Event Notification Report for September 26, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/25/2003 - 09/26/2003
Power Reactor
Event Number: 40200
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RODEN
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RODEN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/26/2003
Notification Time: 16:31 [ET]
Event Date: 09/26/2003
Event Time: 08:50 [EDT]
Last Update Date: 09/29/2003
Notification Time: 16:31 [ET]
Event Date: 09/26/2003
Event Time: 08:50 [EDT]
Last Update Date: 09/29/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
GREATER THAN 1 PERCENT OF STEAM GENERATORS 1,2 & 4 TUBES INSPECTED INDICATE THAT THE INSPECTED TUBES REQUIRE PLUGGING.
"At 0850 EST on September 26, 2003, with Watts Bar Nuclear Plant Unit 1 defueled, steam generator inspections were being performed in accordance with Technical Specification (TS) 5.7.2.12, 'Steam Generator Tube Surveillance Program.' The results of the inspections performed on Steam Generator Numbers 1, 2, and 4 indicated that greater than 1% of the inspected tubes require repair. Based on TS 5.7.2.12, this determination results in the classification of C-3. The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73. However, for classification C-3, WBN TS Table 5.7.2.12-1, 'SG Tube Inspection Supplemental Sampling Requirements, 'requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of the Licensee Event Report in accordance with 10 CFR 50.73 is not planned."
The NRC Resident Inspector was notified of this event by the licensee.
**** Update on 09/29/03 at 1439 EDT by John Roden taken by MacKinnon ****
"In addition, at 0800 on September 29, 2003 Steam Generator Number 3 has been determined to be in the classification of C-3 (48 tubes). The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73. However, for classification C-3, WBN TS Table 5.7.2.12-1, 'SG Tube Inspection Supplemental Sampling Requirements,' requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of a Licensee Event Report in accordance with 10 CFR 50.73 is not planned." R2DO (Mark Lesser) notified.
The NRC Resident Inspector was notified of this update by the licensee.
"At 0850 EST on September 26, 2003, with Watts Bar Nuclear Plant Unit 1 defueled, steam generator inspections were being performed in accordance with Technical Specification (TS) 5.7.2.12, 'Steam Generator Tube Surveillance Program.' The results of the inspections performed on Steam Generator Numbers 1, 2, and 4 indicated that greater than 1% of the inspected tubes require repair. Based on TS 5.7.2.12, this determination results in the classification of C-3. The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73. However, for classification C-3, WBN TS Table 5.7.2.12-1, 'SG Tube Inspection Supplemental Sampling Requirements, 'requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of the Licensee Event Report in accordance with 10 CFR 50.73 is not planned."
The NRC Resident Inspector was notified of this event by the licensee.
**** Update on 09/29/03 at 1439 EDT by John Roden taken by MacKinnon ****
"In addition, at 0800 on September 29, 2003 Steam Generator Number 3 has been determined to be in the classification of C-3 (48 tubes). The current inspection results do not meet the criteria specified for steam generator tube degradation in Revision 2 of NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73. However, for classification C-3, WBN TS Table 5.7.2.12-1, 'SG Tube Inspection Supplemental Sampling Requirements,' requires that the results of the inspection be reported under 10 CFR 50.72. At this time, the submittal of a Licensee Event Report in accordance with 10 CFR 50.73 is not planned." R2DO (Mark Lesser) notified.
The NRC Resident Inspector was notified of this update by the licensee.
General Information or Other
Event Number: 40201
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: COMPUTALOG
Region: 4
City: FORT WORTH State: TX
County:
License #: L04286
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS
HQ OPS Officer: JOHN MacKINNON
Licensee: COMPUTALOG
Region: 4
City: FORT WORTH State: TX
County:
License #: L04286
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/26/2003
Notification Time: 18:40 [ET]
Event Date: 09/26/2003
Event Time: 12:00 [CDT]
Last Update Date: 09/26/2003
Notification Time: 18:40 [ET]
Event Date: 09/26/2003
Event Time: 12:00 [CDT]
Last Update Date: 09/26/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GREG PICK (R4)
GARY JANOSKO (NMSS)
GREG PICK (R4)
GARY JANOSKO (NMSS)
LEAKING SEALED SOURCE FOUND: 5 CURIE AMERICIUM-241/BERYLLIUM
"A 5 curie AM-241/Be sealed source was found leaking during a routine leak test on September 26, 2003. The removable contamination was 0.081 microcuries. The source is a Gulf Nuclear model 71-1 serial # 71-1448B. The source was transported during September 2003 from the Licensee's Edinburg, TX site to the Ft. Worth site. The contamination was confined to the inside of the transport container and the source housing. A second source that had been stored as a companion in the same down hole storage in Edinburg also had a small amount of contamination on it (399 dpm found, below the 11,000 dpm limit). Therefore, the Edinburg downhole site will be checked by the Licensee for contamination. The storage facility in Edinburg has been taken out of service and off limits until proper surveys are made.
"An update will be provided when more information is available
"Transport vehicle description: Computalog company vehicle"
Texas Incident No: I-8059.
"A 5 curie AM-241/Be sealed source was found leaking during a routine leak test on September 26, 2003. The removable contamination was 0.081 microcuries. The source is a Gulf Nuclear model 71-1 serial # 71-1448B. The source was transported during September 2003 from the Licensee's Edinburg, TX site to the Ft. Worth site. The contamination was confined to the inside of the transport container and the source housing. A second source that had been stored as a companion in the same down hole storage in Edinburg also had a small amount of contamination on it (399 dpm found, below the 11,000 dpm limit). Therefore, the Edinburg downhole site will be checked by the Licensee for contamination. The storage facility in Edinburg has been taken out of service and off limits until proper surveys are made.
"An update will be provided when more information is available
"Transport vehicle description: Computalog company vehicle"
Texas Incident No: I-8059.