Event Notification Report for January 19, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/18/2005 - 01/19/2005
Power Reactor
Event Number: 41347
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/19/2005
Notification Time: 15:54 [ET]
Event Date: 01/19/2005
Event Time: 12:51 [CST]
Last Update Date: 01/19/2005
Notification Time: 15:54 [ET]
Event Date: 01/19/2005
Event Time: 12:51 [CST]
Last Update Date: 01/19/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 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)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JEFFERY CLARK (R4)
JEFFERY CLARK (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
CALLAWAY AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR LEVEL
"Unit experienced an automatic reactor trip following a momentary loss of power to a process control system power supply that resulted in a low Steam Generator water level. This event is being reported in accordance with 10CFR50.72(b)(2)(iv)(B) due to an automatic Reactor Trip and subsequent Aux Feedwater actuation and Feedwater isolation. On 1/19/2005 at 12:51 CST with Callaway plant at 100% reactor power, a Reactor Trip occurred on low Steam Generator 'A' level due to an apparent momentary loss of power in Control Cabinet [Relay Panel] RP043.
"A failed Primary Power Supply to RP043 replacement was in progress at the time of the trip. A momentary power spike on the in-service backup power supply caused the Main Feedwater Regulating valve [MFRV] 'A' to shut and both Main Feedwater Pumps [MFPs] went to their low speed stops. Attempts by the Reactor Operator to take manual control of 'A' MFRV and the MFPs were unsuccessful resulting in the Reactor Trip.
"Following the reactor trip all systems responded as designed with no abnormal responses.
"The plant is currently stable in Mode 3 with RCS pressure at 2237 psig and RCS temperature at 557.8 F. The Auxiliary Feedwater is currently supplying the Steam Generators with steam flow to the Main Condenser for decay heat removal. All control rods fully inserted.
"Both NRC Resident Inspectors were contacted and responded to the Control Room. Corporate Communications will be providing public information on the plant trip to the media."
"Unit experienced an automatic reactor trip following a momentary loss of power to a process control system power supply that resulted in a low Steam Generator water level. This event is being reported in accordance with 10CFR50.72(b)(2)(iv)(B) due to an automatic Reactor Trip and subsequent Aux Feedwater actuation and Feedwater isolation. On 1/19/2005 at 12:51 CST with Callaway plant at 100% reactor power, a Reactor Trip occurred on low Steam Generator 'A' level due to an apparent momentary loss of power in Control Cabinet [Relay Panel] RP043.
"A failed Primary Power Supply to RP043 replacement was in progress at the time of the trip. A momentary power spike on the in-service backup power supply caused the Main Feedwater Regulating valve [MFRV] 'A' to shut and both Main Feedwater Pumps [MFPs] went to their low speed stops. Attempts by the Reactor Operator to take manual control of 'A' MFRV and the MFPs were unsuccessful resulting in the Reactor Trip.
"Following the reactor trip all systems responded as designed with no abnormal responses.
"The plant is currently stable in Mode 3 with RCS pressure at 2237 psig and RCS temperature at 557.8 F. The Auxiliary Feedwater is currently supplying the Steam Generators with steam flow to the Main Condenser for decay heat removal. All control rods fully inserted.
"Both NRC Resident Inspectors were contacted and responded to the Control Room. Corporate Communications will be providing public information on the plant trip to the media."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 41344
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FREDERICK SMITH
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FREDERICK SMITH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/19/2005
Notification Time: 05:54 [ET]
Event Date: 01/19/2005
Event Time: 02:37 [EST]
Last Update Date: 03/23/2005
Notification Time: 05:54 [ET]
Event Date: 01/19/2005
Event Time: 02:37 [EST]
Last Update Date: 03/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANNE MARIE STONE (R3)
ANNE MARIE STONE (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE DUE TO AN UNANALYZED CONDITION
"The environmental temperature of the tornado missile enclosure for the Emergency Diesel Generators during an accident condition when all three testable rupture disks open is expected to exceed the limiting temperature for the structural concrete. A detailed analysis of the capability of the tornado missile enclosure concrete to meet that standard cited in the USAR section 3.8.3.3.7 has not been located. At 0237 on 19 January 2005, Division 1,2 & 3 Diesel Generators were declared inoperable. Actions of Technical Specification 3.8.2 were directed and compliance verified."
NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 03/23/05 @ 1524 BY KEN MEADE TO CHAUNCEY GOULD * * * RETRACTION
The following information was provided by the licensee by fax:
"An 8-hour notification was made on January 19, 2005, in accordance with 10CFR50.72(b)(3)(ii)(B), for an unanalyzed condition and 10CFR50.72(b)(3)(v)(D), for the loss of the accident mitigation safety function. This report was made after declaring division 1, 2, and 3 diesel generators inoperable because the tornado missile enclosure concrete analysis demonstrating compliance with USAR section 3.8.3.3.7 could not be located. Compensatory measures were taken to protect the concrete and vent lines in the area while an analysis was performed."
