Event Notification Report for November 27, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/26/2003 - 11/27/2003
EVENT NUMBERS
40357403584035940360
Power Reactor
Event Number: 40357
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TODD GRANLUND
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TODD GRANLUND
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/27/2003
Notification Time: 03:24 [ET]
Event Date: 11/27/2003
Event Time: 00:52 [CST]
Last Update Date: 11/27/2003
Notification Time: 03:24 [ET]
Event Date: 11/27/2003
Event Time: 00:52 [CST]
Last Update Date: 11/27/2003
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):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 23 | Power Operation | 0 | Hot Shutdown |
REACTOR MANUALLY SCRAMMED FROM 23% DUE TO DECREASING REACTOR VESSEL WATER LEVEL
A manual reactor scram was initiated due to a decreasing reactor vessel water level. The decreasing water level occurred during a feedwater transient while performing a power reduction in preparation for taking the main generator off line for maintenance. The licensee is investigating the cause of the feedwater transient, but it occurred while one turbine driven reactor feed pump was being taken off line. All rods fully inserted following the scram and no ECCS or safety relief valves actuated. Residual heat is being rejected to the condenser.
The licensee notified NRC Resident Inspector.
A manual reactor scram was initiated due to a decreasing reactor vessel water level. The decreasing water level occurred during a feedwater transient while performing a power reduction in preparation for taking the main generator off line for maintenance. The licensee is investigating the cause of the feedwater transient, but it occurred while one turbine driven reactor feed pump was being taken off line. All rods fully inserted following the scram and no ECCS or safety relief valves actuated. Residual heat is being rejected to the condenser.
The licensee notified NRC Resident Inspector.
Power Reactor
Event Number: 40358
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BRUCE FERGUSON
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: BRUCE FERGUSON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/27/2003
Notification Time: 06:51 [ET]
Event Date: 11/27/2003
Event Time: 06:29 [EST]
Last Update Date: 11/28/2003
Notification Time: 06:51 [ET]
Event Date: 11/27/2003
Event Time: 06:29 [EST]
Last Update Date: 11/28/2003
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):
ANTHONY DIMITRIADIS (R1)
ANTHONY DIMITRIADIS (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 20 | Power Operation | 0 | Hot Standby |
PLANT HAD A MANUAL REACTOR TRIP FROM 23% POWER DUE TO TURBINE VIBRATION
While rolling the turbine when at 20% power they experienced an over speed turbine trip. During a second attempt when at 23% power, the turbine had high vibration so they manually tripped the reactor. Cause for the vibration is being investigated since a new rotor had just been installed in the turbine. All rods fully inserted during the reactor trip and no ECCS injection occurred or primary relief valves lifted.
The licensee notified the NRC Resident, the State of Connecticut and Local agencies
* * * UPDATE AT 1423 EST ON 11/28/03 FROM FRANKS TO GOTT * * *
The following clarifying information was provided by the licensee.
"While at 23% power of a scheduled power ascension following a refueling outage, Millstone Unit 2 performed a required manual reactor trip when main turbine vibration reached a trip set point of 12 MILS. The main turbine vibrations were anticipated during the power ascension due to a newly installed low pressure "Mono-Block" rotor. All control rods fully inserted during the reactor trip and no ECCS injection occurred or primary relief valves lifted."
The overspeed trip discussed in the original report was a test conducted prior to placing the main turbine on the grid.
Notified R1DO (Dimitriadis). The licensee will notify the NRC Residence Inspector.
While rolling the turbine when at 20% power they experienced an over speed turbine trip. During a second attempt when at 23% power, the turbine had high vibration so they manually tripped the reactor. Cause for the vibration is being investigated since a new rotor had just been installed in the turbine. All rods fully inserted during the reactor trip and no ECCS injection occurred or primary relief valves lifted.
The licensee notified the NRC Resident, the State of Connecticut and Local agencies
* * * UPDATE AT 1423 EST ON 11/28/03 FROM FRANKS TO GOTT * * *
The following clarifying information was provided by the licensee.
"While at 23% power of a scheduled power ascension following a refueling outage, Millstone Unit 2 performed a required manual reactor trip when main turbine vibration reached a trip set point of 12 MILS. The main turbine vibrations were anticipated during the power ascension due to a newly installed low pressure "Mono-Block" rotor. All control rods fully inserted during the reactor trip and no ECCS injection occurred or primary relief valves lifted."
The overspeed trip discussed in the original report was a test conducted prior to placing the main turbine on the grid.
Notified R1DO (Dimitriadis). The licensee will notify the NRC Residence Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40359
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMIE MCCONNELL
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMIE MCCONNELL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/28/2003
Notification Time: 01:55 [ET]
Event Date: 11/27/2003
Event Time: 22:55 [EST]
Last Update Date: 01/26/2004
Notification Time: 01:55 [ET]
Event Date: 11/27/2003
Event Time: 22:55 [EST]
Last Update Date: 01/26/2004
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):
STEPHEN CAHILL (R2)
STEPHEN CAHILL (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
COMPONENT COOLING SYSTEM SURGE TANK SUPPORTS MAY FAIL DURING A SEISMIC EVENT
During an ISI inspection of the component cooling system, it was discovered that several of the surge tank support stiffener plates were missing due to a design change that was never fully implemented. This condition creates a question as to the adequacy of the tanks to withstand a seismic event. This deficiency affects both trains of component cooling on Units 1 and 2. The problem will be corrected on Unit 1 while it is in its refueling outage. Work on the Unit 2 "A" train is currently ongoing, making that train of the component cooling system inoperable, therefore, putting the plant in a 72 hour LCO. When work on the "A" train is completed, they will exit the LCO, but re-enter it when work begins on the "B" train.
