Event Notification Report for February 16, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/15/2001 - 02/16/2001
EVENT NUMBERS
37763377543775537757377583775937819
General Information or Other
Event Number: 37763
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: QUALITY INSPECTION SERVICES, INC.
Region: 2
City: JACKSONVILLE State: FL
County:
License #: 3043-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: FANGIE JONES
Licensee: QUALITY INSPECTION SERVICES, INC.
Region: 2
City: JACKSONVILLE State: FL
County:
License #: 3043-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: FANGIE JONES
Notification Date: 02/19/2001
Notification Time: 13:47 [ET]
Event Date: 02/16/2001
Event Time: 12:30 [EST]
Last Update Date: 02/19/2001
Notification Time: 13:47 [ET]
Event Date: 02/16/2001
Event Time: 12:30 [EST]
Last Update Date: 02/19/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANNE BOLAND (R2)
E. WILLIAM BRACH (NMSS)
ANNE BOLAND (R2)
E. WILLIAM BRACH (NMSS)
AGREEMENT STATE REPORT OF PERSONNEL OVEREXPOSURE
The following is a portion of the information provided:
"Approximately 12:30 am February 16 following a shoot, the source was reeled into what was thought to be a locked position. A complete survey was not done to confirm position of the source. The two individuals involved proceeded in front of the camera to set up the next shot, taking less than 5 minutes. When they went to unlock the source they realized that it was not locked and noticed the survey meter was off scale. They exited the area and fully retracted the source. Both pocket dosimeters were off scale. One rate alarm meter was turned off and the other had a low battery and did not give a audio alarm. Film badges showed 2.9 and 39.2 R exposure. The individual with the high exposure has had blood drawn for analysis but no results are available yet. Landauer has been asked recheck the film badge readings. The wrong state office was notified 16 February. This office was notified 19 February."
The camera contains a 58 Ci source of Ir-192.
The following is a portion of the information provided:
"Approximately 12:30 am February 16 following a shoot, the source was reeled into what was thought to be a locked position. A complete survey was not done to confirm position of the source. The two individuals involved proceeded in front of the camera to set up the next shot, taking less than 5 minutes. When they went to unlock the source they realized that it was not locked and noticed the survey meter was off scale. They exited the area and fully retracted the source. Both pocket dosimeters were off scale. One rate alarm meter was turned off and the other had a low battery and did not give a audio alarm. Film badges showed 2.9 and 39.2 R exposure. The individual with the high exposure has had blood drawn for analysis but no results are available yet. Landauer has been asked recheck the film badge readings. The wrong state office was notified 16 February. This office was notified 19 February."
The camera contains a 58 Ci source of Ir-192.
Power Reactor
Event Number: 37754
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: BOB STRANSKY
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/16/2001
Notification Time: 14:47 [ET]
Event Date: 02/16/2001
Event Time: 08:15 [EST]
Last Update Date: 02/16/2001
Notification Time: 14:47 [ET]
Event Date: 02/16/2001
Event Time: 08:15 [EST]
Last Update Date: 02/16/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
CLIFFORD ANDERSON (R1)
CLIFFORD ANDERSON (R1)
| 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 |
FITNESS FOR DUTY REPORT
A non-licensed employee tested positive for the use of illegal drugs during a random test. The test results were confirmed positive by the licensee Medical Review Officer. The individual's access to the plant has been suspended in accordance with the licensee's FFD program. The NRC resident inspector has been informed of this notification by the licensee.
A non-licensed employee tested positive for the use of illegal drugs during a random test. The test results were confirmed positive by the licensee Medical Review Officer. The individual's access to the plant has been suspended in accordance with the licensee's FFD program. The NRC resident inspector has been informed of this notification by the licensee.
Power Reactor
Event Number: 37755
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JIM HICKEY
HQ OPS Officer: BOB STRANSKY
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JIM HICKEY
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/16/2001
Notification Time: 15:40 [ET]
Event Date: 02/16/2001
Event Time: 15:05 [EST]
Last Update Date: 02/16/2001
Notification Time: 15:40 [ET]
Event Date: 02/16/2001
Event Time: 15:05 [EST]
Last Update Date: 02/16/2001
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):
ANNE BOLAND (R2)
ANNE BOLAND (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO RECEIPT OF CONTAMINATED ITEMS
"While performing routine surveys, Turkey Point Health Physics personnel discovered low levels of radioactivity on several plastic Caution signs received from the Byron Nuclear Power Station. The signs were surveyed at Turkey Point prior to use in the site's radiation controlled area. These items were counted in a Small Articles Monitor (SAM) and indicated low level contamination was present. In total, 6 out of approximately 650 items surveyed indicated the presence of low level fixed activity. The highest level measured was 7,000 disintegrations per minute (dpm) using a standard HP-210 (pancake GM) probe. Isotopic analysis indicates cobalt-60 and manganese-54. One item had low levels of loose surface contamination (57 dpm/100 cm2). The items identified with low level fixed contamination are now being held inside the Turkey Point radiation controlled area. The signs were shipped in cardboard boxes and no loose surface contamination was found on the exterior of the boxes
"Florida Power & Light Company has notified the Byron Station and the State of Florida (Department of Health, Bureau of Radiation Control) of this matter."
