Event Notification Report for March 08, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/07/2010 - 03/08/2010
EVENT NUMBERS
45749457514575245753
Power Reactor
Event Number: 45749
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES KURAS
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES KURAS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/08/2010
Notification Time: 05:46 [ET]
Event Date: 03/08/2010
Event Time: 03:33 [CST]
Last Update Date: 03/08/2010
Notification Time: 05:46 [ET]
Event Date: 03/08/2010
Event Time: 03:33 [CST]
Last Update Date: 03/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHUCK CAIN (R4DO)
CHUCK CAIN (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 42 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOSS OF ALL MAIN FEEDWATER
"Wolf Creek experienced an 'A' Main Feedwater Pump (MFP) trip at 0332 CST during a plant startup. Reactor power was 42% at the time of the manual reactor trip. The loss of the 'A' MFP resulted in no feedwater flow to the Steam Generators and a manual reactor trip was ordered due to the impending reactor trip on low-low Steam Generator level.
"Post-trip decay heat was being removed by the Condenser and Auxiliary Feedwater System. Reactor Coolant System (RCS) temperature dropped below 550 degrees Fahrenheit, which required emergency boration to ensure shutdown margin was maintained. Emergency boration was secured at 0404 CST when RCS temperature was raised to greater than 550 degrees Fahrenheit. The lowest RCS temperature reached following the reactor trip was 544 degrees Fahrenheit.
"The cause of the 'A' Main Feedwater Pump trip is not known at this time.
"Primary to secondary leakage is less than 0.224 gallons per day. All systems functioned as designed.
"The plant is being maintained at normal Mode 3 pressure and temperature.
"The licensee has notified the Senior NRC Resident Inspector."
All control rods fully inserted. The plant is in a normal post-trip electrical line-up.
"Wolf Creek experienced an 'A' Main Feedwater Pump (MFP) trip at 0332 CST during a plant startup. Reactor power was 42% at the time of the manual reactor trip. The loss of the 'A' MFP resulted in no feedwater flow to the Steam Generators and a manual reactor trip was ordered due to the impending reactor trip on low-low Steam Generator level.
"Post-trip decay heat was being removed by the Condenser and Auxiliary Feedwater System. Reactor Coolant System (RCS) temperature dropped below 550 degrees Fahrenheit, which required emergency boration to ensure shutdown margin was maintained. Emergency boration was secured at 0404 CST when RCS temperature was raised to greater than 550 degrees Fahrenheit. The lowest RCS temperature reached following the reactor trip was 544 degrees Fahrenheit.
"The cause of the 'A' Main Feedwater Pump trip is not known at this time.
"Primary to secondary leakage is less than 0.224 gallons per day. All systems functioned as designed.
"The plant is being maintained at normal Mode 3 pressure and temperature.
"The licensee has notified the Senior NRC Resident Inspector."
All control rods fully inserted. The plant is in a normal post-trip electrical line-up.
Power Reactor
Event Number: 45751
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: GEOFF COOK
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: GEOFF COOK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/08/2010
Notification Time: 16:31 [ET]
Event Date: 03/08/2010
Event Time: 10:25 [PST]
Last Update Date: 03/08/2010
Notification Time: 16:31 [ET]
Event Date: 03/08/2010
Event Time: 10:25 [PST]
Last Update Date: 03/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MICHAEL HAY (R4DO)
MICHAEL HAY (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 3 | N | Y | 72 | Power Operation | 72 | Power Operation |
FITNESS FOR DUTY REPORT
A non-licensed employee supervisor had a confirmed positive for alcohol during a follow-up fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
A non-licensed employee supervisor had a confirmed positive for alcohol during a follow-up fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
Fuel Cycle Facility
Event Number: 45752
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: BRYAN MILLER
HQ OPS Officer: CHARLES TEAL
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: BRYAN MILLER
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/08/2010
Notification Time: 20:03 [ET]
Event Date: 03/08/2010
Event Time: 00:00 [EST]
Last Update Date: 03/08/2010
Notification Time: 20:03 [ET]
Event Date: 03/08/2010
Event Time: 00:00 [EST]
Last Update Date: 03/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BINOY DESAI (R2DO)
JAMES RUBENSTONE (NMSS)
MARK DELLIGATTI (FSME)
BINOY DESAI (R2DO)
JAMES RUBENSTONE (NMSS)
MARK DELLIGATTI (FSME)
POTENTIAL RELEASE OF CONTAMINATED MATERALS OFF-SITE
"At 1705 hours on 03/08/2010, the USEC-GS Plant Shift Superintendents' (PSS) Office at Portsmouth was notified of an inadvertent release of radioactively contaminated materials to an off-site location in Pike County, OH. The contamination was the result of a contractor neutralizing a fluorine service pipe connecting the X-326 building with the X-760 building. The X-760 building has been "de-leased" by USEC back to the Department of Energy (DOE) and is being prepared for decommission and demolition. The contaminated items consisted of five (5) 5-gallon buckets containing some rusty solution. The highest contamination levels were on one (1) bucket with 14K Beta removable and 50K Beta fixed. All other tools and personal protective equipment were monitored and found to be uncontaminated. There is a filtering unit located in Atlanta, GA that remains to be surveyed. A team of USEC health physics personnel is preparing to travel to the contractor's facility in Atlanta to complete the surveys.
