| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/21/2007 - 06/22/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43427 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: NODARSE AND ASSOCIATES
Region: 1
City: WEST PALM BEACH State: FL
County:
License #: 2429-1
Agreement: Y
Docket:
NRC Notified By: STEVE L FURNACE
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/18/2007
Notification Time: 12:17 [ET]
Event Date: 02/18/2007
Event Time: 12:00 [EDT]
Last Update Date: 06/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM COOK (R1)
GREG MORELL (FSME)
| Event Text AN AGREEMENT STATE REPORT FROM THE STATE OF FLORIDA - DAMAGED TROXLER GAUGE
This event was called in by the State of Florida Bureau of Radiation Control:
"Troxler Gauge damaged on site February 22, 2007. Company RSO notified this office on June 18, 2007. Back loader drove over gauge and damaged it. Gauge leak tested by Atlantic Drilling and found to be satisfactory."
Incident Location: Fort Lauderdale, Davie Blvd between 31st and 32 streets.
Isotope(s)/Activities: Cs-137 (10 mCi) and Am-241/Be (40 mCi)
State of Florida Incident Number: FL07-100 |
| General Information or Other | Event Number: 43431 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: THYRO-CAT, LLP
Region: 1
City: WALPOLE State: MA
County:
License #: 44-0550
Agreement: Y
Docket:
NRC Notified By: MIKE WHALEN
HQ OPS Officer: JOHN MacKINNON | Notification Date: 06/19/2007
Notification Time: 14:41 [ET]
Event Date: 06/13/2007
Event Time: 11:00 [EDT]
Last Update Date: 06/19/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM COOK (R1)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE REPORT FROM MASSACHUSETTS - CONTAMINATION DUE TO IODINE-131
This Agreement State report from the Commonwealth of Massachusetts was received via facsimile:
"Cat moved (kicked) during I-131 injection resulting in a couple of drops on veterinarian gloved hands, exam table, and floor. Contaminated Area subsequently mopped which seemed to spread more than clean the area. Contaminated area covered with plastic and access was restricted for more than 24 hours. Inside the room, the highest measurements on the floor, with a Ludlum 44-88 GM, was 12 Mr/hr on one spot, and 2-5 Mr/hr in all other floor areas - all measurements are at 1 cm. There was no personal contaminations and one small spot on a technicians sweatshirt sleeve which measured 15 mR/hr at 1 cm. With the 44-88 GM. All thyroid measurements indicate no internal intake of I-131. "
Event type Description: Contaminated Area restricted for more than 24 hours.
Cause of Description: Cat moved (kicked) during I-131 injection resulting in a couple of drops on veterinarian gloved hands, exam table, and floor.
Contributing Factor: Contaminated Area subsequently mopped which seemed to spread more than clean the area.
Docket No.: 06-7113 |
| Power Reactor | Event Number: 43435 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: JOEL BARNETT
HQ OPS Officer: PETE SNYDER | Notification Date: 06/21/2007
Notification Time: 03:24 [ET]
Event Date: 06/20/2007
Event Time: 22:50 [PDT]
Last Update Date: 06/21/2007 | 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
| Person (Organization):
BLAIR SPITZBERG (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 96 | Power Operation | 0 | Hot Standby | Event Text FAILED INSTRUMENT AIR HEADER LEADS TO MANUAL REACTOR TRIP
At 2250 on 6/20/07, "Instrument Air header pressure failed at a brazed joint. The loss of Instrument Air pressure caused the Steam Generator (S/G) Feedwater Regulating Valves to stop controlling and S/G level, E-088, to rise uncontrolled. Control Room Operators tripped the reactor manually. Main Feedwater Pumps were manually tripped to stop excess feedwater to the S/Gs. Loss of Instrument Air failed the normal cooling to Containment. Containment Emergency Cooling units were manually started to provide containment cooling. The standard post trip actions were carried out with all safety functions satisfied." The site is proceeding with post trip recovery. The Instrument Air leak was isolated at 2321 PDT.
All control rods fully inserted on the manual trip. RCPs are in operation transferring decay heat to the S/Gs. Emergency feedwater is feeding the S/Gs with steam being discharged to the condenser via the steam dumps. Atmospheric relief valves were used to discharge steam to the atmosphere initially for approximately 20 minutes following the trip. There are no primary to secondary tube leaks. Containment isolation failed closed as expected following the loss of instrument air pressure to the containment.
Normal offsite power is available and the emergency diesel generators are available if needed.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43436 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NED DENNIN
HQ OPS Officer: JOE O'HARA | Notification Date: 06/21/2007
Notification Time: 04:05 [ET]
Event Date: 06/21/2007
Event Time: 03:15 [EDT]
Last Update Date: 06/21/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
WILLIAM COOK (R1)
|
| 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 HPCI INOPERABLE DUE TO QUARTERLY VALVE STROKE TEST FAILURE
"During performance of the quarterly HPCI valve stroke test the HV-55-2F006, HPCI pump discharge isolation valve to Core Spray failed to open within the maximum allowed time. The HV-55-2F006 valve is a motor operated valve and the maximum allowed opening time is 17.25 seconds. The valve was given an open signal via the handswitch as required by the test but did not initially respond. Several minutes later the valve went full open. HPCI was declared inoperable at 0315 on 6/21/2007. Cause for valve stroke time failure is not known at this time."
