Event Notification Report for March 19, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/18/2005 - 03/19/2005
Power Reactor
Event Number: 41504
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: EUGENE PAINTER
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: EUGENE PAINTER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/19/2005
Notification Time: 02:12 [ET]
Event Date: 03/19/2005
Event Time: 01:30 [CST]
Last Update Date: 03/19/2005
Notification Time: 02:12 [ET]
Event Date: 03/19/2005
Event Time: 01:30 [CST]
Last Update Date: 03/19/2005
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):
TOM FARNHOLTZ (R4)
TOM FARNHOLTZ (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
ADVANCED NOTIFICATION PRIOR TO TAKING SPDS OUT OF SERVICE
At 01:30 CST the Safety Parameter Display System (SPDS) will be taken out of service for planned maintenance. This planned maintenance is scheduled for approximately four hours.
ANO Unit-2 is currently in a refueling outage with the reactor defueled.
The licensee notified the NRC Resident Inspector and the Arkansas Department of Health.
* * * UPDATE PROVIDED BY OLSON TO ABRAMOVITZ @ 1102 3/19/2005 * * *
SPDS restored at 09:40 CST. Resident Inspector will be notified by the licensee.
Notified R4DO (FARNHOLTZ)
At 01:30 CST the Safety Parameter Display System (SPDS) will be taken out of service for planned maintenance. This planned maintenance is scheduled for approximately four hours.
ANO Unit-2 is currently in a refueling outage with the reactor defueled.
The licensee notified the NRC Resident Inspector and the Arkansas Department of Health.
* * * UPDATE PROVIDED BY OLSON TO ABRAMOVITZ @ 1102 3/19/2005 * * *
SPDS restored at 09:40 CST. Resident Inspector will be notified by the licensee.
Notified R4DO (FARNHOLTZ)
Power Reactor
Event Number: 41505
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE KASPAR
HQ OPS Officer: BILL GOTT
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE KASPAR
HQ OPS Officer: BILL GOTT
Notification Date: 03/19/2005
Notification Time: 12:27 [ET]
Event Date: 03/19/2005
Event Time: 08:27 [CST]
Last Update Date: 03/19/2005
Notification Time: 12:27 [ET]
Event Date: 03/19/2005
Event Time: 08:27 [CST]
Last Update Date: 03/19/2005
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):
TOM FARNHOLTZ (R4)
TOM FARNHOLTZ (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
OFFSITE NOTIFICATION DUE TO INJURED CONTRACT EMPLOYEE
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"South Texas Project Nuclear Operating Company has been in contact with various news agencies following an industrial accident that occurred at 0827 this morning. A contract employee fell approximately eight to ten feet while descending a permanent plant ladder on a structure in the secondary plant. The individual sustained injuries to his head and back, and has been transported to Herman Hospital in Houston, TX by a Life Flight Helicopter.
"The NRC Regional Office has been informed."
The individual was conscious and in stable condition when he left the facility.
The licensee notified the NRC Resident Inspector.
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"South Texas Project Nuclear Operating Company has been in contact with various news agencies following an industrial accident that occurred at 0827 this morning. A contract employee fell approximately eight to ten feet while descending a permanent plant ladder on a structure in the secondary plant. The individual sustained injuries to his head and back, and has been transported to Herman Hospital in Houston, TX by a Life Flight Helicopter.
"The NRC Regional Office has been informed."
The individual was conscious and in stable condition when he left the facility.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 41702
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RICHARD SCHEIDE
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RICHARD SCHEIDE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 05/17/2005
Notification Time: 11:24 [ET]
Event Date: 03/19/2005
Event Time: 00:00 [CDT]
Last Update Date: 05/17/2005
Notification Time: 11:24 [ET]
Event Date: 03/19/2005
Event Time: 00:00 [CDT]
Last Update Date: 05/17/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
REBECCA NEASE (R4)
OMID TABATABAI (NRR)
REBECCA NEASE (R4)
OMID TABATABAI (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
PART 21 FOR A FLEX - WEDGE DISC FABRICATED BY CRANE - ALOYCO
"On March 19, 2005, during refueling Outage 2R17, it was identified that a Flex-wedge disc intended for installation in a Containment Sump isolation valve, did not have a machined slot around the disc edge, as required by the purchase specifications. A feature of the flex-wedge design is to allow the disc faces to flex, thereby reducing the potential for thermal binding. The discrepancy was identified during pre-installation inspection; therefore, the disc was not installed in the plant. Considering that extensive machining and handling of the disc is necessary during installation, it is extremely unlikely that the discrepancy could have gone undetected. The outboard containment sump isolation valve is normally closed and receives a Recirculation Actuation Signal (RAS) to open when the Refueling Water Tank volume is depleted (post-LOCA) in order to shift the Emergency Core Cooling System (ECCS) suction to the sump. Had the subject disc been installed in this valve, the discrepancy could have resulted in thermal binding of the disc, thereby rendering a complete train of ECCS inoperable upon initiation of a RAS. The subject disc was manufactured by Crane - Aloyco, and was delivered to Arkansas Nuclear One in 1991."
"This condition was determined to be reportable pursuant to 10CFR21 on 5/17/2005."
"On March 19, 2005, during refueling Outage 2R17, it was identified that a Flex-wedge disc intended for installation in a Containment Sump isolation valve, did not have a machined slot around the disc edge, as required by the purchase specifications. A feature of the flex-wedge design is to allow the disc faces to flex, thereby reducing the potential for thermal binding. The discrepancy was identified during pre-installation inspection; therefore, the disc was not installed in the plant. Considering that extensive machining and handling of the disc is necessary during installation, it is extremely unlikely that the discrepancy could have gone undetected. The outboard containment sump isolation valve is normally closed and receives a Recirculation Actuation Signal (RAS) to open when the Refueling Water Tank volume is depleted (post-LOCA) in order to shift the Emergency Core Cooling System (ECCS) suction to the sump. Had the subject disc been installed in this valve, the discrepancy could have resulted in thermal binding of the disc, thereby rendering a complete train of ECCS inoperable upon initiation of a RAS. The subject disc was manufactured by Crane - Aloyco, and was delivered to Arkansas Nuclear One in 1991."
"This condition was determined to be reportable pursuant to 10CFR21 on 5/17/2005."