| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/18/2005 - 03/21/2005 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 41477 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MIKE MCBREARTY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/09/2005
Notification Time: 20:36 [ET]
Event Date: 03/09/2005
Event Time: [PST]
Last Update Date: 03/18/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
TROY PRUETT (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text PLANNED LOSS OF THE EMERGENCY RESPONSE DATA SYSTEM
The following information was obtained from the licensee via e-mail (licensee text in quotes):
"On Thursday, March 10, 2005 San Onofre Nuclear Generating Station, Unit 2, will remove a portion of the Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) from service for a planned upgrade to ensure long-term reliability and improve the human-machine interface. This work is expected to complete within seven days.
"The SPDS emergency assessment function at San Onofre is implemented by a combination of the Qualified Safety Parameter Display System (QSPDS) and the Critical Function Monitoring System (CFMS). The QSPDS portion, which provides emergency assessment capability to plant operators in the control room, will remain functional. The CFMS portion, which receives input from the QSPDS, implements the ERDS and communicates data to the Technical Support Center and Emergency Offsite Facility. Only the CFMS and ERDS are impacted by this upgrade.
"This planned CFMS outage is being reported in accordance with 10CFR50.72(b)(3)(xiii) as a courtesy notification even though only a portion of the SPDS will be removed from service and preplanned compensatory measures will be in place for the duration of the work.
"At the time of this report, Unit 2 and Unit 3 were operating at about 79 percent and 99 percent power, respectively.
"The NRC Resident Inspectors will be notified of this occurrence and will be provided with a copy of this report."
Should an emergency event occur, the licensee intends to transmit emergency response data to the NRC via facsimile and voice via the emergency notification system. No electronic data will be sent to the NRC Operations Center for the outage duration.
* * * UPDATE FROM CLAY WILLIAMS TO HOWIE CROUCH ON MARCH 18, 2005 @ 1551 EST * * *
"The CFMS upgrade work was completed on March 17, 2005 at 2310 PST. The SPDS and ERDS have been returned to service."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Farnholtz). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 41489 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF ERDMANN
HQ OPS Officer: MIKE RIPLEY | Notification Date: 03/14/2005
Notification Time: 13:38 [ET]
Event Date: 03/14/2005
Event Time: 10:17 [EST]
Last Update Date: 03/18/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
LAWRENCE DOERFLEIN (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 | Event Text OFFSITE NOTIFICATION OF SODIUM HYPOCHLORITE SPILL
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"This is a 4-hour notification to report a sodium hypochlorite spill from a pipe flange elbow on the permanent sodium hypochlorite tank to the ground at Salem generating station. The spill was over an excavation trench that was filled with rain water. The trench was being pumped to the nearest manhole. Maintenance personnel noticed a 2 drops per second sodium hypochlorite leak from the elbow. The operations shift manager made a 15-minute report to the State of New Jersey to report the spill. The sodium hypochlorite tank was out of service at the time undergoing corrective maintenance. The spill has been contained. Chemistry samples are being taken to determine if any reportable quantities were pumped to the nearest manhole. There was no effect on plant operation since the tank was out of service. Actions include follow up samples and if necessary remediation of the ground soil. There was no one injured during the event."
The licensee notified State and local authorities and the NRC Resident Inspector.
* * * RETRACTION FROM S. SAUER TO W. GOTT AT 2037 ON 3/18/05 * * *
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"On March 14, PSEG reported to the NRC that Report had been made to the New Jersey Department of Environmental Protection regarding a spill of sodium hypochlorite (Event No. 41489). As the spill was cleaned up within 24 hours and there was no direct discharge to the Delaware River, this report has been retracted from the State of New Jersey. Chemistry samples taken indicated no reportable quantities pumped to the river. Ground water was pumped from the excavation to a concrete diked area and the excavation flushed with fresh water until chemistry samples indicated no residual sodium hypochlorite. This EVENT is retracted."
The licensee will notify the NRC Resident Inspector.
