| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/23/2012 - 10/24/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48409 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: WATCH CITY MUSEUM
Region: 1
City: WALTHAM State: MA
County:
License #: GENERAL
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/16/2012
Notification Time: 11:31 [ET]
Event Date: 09/11/2012
Event Time: [EDT]
Last Update Date: 10/16/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAKE WELLING (R1DO)
FSME EVENTS RESOURCE (E-MA)
| Event Text AGREEMENT STATE- DAMAGED WATCH WITH REMOVABLE RADIUM CONTAMINATION
The following report was received from the Commonwealth of Massachusetts via facsimile:
"During a decommissioning survey of the Watch City Museum, the museum's consultant 'Babcock Services, Inc.' (BSI), discovered an antique radium watch with potential damage. The subject watch, marked '8-Day Watch' was missing the glass face. BSI obtained the following radiological survey results:
- Maximum radiation reading on contact [was] 0.38 mR/hr and
- Alpha plus beta removable contamination smear of 52,767 dpm/100 cm2.
- The estimated Ra-226 activity is less than 1 microCuries
"The 8-Day Watch was removed from the museum, securely wrapped, and placed in a secure container.
"The owner of the 8-Day Watch, 'Charles River Museum of Industry and Innovation', was notified about the condition of the 8-Day Watch. The timepiece owner and the Watch City Museum agreed that the damaged timepiece should be properly disposed as radioactive waste. The 'Watch City Museum' arranged for the disposal of the timepiece with their decommissioning consultant, BSI. The Agency agreed with the disposition of the damaged timepiece.
"The Agency conducted a confirmatory radiological survey of the timepiece display case and the adjacent museum floor. The survey included the display case glass cover (outside and inside surfaces), the display case base, the adjacent floor within 2 feet of the display case, the secured container of the 8-Day Watch, [and] the viewing surface where the timepiece was displayed. [The] inspector observed no readings above background of 10 cpm using an alpha probe. Maximum radiation level at the surface of the time piece container was 0.2 mR/hr using a gamma probe.
"The Agency considers this event to be closed." |
| Agreement State | Event Number: 48411 | Rep Org: NV DIV OF RAD HEALTH
Licensee: 21ST CENTURY ONCOLOGY
Region: 4
City: LAS VEGAS State: NV
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/16/2012
Notification Time: 17:23 [ET]
Event Date: 10/15/2012
Event Time: [PDT]
Last Update Date: 10/16/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
FSME EVENTS RESOURCE (E-MA)
| Event Text AGREEMENT STATE REPORT - DOSE DIFFERENT FROM PRESCRIBED
The following report was received from the Nevada Radiation Control Program via e-mail:
"We would just like to inform you of a medical event.
"Preliminary info: Yesterday (10-15-2012) we received a call from the RSO of 21st Century Oncology, regarding an incident that occurred with their HDR. Due to a faulty ruler, a parameter was entered incorrectly in the HDR control panel, resulting in a dose to the skin of the patient of around 160 centiGray. The skin area was one cubic cm. The intended dose was 160-170 cGy [to a different treatment site].
"The intended target was an almost spherical volume located in the right breast. The skin that was exposed is located in the right breast, at the entrance of the device (multi lumen mammosite) catheter.
"The closest organ is the right lung.
"The patient is fine and was informed of this.
"The sealed source remained inside the tube.
