| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/15/2010 - 04/16/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45826 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: PETER COFER NDE INCORPORATED
Region: 1
City: TAMPA State: FL
County:
License #: 3404-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: CHARLES TEAL | Notification Date: 04/08/2010
Notification Time: 16:33 [ET]
Event Date: 04/08/2010
Event Time: [EDT]
Last Update Date: 04/15/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES TRAPP (R1DO)
BILL VONTILL (FSME)
| Event Text AGREEMENT STATE REPORT - POTENTIAL RADIOGRAPHER OVEREXPOSURE
The following information was received via fax:
"An employee's TLD recorded an overexposure of 6.8 rem. The date was 22 March 2010 when the overexposure occurred. The affected employee claims he left his leather pouch with the TLD [in it] in the exposure area for two shots. His pocket dosimeter reading was also off scale. The RSO originally calculated the employee's dose to be approximately 4 rem which is not required to be reported to the state. The RSO received Landauer's dosimeter report sometime after 22 Mar 2010 which showed a 6.8 rem dose. The licensee contacted Licensing and Materials on 7 April 2010. The Tampa Inspection Office will investigate."
* * * UPDATE FROM STEVE FURNACE TO HOWIE CROUCH @ 1340 EDT ON 4/15/10 * * *
A Florida Department of Health investigator made a site visit on 4/15/10 to investigate the circumstances of the event. After recreating the event, the investigator agrees that the overexposure to the TLD could have only occurred if the employee left his TLD in the test area. Florida considers this case closed.
Notified R1DO (Gray) and FSME EO (McIntosh). |
| General Information or Other | Event Number: 45829 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: JANX INTEGRITY GROUP
Region: 3
City: PARMA State: MI
County:
License #: 03320990002
Agreement: N
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: PETE SNYDER | Notification Date: 04/09/2010
Notification Time: 17:37 [ET]
Event Date: 04/09/2010
Event Time: [EDT]
Last Update Date: 04/15/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HIRONORI PETERSON (R3DO)
BILL VONTILL (FSME)
| Event Text RADIOGRAPHY CAMERA SOURCE NOT FULLY RETRACTED
The following information was received via email:
"Radiographer failed to fully retract Se-75 source into QSA Model 880 camera while on a job site in Stratton, Ohio. No additional information regarding device or source is available at this time.
"Radiographer did not 'bump check' the source after retraction to make sure that the source was locked in the camera. He stated that he was using a survey meter as he approached the camera, but it slipped from his hand during his approach and fell to the ground. He stated that he did not verify proper operation after picking up the meter. He was approaching the camera from the rear and stated that he had not observed any reading on the meter. As the radiographer disconnected the guide tube, he noted that the source cable was still sticking out of the camera with the source. He stated that he turned the crank handle about 3/4 of a turn, at which time the source was retracted. The radiographer stated that he could not hear his alarming rate meter due to loud noise in the power plant where the work was being done. The radiographers pocket dosimeter (0 - 200 Mr) was reported as having gone off-scale.
"The licensee has estimated a whole body exposure of 1.8 R and an extremity dose to the radiographer's hand of between 3 R and 20 R. The licensee has shipped the radiographer's dosimeter for rush processing and expects to have results late Monday (4/12/10) or Tuesday. ODH [Ohio Department of Health] will conduct an investigation.
"NOTE: This report is being made as a precaution until the actual dose received by the radiographer is confirmed."
Ref: OH 2010-013
* * * UPDATE FROM STEPHEN JAMES TO PETE SNYDER AT 0950 ON 4/15/10 * * *
The following information was received via email:
"1. Camera was a QSA Model 880 Delta, S/N D6162.
"2. Source was a QSA Se-75 source, 73 Curies on 4/9/10, S/N 2739.
"3. Extremity exposure was to right hand.
"4. The radiographer's dosimeter was processed and indicated a whole body dose (shallow) dose of 0.563 Rem for April 2010, through April 9, 2010. This is approximately four times higher than the radiographer received in March 2010 (0.147 Rem).
"5. ODH [Ohio Department of Health] will investigate the week of April 19 to recreate event and verify dose estimates and events leading to the exposure.