"This event has been classified as reportable in accordance with procedure UE2-RA-RE1030, Portsmouth GDP SAR 6.9, and 10CFR76. No 10CFR20 exposure limits were reached or exceeded."
The licensee notified the NRC Resident Inspector.
"At 1705 hours on 03/08/2010, the USEC-GS Plant Shift Superintendents' (PSS) Office at Portsmouth was notified of an inadvertent release of radioactively contaminated materials to an off-site location in Pike County, OH. The contamination was the result of a contractor neutralizing a fluorine service pipe connecting the X-326 building with the X-760 building. The X-760 building has been "de-leased" by USEC back to the Department of Energy (DOE) and is being prepared for decommission and demolition. The contaminated items consisted of five (5) 5-gallon buckets containing some rusty solution. The highest contamination levels were on one (1) bucket with 14K Beta removable and 50K Beta fixed. All other tools and personal protective equipment were monitored and found to be uncontaminated. There is a filtering unit located in Atlanta, GA that remains to be surveyed. A team of USEC health physics personnel is preparing to travel to the contractor's facility in Atlanta to complete the surveys.
"This event has been classified as reportable in accordance with procedure UE2-RA-RE1030, Portsmouth GDP SAR 6.9, and 10CFR76. No 10CFR20 exposure limits were reached or exceeded."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45753
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TERRY HOLCOMBE
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TERRY HOLCOMBE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/08/2010
Notification Time: 19:47 [ET]
Event Date: 03/08/2010
Event Time: 16:35 [CST]
Last Update Date: 03/08/2010
Notification Time: 19:47 [ET]
Event Date: 03/08/2010
Event Time: 16:35 [CST]
Last Update Date: 03/08/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MICHAEL HAY (R4DO)
MICHAEL HAY (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL
"An 'A' reactor feed pump trip occurred and initiated a recirculation pump flow control valve runback. During the flow control valve runback, the 'A' recirculation hydraulic power unit tripped causing an incomplete runback.
"Reactor water level 3 (11.4 inches) was reached which is an RPS scram setpoint and also a setpoint for Group 2 (RHR to Radwaste) and Group 3 (Shutdown Cooling Isolation). No valves isolated in these systems due to [the valves] being in their normally closed position. The lowest reactor water level reached was -28 inches wide range.
"Appropriate off normal event procedures were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached, and no ECCS or Diesel Generator initiation occurred. All safety systems performed as expected.
"MSIVs remained open and no SRVs lifted. Main condenser and pressure control systems remained in service. Currently, reactor water level is being maintained by the condensate and feedwater system in the normal level band and reactor pressure is being controlled to limit cooldown."
During the scram, all rods inserted into the core. The plant is in its normal shutdown electrical lineup. Decay heat removal is via the steam bypass valves to the condenser.
The licensee has notified the NRC Resident Inspector.
"An 'A' reactor feed pump trip occurred and initiated a recirculation pump flow control valve runback. During the flow control valve runback, the 'A' recirculation hydraulic power unit tripped causing an incomplete runback.
"Reactor water level 3 (11.4 inches) was reached which is an RPS scram setpoint and also a setpoint for Group 2 (RHR to Radwaste) and Group 3 (Shutdown Cooling Isolation). No valves isolated in these systems due to [the valves] being in their normally closed position. The lowest reactor water level reached was -28 inches wide range.
"Appropriate off normal event procedures were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached, and no ECCS or Diesel Generator initiation occurred. All safety systems performed as expected.
"MSIVs remained open and no SRVs lifted. Main condenser and pressure control systems remained in service. Currently, reactor water level is being maintained by the condensate and feedwater system in the normal level band and reactor pressure is being controlled to limit cooldown."
During the scram, all rods inserted into the core. The plant is in its normal shutdown electrical lineup. Decay heat removal is via the steam bypass valves to the condenser.
The licensee has notified the NRC Resident Inspector.