| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/07/2008 - 04/08/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44116 | Rep Org: NV DIV OF RAD HEALTH
Licensee: APEX TESTING COMPANY
Region: 4
City: LAS VEGAS State: NV
County: CLARK
License #: 00-11-0598-01
Agreement: Y
Docket:
NRC Notified By: KAREN BECKLEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/02/2008
Notification Time: 15:21 [ET]
Event Date: 04/02/2008
Event Time: 04:30 [PDT]
Last Update Date: 04/02/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RYAN LANTZ (R4)
GREG MORELL (FSME)
ILTAB via email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT INVOLVING STOLEN TROXLER MOISTURE DENSITY GAUGE
On 04/02/08 at 0400 PDT, the Authorized Gauge User checked out a Troxler Model #3440, S/N 30441, from his company and was enroute to the jobsite when he received a call that the job was cancelled. He went home to have breakfast at 0430 PDT. At 0500 PDT, he found that the chains securing the device for transport had been cut and the gauge was missing from the transport vehicle parked at the users home.
The gauge contains two sources: 9 mCi Cs-137 and 44 mCi Am-241:Be. The last leak test was performed on 03/04/08. The licensee notified the Nevada Highway Patrol and Las Vegas Metro Police of the theft. A contributing factor to the theft may have been the lack of two tangible barriers securing the gauge.
NV Event Report ID No.: NV-NV080002
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. |
| Power Reactor | Event Number: 44121 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: DAVID BALFOUR
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/06/2008
Notification Time: 14:13 [ET]
Event Date: 04/06/2008
Event Time: 13:17 [EDT]
Last Update Date: 04/07/2008 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
SAM HANSELL (R1)
THEODORE QUAY (NRR)
JIM DYER (NRR)
JEFFREY CRUZ (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text UNUSUAL EVENT FROM REACTOR COOLANT SYSTEM LEAKAGE
Millstone unit 2 entered a refueling outage on 4/6/2008. The plant was in the process of placing shutdown cooling in service when at 1236 a 10-15 gpm leak was detected by decreasing pressurizer level. The release path was determined to be from the Reactor Coolant System (RCS) to the Refueling Water Storage Tank (RWST). Pressurizer level is stable and RWST level is rising slowly. Two charging pumps are available for RCS makeup. Decay heat is being removed with Atmospheric Dump Valves. The vent line on the RWST does not contain a radiation monitor and this is an potential unmonitored radiation release path.
The Unusual Event was declared at 1317. The leak was terminated at 1320. Monitoring of the potential release path commenced at 1610.
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 4/6/2008 AT 1910 FROM WAYNE GAMMON TO MARK ABRAMOVITZ * * *
"The leak path has been isolated by closing the two air operated ECCS recirc header stops 2-SI-659/660."
The Unusual Event was terminated at 1856 and the NRC exited "monitoring mode" at 1920.
Notified IRD (Cruz), NRR EO (Quay), and R1DO (Hansell).
EPA Incident Report Number: 867171
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 4/07/08 @ 1110 EDT FROM JIM KUNZE TO HOWIE CROUCH * * *
"Upon further review, the times that the RCS leak occurred and was isolated require correction. The RCS leak occurred at 1243 when valve 2-SI-651 was opened to place shutdown cooling in service. The leak was terminated at 1356 when valve 2-Sl-659 was closed.
"The NRC Sr. Resident Inspector has been notified."
Notified R1DO (Conte). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 44122 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/07/2008
Notification Time: 05:11 [ET]
Event Date: 04/07/2008
Event Time: 04:30 [EDT]
Last Update Date: 04/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (R3)
|
| 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 | Event Text TECHNICAL SUPPORT CENTER MAY BECOME UNINHABITABLE DUE TO SCHEDULED MAINTENANCE
"At 04:30 hours on Monday, April 7, 2008, the Cook Nuclear Plant (CNP) removed the Technical Support Center [TSC] Heating Ventilation Air Conditioning [HVAC] System from service for planned maintenance. The TSC HVAC system will remain out of service for a period of approximately three days.
"Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"This notification is being made in accordance with NUREG 1022 as a potential unavailability of an emergency response facility in accordance with 10 CFR 50.72 (b)(3)(xiii).
"The licensee notified the NRC Resident Inspector. The licensee will supplement this notification upon returning the TSC HVAC system to normal operational status."
* * * UPDATE PROVIDED AT 1329 ON 04/07/08 BY RICHARD HACKMAN TO JEFF ROTTON * * *
The following information was provided by the licensee to RETRACT the event:
"Upon additional evaluation CNP determined that the planned maintenance reported above was limited in scope and did not remove the entire TSC HVAC system from service. The planned maintenance resulted in two of three fully redundant air chillers (air conditioners) being removed from service for maintenance. The third chiller and the TSC HVAC system is operable and remains in service. Therefore, the CNP TSC has been maintained in a configuration that ensures habitability.
"The NRC Resident Inspector has been notified of the retraction."
