Event Notification Report for July 27, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/26/2005 - 07/27/2005
Power Reactor
Event Number: 41875
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: J. GAINES
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: J. GAINES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/27/2005
Notification Time: 16:03 [ET]
Event Date: 07/27/2005
Event Time: 15:00 [EDT]
Last Update Date: 07/27/2005
Notification Time: 16:03 [ET]
Event Date: 07/27/2005
Event Time: 15:00 [EDT]
Last Update Date: 07/27/2005
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)
SCOTT MOORE (NMSS)
GLENN MEYER (R1)
SCOTT MOORE (NMSS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
IMPROPERLY LABELED RADIOACTIVE MATERIAL SHIPMENT
The licensee reported that three main steam line radiation monitors (unused) were recently shipped from a site storage warehouse to a salvage vendor (ATS Corporation in Woodridge, Illinois). When the material arrived at the vendor, it was discovered that each of the monitors contained a 100 nanocurie Americium-241 source (a total of three 100 nanocurie sources). The vendor informed Calvert Cliffs of the radioactive sources in the shipment. Apparently, the licensee was unaware of the sources in the monitors when the material was sent to salvage. Calvert is sending a representative to the vendor to retrieve the sources. Calvert will also be issuing a 30 day Hazardous Material Incident Report in accordance with 49 CFR 171.21 for making the shipment without properly marking the packaging as containing radioactive material.
The licensee notified the NRC Resident Inspector.
The licensee reported that three main steam line radiation monitors (unused) were recently shipped from a site storage warehouse to a salvage vendor (ATS Corporation in Woodridge, Illinois). When the material arrived at the vendor, it was discovered that each of the monitors contained a 100 nanocurie Americium-241 source (a total of three 100 nanocurie sources). The vendor informed Calvert Cliffs of the radioactive sources in the shipment. Apparently, the licensee was unaware of the sources in the monitors when the material was sent to salvage. Calvert is sending a representative to the vendor to retrieve the sources. Calvert will also be issuing a 30 day Hazardous Material Incident Report in accordance with 49 CFR 171.21 for making the shipment without properly marking the packaging as containing radioactive material.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 41876
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ROY GILLOW
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ROY GILLOW
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/27/2005
Notification Time: 21:08 [ET]
Event Date: 07/27/2005
Event Time: 20:00 [EDT]
Last Update Date: 07/27/2005
Notification Time: 21:08 [ET]
Event Date: 07/27/2005
Event Time: 20:00 [EDT]
Last Update Date: 07/27/2005
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)
GLENN MEYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 45 | Power Operation |
OFFSITE NOTIFICATION CONCERNING POWER REDUCTION TO TAKE PLANT OFFLINE
"The New York State Public Service Commission was notified that Ginna is coming offline due to chemistry concerns. EPRI level 3 guidelines [for sodium and chloride levels] were exceeded during line-up of the blow down system during maintenance. Required action is to reduce power to less than 5% reactor power and perform system cleanup."
The licensee notified the NRC Resident Inspector.
"The New York State Public Service Commission was notified that Ginna is coming offline due to chemistry concerns. EPRI level 3 guidelines [for sodium and chloride levels] were exceeded during line-up of the blow down system during maintenance. Required action is to reduce power to less than 5% reactor power and perform system cleanup."
The licensee notified the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 41877
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: HOPE BARDLEY
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: HOPE BARDLEY
HQ OPS Officer: JOHN MacKINNON
Notification Date: 07/28/2005
Notification Time: 05:57 [ET]
Event Date: 07/27/2005
Event Time: 21:25 [CDT]
Last Update Date: 09/09/2005
Notification Time: 05:57 [ET]
Event Date: 07/27/2005
Event Time: 21:25 [CDT]
Last Update Date: 09/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID GRAVES (R4)
DAVID GRAVES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
TWO TRAINS OF CONTROL ROOM EMERGENCY VENTILATION SYSTEMS (CREVS) INOPERABLE AND NOT RESTORED WITHIN 24 HOURS
"At 2125 on 7/27/05, Door 33021 (B Engineering Safety Feature Switchgear to B Emergency Diesel Generator) (B ESF Switchgear to B EDG) was found not to be latched. Reviewing history; the door was first discovered not to latch at 1215 on 7/26/05, by Security. The Control Room was notified at 2125 on 7/27/05 by an Equipment Operator, who found the door unlatched. Door was subsequently latched closed at 2155 on 7/27/05.