"NOTE: As of the current information, the exposure received by the radiographer would not require reporting of the event. Final determination will be made upon completion of investigation by ODH."
Notified R3DO (Orth) and FSME (McIntosh). |
| Other Nuclear Material | Event Number: 45842 | Rep Org: INDIANA MICHIGAN POWER
Licensee: AMERICAN ELECTRIC POWER
Region: 3
City: ROCKPORT State: IN
County: SPENCER
License #: GL-704402-14
Agreement: N
Docket:
NRC Notified By: PHILIP C. CASPER
HQ OPS Officer: VINCE KLCO | Notification Date: 04/15/2010
Notification Time: 15:44 [ET]
Event Date: 04/11/2010
Event Time: 09:13 [EDT]
Last Update Date: 04/15/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
STEVE ORTH (R3DO)
JACK FOSTER (FSME)
| Event Text FIRE DAMAGED A DEVICE CONTAINING LICENSED MATERIAL
"On Sunday, April 11, 2010 at approximately 0813 hrs (CST), two of three dust collector ducts failed on Unit 2 at the Rockport coal fired electric power plant. This resulted in the release of boiler gas in excess of 800 F which caused several small fires of combustible equipment and material. Damage included the rubber sheath covering the remote control cable that opens and closes the level indicator, [which contains the licensed material], and is located in a nearby gas recirculation hopper.
"On Wednesday, April 14, 2010 at 1400 hrs (CST), the three (3) shutters on each Unit's level indicators were inspected and found and verified to be in the closed position. The vendor indicates that the estimated shipping date for a replacement is June 18, 2010. An alternative source is being investigated. There was no exposure or injury to any personnel. The adjacent area has been cordoned off and access is restricted. The affected indicator has been tagged in accordance with company energy isolation procedures."
The gas recirculation hopper level indicator device was manufactured by Texas Nuclear (device number 5197; serial number LE/LX 7015; source serial number B2628) containing 100 mCi of CS-137. |
| Power Reactor | Event Number: 45843 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES PIKE
HQ OPS Officer: VINCE KLCO | Notification Date: 04/15/2010
Notification Time: 17:49 [ET]
Event Date: 04/15/2010
Event Time: 15:39 [EDT]
Last Update Date: 04/15/2010 | 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):
GEORGE HOPPER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text UNPLANNED MANUAL REACTOR TRIP
"At 1539 [EDT], Unit 2 was manually tripped due to lifting of the 2B moisture separator reheater relief valve. The Unit commenced a rapid downpower and then a manual reactor trip was initiated at approximately 95% power. All CEA's [control element assemblies] fully inserted on the trip. Auxiliary feedwater automatically initiated on low steam generator level due the 2A steam generator 15% feedwater bypass not opening. No pressurizer power operated relief valves (PORVs) opened. RCS heat removal is now being maintained with auxiliary feedwater and the steam bypass control system. Main feedwater is available. All other systems functioned normally, and the plant is stabilized at normal operating temperature and pressure in Mode 3. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to manual RPS actuation and 10 CFR 50.72(b)(3)(iv)(A) due to auxiliary feedwater system actuation."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45844 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: BRIAN PIGG
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/15/2010
Notification Time: 17:57 [ET]
Event Date: 04/15/2010
Event Time: 11:19 [CDT]
Last Update Date: 04/15/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| 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 HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE DUE TO VOIDING IN DISCHARGE PIPING
"The Unit 2 HPCI [High Pressure Coolant Injection] system was declared inoperable due to failure to meet acceptance criteria for air voiding in the discharge piping. UT [Ultrasonic Testing] inspection identified an air void of approximately 0.515 cubic ft. HPCI remains available and on-line risk remains green.
"The HPCI discharge piping has been vented. Preliminary post venting UT inspections indicate current void volume is less than acceptance criteria. Certified UT inspectors have been dispatched to validate preliminary UT results.
"The event is being reported under 10CFR50.72(b)(3)(v)(D).
"The NRC Senior Resident Inspector has been informed of the event."
The acceptance criteria for voids is less than or equal to 0.052 cubic ft. | |