Event Notification Report for May 13, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/12/2010 - 05/13/2010
EVENT NUMBERS
45926459244592545922
Fuel Cycle Facility
Event Number: 45926
Facility: WESTINGHOUSE ELECTRIC CORPORATION
Region: 2 State: SC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: GERARD COUTURE
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: SC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: GERARD COUTURE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/14/2010
Notification Time: 10:54 [ET]
Event Date: 05/13/2010
Event Time: 12:33 [EDT]
Last Update Date: 05/14/2010
Notification Time: 10:54 [ET]
Event Date: 05/13/2010
Event Time: 12:33 [EDT]
Last Update Date: 05/14/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KING STABLEIN (NMSS)
KATHLEEN O'DONOHUE (R2DO)
KING STABLEIN (NMSS)
A VALVE CLASSIFIED AS AN ITEM RELIED ON FOR SAFETY FOUND CLOSED WHILE POSITION INDICATOR SHOWED OPEN
"It was reported to EH&S [Environmental Health & Safety] Management that on May 13, 2010 that the XV-202-I valve actuator was showing open when the valve was closed. This valve is the Uranium Hexafluoride (UF6) eduction back-up emergency shut off valve and is credited as a protective feature for a high level condition in the hydrolysis column. This valve is a key component of an Item Relied On for Safety (IROFS) and is identified in the Integrated Safety Analysis (ISA) Summary for the conversion area of the Columbia Fuel Fabrication Facility. This IROFS designation is ADUVAP-110. No process upset occurred and the condition was discovered by the production staff during normal operation.
"This notification is made based on 10CFR70 Appendix A (b) (2), 'Loss or degradation of items relied on for safety that results in failure to meet the performance requirements of 10CFR70.61.' The performance requirements for this accident sequence require the Overall Likelihood Index (OLI) be a -4, which corresponds to Highly Unlikely. With this control failure the sequence OLI is a -3 which corresponds to Unlikely.
"Immediate Corrective Actions:
- Upon identification of the issue on May 13, production shut down conversion line 2 and generated a 'red book' to inform EH&S.
- Maintenance determined the valve actuator had been installed incorrectly.
- Maintenance properly installed the actuator on the valve and demonstrated proper performance.
- The event has been entered into the Corrective Action Process IR# 10-134-C001.
- Conversion line 2 remains shutdown pending staff management authorization for restart.
- For all modifications/maintenance activity on IROFS in safety significant systems, staff management approval is required for restart of the system."
The licensee believes that the valve mis-position and indication issues occurred during maintenance on the valve approximately one week prior to discovery of the condition.
"It was reported to EH&S [Environmental Health & Safety] Management that on May 13, 2010 that the XV-202-I valve actuator was showing open when the valve was closed. This valve is the Uranium Hexafluoride (UF6) eduction back-up emergency shut off valve and is credited as a protective feature for a high level condition in the hydrolysis column. This valve is a key component of an Item Relied On for Safety (IROFS) and is identified in the Integrated Safety Analysis (ISA) Summary for the conversion area of the Columbia Fuel Fabrication Facility. This IROFS designation is ADUVAP-110. No process upset occurred and the condition was discovered by the production staff during normal operation.
"This notification is made based on 10CFR70 Appendix A (b) (2), 'Loss or degradation of items relied on for safety that results in failure to meet the performance requirements of 10CFR70.61.' The performance requirements for this accident sequence require the Overall Likelihood Index (OLI) be a -4, which corresponds to Highly Unlikely. With this control failure the sequence OLI is a -3 which corresponds to Unlikely.
"Immediate Corrective Actions:
- Upon identification of the issue on May 13, production shut down conversion line 2 and generated a 'red book' to inform EH&S.
- Maintenance determined the valve actuator had been installed incorrectly.
- Maintenance properly installed the actuator on the valve and demonstrated proper performance.
- The event has been entered into the Corrective Action Process IR# 10-134-C001.
- Conversion line 2 remains shutdown pending staff management authorization for restart.
- For all modifications/maintenance activity on IROFS in safety significant systems, staff management approval is required for restart of the system."
The licensee believes that the valve mis-position and indication issues occurred during maintenance on the valve approximately one week prior to discovery of the condition.
Power Reactor
Event Number: 45924
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: MICHAEL TURNER
HQ OPS Officer: VINCE KLCO
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: MICHAEL TURNER
HQ OPS Officer: VINCE KLCO
Notification Date: 05/13/2010
Notification Time: 16:55 [ET]
Event Date: 05/13/2010
Event Time: 13:32 [CDT]
Last Update Date: 05/13/2010
Notification Time: 16:55 [ET]
Event Date: 05/13/2010
Event Time: 13:32 [CDT]
Last Update Date: 05/13/2010
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):
GREG PICK (R4DO)
GREG PICK (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION
"At 1332 CDT, FCS [Fort Calhoun Station] control room received notification that a person inside the Protected Area appeared to be having a heart attack. EMTs were immediately paged/dispatched and the victim was transported offsite for emergency medical treatment via helicopter.
"At 1415 CDT, FCS control room received notification that another person suffered a severe hand laceration due to the closing of a security gate. Again, EMTs were immediately paged/dispatched and the victim was transported offsite for emergency medical treatment via ambulance.
"Neither of these individuals were radioactively contaminated."
The licensee notified the NRC Resident Inspector
"At 1332 CDT, FCS [Fort Calhoun Station] control room received notification that a person inside the Protected Area appeared to be having a heart attack. EMTs were immediately paged/dispatched and the victim was transported offsite for emergency medical treatment via helicopter.
"At 1415 CDT, FCS control room received notification that another person suffered a severe hand laceration due to the closing of a security gate. Again, EMTs were immediately paged/dispatched and the victim was transported offsite for emergency medical treatment via ambulance.
