| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/05/2006 - 07/06/2006 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42651 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JIM BLASEK
HQ OPS Officer: JOE O'HARA | Notification Date: 06/19/2006
Notification Time: 00:29 [ET]
Event Date: 06/18/2006
Event Time: 14:55 [MST]
Last Update Date: 07/05/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
ANTHONY GODY (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF ONSITE EMERGENCY SAFETY FUNCTION - "B" EDG FAILED TO START DURING TEST RUN
"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 June 18, 2006, at approximately 1455 Mountain Standard Time (MST), Palo Verde Nuclear Generating Station
Unit 1 was operating at 0% power in Mode 6 with the 'A' Emergency Diesel Generator (EDG) inoperable for troubleshooting of the train 'A' load sequencer, The 'B' EDG failed to start during a test run resulting in a loss of the onsite emergency power safety function required by General Design Criterion (GDC) 17. The offsite power source safety function remains available to the plant.
"The unit entered Technical Specification 3.8.2, AC Sources - Shutdown Condition B for one required DG inoperable.
There was no movement of irradiated fuel assemblies, therefore the unit remained in compliance with the Required
Actions. The offsite electrical grid is stable.
"At 1810 MST the 'A' EDG was declared operable, exiting Technical Specification 3.8.2. With the 'A' EDG operable,
the safety function for the onsite emergency power was also restored.
"There were no structures, systems or components that were inoperable at the start of event that contributed to the
event. This condition did not result in any challenges to the fission product barrier or result in any releases of
radioactive materials. There were no adverse safety consequences or implications as a result of this event. This
condition did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified of this condition and this ENS notification."
* * * RETRACTION RECEIVED VIA E-MAIL FROM DAN HAUTALA TO JOE O'HARA AT 1702 ON 7/5/06 * * *
" Further evaluation has determined that this event is not reportable. In the 'test' mode, an 'Incomplete Sequence' trip is enabled and functions on an engine start to trip the engine if starting air is not terminated within 15 seconds. Due to a delay in opening the engine fuel racks by the test mode pneumatic control valve loop, the 'Incomplete Sequence' trip actuated. During an emergency start, the electrically operated emergency fuel solenoids control the operation of the engine fuel racks and the 'Incomplete Sequence' trip function is bypassed. Engineering evaluation found none of the equipment required to operate the 'B' EDG in the emergency mode degraded or malfunctioning. The 'B' EDG was still capable of performing its design function and was 'OPERABLE'. Additionally, it was determined that the 'A' EDG was fully functional and in a standby condition, capable of performing its design function at the time the 'B' EDG test run trip occurred.
"Therefore, this condition is not reportable per 10CFR50.72(2)(b)(v)(B) or (2)(b)(v)(D)."
The licensee notified the NRC Resident Inspector. R4DO(Pick) has been notified. |
| General Information or Other | Event Number: 42679 | Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: FAIRVIEW RIVERSIDE HOSPITAL
Region: 3
City: MINNEAPOLIS State: MN
County:
License #: 1035-200-27
Agreement: Y
Docket:
NRC Notified By: GEORGE JOHNS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/30/2006
Notification Time: 22:22 [ET]
Event Date: 06/30/2006
Event Time: 15:00 [CDT]
Last Update Date: 06/30/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN MADERA (R3)
ROBERT PIERSON (NMSS)
CANADA (E-MAIL) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOSS OF SEVEN Pd-103 PROSTATE IMPLANT SEEDS
"At 1853 hrs CST on June 30, 2006, University of Minnesota Medical Center, Fairview Riverside Hospital notified the Minnesota Department of Health that seven Palladium-103 seeds had been lost.
"At approximately 1500 hrs on June 30, 2005, the licensee completed a seed implant for prostate cancer. At the completion of that procedure, a scrub tech removed the tray from the area. The physicist reported 39 unused seeds ten of which were most probably on a partially used ribbon. (The licensee was using a MIC applicator.) When the nuclear medicine technologist inventoried the sources, only 29 were present. The facility located two seeds in a sink and a third in the drain of that sink. The Radiation Safety Officer believes that the seven lost sources are in the sewer system.
"Each seed is 1.2 mCi of Palladium-103."
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Other Nuclear Material | Event Number: 42686 | Rep Org: ADVANTAGE ENGINEERING
Licensee: ADVANTAGE ENGINEERING
Region: 1
City: MECHANICSBURG State: PA
County:
License #: 37-30704
Agreement: N
Docket:
NRC Notified By: DAN SCHAUBLE
HQ OPS Officer: JOE O'HARA | Notification Date: 07/05/2006
Notification Time: 15:12 [ET]
Event Date: 07/01/2006
Event Time: 14:20 [EDT]
Last Update Date: 07/05/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
PAMELA HENDERSON (R1)
ROBERT PIERSON (NMSS)
| Event Text DAMAGED MOISTURE DENSITY GAUGE
A Troxler Model 3411 moisture density gauge was damaged when it was run over by a bulldozer at the Rydal-Waters construction site on Brooke Road in Abington Township, Montgomery County, PA. The gauge was left unattended and uncontrolled while the gauge operator went to retrieve a vehicle to transport the gauge. While left unattended, the gauge was run over by a bulldozer resulting in the gauge being broken and the instrument case being damaged. The sources remained in place in their rods. The rods were placed back inside the gauge, and the gauge was placed back inside its case. Soil surveys resulted in no spread of contamination. Radiation levels taken were not abnormal. There are two sealed sources inside the gauge Cs-137, serial number 40-8387, 5.4 millicuries and Am-241/Be, serial number 47-6341, 38.8 millicuries.
The licensee notified NRC (Sattar Lodhi, Region I ), Troxler, and local authorities: Abington Township Emergency Responders and Montgomery County Emergency Management. The gauge has been removed from the Rydal-Waters site to Advantage Engineering's Allentown, PA. office. Troxler is leak testing the gauge and evaluating a transportation plan to return the gauge to Troxler's corporate location. |
| Power Reactor | Event Number: 42687 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: PHIL SANTINI
HQ OPS Officer: ARLON COSTA | Notification Date: 07/06/2006
Notification Time: 04:25 [ET]
Event Date: 07/06/2006
Event Time: 03:52 [EDT]
Last Update Date: 07/06/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
PAMELA HENDERSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE TO GENERATOR DIFFERENTIAL
"Indian Point Unit 3 tripped on Generator Differential (Direct Generator Trip). Current conditions are stable, mode 3 operation with all automatic actions occurring properly. Steam Generators levels are stable on aux. feed water.
"Unit 2 was unaffected by the trip."
All control rods inserted fully and decay heat is being removed via steam dump to the condenser. All required safety related systems are working properly and the electrical buses and diesel generators are in their normal alignment.
The licensee will notify the NRC Resident Inspector. | |