| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/24/2009 - 08/25/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45275 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: CENTURA HEALTH PENROSE - ST. FRANCIS HEALTH SERVICES
Region: 4
City: COLORADO SPRINGS State: CO
County: EL PASO
License #: 197-02
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: KARL DIEDERICH | Notification Date: 08/19/2009
Notification Time: 15:10 [ET]
Event Date: 08/06/2009
Event Time: [MDT]
Last Update Date: 08/19/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM JONES (R4DO)
LARRY CAMPER (FSME)
| Event Text AGREEMENT STATE REPORT - MEDICAL DOSE DIFFERENT THAN PRESCRIBED
The following was received from the state via e-mail:
"This incident was reported by a medical licensee (Centura Health Penrose - St. Francis Health Services License # 197-02) on 08/06/2009.
"On 22 July 2009, at patient at Penrose Hospital was implanted with 70 Palladium-103 seeds, 2.5 U each on that day. The application was via a Mick applicator, using intra-operative planning with a Variseed planning system. It was noted on the C arm film taken at the completion of the implant that there was some clumping of the seeds in groups. A post implant CT scan was done on 23 July 2009. The results of the computerized dosimetry plan was evaluated on the 5 August 2009 and it was determined that the prostate gland was under dosed, receiving a dose to 90% of the prostate volume (D90) of 36.6% of the prescribed 125 Gy. The AU [Authorized User] written directive listed an expected range of D90 to be 90% to 135%. The discrepancy between actual dose and prescribed falls outside of the 20% tolerance for delivered dose according to [Colorado State Regulation] RH 7.21.1.1 (1). A full report is expected from the licensee within 30 days."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| General Information or Other | Event Number: 45276 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: SUNCOR ENERGY
Region: 4
City: DENVER State: CO
County: DENVER
License #: 615-02
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: KARL DIEDERICH | Notification Date: 08/19/2009
Notification Time: 15:43 [ET]
Event Date: 08/19/2009
Event Time: [MDT]
Last Update Date: 08/19/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM JONES (R4DO)
LARRY CAMPER (FSME)
| Event Text AGREEMENT STATE REPORT - FLOW GAUGE SHUTTER UNABLE TO CLOSE
The following report was received from the state via e-mail:
"A Colorado Specific licensee, Suncor Energy (USA) Inc. (License # 615-02), reported that a fixed nuclear gauge was having shutter problems. The shutter was unable to be returned to a closed position during a routine check. The gauge is an Ohmart Vega Model SH-F2 containing 250 mCi of Cs-137 (serial number M-7105). The licensee plans to have a Ohmart Vega Technician on site within the next few weeks to take a look at the gauge and determine whether or not the gauge can be fixed or [if] it needs to be replaced."
The gauge is a flow gauge on a pipe in an oil refinery, and the shutter is normally open during facility operation. The radiological control area is normally maintained in force during operations, and remains in force. No inadvertent exposures are expected to have occurred. |
| Power Reactor | Event Number: 45285 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MIKE MacLENNAN
HQ OPS Officer: VINCE KLCO | Notification Date: 08/24/2009
Notification Time: 04:06 [ET]
Event Date: 08/24/2009
Event Time: 02:40 [CDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JOHN GIESSNER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TSC AIR FILTRATION SYSTEM INOPERABLE DUE TO PLANNED MAINTENANCE
"Planned maintenance activities will commence today (August 24, 2009) on the Quad Cities Station Technical Support Center (TSC) ventilation air filtration system. The maintenance will be completed in approximately 36 hours, and is scheduled to be worked continuously to minimize out-of-service time.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing procedures; contingency plans are in place to expeditiously restore the TSC ventilation to an operable status. If TSC evacuation is warranted due to radiological conditions, the facility will be relocated in accordance with existing procedures.
"This event is reportable per 10CFR50.72(b)(3)(xiii) since the scheduled maintenance affects an emergency response facility.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 45286 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: JOSHUA MORSE
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/24/2009
Notification Time: 12:48 [ET]
Event Date: 08/24/2009
Event Time: 11:00 [EDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL TRIP DUE TO LOSS OF POWER TO CONTROL RODS
"Following completion of surveillance testing for the electrical checks of the Control Rod Drive power train, the operating crew observed that Group 7 regulating control rods unexpectedly lost power and inserted into the core. The Operators manually tripped the reactor prior to exceeding any RPS trip set point. There were no other safety system actuations and the plant is stable at normal post-trip temperature and pressure."
