| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/01/2012 - 06/04/2012 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 47958 | Rep Org: DOW CORNING
Licensee: DOW CORNING, MIDLAND PLANT
Region: 3
City: MIDLAND State: MI
County:
License #: 21-08362-12
Agreement: N
Docket:
NRC Notified By: MIKE WHELTON
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/24/2012
Notification Time: 15:29 [ET]
Event Date: 05/24/2012
Event Time: 14:00 [EDT]
Last Update Date: 05/24/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DAVID HILLS (R3DO)
DEBORAH JACKSON (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text DENSITY GAUGE SHUTTER FAILURE
During a routine bi-annual periodic inspection, a density gauge with a 4 milliCurie Cs-137 source was identified to have a stuck shutter. The gauge was an Ohmart Vega Model SHF1-A, S/N 0964C0. The instrument is permanently installed in an isolated tower area, and this event did not result in exposure to any personnel. The licensee plans on having the gauge repaired by the manufacturer.
The licensee notified R3 (Bramnik).
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: 47961 | Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: BRUKER AXS HANDHELD INC
Region: 4
City: KENNEWICK State: WA
County:
License #: WN-I0282-1
Agreement: Y
Docket:
NRC Notified By: CRAIG LAWRENCE
HQ OPS Officer: JOE O'HARA | Notification Date: 05/24/2012
Notification Time: 19:04 [ET]
Event Date: 05/23/2012
Event Time: [PDT]
Last Update Date: 05/25/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
DEBORAH JACKSON (FSME)
| Event Text AGREEMENT STATE REPORT - MANUFACTURER RECEIVED AN ANALYZER WITH AN OPEN SHUTTER
The following was reported from the state via e-mail:
"A Kennewick licensee who manufactures and distributes hand-held devices used to analyze metal alloys notified the Materials Section of an incident that occurred with one of their General License customers in California. The shutter in the device which shields the radioactive material remained in the open position even after disengaging the trigger mechanism to close the shutter. This allowed radiation to stream from the device unabated. The California customer packaged the device for shipping knowing the shutter was open with nothing shielding the radiation and sent it back to the manufacturer in Kennewick for repairs. When the manufacturer received the device, a radiation reading in excess of the package limitations was noted and promptly reported to us. The licensee informed us this is the first shutter malfunction ever for this device model, which has been in service without any similar problems for many years. The Materials staff is working with the licensee to identify compliance issues and to prevent recurrence."
The Bruker AXS hand held XRF analyzer contains 5.9 milliCuries of Co-57.
Incident Number WA-12-037
* * * UPDATE FROM CRAIG LAWRENCE (VIA EMAIL) TO HOWIE CROUCH AT 1125 EDT ON 5/25/12 * * *
The XRF device is owned by Benchmark Environmental. Benchmark Environmental shipped the device to Bruker on May 22, 2012.
"Based on the dose rate measurement taken by Bruker prior to opening the package and removing the instrument, the Washington State Department of Health doesn't believe there were exposures to any member of the public in excess of regulatory limits. A dose rate measurement at 3 feet was 0.3 mR/hr as measured by their Bicron Surveyor 50 (cal date 1/19/12). Reading at approximately six inches from the surface pegged the dose rate meter on the 0 to 0.5 mR/hour scale. Bruker did not take measurements on higher scales.
"At that point, Bruker's shipping and receiving took the MAP FA4C1 analyzer out of the case and carried it at arm's length to the shielded source exchange pit. The instrument was evaluated inside the pit and the shutter was found partially open. The Co-57 source was removed from the analyzer and put into a shielded pig. Bruker examined the analyzer and found the source block was defective and [the analyzer was] sent to production for a replacement source block.
The licensee provided corrective actions in the NMED data entry form. Notified R4DO (Spitzberg) and FSME (via email). |
| Agreement State | Event Number: 47963 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: UNKNOWN
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/25/2012
Notification Time: 11:32 [ET]
Event Date: 05/25/2012
Event Time: [CDT]
Last Update Date: 05/25/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EMAIL ()
| Event Text AGREEMENT STATE REPORT - URANIUM SOURCE FOUND AT METAL CHECK RECYCLING FACILITY
"On May 22, 2012 we [Oklahoma Department of Environmental Quality (OKDEQ)] were contacted by the Director of Radiology at INTEGRIS Southwest Medical Center in Oklahoma City. The Director informed us that an individual had presented at their Emergency Room complaining that he had been exposed to radiation at the Metal Check, Inc. scrap metal yard located at 5700 South High Avenue, Oklahoma City, OK. According to [the Director], the individual was a heavy equipment mechanic who had been sent to Metal Check to repair a piece of their equipment. While working there he was told by some of the Metal Check employees not to enter a certain part of the facility because it contained radioactive pipe. The mechanic immediately left Metal Check and went to the Medical Center."
