| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/11/2004 - 06/14/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40796 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: WALTER O. BOSWELL HOSPITAL
Region: 4
City: SUN CITY WEST State: AZ
County:
License #: AZ-07-138
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: CHAUNCEY GOULD | Notification Date: 06/08/2004
Notification Time: 12:33 [ET]
Event Date: 06/04/2004
Event Time: 13:00 [MST]
Last Update Date: 06/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
LINDA PSYK (NMSS)
| Event Text ARIZONA STATE LICENSEE REPORTED A MISSING I-125 SEED
The State of Arizona has been informed of a missing source by two State Licensees (Walter O. Boswell Hospital lic # AZ-07-138 and Amersham Health lic # AZ-07-346). The missing source is an Iodine-125 seed containing 0.225 millicuries of Iodine-125. The seed was loaded into a shipping container by two employees of Licensee 1. Both employees independently described and certified the loading of the seed into the shipping container. Licensee 2 received the package but did not locate the seed that was supposed to be inside. This is information from the 30 day report, pursuant to Arizona rules equivalent to 10CFR20.2201(a)(ii). The seed was first detected missing April, 18, 2004.
The Agency has opened an active investigation into the circumstances of the loss of this seed. Initial surveys at each Licensee failed to locate the missing seed. |
| General Information or Other | Event Number: 40799 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: MATERIALS TESTING OF ARKANSAS
Region: 4
City: CONWAY State: AR
County:
License #: ARK859BP03-02
Agreement: Y
Docket:
NRC Notified By: JARED THOMPSON
HQ OPS Officer: MIKE RIPLEY | Notification Date: 06/09/2004
Notification Time: 11:54 [ET]
Event Date: 06/08/2004
Event Time: 19:00 [CDT]
Last Update Date: 06/09/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
CHARLES MILLER (NMSS)
| Event Text ARKANSAS AGREEMENT STATE REPORT - MISSING AND THEN FOUND MOISTURE DENSITY GAUGE
The following information was provided via email:
"At 7:00 p.m., June 8, 2004, Materials Testing of Arkansas, Inc., Arkansas Radioactive Materials License Number ARK-859-BP-03-02, notified the Arkansas Department of Health, of a missing Troxler Electronic Laboratories, Inc., Model 3430 moisture density gauge, serial number 26636, containing 44 millicuries of Americium-241: Berylium, and 9 millicuries of Cesium-137. The licensee stated that the gauge had fallen out of the truck during transport from a job site in Conway, Arkansas.
"The Conway Police Department, Faulkner County Sheriff's Office, Arkansas State Police and the Arkansas Department of Emergency Management were notified.
"At 7:00 a.m., June 9, 2004, Materials Testing of Arkansas, Inc. reported the gauge had been recovered and was being returned to the storage location. The gauge was recovered by another Arkansas Radioactive Material Licensee who secured the gauge overnight. The gauge does not appear to have been tampered with or damaged.
"The Department is investigating the incident and will provide follow-up information upon receipt of the licensee's formal notification report." |
| General Information or Other | Event Number: 40800 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: GEOTECH
Region: 1
City: Rayham State: MA
County:
License #: UNKNOWN
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: MIKE RIPLEY | Notification Date: 06/09/2004
Notification Time: 14:43 [ET]
Event Date: 06/08/2004
Event Time: [EDT]
Last Update Date: 06/09/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTOPHER CAHILL (R1)
LINDA PSYK-GERSEY (NMSS)
| Event Text MASSACHUSETTS AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
On the afternoon of 06/08/04, a Troxler moisture density gauge (model/serial number not yet known) was run over by a pickup truck at a construction site in Rayham, MA. The source rod was detached but not bent. The area was cordoned off and the licensee RSO was notified. The RSO arrived, positioned the source rod back into the gauge, secured the gauge and performed a radiological survey with negative results. The results of a source leak test are pending. |
| Power Reactor | Event Number: 40804 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BRAD BROWN
HQ OPS Officer: ARLON COSTA | Notification Date: 06/10/2004
Notification Time: 16:11 [ET]
Event Date: 06/10/2004
Event Time: 13:13 [EDT]
Last Update Date: 06/11/2004 | 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):
MARK LESSER (R2)
BILL BATEMAN (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP WHILE PERFORMING SCHEDULED SOLID STATE PROTECTION TESTING
A Unit 2 automatic reactor trip occurred while the licensee was performing planned periodic testing on train "A" solid state protection. All control rods fully inserted into the reactor core. The Auxiliary Feedwater Pumps automatically started as expected immediately following the reactor trip due to low-low level in the steam generators. The unit is being maintained stable in mode 3 and heat sink is being performed via steam dump to the condensers. All other systems functioned as required. The cause of the reactor trip is under investigation.