The licensee has informed the NRC resident inspector of this notification.
"While performing routine surveys, Turkey Point Health Physics personnel discovered low levels of radioactivity on several plastic Caution signs received from the Byron Nuclear Power Station. The signs were surveyed at Turkey Point prior to use in the site's radiation controlled area. These items were counted in a Small Articles Monitor (SAM) and indicated low level contamination was present. In total, 6 out of approximately 650 items surveyed indicated the presence of low level fixed activity. The highest level measured was 7,000 disintegrations per minute (dpm) using a standard HP-210 (pancake GM) probe. Isotopic analysis indicates cobalt-60 and manganese-54. One item had low levels of loose surface contamination (57 dpm/100 cm2). The items identified with low level fixed contamination are now being held inside the Turkey Point radiation controlled area. The signs were shipped in cardboard boxes and no loose surface contamination was found on the exterior of the boxes
"Florida Power & Light Company has notified the Byron Station and the State of Florida (Department of Health, Bureau of Radiation Control) of this matter."
The licensee has informed the NRC resident inspector of this notification.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37757
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MARTY McADORY
HQ OPS Officer: BOB STRANSKY
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MARTY McADORY
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/16/2001
Notification Time: 19:41 [ET]
Event Date: 02/16/2001
Event Time: 16:30 [CST]
Last Update Date: 02/20/2001
Notification Time: 19:41 [ET]
Event Date: 02/16/2001
Event Time: 16:30 [CST]
Last Update Date: 02/20/2001
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):
GREG PICK (R4)
GREG PICK (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 |
HIGH PRESSURE CORE SPRAY SYSTEM DECLARED INOPERABLE
"During performance of 1C3 battery all-cell checks, battery cell #38 was found to be >0.020 below the average for specific gravity. Tech Spec 3.8.6, 'Battery Cell Parameters,' requires declaring 1C3 battery inoperable. This caused entry into Tech Spec 3.8.4 Action D, which is to declare the High Pressure Core Spray system inoperable. This requires entry into a 14 day LCO. This event is reportable since High Pressure Core Spray is a single train system."
The NRC resident inspector has been informed of this event by the licensee.
* * * RETRACTED AT 1549 EST ON 2/20/01 BY CHRIS MILLER TO FANGIE JONES * * *
The licensee is retracting this event notification. After further review it has been determined that the entry conditions for the LCO were not met and the division 3 batteries were never inoperable.
The licensee notified the NRC Resident Inspector. The R4DO (Linda Smith) has been notified.
"During performance of 1C3 battery all-cell checks, battery cell #38 was found to be >0.020 below the average for specific gravity. Tech Spec 3.8.6, 'Battery Cell Parameters,' requires declaring 1C3 battery inoperable. This caused entry into Tech Spec 3.8.4 Action D, which is to declare the High Pressure Core Spray system inoperable. This requires entry into a 14 day LCO. This event is reportable since High Pressure Core Spray is a single train system."
The NRC resident inspector has been informed of this event by the licensee.
* * * RETRACTED AT 1549 EST ON 2/20/01 BY CHRIS MILLER TO FANGIE JONES * * *
The licensee is retracting this event notification. After further review it has been determined that the entry conditions for the LCO were not met and the division 3 batteries were never inoperable.
The licensee notified the NRC Resident Inspector. The R4DO (Linda Smith) has been notified.
Fuel Cycle Facility
Event Number: 37758
Facility: PADUCAH GASEOUS DIFFUSION PLANT
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: TOM WHITE
HQ OPS Officer: STEVE SANDIN
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: TOM WHITE
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/17/2001
Notification Time: 03:17 [ET]
Event Date: 02/16/2001
Event Time: 10:20 [CST]
Last Update Date: 02/17/2001
Notification Time: 03:17 [ET]
Event Date: 02/16/2001
Event Time: 10:20 [CST]
Last Update Date: 02/17/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
MONTE PHILLIPS (R3)
E. WILLIAM BRACH (NMSS)
MONTE PHILLIPS (R3)
E. WILLIAM BRACH (NMSS)
SAFETY EQUIPMENT FAILED TO FUNCTION AS REQUIRED BY TECHNICAL SAFETY REQUIREMENT
"At 1020 on 02-16-01, the Plant Shift Superintendent (PSS) was notified of a safety system failure in the C-315 building. While closing the cylinder valve on a full liquid cylinder, the valve failed to close completely when a shear pin broke on the emergency cylinder valve closure mechanism. At the time of the failure the cylinder valve was still approximately one eighth of a turn open. The operator manually closed the valve thus placing the cylinder in a safe mode. The emergency cylinder valve closure mechanism is part of the Low Voltage UF6 Release Detection and Isolation System at the Withdrawal Stations, and is required to be operable according to TSR 2.3.4.1.