"Due to this door not being able to be verified latched, T/S LCO 3.7.10.B should have been entered at 1215 on 7/26/05. This renders 2 trains of Control Room Emergency Ventilation Systems (CREVS) inoperable, and if not restored within 24 hours, a plant shutdown is required; being in Mode 3 (Hot Standby) in 6 hours and Mode 5 (Cold Shutdown) in 36 hours. The plant should have been in Mode 3 at 1815 on 7/27/05. This time was not met. As stated previously, the door was verified to be latched at 2155 on 7/27/05. A plant shutdown is not being made due to the LCO 3.7.10.B being satisfied at 2155 on 7/27/05.
"Door 33021 (B ESF Switchgear to B Emergency Diesel Generator) was repaired at 0022 on 7/28/05.
"This issue has been entered in the licensee corrective action program."
The NRC Resident Inspector was notified of this event by the licensee.
* * * RETRACTION FROM R. REIDMEYER TO M. RIPLEY 1419 EDT 09/09/05 * * *
"Upon further review, it was concluded that this event is not reportable. The design functions of this door are pressure boundary and fire protection. Based upon the following criteria, this event was determined to be not reportable:
"1) Pressure boundary: Actual duration of door inoperability did not result in a violation of Control Room Emergency Ventilation System Technical Specification Action completion time limits.
"2) Fire protection: Only one fire suppression system was impacted and the inoperability of a fire protection suppression system for a single area is not reportable with regards to the Fire Protection Program.
"The loss of one fire suppression system was bounded by Callaway licensing basis."
The licensee will notify the NRC Resident Inspector. Notified R4 DO (Powers)
"At 2125 on 7/27/05, Door 33021 (B Engineering Safety Feature Switchgear to B Emergency Diesel Generator) (B ESF Switchgear to B EDG) was found not to be latched. Reviewing history; the door was first discovered not to latch at 1215 on 7/26/05, by Security. The Control Room was notified at 2125 on 7/27/05 by an Equipment Operator, who found the door unlatched. Door was subsequently latched closed at 2155 on 7/27/05.
"Due to this door not being able to be verified latched, T/S LCO 3.7.10.B should have been entered at 1215 on 7/26/05. This renders 2 trains of Control Room Emergency Ventilation Systems (CREVS) inoperable, and if not restored within 24 hours, a plant shutdown is required; being in Mode 3 (Hot Standby) in 6 hours and Mode 5 (Cold Shutdown) in 36 hours. The plant should have been in Mode 3 at 1815 on 7/27/05. This time was not met. As stated previously, the door was verified to be latched at 2155 on 7/27/05. A plant shutdown is not being made due to the LCO 3.7.10.B being satisfied at 2155 on 7/27/05.
"Door 33021 (B ESF Switchgear to B Emergency Diesel Generator) was repaired at 0022 on 7/28/05.
"This issue has been entered in the licensee corrective action program."
The NRC Resident Inspector was notified of this event by the licensee.
* * * RETRACTION FROM R. REIDMEYER TO M. RIPLEY 1419 EDT 09/09/05 * * *
"Upon further review, it was concluded that this event is not reportable. The design functions of this door are pressure boundary and fire protection. Based upon the following criteria, this event was determined to be not reportable:
"1) Pressure boundary: Actual duration of door inoperability did not result in a violation of Control Room Emergency Ventilation System Technical Specification Action completion time limits.
"2) Fire protection: Only one fire suppression system was impacted and the inoperability of a fire protection suppression system for a single area is not reportable with regards to the Fire Protection Program.
"The loss of one fire suppression system was bounded by Callaway licensing basis."
The licensee will notify the NRC Resident Inspector. Notified R4 DO (Powers)