As a result, the licensee is in a 14 day shutdown LCO.
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 43438 | Facility: AREVA NP INC RICHLAND
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION
FABRICATION & SCRAP
COMMERCIAL LWR FUEL
Region: 2
City: RICHLAND State: WA
County: PENTON
License #: SNM-1227
Agreement: Y
Docket: 07001257
NRC Notified By: ROBERT LINK
HQ OPS Officer: JASON KOZAL | Notification Date: 06/21/2007
Notification Time: 16:26 [ET]
Event Date: 06/21/2007
Event Time: 01:42 [PDT]
Last Update Date: 06/21/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(4) - FIRE/EXPLOSION
| Person (Organization):
EUGENE GUTHRIE (R2)
JACK DAVIS (FSME)
THOMAS BLOUNT (IRD)
| Event Text FIRE DUE TO SEQUENCING PROBLEM
"At approximately 0142 hours on 6/21/2007, during Solid Waste Uranium Recovery (SWUR) operations, a sequencing problem caused a cardboard box containing combustible waste with about [Deleted] U-235 to be fed on top of a closed feed hopper door. As the equipment cycled the incinerator fire door, the box, which was on top of the feed hopper door ignited. The box was inside the feed hopper containment shroud when it ignited. The integrity of the containment shroud remained intact during the fire. However, some smoke did escape into the room.
"Operational personnel put out the fire (a single box of 3.5 cubic feet) using a hand held fire extinguisher.
"The plant emergency response team (PERT) was activated via plant paging system at 0145 and the Richland Fire Department was called. The Richland Fire Department arrived at 0155. With appropriate PPE (SCBA), two PERT and two Richland Fire Fighters entered the facility and confirmed that the fire had been previously extinguished.
"The SWUR process is currently shut down and will remain down pending investigation and completion of appropriate corrective actions.
"The fire was limited to a single 3.5 cubic foot box containing [Deleted] U-235. All facility HEPA filters remained undamaged during the event."
There was no release of radioactive materials. All areas surveyed after the fire was extinguished were free of radioactive contamination. The individuals that put out the fire and the individuals that subsequently entered the area to confirm that the fire had been extinguished were evaluated for internal contamination with negative results. |
| Fuel Cycle Facility | Event Number: 43439 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: JEFF ROTTON | Notification Date: 06/21/2007
Notification Time: 17:29 [ET]
Event Date: 06/21/2007
Event Time: 16:30 [EDT]
Last Update Date: 06/21/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(a) - PROTECTIVE ACTION PREVENTED
| Person (Organization):
EUGENE GUTHRIE (R2)
JACK DAVIS (FSME)
THOMAS BLOUNT (IRD)
| Event Text ITEM RELIED ON FOR SAFETY NOT RELIABLE UNDER ALL SCENARIOS.
"During a review of the Integrated Safety Analysis for an additive addition step, it was determined that one of the Items Relied on for Safety (IROFS), as documented in the ISA Summary was not reliable. This report is submitted for administrative reporting pursuant to 10CFR7O.50 Appendix A (a)(5). At no time did an unsafe condition exist. The existing criticality safety analysis of the operation bounded the situation, was effective and was not challenged.
"The IROFS described for the additive sequence did not prevent incorrect type of additive from being added under all scenarios.
"All affected equipment is in the process of being shut down pending revision of the ISA IROFS for this additive addition process. Units will remain shutdown pending final investigation and implementation of additional preventive actions.
"Independent controls on moderation remained intact. The as found condition was previously analyzed and demonstrated to be safe. At no time did an unsafe condition exist."
Licensee will notify NRC Region 2, North Carolina Radiation Protection Agency, and the New Hanover County Emergency Management Agency. |
| Power Reactor | Event Number: 43440 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: TERRY DAMASHEK
HQ OPS Officer: PETE SNYDER | Notification Date: 06/22/2007
Notification Time: 03:34 [ET]
Event Date: 06/21/2007
Event Time: 20:00 [CDT]
Last Update Date: 06/22/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BLAIR SPITZBERG (R4)
|
| 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 "SPDS (SAFETY PARAMETER DISPLAY SYSTEM) INOPERABLE DUE TO PLANT COMPUTER INOPERABILITY
"The Wolf Creek Nuclear Plant Information System (NPIS; Plant Computer) was conservatively declared inoperable at 2000 (CDT) on 06/21/2007 due to questions concerning accuracy of some of the computer point outputs. Initial troubleshooting and investigation identified that some computer points may be reading 0.1% to 0.2% lower than actual process parameter. Investigation is ongoing to determine the scope and cause for this condition and to correct the problem. Compensatory measures for loss of NPIS are being implemented in accordance with procedure OFN RJ-023, NPIS Malfunctions. The plant is stable with power being maintained at or below 100% based on Nuclear Instruments."
The licensee notified the NRC Resident Inspector. | |