There are seven rods in Group 7. Operators tripped the unit within 7 seconds.
All rods fully inserted on the trip. The plant is removing decay heat through the main condenser and feeding generators with auxiliary feed.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45287 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: PETE SNYDER | Notification Date: 08/24/2009
Notification Time: 13:01 [ET]
Event Date: 08/24/2009
Event Time: 09:00 [EDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STEVE ORTH (R3DO)
|
| 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 EOF BACKUP DIESEL FAILURE AND EOF OUTAGE
"On August 24, 2009 at 0900 EDT the Fermi 2 Emergency Operations Facility (EOF) was declared unavailable due to failure of the EOF backup diesel generator to start during weekly testing. Fermi 2 is making this notification in accordance with 10 CFR 50.72(b)(3)(xiii). In the event that EOF activation is necessary, the alternate EOF will be utilized. Activation and use of the alternate EOF is included in Fermi's Radiological Emergency Response Preparedness Plan. The alternate EOF has been verified available. Investigation into the failure of the EOF backup diesel generator start failure is in progress. Fermi will notify the NRC when EOF availability is restored. "
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45289 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JASON MURPHY
HQ OPS Officer: PETE SNYDER | Notification Date: 08/24/2009
Notification Time: 21:21 [ET]
Event Date: 08/24/2009
Event Time: 14:15 [EDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JOHN WHITE (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 95 | Power Operation | 95 | Power Operation | Event Text STATION SAFETY GRADE PNEUMATIC SUPPLY ISSUE
"This event is being reported pursuant to the requirements of 10 CFR 50.72(b)(3)(v) as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of systems supplied by the station safety-grade pneumatic supply. The systems affected include the primary containment isolation valves (i.e., large primary containment isolation valve boot seals) and the reactor-building to suppression pool vacuum breakers.
"On 8/24/09 at 1330, while troubleshooting the receipt of unexpected alarms during containment valve stroking the previous week, Exelon personnel discovered a valve closed instead of the expected open position. Licensed personnel concluded at 1415 that the out of position valve was restricting the Containment Atmospheric Dilution tank from supplying operating nitrogen to the Safety Grade Instrument Gas (SGIG) system headers for Peach Bottom Units 2 and 3. The valve was re-opened at 1445 (within the one hour action time required by Technical Specifications) and other system valves were verified to be in the required positions."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45290 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOE BENNETT
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/24/2009
Notification Time: 23:38 [ET]
Event Date: 08/24/2009
Event Time: 18:50 [CDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text CONDENSATE BOOSTER PUMP TRIP RESULTING IN A MANUAL REACTOR SCRAM
"On 8/24/09, at 18:50 Unit 3 was manually scrammed due to loss of 2 of the 3 Condensate Booster Pumps due to low pump suction pressure. The cause for the Condensate Booster Pump low suction pressures is unknown at this time, but is under investigation. After the reactor was scrammed manually, reactor water level lowered below the automatic scram set point (+2 inches) and below the automatic start for HPCI and RCIC (-45 inches). All expected Primary and Secondary Containment isolation valves operated as required, isolation groups 2,3,6 and 8 were actuated. Both reactor recirculation pumps tripped due to the low reactor water level. HPCI and RCIC actuated as expected to restore reactor water level. Reactor pressure control was maintained on the turbine bypass valves, and no Main Steam Relief Valves (MSRVs) were opened as a result of the transient.
"At this time the unit is stable in mode 3. Reactor water level is being controlled using one Reactor Feedwater pump, HPCI and RCIC have been returned to standby readiness. The 3B Reactor Recirculation Pump has been returned to service. Reactor pressure is being automatically maintained by the main turbine bypass valves.
"This event is reportable as a 4 hour non-emergency report due to 10CFR 50.72(b)(2)(iv)(A) and (B) (ECCS discharge to the reactor and Reactor Protection System (RPS) actuation) and as an 8 hour non-emergency report due to 10CFR50.72(b)(3)(iv)(A) (specified system actuations)."
All rods fully inserted on the SCRAM. The plant is in its normal shutdown lineup.
The licensee notified the NRC Resident Inspector. | |