Licensee will notify the NRC Resident Inspector, the State and local agencies.
* * * RETRACTION AT 1025 EST ON 01/26/04 BY MIKE HEAVNER TO JOLLIFFE * * *
"The subject EN #40359 was made on 11/28/03. Following additional review by the licensee, this event was determined to not meet the reportability requirements of 10 CFR 50.72. The event was determined to not result in a condition that could have prevented fulfillment of a safety function, as the tank supports were analyzed to withstand a seismic event. In addition, the event did not result in the plant being in an unanalyzed condition. The condition did not prevent the fulfillment of a safety function or system that is needed to remove residual heat or mitigate the consequences of an accident."
The licensee plans to notify the NRC Resident Inspector.
Notified R2DO Caudle Julian.
During an ISI inspection of the component cooling system, it was discovered that several of the surge tank support stiffener plates were missing due to a design change that was never fully implemented. This condition creates a question as to the adequacy of the tanks to withstand a seismic event. This deficiency affects both trains of component cooling on Units 1 and 2. The problem will be corrected on Unit 1 while it is in its refueling outage. Work on the Unit 2 "A" train is currently ongoing, making that train of the component cooling system inoperable, therefore, putting the plant in a 72 hour LCO. When work on the "A" train is completed, they will exit the LCO, but re-enter it when work begins on the "B" train.
Licensee will notify the NRC Resident Inspector, the State and local agencies.
* * * RETRACTION AT 1025 EST ON 01/26/04 BY MIKE HEAVNER TO JOLLIFFE * * *
"The subject EN #40359 was made on 11/28/03. Following additional review by the licensee, this event was determined to not meet the reportability requirements of 10 CFR 50.72. The event was determined to not result in a condition that could have prevented fulfillment of a safety function, as the tank supports were analyzed to withstand a seismic event. In addition, the event did not result in the plant being in an unanalyzed condition. The condition did not prevent the fulfillment of a safety function or system that is needed to remove residual heat or mitigate the consequences of an accident."
The licensee plans to notify the NRC Resident Inspector.
Notified R2DO Caudle Julian.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40360
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ROBIN NYE
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ROBIN NYE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 11/28/2003
Notification Time: 08:18 [ET]
Event Date: 11/27/2003
Event Time: 23:30 [EST]
Last Update Date: 12/08/2003
Notification Time: 08:18 [ET]
Event Date: 11/27/2003
Event Time: 23:30 [EST]
Last Update Date: 12/08/2003
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):
ANTHONY DIMITRIADIS (R1)
ANTHONY DIMITRIADIS (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PLANT HAD AN INADVERTENT SIREN ACTIVATION
"At 2330 11/27/2003 RG&E Energy Operations Center Notified the Control Room that an Emergency Notification Siren on Arbor Road was going off. The Siren System Controller was checked and verified that the siren had inadvertently activated. The Siren System Controller was used to reset and then check that the siren was operable. The siren was reset by 2345 11/27/2003. The 4 hour notification was inadvertently missed by the midnight shift."
The licensee will be investigating the cause of this inadvertent siren activation.
The licensee notified the NRC Resident Inspector.
* * * EVENT RETRACTED ON 12/08/03 AT 1232 BY ROBIN NYE TO GERRY WAIG
"At 2330 on November 27, 2003, RG&E was notified that an Emergency Notification Siren on Arbor Road appeared to have inadvertently activated. However, since that time, RG&E has performed an extensive evaluation and determined that there is no indication that the siren in the vicinity had been activated. This event has been discussed with the resident inspector and he has been informed that the event will be retracted."
Notified R1DO (Aniello Della Greca)
"At 2330 11/27/2003 RG&E Energy Operations Center Notified the Control Room that an Emergency Notification Siren on Arbor Road was going off. The Siren System Controller was checked and verified that the siren had inadvertently activated. The Siren System Controller was used to reset and then check that the siren was operable. The siren was reset by 2345 11/27/2003. The 4 hour notification was inadvertently missed by the midnight shift."
The licensee will be investigating the cause of this inadvertent siren activation.
The licensee notified the NRC Resident Inspector.
* * * EVENT RETRACTED ON 12/08/03 AT 1232 BY ROBIN NYE TO GERRY WAIG
"At 2330 on November 27, 2003, RG&E was notified that an Emergency Notification Siren on Arbor Road appeared to have inadvertently activated. However, since that time, RG&E has performed an extensive evaluation and determined that there is no indication that the siren in the vicinity had been activated. This event has been discussed with the resident inspector and he has been informed that the event will be retracted."
Notified R1DO (Aniello Della Greca)