| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/01/2003 - 10/02/2003 ** EVENT NUMBERS ** |
 | 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 | 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 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4)
GARY JANOSKO (NMSS)
| Event Text 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. |
| Power Reactor | Event Number: 40210 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: GERRY WAIG | Notification Date: 10/01/2003
Notification Time: 00:43 [ET]
Event Date: 09/30/2003
Event Time: 20:50 [EDT]
Last Update Date: 10/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JULIO LARA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 84 | Power Operation | Event Text PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO INOPERABLE CONTROL CENTER HVAC
"With the plant in Mode 1 and 100% reactor power at 2043 [EDT] on September 30, 2003, while shifting divisions of Control Center HVAC (CCHVAC), the Division 1 chiller failed to start and Division 1 CCHVAC was declared INOPERABLE. At 2050, a restart of Division 2 CCHVAC was attempted and the Division 2 chiller failed to start. Division 2 CCHVAC was declared INOPERABLE, and the plant entered LCO 3.0.3 as required by LCO 3.7.4 Condition D. Plant shutdown was initiated at 2146. Division 1 CCHVAC was declared OPERABLE at 2315, and LCO 3.0.3 was exited. Plant shutdown was terminated at 2315 with the reactor at 84% power. Division 2 CCHVAC remains INOPERABLE and under investigation, with plant operating under LCO 3.7.4 Condition A. Plans are to return to 100% reactor power. All ECCS systems remained OPERABLE during this event.
"The NRC Resident Inspector has been notified. This report is being made pursuant to 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(v)(D)." |
| Power Reactor | Event Number: 40211 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MICHAEL McDONNELL
HQ OPS Officer: GERRY WAIG | Notification Date: 10/01/2003
Notification Time: 11:12 [ET]
Event Date: 10/01/2003
Event Time: 04:30 [EDT]
Last Update Date: 10/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
EUGENE COBEY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text REACTOR PRESSURE VESSEL BOUNDRY LEAKAGE FOUND DURING INSPECTION
"At approximately 0430 on October 1, 2003 with the reactor Mode Switch in Refuel, reactor water level 210" above Top of Active Fuel, and reactor water temperature less than 110F, investigations and walkdowns were being performed to identify potential sources of drywell leakage. Drywell leakage was well within Technical Specification limits. During these walkdowns a small leak in a cap of a nozzle of the reactor pressure vessel boundary, nozzle N10, located at reactor vessel height 440" was identified. This location is 84" above Top of Active Fuel. This is a cut and capped 4" Control Rod Drive return line. The leak appears to be on the cap weld. This notification is being made per 10 CFR 50.72(b)3(ii)(A). All required ECCS systems are presently operable.
"Investigation is continuing. The [NRC] resident inspector has been notified." |
| Other Nuclear Material | Event Number: 40212 | Rep Org: U.S. ARMY WHITE SANDS MISSILE RANGE
Licensee: U.S. ARMY WHITE SANDS MISSILE RANGE
Region: 4
City: WHITE SANDS State: NM
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DOUGLAS MCDONALD
HQ OPS Officer: ERIC THOMAS | Notification Date: 10/01/2003
Notification Time: 17:20 [ET]
Event Date: 10/01/2003
Event Time: 08:00 [MDT]
Last Update Date: 10/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
JULIO LARA (R3)
CHUCK CAIN (R4)
GARY JANOSKO (NMSS)
| Event Text LEAKING CO-60 IRRADIATOR SOURCE
On 10/1/03, during a bi-annual wipe test on the delivery head of a Co-60 irradiator, the licensee found evidence of leakage from the source. The level of removable contamination on the wipe was .02 microcuries, which is 4 times the limit of .005 microcuries. At the time of the wipe test, the Co-60 source was in the stored position. The source has been in the irradiator since 1999, and had an original activity of 4000 Curies in 1996.
The source is currently in a storage pig, which is stored behind a locked solenoid valve. The licensee intends to remove the source from the system and place it in floor storage for later disposal. The licensee will then decontaminate the system and install a new source. There were no personnel exposures as a result of this leakage.
The Licensee informed the Region IV inspector (Robert Brown). |
| Power Reactor | Event Number: 40213 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RYAN RODE
HQ OPS Officer: ERIC THOMAS | Notification Date: 10/01/2003
Notification Time: 20:42 [ET]
Event Date: 10/01/2003
Event Time: 07:00 [CDT]
Last Update Date: 10/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
JULIO LARA (R3)
MICHAEL TSCHILTZ (NRR)
|
| 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 | 77 | Power Operation | 77 | Power Operation | Event Text FFD 26.73 REPORT
"On 10/01/03 at approximately 07:00 CDT, an access authorization (AA) group employee detected the possible odor of alcohol on a contract supervisor while speaking with the individual in the Point Beach Nuclear Plant (PBNP) Training building (outside of the protected area). AA supervision was immediately notified so corroboration of the condition would be made. The AA employee and AA supervisor were unsuccessful in locating the contractor supervisor. Security was then contacted and directed to place a hold on the individual's badge in order to prevent entry to the PBNP protected area (PA).
"The contract supervisor entered the PA at 07:12:56. The SAS operator placed the person's badge on hold at 07:13:30. The individual attempted to enter the plant's north service building at 07:17:00. Security personnel responded and escorted the individual to the gatehouse, at which time the contract supervisor was instructed to return to the AA group. At approximately 07:35, the FFD Manager met with the individual whereupon the odor of alcohol was corroborated. The individual was escorted to Medical and given a "for cause" test. Results of the test were positive for alcohol. A confirmatory blood draw was offered to the individual, which was accepted. Results of confirmatory testing are pending. The individual was denied access to PBNP and all other Nuclear Management Company (NMC) sites.
"A review of the individual's work was performed. This review concluded the individual had not been engaged in safety-related work activities.
"The NRC Region III safeguards inspector assigned to PBNP was informed of this event at approximately 14:35." | |