Event Notification Report for December 31, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/30/2001 - 12/31/2001
Power Reactor
Event Number: 38599
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: S. SAUER
HQ OPS Officer: FANGIE JONES
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: S. SAUER
HQ OPS Officer: FANGIE JONES
Notification Date: 12/31/2001
Notification Time: 02:00 [ET]
Event Date: 12/31/2001
Event Time: 00:10 [EST]
Last Update Date: 12/31/2001
Notification Time: 02:00 [ET]
Event Date: 12/31/2001
Event Time: 00:10 [EST]
Last Update Date: 12/31/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MICHELE EVANS (R1)
MICHELE EVANS (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 Standby |
REACTOR TRIP AND SAFETY INJECTION DUE TO SPRAY VALVE FAILING OPEN
The unit experienced a reactor trip and safety injection as a result of a pressurizer spray valve (2PS3) failing open. This caused a reactor trip on Overtemperature DeltaT and a safety injection on low reactor coolant system pressure. All emergency equipment responded properly, all safety injection pumps started and all control rods fully inserted. The emergency diesels started, but were not required to load. The auxiliary feedwater pumps started on low steam generator level. The pressurizer spray valve closed when the valve's operating air was isolated.
The unit is stable in Mode 3 (Hot Standby) at normal temperature and pressure. Auxiliary feedwater and steam dumps are in use to maintain steam generator level and remove excess heat. An investigation of the failure is underway.
The licensee intends to notify the NRC Resident Inspector and the local Township.
The unit experienced a reactor trip and safety injection as a result of a pressurizer spray valve (2PS3) failing open. This caused a reactor trip on Overtemperature DeltaT and a safety injection on low reactor coolant system pressure. All emergency equipment responded properly, all safety injection pumps started and all control rods fully inserted. The emergency diesels started, but were not required to load. The auxiliary feedwater pumps started on low steam generator level. The pressurizer spray valve closed when the valve's operating air was isolated.
The unit is stable in Mode 3 (Hot Standby) at normal temperature and pressure. Auxiliary feedwater and steam dumps are in use to maintain steam generator level and remove excess heat. An investigation of the failure is underway.
The licensee intends to notify the NRC Resident Inspector and the local Township.
Power Reactor
Event Number: 38600
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: RICHARD WALLEMAN
HQ OPS Officer: FANGIE JONES
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: RICHARD WALLEMAN
HQ OPS Officer: FANGIE JONES
Notification Date: 01/01/2002
Notification Time: 03:19 [ET]
Event Date: 12/31/2001
Event Time: 19:22 [EST]
Last Update Date: 01/01/2002
Notification Time: 03:19 [ET]
Event Date: 12/31/2001
Event Time: 19:22 [EST]
Last Update Date: 01/01/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GARY SHEAR (R3)
GARY SHEAR (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE
The licensee reported that the SPDS display screens were locked up and thus unavailable for use in case of an incident. Several procedures including the Emergency Operating Procedures refer to the displays for information. With the system unavailable for greater than 8 hours a report under loss of assessment capabilities was made. The SPDS is being worked on at this time and is expected back in service in a short period of time.
The licensee intends to notify the NRC Resident Inspector.
* * * UPDATE 1622EST ON 1/1/02 FROM TOM COBBLEDICK TO S. SANDIN * * *
The SPDS was restored to service as of 1615EST. The licensee will inform the NRC Resident Inspector. Notified R3DO(Shear).
The licensee reported that the SPDS display screens were locked up and thus unavailable for use in case of an incident. Several procedures including the Emergency Operating Procedures refer to the displays for information. With the system unavailable for greater than 8 hours a report under loss of assessment capabilities was made. The SPDS is being worked on at this time and is expected back in service in a short period of time.
The licensee intends to notify the NRC Resident Inspector.
* * * UPDATE 1622EST ON 1/1/02 FROM TOM COBBLEDICK TO S. SANDIN * * *
The SPDS was restored to service as of 1615EST. The licensee will inform the NRC Resident Inspector. Notified R3DO(Shear).