The licensee notified the NRC Resident Inspector.
*** UPDATE ON 6/11/04 AT 12:23 EDT FROM B. BROWN TO A. COSTA * * *
"This is an update to event notification 40804. At 1313 hours on June 10, 2004, North Anna Unit 2 experienced an automatic trip from 100 percent during the performance of 2-PT-36.1A (Train 'A' Reactor Protection and ESF Logic Actuation Logic Test). The cause of the reactor trip, was determined to be an incorrect configuration of the cell switch (52h contract) on 'A' Reactor Bypass Breaker, 2-EP-BKR-BYA. The incorrect cell switch configuration resulted in a turbine trip signal being generated during testing which resulted in a reactor trip signal being generated in the 'B' train Reactor Protection System. The Auxiliary Feedwater System actuated in response to the event.
"Control room personnel responded to the event in accordance with emergency procedure E-0, Reactor Trip or Safety Injection. The control room team stabilized the plant using ES-0.1 Reactor Trip recovery. The lowest Reactor Coolant System (RCS) pressure during the event was 1988 psig and the lowest RCS temperature was 549 degrees. No human performance issues were identified during this event.
"A non-emergency four-hour report was made to the NRC operations center at 1611 hours pursuant to 10CFR50.72(b)(2)(iv)(B) for an actuation of the Reactor Protection System while critical. An eight-hour report was also made to the NRC in accordance with 10CFR 50.72(b)(3)(iv)(A) due to the Auxiliary Feedwater Pump starts (Engineering Safety Features Actuation). The Reactor Protection System, AMSAC [ATWAS Mitigating System Actuation Circuit], and the Auxiliary Feedwater System operated properly in response to the event. During the Unit 2 reactor trip, a blown output fuse on a logic card (that feeds the permissive for arming the Steam Dumps from loss of load) prevented the Main Steam Dump Valves from opening in Tavg Mode as expected. The Steam Generator Power Operated Relief Valves (PORVs) lifted and operated to control RCS temperature until transferring Steam Dump control to the Steam Pressure Mode. The fuse was replaced.
"A post trip review was conducted at 1500 hours on June 10, 2004. The cell switches on the Reactor Trip Bypass breakers have been repaired and post maintenance testing has been completed. Management approval was granted to start-up Unit 2. North Anna Unit 2 is currently in Mode 1 and is preparing to be placed on-line."
The licensee notified the NRC Resident Inspector.
Notified R2DO (Lesser) and NRR EO (Bateman). |
| Power Reactor | Event Number: 40806 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD DeSANCTIS
HQ OPS Officer: ARLON COSTA | Notification Date: 06/11/2004
Notification Time: 12:58 [ET]
Event Date: 04/12/2004
Event Time: 15:43 [EDT]
Last Update Date: 06/11/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
CHRISTOPHER CAHILL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text 60-DAY NOTIFICATION OF INVALID ACTUATION OF SAFETY INJECTION SIGNAL
"On April 12, 2004, Salem station made an 8 hr report titled ACCIDENT MITIGATION - COMMON CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM per 10 CFR 50.72(b)(3)(v) (Event number 40670). This report was the result of an invalid Unit 1 Safety Injection signal during troubleshooting/testing of Train 'B' of Solid State Protection. During the troubleshooting a card was moved from one slot to another, when the card was inserted into the new slot a safety injection signal was generated. The failed part of the card (a malfunctioning isolator card) was not used in its prior position, thus the failed circuit remained undetected.
