| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/05/2012 - 07/06/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48050 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: METRO METALS
Region: 4
City: PORTLAND State: OR
County: MULTNOMAH
License #:
Agreement: Y
Docket: 12-0551
NRC Notified By: KEVIN SIEBERT
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/27/2012
Notification Time: 11:30 [ET]
Event Date: 06/25/2012
Event Time: 13:00 [PDT]
Last Update Date: 06/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JEFF CLARK (R4DO)
FSME RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text STATIC ELIMINATOR BAR FOUND IN SCRAP YARD
"[Metro Metals] phoned that a flatbed truck with metal scrap from a recycler in WA (Paymore Recycling & Salvage, Montesano, WA) set off their portal monitor. Hand-held exposure meters were used to survey the load and levels were found at 4000 microrem/hr. This load is waiting for RPS [Radiation Protection Services] to check.
"Responded to Metro Metals. Found a static bar. Wrapped and sent back to recycler. Max reading, with Ludlum 2401 EC, at front edge of bar was 6 mR/hr. Exploranium identified Am-241. Static bar was about 5 to 6 feet in length and was cut in half. Item was wrapped in plastic and placed in a drum for return to the recycler."
Radiation Protection Services No: 12-0020
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State | Event Number: 48054 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: MILLER ENGINEERING & TESTING
Region: 1
City: NORTHBORO State: MA
County:
License #:
Agreement: Y
Docket: 23-4571
NRC Notified By: DOUG CULLEN
HQ OPS Officer: JOE O'HARA | Notification Date: 06/28/2012
Notification Time: 14:18 [ET]
Event Date: 06/28/2012
Event Time: 11:30 [EDT]
Last Update Date: 06/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
ILTAB VIA EMAIL ()
FSME RESOURCE ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text STOLEN NUCLEAR DENSITY GAUGE
The following was received from the Commonwealth of MA. via fax.
"An automobile with a Nuclear Density Gauge stored in its trunk was stolen from a work site in Roslindale, MA. The nuclear density gauge was manufactured by Campbell-Pacific, Model No. MC3, Serial No. M390204846, containing sealed sources of Cs-137 and Am-241, of less than 10 millicuries and 50 millicuries, respectively. The gauge is licensed with the MA Radiation control Program, with Miller Engineering & Testing of Northboro, MA under license No. 23-4571.
"A police report for the stolen property is being filed with the Boston Police.
"Agency [state] continues with the investigation into this matter, and has asked the licensee for a copy of the police report and subsequent findings. Thus, the investigation remains open."
* * * UPDATE FROM DOUG CULLEN TO JOE O'HARA AT 1607 EDT ON 6/28/12 * * *
The Boston Police Department has recovered the stolen vehicle with the gauge intact in the trunk of the vehicle. The radiation profile is normal for the gauge and the police have notified the company to come and recover the gauge.
Notified R1DO (DeFrancisco) and FSME/ILTAB via e-mail
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Power Reactor | Event Number: 48071 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JASON MORGAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 07/05/2012
Notification Time: 17:45 [ET]
Event Date: 07/05/2012
Event Time: 10:00 [EDT]
Last Update Date: 07/05/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
PAMELA HENDERSON (R1DO)
|
| 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 VALVE IMPROPERLY ALIGNED FOR ACCIDENT MITIGATION
"On 7/5/12 at 0307 hrs (EDT), Salem Unit 2 declared 21 Auxiliary Feedwater Pump out of service due to the failure of the 23AF21, Auxiliary Feedwater Flow Control valve to the 23 Steam Generator. 23AF21 had failed to a full open position during performance of the in-service test. Salem Unit 2 entered Technical Specification 3.7.1.2 a, Action Statement a, which requires restoring the pump to operable status within 72 hours, otherwise be in at least Hot Standby within the next 6 hrs and in Hot Shutdown within the following 6 hours.
"At 1000 hrs on 7/5/12, the air supply to the 23AF21 was found isolated. Troubleshooting and repair of the 23AF21 was completed and, following in service testing, the valve was declared operable at 1349 hrs.
"Review of the valve's operability concluded that the failure of the 23AF21 valve to close represented a condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. The Salem UFSAR assumes that during a Category IV Main Steam break accident, a faulted Steam Generator would be identified and Auxiliary Feedwater would be isolated to the affected Steam Generator within 10 minutes. Since the valve was failed open and could not be operated from the control room, the plant would have to manually isolate 23AF21 or trip the 21 Auxiliary Feedwater Pump to ensure feedwater isolation to the affected, faulted Steam Generator. The time to perform manual isolation or tripping of the Auxiliary Feedwater Pump may have required more time than that analyzed by the plant UFSAR.
"This is being reported under 10CFR50.72(b)(3)(v), the nuclear plant being in a condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident.
"There were no other safety related systems affected by this event and there were no injuries associated with this event."
Maintenance was last performed on this system on May 17, 2012.
The licensee will notify the NRC Resident Inspector and Lower Alloways Creek Township. |
| Power Reactor | Event Number: 48072 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: WILLIAM STANG
HQ OPS Officer: HOWIE CROUCH | Notification Date: 07/05/2012
Notification Time: 21:24 [ET]
Event Date: 07/05/2012
Event Time: 12:58 [CDT]
Last Update Date: 07/05/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ROBERT DALEY (R3DO)
|
| 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 UNANALYZED CONDITION DUE TO BLOCKING BOTH REACTOR BUILDING RAILROAD BAY DOORS
"At 1258 CDT on 07/05/2012, Operations was notified that both panels of Door 45 (south doors for the reactor building railroad bay airlock) were blocked by a man lift. Blocking both doors represents an unanalyzed condition as a flow path through the door is assumed for pressure relief during postulated HELB events. The man lift was immediately removed correcting the situation and all work related to Door 45 was stopped. Door 45 was blocked for approximately 20 minutes.
"The NRC Resident Inspector has been notified." | |