Event Notification Report for October 01, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/30/2003 - 10/01/2003
EVENT NUMBERS
40211402124021340274
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
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
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
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
EUGENE COBEY (R1)
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 |
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."
"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
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
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
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
JULIO LARA (R3)
CHUCK CAIN (R4)
GARY JANOSKO (NMSS)
JULIO LARA (R3)
CHUCK CAIN (R4)
GARY JANOSKO (NMSS)
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).
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
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
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
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JULIO LARA (R3)
MICHAEL TSCHILTZ (NRR)
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 |
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."
"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."
Other Nuclear Material
Event Number: 40274
Rep Org: U.S. GEOLOGICAL SURVEY
Licensee: UNKNOWN
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: DARRYL LILES
HQ OPS Officer: HOWIE CROUCH
Licensee: UNKNOWN
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: DARRYL LILES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/24/2003
Notification Time: 12:32 [ET]
Event Date: 10/01/2003
Event Time: 00:00 [CDT]
Last Update Date: 10/24/2003
Notification Time: 12:32 [ET]
Event Date: 10/01/2003
Event Time: 00:00 [CDT]
Last Update Date: 10/24/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ROBERTO TORRES (NMSS)
DAVID LOVELESS (R4)
ROBERTO TORRES (NMSS)
DAVID LOVELESS (R4)
RADIOACTIVE SOURCE DISCOVERED IN SURPLUS VEHICLE
On 10/01/03, the U.S. Geological Survey (USGS) office in Oklahoma City, OK obtained a van from government surplus. When they received the vehicle, they discovered a Shimadzu series GC-14A gas chromatograph in the back of the van. The chromatograph contains a 10 milliCurie nickel-63 source. USGS contacted the van's previous owner but was not able to return the chromatograph.
The chromatograph is presently secured in locked storage. USGS will leak test the source and return the chromatograph to the manufacturer for proper disposal.
On 10/01/03, the U.S. Geological Survey (USGS) office in Oklahoma City, OK obtained a van from government surplus. When they received the vehicle, they discovered a Shimadzu series GC-14A gas chromatograph in the back of the van. The chromatograph contains a 10 milliCurie nickel-63 source. USGS contacted the van's previous owner but was not able to return the chromatograph.
The chromatograph is presently secured in locked storage. USGS will leak test the source and return the chromatograph to the manufacturer for proper disposal.