"[The event is] being reported under 10 CFR 35.3045 (a)(3): A dose to the skin or an organ or tissue other than the treatment site that exceeds by 0.5 Sv (50 rem) to an organ or tissue and 50 percent or more of the dose expected from the administration defined in the written directive (excluding, for permanent implants, seeds that were implanted in the correct site but migrated outside the treatment site)."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Non-Agreement State | Event Number: 48412 | Rep Org: HEMLOCK SEMICONDUCTOR CORPORATION
Licensee: HEMLOCK SEMICONDUCTOR CORPORATION
Region: 3
City: HEMLOCK State: MI
County:
License #: 21-32682-01
Agreement: N
Docket:
NRC Notified By: WALLACE MILLETT
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/16/2012
Notification Time: 17:32 [ET]
Event Date: 10/16/2012
Event Time: [EDT]
Last Update Date: 10/16/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
STEVE ORTH (R3DO)
FSME EVENTS RESOURCE (E-MA)
| Event Text PROCESS GAUGE SHUTTER STUCK OPEN
The RSO reported a shutter problem on a fixed mounted process gauge manufactured by Vega Americas (Model SHF-2B) containing an 800 mCi Cs -137 source. The shutter problem was discovered during a semi-annual shutter check when it was determined that the shutter would not close. The shutter is normally always open to support the manufacturing process and the failure to close does not pose any personnel exposure risk. The RSO is following up with a vendor to repair the shutter onsite. |
| Power Reactor | Event Number: 48435 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: BRUCE THOMPSON
HQ OPS Officer: VINCE KLCO | Notification Date: 10/23/2012
Notification Time: 20:59 [ET]
Event Date: 10/23/2012
Event Time: 19:22 [EDT]
Last Update Date: 10/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
RANDY MUSSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text DEGRADED CONDITION DUE TO REACTOR HEAD VESSEL PENETRATION INDICATIONS
"On October 23, 2012, V. C. Summer Station Unit 1 (VCSNS) identified two reactor vessel head penetrations (19 and 52) that did not meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1. The station is in a refueling outage (RF20) and the plant is currently shutdown and in Mode 6. The reactor vessel head (RVH) contains a total of 66 penetrations and inspection efforts are approximately 50% percent complete. There have been no previous repairs to the reactor vessel head penetrations and/or j-groove welds. The indications are not through wall as indicated by volumetric and bare metal visual inspections. The penetrations will be repaired to meet the requirements of 10CFR50.55a prior to returning the vessel head to service.
"The inspection results are reportable pursuant to 10CFR50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified."
The licensee will notify the State of South Carolina and local counties. |
| Power Reactor | Event Number: 48436 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: JONATHAN ALLEN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/24/2012
Notification Time: 02:40 [ET]
Event Date: 10/24/2012
Event Time: 01:47 [EDT]
Last Update Date: 10/24/2012 | 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
OTHER UNSPEC REQMNT
| Person (Organization):
RANDY MUSSER (R2DO)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 99 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL AND DISCOVERY OF AFTER-THE-FACT UNUSUAL EVENT CONDITION
"On 10/24/12 at 0147, North Anna Unit 2 reactor tripped automatically. The reactor first out is the 'C' steam generator lo-lo level. The turbine first out is reactor tripped, turbine trip. The event was apparently initiated by a loss of load on the secondary side. The cause of the loss of load is still being investigated. All systems responded as expected. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) due to actuation of the Reactor Protection System.
"The Auxiliary Feedwater pumps received an automatic start signal due to low-low level in all steam generators at the time of the trip, Steam generator levels have been restored to normal operating level. The Auxiliary Feedwater System operated as designed with no abnormalities noted. This event is reportable per 10 CFR 50.72(b)(3)(iv)(A) due to actuation of an ESF system.
"All control rods inserted into the core at the time of the trip and decay heat is being removed via the main condenser steam dumps. Several secondary [feedwater] relief valves lifted and reseated during the event. North Anna Unit 2 is currently stable at no load temperature and pressure in mode 3.
"At 0147 EDT, the Unit 2 Pressurizer Power Operated Relief Valve (PORV) , 2-RC-PCV-2455C, opened during an automatic reactor trip of Unit 2. The valve indicated open for less than 1 second. During this time, the identified leakage threshold for EAL SU6.1 [25 gpm] was exceeded."
The cause of the loss of secondary load, which is believed to have caused the low steam generator water level and the lifting of the pressurizer PORV, is still under investigation. The licensee is focusing on the high pressure to low pressure turbine intercept valves or reheat valves going shut for reasons unknown at this time. The licensee's data shows that a pressurizer PORV opened momentarily. The instantaneous leak rate exceeded the unusual event threshold leak rate of 25 gpm. The PORV reseated and no ongoing leakage occurred during the transient. The rest of the transient was characterized as uncomplicated. The unit is in a normal post-trip electrical configuration. All systems functioned as required. There was no impact on Unit 1.
The licensee has notified the NRC Resident Inspector. | |