"That afternoon [an inspector with OKDEQ] went to Metal Check and spoke with the owner and the manager. They agreed to allow [the inspector] to survey the pipe in question and showed [the inspector] the area where it was stored and where the mechanic was working. It appeared to [the inspector] that the pipe was located approximately 40 feet from where the equipment was being repaired, making it impossible for the mechanic to receive any significant dose from this material. [The manager] showed [the inspector] a small bin approximately six feet long by four feet high by four feet deep filled with miscellaneous pieces of scrap metal. The top of the bin was surveyed with a Ludlum Model 19 microR meter (S/N 70537, cal. Aug. 18, 2011) which produced a reading of approximately 1100 microR/hr. This was very high for NORM [naturally occurring radioactive material] pipe and [the inspector] also noted that the radiation level was not uniform along the length of the bin, having a definite spike approximately two feet from the left end. This led [the inspector] to conclude that there was a localized source somewhere in the bin at that point. [The inspector] then contacted [his supervisor] and related what [he] had found at the facility. [The inspector] suggested returning the next day with an additional person and additional instruments, and attempting to locate the postulated radiation source.
"The following morning [the inspector and an associate] returned to Metal Check and began to unload the bin. Almost immediately [they] found what appeared to be a badly corroded metal bucket which had been crushed around an object inside it. A survey of the object with the same Model 19 used the previous day produced a reading of 2.2 mR/hr on contact with the bucket. A Thermo Fisher Interceptor portable gamma spec was used to collect a gamma spectrum from the object, which the instrument identified as shielded Uranium. A second spectrum was collected through a hole in the bucket surrounding the object; this was identified as natural Uranium. A portion of the object was wiped through a hole in the bucket; analysis of the wipe by the DEQ Environmental Lab confirmed the presence of U-235 and U-238, and their daughters. The object was roughly disk-shaped, approximately 12 inches in diameter and one inch thick. One side had a second, smaller disk, approximately 10 inches in diameter, centered on the larger and approximately 2 inches thick. No markings or labels were visible. [The inspectors] estimate the weight of the object at approximately 40 lbs. Three pieces of NORM pipe were also found with high radiation levels (1 mR/hr). All four objects were removed from the bin which was then surveyed again, producing readings of approximately 300 to 400 microR/hr. Rachel Browder and Michelle Hammond of the NRC were informed of the situation later that day by phone. The uranium object was placed in a locked room at the Metal Check facility pending further guidance from NRC." |
| Agreement State | Event Number: 47964 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: ALCOA
Region: 1
City: ALCOA CENTER State: PA
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/25/2012
Notification Time: 13:29 [ET]
Event Date: 05/18/2012
Event Time: [EDT]
Last Update Date: 05/25/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES TRAPP (R1DO)
FSME VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS
The following information was obtained from the Commonwealth of Pennsylvania via fax:
"Alcoa was doing some renovations and had a previous inventory of nine (9) general license [GL] tritium exit signs. During the renovation it was discovered that only seven (7) were accounted for.
"Details of the two missing exit signs: Evenlite, Inc. Model #201, serial numbers 1388F and 389F, each containing 10.5 Ci of tritium.
"CAUSE OF THE EVENT: Though these GL tritium exit signs comply with NRC regulations for labeling to alert the user that they contain radioactive material, the size of the label is woefully inadequate to prevent unintentional loss of the GL device. This event is another example.
"ACTIONS: No reactive inspection is planned at this time. It is expected these two tritium exit signs have or will end up in an unlicensed Commonwealth of Pennsylvania landfill."