Notified R3DO (Skokowski). |
| Power Reactor | Event Number: 44123 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/07/2008
Notification Time: 12:06 [ET]
Event Date: 04/07/2008
Event Time: 10:33 [CDT]
Last Update Date: 04/07/2008 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
RYAN LANTZ (R4)
ELMO COLLINS (RA)
JIM WIGGINS (NRR)
JEFF CRUZ (IRD)
MJ ROSS-LEE (NRR)
ED HOISINGTON (DHS)
KEVIN BISCOE (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text UNUSUAL EVENT - LOSS OF OFF-SITE POWER WHILE DEFUELED
At 1020 CDT on 4/7/08 a loss of off-site power was experienced due to maintenance work in the switch yard. At 1033 CDT the licensee declared an Unusual Event. Presently, off-site power is in the process of being restored . The "B" Emergency Diesel Generator is running and loaded, while the "A" Emergency Diesel Generator and "A" bus is tagged out of service for maintenance. The Essential Service Water system developed a leak in the end bell of a cooling unit, which in turn caused licensee to secure control room cooling. This put the licensee in LCO 3.7. The plant is currently defueled. Spent fuel pool cooling has been reestablished.
The licensee notified the NRC Resident Inspector. Licensee will be contacting other state, local, and government agencies, and will be issuing a press release.
* * * UPDATE PROVIDED AT 1406 EDT ON 04/07/08 FROM JEFF ISCH TO JEFF ROTTON * * *
At 1250 CDT, normal off-site power was restored to NB02 and the Unusual Event was terminated. The "B" Emergency Diesel Generator was secured and placed in standby. The licensee has notified the state and local emergency response organizations and will be notifying the NRC Resident Inspector.
Notified R4DO(Lantz), NRREO (Ross-Lee), IRD (Cruz), DHS (Akers), and FEMA (Biscoe). |
| Power Reactor | Event Number: 44124 | Facility: RANCHO SECO
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP
NRC Notified By: STEVE REDEKER
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/07/2008
Notification Time: 18:41 [ET]
Event Date: 04/05/2008
Event Time: 11:40 [PDT]
Last Update Date: 04/07/2008 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
RYAN LANTZ (R4)
THEODORE QUAY (NRR)
JEFFREY CRUZ (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Decommissioned | 0 | Decommissioned | Event Text UNUSUAL EVENT REPORTED AFTER-THE- FACT DUE TO A FIRE ONSITE
"Rancho Seco is a defueled reactor. All fuel is in the Rancho Seco ISFSI.
"During decommissioning operations in the reactor building, a debris fire occurred while the contractor was cutting rebar during the removal of interior concrete. Assorted trash and combustible materials were ignited.
"The building was evacuated per procedures and onsite SMUD staff and contractors brought the fire under control utilizing available fire suppression equipment after several minutes and the fire was deemed extinguished at 1340 hours, 4/5/08.
"No injuries occurred.
"All weekend work operations were ceased and a fire watch was established. A review of the incident occurred and measures to prevent future fires were employed.
"Decommissioning work resumed Monday, 4/7/08. As part of the After Action Review it was determined official notification to response and regulatory agencies still needed to be made.
"No detectable airborne contamination occurred.
"No contaminated personnel occurred."
The fire was detected in destruction debris under a pile of concrete rubble in the reactor building. The fire was initially extinguished at 1045 PDT by onsite personnel. The fire reflashed two additional times and was extinguished until it was determined to by completely extinguished at 1340 PDT on 04/05/08 and the licensee terminated the Unusual Event. The event was declared and logged by the ISFSI Technician on 04/05/08, who is also the onsite Emergency Coordinator when an emergency is declared. It was discovered on the morning of 04/07/08 that the emergency declaration was made and logged on 04/05/08 at 1140 PDT, but no offsite regulatory notifications had been made.
The licensee notified the local NRC Inspector (Garcia) and Region 4 (Keller). The licensee will be notifying the state and local emergency response organizations. |
| Power Reactor | Event Number: 44125 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CHUCK OLSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/07/2008
Notification Time: 20:44 [ET]
Event Date: 04/07/2008
Event Time: 13:45 [CDT]
Last Update Date: 04/07/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RYAN LANTZ (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text CORE ELEMENT ASSEMBLY CALCULATORS DECLARED INOPERABLE
"On 4/7/2008, at approximately 1345 CDT, with ANO-2 in Mode 3 (Hot Shutdown) at normal operating temperature and pressure, and with all control element assemblies (CEAs) withdrawn approximately 2 stops, the Control Room was notified by the Computer Support Group (CSG) that the software verification for CEAC1 and CEAC2 (Core Element Assembly Calculators) had not been verified. Both CEAC's were declared inoperable. The Reed Switch Position Indicators (CEA positions) are considered inoperable if the CEAC's are inoperable. Tech Spec 3.1.3.3 requires at least one of these position indicators be operable in Modes 3 through 5 for each CEA not fully inserted. All CEAs were approximately 2 steps withdrawn from fully inserted during plant heatup to clear the rod bottom indications in preparations for CEA Drop Time Testing. At 1350 the reactor trip breakers were opened and CEA's were verified to be fully inserted to meet the Action Statement for Tech Spec 3.1.3.3. Note that no actual position indication was lost, nor did the CEAC show any signs of malfunction. The software verifications have been completed by the CSG."
The licensee notified the NRC Resident Inspector. The licensee also notified the state. | |