Event Notification Report for February 02, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/01/2004 - 02/02/2004
Power Reactor
Event Number: 40497
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM CROSSMAN
HQ OPS Officer: MIKE RIPLEY
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM CROSSMAN
HQ OPS Officer: MIKE RIPLEY
Notification Date: 02/02/2004
Notification Time: 16:41 [ET]
Event Date: 02/02/2004
Event Time: 08:35 [EST]
Last Update Date: 02/02/2004
Notification Time: 16:41 [ET]
Event Date: 02/02/2004
Event Time: 08:35 [EST]
Last Update Date: 02/02/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
GEORGE KUZO (R2)
GEORGE KUZO (R2)
| 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
A licensed operator was determined to be under the influence of alcohol during a random test. However, it was below the 10CFR26 cut-off level but could have resulted in the individual being unfit for scheduled work activities. The employee's access to the plant has been put on fitness-for-duty hold pending resolution. Contact the HOO for additional details.
The licensee notified the NRC Resident Inspector.
A licensed operator was determined to be under the influence of alcohol during a random test. However, it was below the 10CFR26 cut-off level but could have resulted in the individual being unfit for scheduled work activities. The employee's access to the plant has been put on fitness-for-duty hold pending resolution. Contact the HOO for additional details.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 40498
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: MIKE RIPLEY
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 02/02/2004
Notification Time: 17:33 [ET]
Event Date: 02/02/2004
Event Time: 09:01 [EST]
Last Update Date: 02/02/2004
Notification Time: 17:33 [ET]
Event Date: 02/02/2004
Event Time: 09:01 [EST]
Last Update Date: 02/02/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 87 | Power Operation | 87 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY
A contractor foreman/supervisor was determined to be under the influence of alcohol during a pre-access FFD test as part of processing for unescorted access. The supervisor was denied unescorted access to the protected area. Contact the HOO for additional details
The licensee notified the NRC Resident Inspector.
A contractor foreman/supervisor was determined to be under the influence of alcohol during a pre-access FFD test as part of processing for unescorted access. The supervisor was denied unescorted access to the protected area. Contact the HOO for additional details
The licensee notified the NRC Resident Inspector.
Fuel Cycle Facility
Event Number: 40499
Facility: PADUCAH GASEOUS DIFFUSION PLANT
Region: 2 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: ERIC WALKER
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: ERIC WALKER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 02/03/2004
Notification Time: 03:06 [ET]
Event Date: 02/02/2004
Event Time: 04:15 [CST]
Last Update Date: 02/03/2004
Notification Time: 03:06 [ET]
Event Date: 02/02/2004
Event Time: 04:15 [CST]
Last Update Date: 02/03/2004
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):
GEORGE KUZO (R2)
DANIEL GILLEN (NMSS)
GEORGE KUZO (R2)
DANIEL GILLEN (NMSS)
FAILURE OF C-360 #1 AUTOCLAVE HIGH PRESSURE ISOLATION SYSTEM.
At 0415 on 02-02-04 the Plant Shift Superintendent (PSS) was notified of a failure of the C-130 # 1 Autoclave High Pressure Isolation System. Water was observed leaking from the autoclave head-to-shell interface near the six o'clock position shortly after initiating a cylinder heat cycle. At the time of discovery, the autoclave was in TSR Mode 5 (heating) and the High Pressure Isolation System was required to be operable while in this mode. This system is designed to provide containment of the autoclave and prevent an external release of UF6 during a system breach while heating a UF6 cylinder. The PSS declared the system inoperable and TSR LCO 2.1.3.1.C.1 actions were implemented to remove the autoclave from service and place it in Mode 2, "Out of Service". The event is reportable as a 24 hour event, as required by 10 CFR76.120(c)(2)(i); An event in which equipment is disabled or fails to function as designed when the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specific limits, mitigate the consequences of an accident, or restore this facility to a preestablished safe condition after an accident. The equipment was required by TSR to be available and operable and no redundant equipment was available to perform the required safety function.
The Senior NRC Resident Inspector has been notified of this event.
At 0415 on 02-02-04 the Plant Shift Superintendent (PSS) was notified of a failure of the C-130 # 1 Autoclave High Pressure Isolation System. Water was observed leaking from the autoclave head-to-shell interface near the six o'clock position shortly after initiating a cylinder heat cycle. At the time of discovery, the autoclave was in TSR Mode 5 (heating) and the High Pressure Isolation System was required to be operable while in this mode. This system is designed to provide containment of the autoclave and prevent an external release of UF6 during a system breach while heating a UF6 cylinder. The PSS declared the system inoperable and TSR LCO 2.1.3.1.C.1 actions were implemented to remove the autoclave from service and place it in Mode 2, "Out of Service". The event is reportable as a 24 hour event, as required by 10 CFR76.120(c)(2)(i); An event in which equipment is disabled or fails to function as designed when the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specific limits, mitigate the consequences of an accident, or restore this facility to a preestablished safe condition after an accident. The equipment was required by TSR to be available and operable and no redundant equipment was available to perform the required safety function.
The Senior NRC Resident Inspector has been notified of this event.