"Further investigation determined that the safety injection signal was invalid; it was not the result of a plant condition requiring the protective action. Therefore this event is not reportable per 10CFR50.72(b)(3)(iv)(A) 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' This event is reportable as it 60-day phone call in accordance with 10CFR50.73(a)(2)(iv)(A)(1) 'Any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of this section, except when: (1) The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; or (2) The actuation was invalid..'
"Licensee event report 311/04-003 is being submitted to report the loss of accident mitigation capability for Unit 2. Event number for reference 40670."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40808 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: GEORGE VOISHNIS
HQ OPS Officer: ARLON COSTA | Notification Date: 06/11/2004
Notification Time: 16:01 [ET]
Event Date: 06/11/2004
Event Time: 15:10 [EDT]
Last Update Date: 06/11/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
CHRISTOPHER CAHILL (R1)
|
| 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 OFFSITE NOTIFICATION OF OIL LADEN WATER INTO STORM DRAIN
Oil was spilled on the asphalt in the Protected Area and was cleaned up. Recent rains pulled out the percolated oil laden water which entered the storm drain. Less than one gallon of oil entered the storm drain. The source of the oil spill (possibly from a vehicle) is under investigation.
The licensee notified the NJ Department of Environmental Protection, National Response Center, Environmental Protection Agency and the U.S. NRC Resident Inspector. |
| General Information or Other | Event Number: 40809 | Rep Org: GARDIAN AUTOMOTIVE INC
Licensee:
Region: 3
City: EVANSVILLE State: IN
County:
License #: NY 13911811
Agreement: N
Docket:
NRC Notified By: MARK BERTRAM
HQ OPS Officer: GERRY WAIG | Notification Date: 06/11/2004
Notification Time: 15:54 [ET]
Event Date: 06/11/2004
Event Time: [CST]
Last Update Date: 06/11/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
MICHAEL PARKER (R3)
CHRISTOPHER CAHILL (R1)
JOHN GREEVES (NMSS)
| Event Text LOST OR STOLEN POLONIUM - 210 STATIC ELIMINATOR
On 6/11/04 a Polonium - 210 static eliminator source was reported missing by the user of the source in Indiana. The source is 1.3 millicurie (current activity determined by the licensee, NRD) and was last used on 5/13/04 in a paint spray application. The source was received by the user on 5/15/03. The user has reviewed the "tracking form" and has interviewed employees in an unsuccessful effort to locate the source. The user notified the source licensee, NRD, 2937 Alt Ave, PO Box 310, Grand Island, NY 14072 of the missing source on 6/11/04. The user has implemented a once-per-shift verification check sheet to maintain accountability of their other static sources. |
| Power Reactor | Event Number: 40811 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: AMY MONROE
HQ OPS Officer: MIKE RIPLEY | Notification Date: 06/13/2004
Notification Time: 02:23 [ET]
Event Date: 06/12/2004
Event Time: 20:29 [EDT]
Last Update Date: 06/13/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
MARK LESSER (R2)
|
| 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 EMERGENCY DIESEL STARTED AND LOADED ON BUS UNDERVOLTAGE SIGNAL
"At 2029 on 6/12/2004, the normal incoming feed (1DA) to the plant opened on an undervoltage signal. At the time of the event a severe thunderstorm was in progress. The 'A' Emergency Diesel Generator started and loads sequenced on as designed. The 'A' Residual Heat Removal pump started but did not inject any water into the Reactor Coolant System. The 'A' Emergency Feedwater Pump started and ran for approximately seven minutes. Other plant equipment also responded as expected.
"The plant transferred back to offsite power at 2252. A follow-up LER will be provide in 60 days."
The licensee notified the NRC Resident Inspector. | |