the Average Power Range Monitoring (APRM) Thermal Power trip was NOT exceeded. The only APRM scram signal received was the expected APRM neutron monitoring scram which occurred when the mode switch was taken out of the run position. With the mode switch not in run, the APRM neutron monitoring scram setpoint is 15% which was exceeded due to power being at 75%."
The licensee notified the NRC Resident Inspector. The R1DO (John Rogge) has been notified.
Power Reactor
Event Number: 38532
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: PETRELLI
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: PETRELLI
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/02/2001
Notification Time: 20:40 [ET]
Event Date: 12/02/2001
Event Time: 17:21 [EST]
Last Update Date: 12/02/2001
Notification Time: 20:40 [ET]
Event Date: 12/02/2001
Event Time: 17:21 [EST]
Last Update Date: 12/02/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WILLIAM RULAND (R1)
WILLIAM RULAND (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
PLANT RECEIVED A SECOND SCRAM WHILE IN MODE 3
Following the manual scram at 1448 the plant had a second scram at 1721 which was an automatic scram on low water level (Level 3 - 159.3") when lowering reactor pressure to inject with the booster pumps at 1721. The scram was reset and plant shutdown and cooldown is continuing.
The NRC Resident Inspector was notified.
HOO NOTE: see event #38531
Following the manual scram at 1448 the plant had a second scram at 1721 which was an automatic scram on low water level (Level 3 - 159.3") when lowering reactor pressure to inject with the booster pumps at 1721. The scram was reset and plant shutdown and cooldown is continuing.
The NRC Resident Inspector was notified.
HOO NOTE: see event #38531