"This event is reportable under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or falls to function as designed.
"The NRC Senior Resident has been notified of this event."
"At 1020 on 02-16-01, the Plant Shift Superintendent (PSS) was notified of a safety system failure in the C-315 building. While closing the cylinder valve on a full liquid cylinder, the valve failed to close completely when a shear pin broke on the emergency cylinder valve closure mechanism. At the time of the failure the cylinder valve was still approximately one eighth of a turn open. The operator manually closed the valve thus placing the cylinder in a safe mode. The emergency cylinder valve closure mechanism is part of the Low Voltage UF6 Release Detection and Isolation System at the Withdrawal Stations, and is required to be operable according to TSR 2.3.4.1.
"This event is reportable under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or falls to function as designed.
"The NRC Senior Resident has been notified of this event."
Fuel Cycle Facility
Event Number: 37759
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: ERIC SPAETH
HQ OPS Officer: BOB STRANSKY
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: ERIC SPAETH
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/17/2001
Notification Time: 12:49 [ET]
Event Date: 02/16/2001
Event Time: 21:37 [EST]
Last Update Date: 02/17/2001
Notification Time: 12:49 [ET]
Event Date: 02/16/2001
Event Time: 21:37 [EST]
Last Update Date: 02/17/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MONTE PHILLIPS (R3)
E. WILLIAM BRACH (NMSS)
MONTE PHILLIPS (R3)
E. WILLIAM BRACH (NMSS)
VALID ACTUATION OF SAFETY SYSTEM
"At 2137 hours on 02/16/01, both the 'A' and 'B' High Level Condensate Alarms activated on Autoclave #1 in the X-343 Feed and Sampling Facility. The activation of either of these alarms will cause the autoclave steam supply valves ('Q' components) to actuate (close). The steam supply valves closed, as designed, upon the activation of the High Condensate Alarms. Autoclave #1 was in TSR Mode II (HEATING) at the time of the alarm activations. Operations personnel immediately responded to the alarms in accordance with the approved Alarm Response Procedures. Both alarms reset when the operations personnel acknowledged the alarms at the local autoclave control panel. All autoclave (and cylinder) operating parameters were determined be to within normal ranges, Autoclave #1 was placed in TSR mode VII (Shutdown) by operations personnel and declared Inoperable by the Plant Shift Superintendent's Office. Based on the actuation of both High Level Condensate alarms, this event is being reported as a valid safety system actuation, a 24-hour NRC event. An Engineering Evaluation has been requested to investigate the circumstances surrounding this safety system actuation."
The NRC resident inspector has been informed of this event.
"At 2137 hours on 02/16/01, both the 'A' and 'B' High Level Condensate Alarms activated on Autoclave #1 in the X-343 Feed and Sampling Facility. The activation of either of these alarms will cause the autoclave steam supply valves ('Q' components) to actuate (close). The steam supply valves closed, as designed, upon the activation of the High Condensate Alarms. Autoclave #1 was in TSR Mode II (HEATING) at the time of the alarm activations. Operations personnel immediately responded to the alarms in accordance with the approved Alarm Response Procedures. Both alarms reset when the operations personnel acknowledged the alarms at the local autoclave control panel. All autoclave (and cylinder) operating parameters were determined be to within normal ranges, Autoclave #1 was placed in TSR mode VII (Shutdown) by operations personnel and declared Inoperable by the Plant Shift Superintendent's Office. Based on the actuation of both High Level Condensate alarms, this event is being reported as a valid safety system actuation, a 24-hour NRC event. An Engineering Evaluation has been requested to investigate the circumstances surrounding this safety system actuation."
The NRC resident inspector has been informed of this event.
Other Nuclear Material
Event Number: 37819
Rep Org: AGILENT TECHNOLOGIES
Licensee: AGILENT TECHNOLOGIES
Region: 1
City: WILMINGTON State: DE
County:
License #: 07-28762-01
Agreement: N
Docket:
NRC Notified By: DAVID BENNET
HQ OPS Officer: DOUG WEAVER
Licensee: AGILENT TECHNOLOGIES
Region: 1
City: WILMINGTON State: DE
County:
License #: 07-28762-01
Agreement: N
Docket:
NRC Notified By: DAVID BENNET
HQ OPS Officer: DOUG WEAVER
Notification Date: 03/09/2001
Notification Time: 15:18 [ET]
Event Date: 02/16/2001
Event Time: 12:00 [EST]
Last Update Date: 03/09/2001
Notification Time: 15:18 [ET]
Event Date: 02/16/2001
Event Time: 12:00 [EST]
Last Update Date: 03/09/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
RONALD BELLAMY (R1)
JOSIE PICCONE (NMSS)
RONALD BELLAMY (R1)
JOSIE PICCONE (NMSS)
Agilent Technologies reported the loss of two electron capture detectors. Each detector contains a 15 mCi Ni-63 source. Because the Ni-63 is plated on the inside of the device and Ni-63 is a low energy Beta emitter, the risk of exposure to the public is low. The detectors were last accounted for in December 1995.