Notified R1DO (L. Doerflein) |
| General Information or Other | Event Number: 41493 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: WAVE FORM SPECIALISTS
Region: 4
City: OMAHA State: NE
County:
License #: GLO-636
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: MIKE RIPLEY | Notification Date: 03/15/2005
Notification Time: 17:02 [ET]
Event Date: 09/30/2004
Event Time: [CST]
Last Update Date: 03/15/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TOM FARNHOLTZ (R4)
GARY JANOSKO (NMSS)
JOE FOSTER (TAS)
| Event Text AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS
The following information was provided by the State via facsimile (State text in quotes):
"Isolite/Safety Light shipped two exit signs [Serial Nos. 281266 and 2181268], model SLX60 with 9.5 curies [each] of H-3 on September 1, 2004 to Wave Form Specialists via General Electric Supply. The signs were to be installed in a new facility for the City of Omaha at 4001 South 120th St, as the end user. Wave Form Specialist never installed the signs. Wave Form Specialists declared bankruptcy in September. Wave Form was bonded and another company finished the electrical contract work. The bonding company and the electrical contactor never found the signs when they took over the job. The signs were not returned to Isolite. Have not been able to contact owner of Wave Form Specialists."
Nebraska Incident No: NE050004 |
| General Information or Other | Event Number: 41495 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: RENAISSANCE HOSPITAL
Region: 4
City: GROVES State: TX
County:
License #: NOT PROVIDED
Agreement: Y
Docket:
NRC Notified By: KAREN VERSER
HQ OPS Officer: MIKE RIPLEY | Notification Date: 03/15/2005
Notification Time: 17:03 [ET]
Event Date: 03/14/2005
Event Time: 09:30 [CST]
Last Update Date: 03/15/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TOM FARNHOLTZ (R4)
GARY JANOSKO (NMSS)
| Event Text AGREEMENT STATE REPORT - CONTAMINATED DIAPER PLACED IN REGULAR TRASH
The following information was provided by the State via email (State text in quotes):
"On March 14, 2005 BFI returned a compactor/dumpster to Renaissance Hospital because of radiation detector alarms. After surveying the entire container, one area was reading 9 mR/hr on contact. The trash from this area was again surveyed. A diaper from a patient that had received an I-131 iodine therapy treatment was accidentally put in the regular hospital trash for immediate disposal. The diaper has been removed from the dumpster and sent to the hospital's Nuclear Medicine department for decay. The dumpster was again surveyed after removing the diaper and there were no dose rates above background found. The diaper was reading 10 mR/hr on contact. The diaper was again surveyed on 3/15/05. It was reading 5 mR/hr on contact with a 1 foot reading of 2 mR/hr."
Texas Incident No. I-8220 |
| Power Reactor | Event Number: 41502 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: STEVE SMITH
HQ OPS Officer: BILL GOTT | Notification Date: 03/18/2005
Notification Time: 17:51 [ET]
Event Date: 03/18/2005
Event Time: 15:00 [MST]
Last Update Date: 03/18/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
TOM FARNHOLTZ (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 70 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE DIESEL GENERATOR
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On March 18, 2005, at approximately 15:00 hours Mountain Standard Time (MST), Palo Verde Nuclear Generating Station (PVNGS) Unit 1 commenced a reactor shutdown required by Technical Specification 3.8.1.
"Limiting Condition for Operability (LCO) 3.8.1 requires two diesel generators (DGs) each capable of supplying one train of the onsite Class 1E AC Electrical Power Distribution System be available. On March 17, 2005, at approximately 04:11 MST, Unit 1 Diesel Generator "A" failed to start during its post maintenance retest. The diesel generator (DG) tripped on incomplete sequence. Prior to tripping, the DG reached approximately 100 rpm for fifteen seconds.
"It has been determined that the cause of the DG failure was due to a governor failure. The failed governor has been replaced. At 17:50 on March 17, 2005, DG "B" was tested satisfactorily to confirm there is not a common cause failure. Unit 1 is being shutdown because the retest of DG "A" requires the Unit to be in Mode 5. The LCO 3.8.1 would expire at 04:00 MST, March 19, 2005 requiring initiation of Shut Down required by Technical Specifications if no action was taken.