PA Report ID No.: PA120015
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 |
| Agreement State | Event Number: 47965 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: CANONSBURG HOSPITAL
Region: 1
City: CANONSBURG State: PA
County:
License #: PA-0393
Agreement: Y
Docket:
NRC Notified By: JOE MELNIC
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/25/2012
Notification Time: 14:19 [ET]
Event Date: 01/20/2012
Event Time: [EDT]
Last Update Date: 05/25/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES TRAPP (R1DO)
FSME VIA EMAIL ()
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING IODINE-125 PROSTATE SEEDS
The following information was obtained from the Commonwealth of Pennsylvania via fax:
"A patient was undergoing treatment with I-125 prostate seeds on January 20, 2012. The patient was prescribed to receive 110 Gy for a determined prostate volume of 21.08 cc. On March 16, 2012 the patient had a follow up CT scan where the prostate volume was determined to be 47 cc and the D90 to the prostate to be 75 Gy. The oncologist questioned the results and ordered an additional CT scan. On May 16, 2012, a second CT scan was performed to confirm the first CT scan. On May 21, 2012, the radiology oncologist calculated the prostate volume to be 33.59 cc and confirmed the D90 to be 75 Gy. The radiation oncologist has no explanation for the edema.
"Cause of the Event: Implant performed using ultrasound, post implant verification via CT.
"Actions: There will be a reactive inspection [by the Commonwealth of Pennsylvania]. The radiation oncologist ordered external beam radiation therapy and feels that the total dose is sufficient. Additional follow up with the patient will occur."
PA Report ID No.: PA120018
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. |
| Agreement State | Event Number: 47966 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: BASF CORPORATION
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2304-L01
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/25/2012
Notification Time: 16:33 [ET]
Event Date: 04/26/2012
Event Time: [CDT]
Last Update Date: 05/25/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LEVEL/DENSITY GAUGE SHUTTER MALFUNCTION
The following information was obtained from the State of Louisiana via fax:
"On April 26, 2012, the Louisiana Department of Environmental Quality (LDEQ) received notification that a shutter malfunctioned on an Ohmart Corporation Level/Density gauge at BASF Corporation. BASF Corporation has a RAM License LA-2304-L01 and Agency Interest Number 2049. The gauge was a Model SH-F1, containing a Cs-137 sealed source, serial number 6274GK with 50 mCi of activity. Ohmart sent out a field engineer to repair the following devices: 1) Ohmart Model SH-F1 level/density gauge, serial number 67471 to replace shutter and rotor; 2) Ohmart Model SH-F1 level/density gauge, serial number 6292GK to lubricate and restore proper shutter function; 3) Ohmart Model SH-F1 level/density gauge, serial number 6247GK, source holder remains stuck in the open position and the gauge is scheduled to be replaced and disposed of at a licensed facility. This incident is reference by LDEQ T139229."
LA Report ID No.: LA120001
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 |
| Part 21 | Event Number: 47981 | Rep Org: SHAW NUCLEAR SERVICES
Licensee: JOSEPH OAT CORPORATION
Region: 1
City: CHARLOTTE State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID BARRY
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/31/2012
Notification Time: 16:17 [ET]
Event Date: 05/31/2012
Event Time: [EDT]
Last Update Date: 05/31/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
STEVEN VIAS (R2DO)
PART 21 GROUP ()
| Event Text PART 21 - DUCTILITY OF REINFORCING STEEL FOR EMBEDMENTS NOT IN ACCORDANCE WITH CODE REQUIREMENT
"The reporting organization provided information pertaining to the identification of a noncompliance associated with the steel reinforcing material (rebar) attached to embedments being supplied as basic components for the Vogtle Units 3 and 4, nuclear project, based on reinforcing bar that exceeded the limit for yield strength.
