Event Notification Report for November 11, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/10/2002 - 11/11/2002
Power Reactor
Event Number: 39362
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: GERRY WAIG
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: GERRY WAIG
Notification Date: 11/11/2002
Notification Time: 07:56 [ET]
Event Date: 11/11/2002
Event Time: 05:15 [EST]
Last Update Date: 11/11/2002
Notification Time: 07:56 [ET]
Event Date: 11/11/2002
Event Time: 05:15 [EST]
Last Update Date: 11/11/2002
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):
LAWRENCE DOERFLEIN (R1)
LAWRENCE DOERFLEIN (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 |
REACTOR SCRAM - RPS ACTUATION ON HIGH REACTOR PRESSURE VESSEL PRESSURE
"At 05:15 [EST] all main steam isolation valves isolated unexpectedly. Reactor protection system actuation occurred due to high reactor pressure vessel pressure. All control rods fully inserted. Reactor pressure vessel pressure is being controlled using safety relief valves. Reactor pressure vessel water level is being controlled using reactor core isolation cooling system. Suppression pool temperature is being controlled using residual heat removal system in suppression pool cooling mode.
"Cause of the main steam isolation valve isolation is unknown. Plant parameters are stable. [The licensee is] making plans to achieve cold shutdown conditions."
The licensee reported that the reactor core isolation cooling system was manually initiated and that reactor vessel level decreased to level 3 during the reactor scram transient. Suppression pool temperature peaked at, and is being maintained steady at, 95 degrees Fahrenheit.
The licensee has notified the NRC Resident Inspector.
"At 05:15 [EST] all main steam isolation valves isolated unexpectedly. Reactor protection system actuation occurred due to high reactor pressure vessel pressure. All control rods fully inserted. Reactor pressure vessel pressure is being controlled using safety relief valves. Reactor pressure vessel water level is being controlled using reactor core isolation cooling system. Suppression pool temperature is being controlled using residual heat removal system in suppression pool cooling mode.
"Cause of the main steam isolation valve isolation is unknown. Plant parameters are stable. [The licensee is] making plans to achieve cold shutdown conditions."
The licensee reported that the reactor core isolation cooling system was manually initiated and that reactor vessel level decreased to level 3 during the reactor scram transient. Suppression pool temperature peaked at, and is being maintained steady at, 95 degrees Fahrenheit.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 39363
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MATTHEW MORGAN
HQ OPS Officer: MIKE NORRIS
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MATTHEW MORGAN
HQ OPS Officer: MIKE NORRIS
Notification Date: 11/11/2002
Notification Time: 22:08 [ET]
Event Date: 11/11/2002
Event Time: 19:46 [EST]
Last Update Date: 11/11/2002
Notification Time: 22:08 [ET]
Event Date: 11/11/2002
Event Time: 19:46 [EST]
Last Update Date: 11/11/2002
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):
LAWRENCE DOERFLEIN (R1)
LAWRENCE DOERFLEIN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 53 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO TURBINE MOTORING CONDITION ALARM
"BVPS Unit 1 was performing a plant shutdown from full power for a scheduled maintenance outage. At 1946 hours [EST], the plant was at 53% power and the 'Turbine Motoring Condition' alarm was received. The condition will cause a Turbine Trip if it exists for thirty seconds. A Turbine Trip will cause an automatic Reactor Trip if greater than 49% reactor power. The Reactor was Manually tripped and the Emergency Operating Procedure E-O was implemented. The Emergency Operating Procedures were exited at 2034 hours [EST]. The Auxiliary Feed Water System actuated as expected. All other systems functioned as required. The cause of the Turbine Motoring alarm is under investigation. The plant is currently stable in Mode 3. Shutdown to Mode 5 will continue for the planned maintenance outage."
The Licensee will be notifying the NRC Resident Inspector.
"BVPS Unit 1 was performing a plant shutdown from full power for a scheduled maintenance outage. At 1946 hours [EST], the plant was at 53% power and the 'Turbine Motoring Condition' alarm was received. The condition will cause a Turbine Trip if it exists for thirty seconds. A Turbine Trip will cause an automatic Reactor Trip if greater than 49% reactor power. The Reactor was Manually tripped and the Emergency Operating Procedure E-O was implemented. The Emergency Operating Procedures were exited at 2034 hours [EST]. The Auxiliary Feed Water System actuated as expected. All other systems functioned as required. The cause of the Turbine Motoring alarm is under investigation. The plant is currently stable in Mode 3. Shutdown to Mode 5 will continue for the planned maintenance outage."
The Licensee will be notifying the NRC Resident Inspector.