Event Notification Report for August 15, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/14/2003 - 08/15/2003
EVENT NUMBERS
40082400774007840080
Fuel Cycle Facility
Event Number: 40082
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: ERIC WALKER
HQ OPS Officer: CHAUNCEY GOULD
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: ERIC WALKER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/16/2003
Notification Time: 13:10 [ET]
Event Date: 08/15/2003
Event Time: 23:55 [CDT]
Last Update Date: 08/16/2003
Notification Time: 13:10 [ET]
Event Date: 08/15/2003
Event Time: 23:55 [CDT]
Last Update Date: 08/16/2003
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):
SONIA BURGESS (R3)
JOHN HICKEY (NMSS)
SONIA BURGESS (R3)
JOHN HICKEY (NMSS)
FAILURE OF AUTOCLAVE HIGH PRESSURE ISOLATION SYSTEM
"At 2355 CST, on 8-15-03 the Plant Shift Superintendent (PSS) was notified of a failure of the C-360 #3 Autoclave High Pressure Isolation System. Steam was observed leaking from the autoclave head-to-shell interface at the six o'clock position shortly after initiating a cylinder heat cycle. At the time of discovery, the autoclave was in TSR mode 5 and the High Pressure Isolation System is required to be operable while in this mode. This system is designed to provide containment of the autoclave and prevent 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 actions were Implemented to remove the autoclave from service and place it in Mode 2, "Out of Service". Initial investigation of the incident revealed damage to the autoclave head-to-shall interface sealing surface. The damage resulted from a previous obstruction within the interface while closing the autoclave. Investigation is ongoing to determine the root cause of failure.
The event is reportable as a 24 hour event, as required by 10 CFR 76,120©(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 specified 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 2355 CST, on 8-15-03 the Plant Shift Superintendent (PSS) was notified of a failure of the C-360 #3 Autoclave High Pressure Isolation System. Steam was observed leaking from the autoclave head-to-shell interface at the six o'clock position shortly after initiating a cylinder heat cycle. At the time of discovery, the autoclave was in TSR mode 5 and the High Pressure Isolation System is required to be operable while in this mode. This system is designed to provide containment of the autoclave and prevent 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 actions were Implemented to remove the autoclave from service and place it in Mode 2, "Out of Service". Initial investigation of the incident revealed damage to the autoclave head-to-shall interface sealing surface. The damage resulted from a previous obstruction within the interface while closing the autoclave. Investigation is ongoing to determine the root cause of failure.
The event is reportable as a 24 hour event, as required by 10 CFR 76,120©(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 specified 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.
Power Reactor
Event Number: 40077
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ETHAN TREPTOW
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ETHAN TREPTOW
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/15/2003
Notification Time: 13:15 [ET]
Event Date: 08/15/2003
Event Time: 11:20 [CDT]
Last Update Date: 08/15/2003
Notification Time: 13:15 [ET]
Event Date: 08/15/2003
Event Time: 11:20 [CDT]
Last Update Date: 08/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
SONIA BURGESS (R3)
MATT HAHN (TAT)
SONIA BURGESS (R3)
MATT HAHN (TAT)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
DISCOVERED BY SECURITY A VULNERABILITY THAT COULD ALLOW UNAUTHORIZED/UNDETECTED ACCESS TO A VITAL AREA. COMPENSATORY MEASURES HAVE BEEN TAKEN.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS BY THE LICENSEE.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS BY THE LICENSEE.
Power Reactor
Event Number: 40078
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RICHARD LOUIE
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: RICHARD LOUIE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/15/2003
Notification Time: 13:25 [ET]
Event Date: 08/15/2003
Event Time: 10:15 [EDT]
Last Update Date: 08/15/2003
Notification Time: 13:25 [ET]
Event Date: 08/15/2003
Event Time: 10:15 [EDT]
Last Update Date: 08/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GLENN MEYER (R1)
GLENN MEYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
| 3 | N | N | 0 | Hot Standby | 0 | Hot Standby |
POWER LOST TO EMERGENCY SIRENS.
At approximately 1015 hours on August 15, 2003 a review of the county siren overviews maps revealed that Westchester County had experienced another major power loss to its service. This resulted in more than 60 sirens being without utility-supplied power. This situation rendered the system inoperable for Westchester County as the sirens were without substantial power by which to be sounded. Further information revealed that the utility had to shed load. Route alerting capability is available.
New York State and County representatives were notified of this event.
The NRC Resident Inspector was notified of this event by the licensee.
At approximately 1015 hours on August 15, 2003 a review of the county siren overviews maps revealed that Westchester County had experienced another major power loss to its service. This resulted in more than 60 sirens being without utility-supplied power. This situation rendered the system inoperable for Westchester County as the sirens were without substantial power by which to be sounded. Further information revealed that the utility had to shed load. Route alerting capability is available.
New York State and County representatives were notified of this event.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 40080
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: L. R. FREELAND
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: L. R. FREELAND
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/15/2003
Notification Time: 19:28 [ET]
Event Date: 08/15/2003
Event Time: 08:31 [EDT]
Last Update Date: 08/15/2003
Notification Time: 19:28 [ET]
Event Date: 08/15/2003
Event Time: 08:31 [EDT]
Last Update Date: 08/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
GLENN MEYER (R1)
GLENN MEYER (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 |
LICENSED PERSON RANDOMLY TESTED FOR BLOOD ALCOHOL
At 0831 hrs on 08/15/2003 at Beaver Valley Power Station, a person licensed under 10 CFR Part 55 was randomly tested for fitness for duty and found to have a blood alcohol content (BAC) level of 0.01. It was determined that this person's BAC did not exceed the limit of 0.04 BAC when it was back calculated for their time on site prior to the random test. Therefore, this was not a positive test for alcohol.
However, it was the opinion of the medical review officer that the tested person was not fit to remain on scheduled duty and the person was provided transportation off site property. This is being reported pursuant to 10 CFR 26.73(a)(2)(iv). The individual's license was not in active status and therefore was not performing licensed duties on 08/15/2003.
The NRC Resident Inspector was notified of this event by the licensee.
At 0831 hrs on 08/15/2003 at Beaver Valley Power Station, a person licensed under 10 CFR Part 55 was randomly tested for fitness for duty and found to have a blood alcohol content (BAC) level of 0.01. It was determined that this person's BAC did not exceed the limit of 0.04 BAC when it was back calculated for their time on site prior to the random test. Therefore, this was not a positive test for alcohol.
However, it was the opinion of the medical review officer that the tested person was not fit to remain on scheduled duty and the person was provided transportation off site property. This is being reported pursuant to 10 CFR 26.73(a)(2)(iv). The individual's license was not in active status and therefore was not performing licensed duties on 08/15/2003.
The NRC Resident Inspector was notified of this event by the licensee.