"The required analysis was performed by a contract engineering firm. On March 23, 2005, the analysis was owner accepted with comments for incorporation into the final report. None of the comments affected the conclusion of the analysis. This analysis confirmed that the concrete enclosure, as originally designed, supported operability of the diesel generators and their support subsystems."
"Modifications are being implemented to improve the design margin of the safety related enclosure under accident conditions with the testable rupture disks open. These design modifications are improvements and were not required for past diesel generator operability."
"Since the operability of the diesel generators and their support subsystems were not affected, there was no unanalyzed condition that significantly degraded plant safety, nor was there a loss of safety function. Since there was no reportable condition, ENF 41344 is retracted."
The NRC Resident Inspector was notified.
Notified RDO (Kozak)
"The environmental temperature of the tornado missile enclosure for the Emergency Diesel Generators during an accident condition when all three testable rupture disks open is expected to exceed the limiting temperature for the structural concrete. A detailed analysis of the capability of the tornado missile enclosure concrete to meet that standard cited in the USAR section 3.8.3.3.7 has not been located. At 0237 on 19 January 2005, Division 1,2 & 3 Diesel Generators were declared inoperable. Actions of Technical Specification 3.8.2 were directed and compliance verified."
NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 03/23/05 @ 1524 BY KEN MEADE TO CHAUNCEY GOULD * * * RETRACTION
The following information was provided by the licensee by fax:
"An 8-hour notification was made on January 19, 2005, in accordance with 10CFR50.72(b)(3)(ii)(B), for an unanalyzed condition and 10CFR50.72(b)(3)(v)(D), for the loss of the accident mitigation safety function. This report was made after declaring division 1, 2, and 3 diesel generators inoperable because the tornado missile enclosure concrete analysis demonstrating compliance with USAR section 3.8.3.3.7 could not be located. Compensatory measures were taken to protect the concrete and vent lines in the area while an analysis was performed."
"The required analysis was performed by a contract engineering firm. On March 23, 2005, the analysis was owner accepted with comments for incorporation into the final report. None of the comments affected the conclusion of the analysis. This analysis confirmed that the concrete enclosure, as originally designed, supported operability of the diesel generators and their support subsystems."
"Modifications are being implemented to improve the design margin of the safety related enclosure under accident conditions with the testable rupture disks open. These design modifications are improvements and were not required for past diesel generator operability."
"Since the operability of the diesel generators and their support subsystems were not affected, there was no unanalyzed condition that significantly degraded plant safety, nor was there a loss of safety function. Since there was no reportable condition, ENF 41344 is retracted."
The NRC Resident Inspector was notified.
Notified RDO (Kozak)
Other Nuclear Material
Event Number: 41345
Rep Org: GREEN BAY PACKAGING
Licensee: GREEN BAY PACKAGING
Region: 1
City: WINCHESTER State: VA
County:
License #: 48-24598-02
Agreement: N
Docket:
NRC Notified By: MIKE DICKEY
HQ OPS Officer: STEVE SANDIN
Licensee: GREEN BAY PACKAGING
Region: 1
City: WINCHESTER State: VA
County:
License #: 48-24598-02
Agreement: N
Docket:
NRC Notified By: MIKE DICKEY
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/19/2005
Notification Time: 11:08 [ET]
Event Date: 01/19/2005
Event Time: 10:30 [EST]
Last Update Date: 01/19/2005
Notification Time: 11:08 [ET]
Event Date: 01/19/2005
Event Time: 10:30 [EST]
Last Update Date: 01/19/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
HAROLD GRAY (R1)
THOMAS ESSIG (NMSS)
HAROLD GRAY (R1)
THOMAS ESSIG (NMSS)
FIXED GAUGE OHMART INSTRUMENT SHUTTER LAMP INDICATOR FAILURE
At approximately 10:30 EST on 1/19/05, an Ohmart fixed gauge with a source BAL holder located on an OD-120 scanning platform experienced failure of the shutter lamp indicator circuit. The licensee suspects failure of the micro switch. The source holder contains 300 millicuries of Kr-85 gas. The gauge is used to scan a 60" wide paper web for coating thickness. The licensee confirmed that the shutter is closed. The service company, i.e., Honeywell Measurex located approximately 2 hours driving distance from their facility, has been contacted for repairs. This particular gauge had the source holder, including the shutter, replaced on 11/11/04.
At approximately 10:30 EST on 1/19/05, an Ohmart fixed gauge with a source BAL holder located on an OD-120 scanning platform experienced failure of the shutter lamp indicator circuit. The licensee suspects failure of the micro switch. The source holder contains 300 millicuries of Kr-85 gas. The gauge is used to scan a 60" wide paper web for coating thickness. The licensee confirmed that the shutter is closed. The service company, i.e., Honeywell Measurex located approximately 2 hours driving distance from their facility, has been contacted for repairs. This particular gauge had the source holder, including the shutter, replaced on 11/11/04.