"The event did not result in the release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified."
At the time of the notification, power was 70% and was being reduced in preparation for reactor shutdown to Mode 3. |
| Power Reactor | Event Number: 41503 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: FRANK CIGANIK
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/18/2005
Notification Time: 19:37 [ET]
Event Date: 03/18/2005
Event Time: 14:00 [EST]
Last Update Date: 03/18/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
LAWRENCE DOERFLEIN (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 | Event Text OTHER UNSPECIFIED REQUIREMENT - LICENSE CONDITION 2.C
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"Report of a violation of the Technical Requirements contained in section 2C of the operating license, which requires initial notification within 24 hours to the NRC via the ENS with written follow-up within 30 days.
"A recent failure of the 'A' CRD pump to start required maintenance on an associated local shutdown panel. Troubleshooting indicated that a relay associated with the panel was the cause of the breaker for the pump to not be set up for a remote start from the control room. The relay in question malfunctioned on Feb. 17th so the 'A' CRD pump was not available since that time. The failure of this pump requires entry into a 7-day shutdown LCO. Troubleshooting, indicated there is firm evidence that this condition, which is prohibited by technical specifications, existed before the discovery on 3/16/5. A 7-day LCO was entered upon discovery and repairs have been completed and the LCO exited."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41504 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: EUGENE PAINTER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/19/2005
Notification Time: 02:12 [ET]
Event Date: 03/19/2005
Event Time: 01:30 [CST]
Last Update Date: 03/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
TOM FARNHOLTZ (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text ADVANCED NOTIFICATION PRIOR TO TAKING SPDS OUT OF SERVICE
At 01:30 CST the Safety Parameter Display System (SPDS) will be taken out of service for planned maintenance. This planned maintenance is scheduled for approximately four hours.
ANO Unit-2 is currently in a refueling outage with the reactor defueled.
The licensee notified the NRC Resident Inspector and the Arkansas Department of Health.
* * * UPDATE PROVIDED BY OLSON TO ABRAMOVITZ @ 1102 3/19/2005 * * *
SPDS restored at 09:40 CST. Resident Inspector will be notified by the licensee.
Notified R4DO (FARNHOLTZ) |
| Power Reactor | Event Number: 41505 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE KASPAR
HQ OPS Officer: BILL GOTT | Notification Date: 03/19/2005
Notification Time: 12:27 [ET]
Event Date: 03/19/2005
Event Time: 08:27 [CST]
Last Update Date: 03/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
TOM FARNHOLTZ (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE NOTIFICATION DUE TO INJURED CONTRACT EMPLOYEE
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"South Texas Project Nuclear Operating Company has been in contact with various news agencies following an industrial accident that occurred at 0827 this morning. A contract employee fell approximately eight to ten feet while descending a permanent plant ladder on a structure in the secondary plant. The individual sustained injuries to his head and back, and has been transported to Herman Hospital in Houston, TX by a Life Flight Helicopter.
"The NRC Regional Office has been informed."
The individual was conscious and in stable condition when he left the facility.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41506 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/21/2005
Notification Time: 03:35 [ET]
Event Date: 03/20/2005
Event Time: 22:30 [EST]
Last Update Date: 03/21/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING HYDRO TEST
The following information was obtained from the licensee via fax (licensee text in quotes):
"At 22:30 on 3/20/2005, the Control Room was notified by the test director that ASME CLASS I Boundary System Leakage Hydrostatic Pressure Test (SE-200-002) had failed. The reason was a leak identified on Reactor Recirc Pump B Discharge Valve, HV243F031B. The leak is coming from the Stub Tube Weld Leakoff Connection for the valve. It is leaking approx. 10 drops per minute. Technical Requirement 3.4.2 was entered. It was determined to be unacceptable under the ASME Section XI Code. Based on guidance provided in NUREG-1022, Rev. 2, this material defect in the primary coolant boundary constitutes a seriously degraded condition and is reportable under 10CFR50.72(b)(3)(ii)(A). A final evaluation of the flaw and a repair plan is being developed."
The NRC Resident was notified. | |