"Neither of these individuals were radioactively contaminated."
The licensee notified the NRC Resident Inspector
Fuel Cycle Facility
Event Number: 45925
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 2 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: GARY SALYERS
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: GARY SALYERS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/13/2010
Notification Time: 19:43 [ET]
Event Date: 05/13/2010
Event Time: 16:02 [EDT]
Last Update Date: 05/13/2010
Notification Time: 19:43 [ET]
Event Date: 05/13/2010
Event Time: 16:02 [EDT]
Last Update Date: 05/13/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KING STABLEIN (NMSS)
KATHLEEN O'DONOHUE (R2DO)
KING STABLEIN (NMSS)
NOTIFICATION OF OHIO ENVIRONMENTAL PROTECTION AGENCY DUE TO EXCEEDING NPDES DISCHARGE PERMIT VALUE
"At 1602 hrs on 5/13/2010 the Plant Shift Superintendent's (PSS) office was notified by USEC Environmental Management that NPDES [National Pollutant Discharge Elimination System] permit maximum concentration limit for fecal coliform at the X-6619 (Sewage Treatment Facility) discharge (NPDES Outfall 003) was exceeded. Sample results from 5/12/2010 revealed the permit limit of 2000 colonies / 100 ml was exceeded which resulted in a notification to the Ohio Environmental Protection Agency (OEPA).
"Procedure UE2-RA-RE1030, appendix D, Section Q (Miscellaneous) which states: 'USEC shall notify NRC of any event or situation, related to the health and safety of the public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been made or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'"
The licensee notified the NRC Resident Inspector.
"At 1602 hrs on 5/13/2010 the Plant Shift Superintendent's (PSS) office was notified by USEC Environmental Management that NPDES [National Pollutant Discharge Elimination System] permit maximum concentration limit for fecal coliform at the X-6619 (Sewage Treatment Facility) discharge (NPDES Outfall 003) was exceeded. Sample results from 5/12/2010 revealed the permit limit of 2000 colonies / 100 ml was exceeded which resulted in a notification to the Ohio Environmental Protection Agency (OEPA).
"Procedure UE2-RA-RE1030, appendix D, Section Q (Miscellaneous) which states: 'USEC shall notify NRC of any event or situation, related to the health and safety of the public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been made or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'"
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45922
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: HERBERT TRITT
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: HERBERT TRITT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/13/2010
Notification Time: 05:00 [ET]
Event Date: 05/13/2010
Event Time: 05:00 [EDT]
Last Update Date: 05/13/2010
Notification Time: 05:00 [ET]
Event Date: 05/13/2010
Event Time: 05:00 [EDT]
Last Update Date: 05/13/2010
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):
HAROLD GRAY (R1DO)
HAROLD GRAY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PARTIAL LOSS OF ERDS AND SPDS DUE TO PLANNED MAINTENANCE
"A partial loss of ERDS [Emergency Response Data System] and SPDS [Safety Parameter Display System] capability will occur while a planned replacement of the site's plant process computer power supplies is performed:
"The following is a list of the inputs to ERDS that will be lost:
IRM 14 PERCENT OF RANGE
SRM 24 NEUTRON FLUX
TORUS WIDE RANGE LEVEL
CORE SPRAY SYSTEM 1 AND 2 FLOWS
MAIN STEAM LINE BAND C RAD LEVELS
DW [Dry Well] WIDE RANGE PRESS
STACK RAGEMS [Radioactive Gas Effluent Monitoring System] LOG LO RNG CH 2
"The following is a list of the SPDS inputs that will be lost:
CORE SPRAY SYSTEM 1 AND 2 FLOWS
EMRV [Electromatic Relief Valves] AND SAFETY VALVE INDICATIONS
DW PRESSURE
MS [Main Steam] A,B,C, AND D RAD MONITORS
DW 02 CONCENTRATION
"ERDS and SPDS are expected to be returned to full functionality by 2000 EDT"
Emergency plan contingency measures are in place to transmit data should it be required during the maintenance period.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM DENNIS MOORE TO DONALD NORWOOD AT 2152 EDT ON 5/13/2010 * * *
ERDS and SPDS returned to service as of 2144 EDT.
The licensee will notify the NRC Resident Inspector. Notified R1DO (Gray).
"A partial loss of ERDS [Emergency Response Data System] and SPDS [Safety Parameter Display System] capability will occur while a planned replacement of the site's plant process computer power supplies is performed:
"The following is a list of the inputs to ERDS that will be lost:
IRM 14 PERCENT OF RANGE
SRM 24 NEUTRON FLUX
TORUS WIDE RANGE LEVEL
CORE SPRAY SYSTEM 1 AND 2 FLOWS
MAIN STEAM LINE BAND C RAD LEVELS
DW [Dry Well] WIDE RANGE PRESS
STACK RAGEMS [Radioactive Gas Effluent Monitoring System] LOG LO RNG CH 2
"The following is a list of the SPDS inputs that will be lost:
CORE SPRAY SYSTEM 1 AND 2 FLOWS
EMRV [Electromatic Relief Valves] AND SAFETY VALVE INDICATIONS
DW PRESSURE
MS [Main Steam] A,B,C, AND D RAD MONITORS
DW 02 CONCENTRATION
"ERDS and SPDS are expected to be returned to full functionality by 2000 EDT"
Emergency plan contingency measures are in place to transmit data should it be required during the maintenance period.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM DENNIS MOORE TO DONALD NORWOOD AT 2152 EDT ON 5/13/2010 * * *
ERDS and SPDS returned to service as of 2144 EDT.
The licensee will notify the NRC Resident Inspector. Notified R1DO (Gray).