Event Notification Report for April 05, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/04/2002 - 04/05/2002
Power Reactor
Event Number: 38836
Facility: MCGUIRE
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THAD REAMES
HQ OPS Officer: LEIGH TROCINE
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THAD REAMES
HQ OPS Officer: LEIGH TROCINE
Notification Date: 04/05/2002
Notification Time: 17:08 [ET]
Event Date: 04/05/2002
Event Time: 15:10 [EST]
Last Update Date: 04/05/2002
Notification Time: 17:08 [ET]
Event Date: 04/05/2002
Event Time: 15:10 [EST]
Last Update Date: 04/05/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RANDY MUSSER (R2)
RANDY MUSSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SPECIFICATION 3.0.3 ENTRY DUE TO INOPERABILITY OF BOTH RESIDUAL HEAT REMOVAL SYSTEM TRAINS FOLLOWING THE DISCOVERY THAT A DISCHARGE CHECK VALVE WAS STUCK OPEN
The following text is a portion of a facsimile received from the licensee:
"Unit 2 entered [Technical Specification] 3.0.3 at 1510 due to both trains of [the] residual heat removal systems being inoperable. During the performance of [a] residual heat removal/containment spray systems dose reduction flush procedure, it was determined that the discharge check valve for [the] 2A residual heat removal pump was stuck open. This diverted flow from the operable train (2B). The 2A residual heat removal pump discharge isolation valve was closed at 1523, and Unit 2 exited [Technical Specification] 3.0.3. The 2A residual heat removal system was logged inoperable under a 72-hour [technical specification limiting condition for operation] until the check valve is repaired."
The licensee stated that all systems functioned as required and that the cause of the discharge check valve failure was under investigation. The licensee also stated that there was nothing unusual or misunderstood other than the cause of the discharge check valve failure.
The licensee notified the NRC resident inspector.
The following text is a portion of a facsimile received from the licensee:
"Unit 2 entered [Technical Specification] 3.0.3 at 1510 due to both trains of [the] residual heat removal systems being inoperable. During the performance of [a] residual heat removal/containment spray systems dose reduction flush procedure, it was determined that the discharge check valve for [the] 2A residual heat removal pump was stuck open. This diverted flow from the operable train (2B). The 2A residual heat removal pump discharge isolation valve was closed at 1523, and Unit 2 exited [Technical Specification] 3.0.3. The 2A residual heat removal system was logged inoperable under a 72-hour [technical specification limiting condition for operation] until the check valve is repaired."
The licensee stated that all systems functioned as required and that the cause of the discharge check valve failure was under investigation. The licensee also stated that there was nothing unusual or misunderstood other than the cause of the discharge check valve failure.
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 38837
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JAMES J. ACKERMAN
HQ OPS Officer: LEIGH TROCINE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JAMES J. ACKERMAN
HQ OPS Officer: LEIGH TROCINE
Notification Date: 04/05/2002
Notification Time: 22:52 [ET]
Event Date: 04/05/2002
Event Time: 22:00 [EST]
Last Update Date: 04/05/2002
Notification Time: 22:52 [ET]
Event Date: 04/05/2002
Event Time: 22:00 [EST]
Last Update Date: 04/05/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GLENN MEYER (R1)
WILLIAM BECKNER (NRR)
GLENN MEYER (R1)
WILLIAM BECKNER (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 96 | Power Operation | 79 | Power Operation |
OFFSITE NOTIFICATION REGARDING COMMENCEMENT OF A UNIT SHUTDOWN FOR MAINTENANCE
The licensee notified state and local officials of commencement of a unit shutdown for maintenance purposes. The shutdown was commenced at 2100 because 'A' reactor coolant pump seal package assembly leakage was becoming excessive. The outage is currently scheduled to last between 72 and 96 hours. Event classification for the offsite notification was made at 2200. The licensee also notified the NRC resident inspector.
The licensee notified state and local officials of commencement of a unit shutdown for maintenance purposes. The shutdown was commenced at 2100 because 'A' reactor coolant pump seal package assembly leakage was becoming excessive. The outage is currently scheduled to last between 72 and 96 hours. Event classification for the offsite notification was made at 2200. The licensee also notified the NRC resident inspector.
Power Reactor
Event Number: 38833
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: CURT STEFFES
HQ OPS Officer: MIKE NORRIS
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: CURT STEFFES
HQ OPS Officer: MIKE NORRIS
Notification Date: 04/05/2002
Notification Time: 14:26 [ET]
Event Date: 04/05/2002
Event Time: 10:28 [CST]
Last Update Date: 04/05/2002
Notification Time: 14:26 [ET]
Event Date: 04/05/2002
Event Time: 10:28 [CST]
Last Update Date: 04/05/2002
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):
DAVID HILLS (R3)
DAVID HILLS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM ON HIGH RPV LEVEL
"At 10:28 [CST] on 04/05/02, Unit 2 inserted a manual SCRAM due to RPV high water level. All control rods inserted to 00 with the manual SCRAM, reactor pressure was maintained with the turbine bypass valves, reactor level was restored to normal and is being controlled with the feedwater system. Group 2 and 3 isolations initiated on low reactor level as expected. Initial investigations are focusing on a potential failure of reactor water level instrumentation, sensing a false low level which caused increased feedwater flow.
"This report is being made in accordance with 10 CFR 50.72(b)(2)(iv) and 10 CFR 50.72(b)(3)(iv)."
Licensee has notified the NRC Resident Inspector.
"At 10:28 [CST] on 04/05/02, Unit 2 inserted a manual SCRAM due to RPV high water level. All control rods inserted to 00 with the manual SCRAM, reactor pressure was maintained with the turbine bypass valves, reactor level was restored to normal and is being controlled with the feedwater system. Group 2 and 3 isolations initiated on low reactor level as expected. Initial investigations are focusing on a potential failure of reactor water level instrumentation, sensing a false low level which caused increased feedwater flow.
"This report is being made in accordance with 10 CFR 50.72(b)(2)(iv) and 10 CFR 50.72(b)(3)(iv)."
Licensee has notified the NRC Resident Inspector.