| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/17/2003 - 10/20/2003 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40237 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: WESTERN TECHNOLOGIES, INC.
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ-07-080
Agreement: Y
Docket:
NRC Notified By: AUBREY V. GODWIN
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/09/2003
Notification Time: 18:08 [ET]
Event Date: 10/09/2003
Event Time: 15:00 [MST]
Last Update Date: 10/17/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM JOHNSON (R4)
JOSEPH HOLONICH (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING MOISTURE DENSITY GAUGE VEHICLE ACCIDENT
"At approximately 2:15 PM [MST] October 9, 2003 the Agency was informed by the Licensee that a truck carrying a moisture-density gauge had been involved in a single vehicle accident and the driver is dead. The reporting individual indicated that they were informed of the accident by the Department of Public Safety. The accident occurred on AZ Highway 260 between Bridgeport and Camp Verde. The moisture-density gauge is a Troxler Model 3440, SN 27494. The device contained 40 mCi Be:Am-241 and 8 mCi Cs-137 [mCi=millicuries]. The device remained in the transporting box inside a locked steel box in bed of pick up. The Licensee is trying to retrieve [it] from law enforcement for storage and leak test. [It is] Currently in an impound yard in Mayer, AZ.
"Agency continues to receive information regarding this fatality. The Agency is unaware of any press coverage regarding radioactive materials.
"The U.S. NRC is being notified of this event."
AZ First Notice: 03-19
*****UPDATE ON 10/17/03 AT 13:30 FROM GODWIN TO LAURA*****
"The leak test was negative. It appears the driver was not wearing his seat belt."
Notified NMSS (D. Broaddus) and R4DO (G. SANBORN) |
| Power Reactor | Event Number: 40256 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By:
HQ OPS Officer: RICH LAURA | Notification Date: 10/17/2003
Notification Time: 11:54 [ET]
Event Date: 10/17/2003
Event Time: 09:00 [EDT]
Last Update Date: 10/17/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JAMES CREED (R3)
TERRY REIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM UNANALYZED CONDITION AT DAVIS BESSE
"System Affected : Steam and Feedwater Rupture Control System (SFRCS)
"Actuation / Initiator Affected: Main Steam Line Rupture on Steam Generator
"Effect of event on plant in current Mode - None
"Actions Taken or planned: Declared SFRCS Actuation Channels 1 and 2 inoperable. Will track as a Mode 3 restraint against T.S. 3.3.2.2 (SFRCS Instrumentation). Will resolve, correct and retest prior to entry into Mode 3.
"Discovered SFRCS Logic Channel 1 block upon restoration and repowering after maintenance activities on 10/16/03. After discussions with Engineering Department representatives it has been determined that a design issue exists with the SFRCS system where it would be possible that SFRCS Channels 1 and 2 low pressure trips could be blocked during a scenario where a Main Steam Line Rupture would be followed by a loss of off-site power. This would result in the potential that the OTSG [once through steam generators] with the main steam line rupture would be fed by the AFW system. This requires an 8 hour notification to the NRC per 10CFR50.72(b)(3)(ii)(B)."
The licensee notified the NRC resident inspector. |
| Power Reactor | Event Number: 40258 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHITWOOD
HQ OPS Officer: JOHN MacKINNON | Notification Date: 10/18/2003
Notification Time: 04:04 [ET]
Event Date: 10/18/2003
Event Time: 00:52 [PDT]
Last Update Date: 10/18/2003 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
GARY SANBORN (R4)
MICHAEL JOHNSON (NRR)
DOUG WEAVER (IRO)
BRUCE MALLET (RA)
PAT GWYNN (DRA)
JOHN CRAIG (NRR)
|
| 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 EARTHQUAKE FELT ON SITE. ENTERED EMERGENCY ACTION LEVEL (EAL) 18
"Earthquake felt on plant site measured at 0.02g. Both Units remain at 100%"
State and Local County notified by the licensee.
Unusual Event declared per EAL 18, (greater than 0.01g) . Two jolts several minutes apart were felt in the Control Room. The electrical grid is stable, all Emergency Core Cooling Systems and all Emergency Diesel Generators are fully operable if needed. Licensee will perform walkdowns of the plant to check for any damage. Turbine supervisor system indicated high main turbine bearing vibration on both main turbines (cleared right away) and one of the Unit 1 Accumulator levels alarmed (also cleared right away).
Following information from Earthquake Center located in Colorado: Two earthquakes both magnitude 3.4, located 10 miles Southwest of San Luis Obispo. First earthquake occurred at 0027 PDT and the other earthquake occurred at 0039 PDT.
The NRC Resident Inspector will be notified.
**** Update at 0635EDT on October 18 by Chitwood taken by MacKinnon ****
EAL 18 exited and Unusual Event Classification terminated at 0330 PDT. Walkdown of plant completed with no damage to plant observed. R4D0 (G. Sanborn), HQPAO (Gagner), FEMA (Austin), DHS (V. Cates), DIRO (S. Frant), & (G. Holahan) notified.
NRC Resident Inspector informed by licensee. |
| Power Reactor | Event Number: 40259 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: MIKE RIPLEY | Notification Date: 10/19/2003
Notification Time: 01:13 [ET]
Event Date: 10/18/2003
Event Time: 17:20 [CDT]
Last Update Date: 10/19/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GARY SANBORN (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS OF EMERGENCY ASSESSMENT CAPABILITY
The Wolf Creek Nuclear Plant Information System (NPIS) became unavailable for unknown reasons. Loss of the NPIS affects the Safety Parameter Display System (SPDS). The SPDS forms a significant portion of the Wolf Creek emergency assessment capability. There is no other loss of emergency assessment capability concurrent with this continuing loss of the SPDS. Plant personnel have entered applicable procedures and are taking local readings of equipment normally monitored by the NPIS.
The licensee has notified the NRC Resident Inspector.
* * * * UPDATE FROM DAVE DEES TO MIKE RIPLEY 0842 ET 10/19/03 * * * *
"The SPDS was restored to service at 0621 CDT 10/19/03."
Notified R4DO (G. Sanborn) | |