| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/23/2007 - 05/24/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43371 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CONAM INSPECTION AND ENGINEERING, INC.
Region: 4
City: PASADENA State: TX
County:
License #: L05010
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/18/2007
Notification Time: 15:08 [ET]
Event Date: 05/17/2007
Event Time: [CDT]
Last Update Date: 05/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RUSSELL BYWATER (R4)
CYNTHIA FLANNERY (FSME)
| Event Text AGREEMENT STATE REPORT - SUSPECTED RADIATION BADGE OVEREXPOSURE
"The RSO called to notify the Agency that for the April '07 dosimeter report, a reading of 5,131 mrem was assigned to the dosimeter worn by a radiography trainee. This individual is no longer employed by the licensee.
"According to existing radiation reports, the trainee was not actively involved in performing industrial radiography for the said time period. He also claims to have stored his badge in a trailer for at least five days of the month opening a question to deliberate tampering. Radiography with Ir-192 was being performed in the general area but the trainee alleges that his participation was limited to a barricade watch. Other personnel with Conam support this recollection. [The Texas Department of Health Incident Investigation Program] will submit a completed report when the licensee and the Agency complete the investigation."
Event Report ID: 07-43371
Texas Incident No: I-8414 |
| General Information or Other | Event Number: 43372 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: APPLIED GEOTECHNICAL ENGINEERING CONSULTANTS, INC
Region: 4
City: SANDY State: UT
County:
License #: UT-1800298
Agreement: Y
Docket:
NRC Notified By: PHILLIP GRIFFIN
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/18/2007
Notification Time: 16:05 [ET]
Event Date: 05/18/2007
Event Time: [MDT]
Last Update Date: 05/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RUSSELL BYWATER (R4)
CYNTHIA FLANNERY (FSME)
JIM WHITNEY (TAB)
| Event Text AGREEMENT STATE REPORT - LOST & RECOVERED TROXLER GAUGE
An employee of Applied Geotechnical Engineering Consultants was using a Troxler moisture density gauge at a jobsite. He left the gauge on the tailgate of his truck and then drove away. The gauge fell off and was picked up by a member of the public, who in turn called the licensee. The licensee picked up the gauge. The state did not have detailed information concerning the Troxler gauge, however, they did say the sources were in the locked position. Typically the Troxler gauge has sources of Am-241/Be (40 mCi) and Cs-137 (8 mCi). |
| Power Reactor | Event Number: 43381 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TIM BOLAND
HQ OPS Officer: BILL HUFFMAN | Notification Date: 05/24/2007
Notification Time: 04:42 [ET]
Event Date: 05/24/2007
Event Time: 02:11 [CDT]
Last Update Date: 05/24/2007 | 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):
BRIAN BONSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 3 | Startup | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO ELECTRO-HYDRAULIC CONTROL (EHC) SYSTEM LEAK
"On 05/24/2007 at 0211 CDT Browns Ferry Unit 1 initiated a Manual reactor SCRAM due to an Electro-Hydraulic Control (EHC) System pressure lowering and reservoir level lowering due to an EHC system leak. The leak was from #6 Main Turbine Combined Intermediate Valve (CIV). All Systems responded as required to the manual SCRAM signal. No Emergency Core Cooling System (ECCS) initiations occurred as a result of the manual SCRAM signal. Reactor water level was maintained in the normal band during the SCRAM. There were no Primary Containment Isolation signals received during the SCRAM. The EHC leak was stopped due to reservoir level depletion and EHC pumps being secured. There were no indications of main steam relief valves (MSRVs) opening. Reactor pressure is being controlled using Main Steam Line Drains. Reactor Level is being maintained in band using Control Rod Drive pumps. Repair of the EHC leak is in progress."
The Scram was characterized as uncomplicated. All rods fully inserted. The only significant equipment out of service at the time was RCIC. When the leak was initially discovered, it was about 60 drops per minute. When repairs were attempted, the piping separated and approximately 600 gallons of EHC fluid was discharged out the break onto the turbine building floor. Cleanup of the EHC fluid is in progress and environmental monitoring is in place to assure no offsite release of the spill.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43382 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEN McKUNE
HQ OPS Officer: STEVE SANDIN | Notification Date: 05/24/2007
Notification Time: 05:11 [ET]
Event Date: 05/24/2007
Event Time: 02:32 [EDT]
Last Update Date: 05/24/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
EUGENE COBEY (R1)
|
| 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 ON LOW STEAM GENERATOR WATER LEVEL
"This 4-hour notification is being made to report that Salem Unit 2 automatically tripped on low steam generator water level. The automatic trip was preceded by lowering steam generator feed pump suction pressure, followed by the trip of both steam generator feed pumps on low suction pressure. The cause of the low suction pressure was due to a condensate system breach that occurred in the Condensate Polisher building. The condensate polishing system has been isolated and condensate pressure has stabilized.
"Salem Unit 2 is currently in mode 3 with reactor coolant system temperature at 547 degrees with pressure at 2235 psig. 21, 22, and 23 auxiliary feedwater pumps started automatically, as expected, due to the low steam generator level. Decay heat removal is via the steam dumps to the main condenser. All equipment functioned as designed. There were no personnel injuries.
"A 15 minute notification was made to the State of New Jersey due to hydrazine laden water exiting the Condensate Polisher building and entering the storm drainage system."
All control rods fully inserted following the reactor trip. Emergency Diesel Generator are available, if needed. The licensee informed the NRC Resident Inspector. | |