"The results of the evaluation of this condition as documented by Shaw Nuclear and conducted in accordance with the procedure for performing evaluations required by 10 CFR 21.21, has concluded that the noncompliance could potentially create a substantial safety hazard, if it were to remain uncorrected. Therefore, it has been determined that this noncompliance is reportable under the requirements of 10 CFR Part 21." |
| Power Reactor | Event Number: 47984 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: AL BOSTIC
HQ OPS Officer: DONG HWA PARK | Notification Date: 06/01/2012
Notification Time: 06:36 [ET]
Event Date: 05/31/2012
Event Time: 23:37 [EDT]
Last Update Date: 06/01/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
STEVEN VIAS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text TRANSPORT OF POTENTIALLY CONTAMINATED PERSON OFFSITE
"At 11:11 PM on May 31, 2012, the Harris main control room was notified that a contract employee in a radiation controlled area was in need of medical assistance. The individual was transported by ambulance to the hospital, accompanied by Harris radiation protection personnel. The individual was considered potentially contaminated because a complete survey to confirm the absence of contamination was not completed prior to transport of the person off site for medical treatment. The individual and the ambulance used to transport the individual were surveyed and released after arrival at the hospital."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47985 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ALLISON HARKEY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/01/2012
Notification Time: 13:21 [ET]
Event Date: 06/01/2012
Event Time: 12:47 [EDT]
Last Update Date: 06/01/2012 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
STEVEN VIAS (R2DO)
HAROLD CHERNOFF (NRR)
VICTOR MCCREE (R2)
BRUCE BOGER (ET)
JASON KOZAL (IRD)
DENNIS ALLSTON (ILTA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text UNUSUAL EVENT DUE TO A BOMB THREAT
Two individuals (one male and one female) drove up to the site security gate and stated they had a bomb in the vehicle (Jeep Cherokee). LLEA was notified and responded to the site. The two individuals are in custody and the Raleigh Police bomb squad is enroute to the site. The site is in a heightened level of security.
Notified DHS, NICC, and FEMA.
* * * UPDATE AT 1544 EDT ON 6/1/2012 FROM ALLISON HARKEY TO MARK ABRAMOVITZ * * *
The Unusual Event was terminated at 1530 EDT on 6/1/2012. The vehicle search did not find a bomb and the two individuals are in custody.
Notified the R2DO (Vias), NRR EO (Chernoff), DHS, NICC, and FEMA. |
| Power Reactor | Event Number: 47986 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RODNEY NACOSTE
HQ OPS Officer: JOHN KNOKE | Notification Date: 06/01/2012
Notification Time: 17:26 [ET]
Event Date: 06/01/2012
Event Time: 09:00 [CDT]
Last Update Date: 06/01/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
STEVEN VIAS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text CABLE ROUTING ERROR COULD FAIL DC CONTROL POWER TO SHUTDOWN BOARD IN A FIRE
"During NFPA 805 transition reviews, a cable routing error has been identified that would fail the DC control power to credited 4kV Shutdown Board 3EA for an Appendix R fire in Fire Area 23.
"Cable 3B181 provides alternate DC Control Power to 4kV Shutdown Board 3EA from Battery Board 2. Cable 3B181 is routed in Fire Area 23. However, cable 3B181 is not identified as being in Fire Area 23 in Browns Ferry Nuclear Plant (BFN) calculation EDQ099920030037, Appendix R Computerized Separation Analysis. This error allowed the analysis to credit alternate DC Control Power to 4kV Shutdown Board 3EA. The normal DC Control Power to 4kV Shutdown Board 3EA is not available in the event of an Appendix R fire in Fire Area 23. The routing error results in the credited 4kV Shutdown Board 3EA being unable to perform its function for Fire Area 23 Appendix R fires due to both the associated normal and alternate DC Control Power cables being routed In Fire Area 23. The failure of 4kV Shutdown Board 3EA could result in a loss of power to credited safe shutdown equipment that would challenge the ability to provide adequate core cooling during performance of BFN Safe Shutdown Instructions.
"Compensatory actions in the form of fire watches to mitigate this condition are in place in accordance with the BFNP Fire Protection Report.
"This event is reportable as an 8 hour notification to the NRC in accordance with 10CFR 50,72(b)(3)(ii)(B). This is also reportable as a 60 day written report in accordance with 10CFR 50.73(a)(2)(ii)(B)."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47987 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/02/2012
Notification Time: 21:52 [ET]
Event Date: 06/02/2012
Event Time: 19:35 [EDT]
Last Update Date: 06/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
STEVEN VIAS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE TO A TURBINE CONTROL SYSTEM FAILURE
"At 1935 during normal full power operations, Unit 1 automatically tripped due to a loss of load caused by an instantaneous failure of the turbine control system. The trip was uncomplicated and all CEAs [control rods] fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause and details of the turbine control system failure are under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Steam Bypass Control Systems with condenser vacuum. The offsite power grid is available and stable.
"This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to RPS actuation with the reactor critical."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47988 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: CRAIG JONES
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/03/2012
Notification Time: 06:07 [ET]
Event Date: 06/03/2012
Event Time: 02:39 [EDT]
Last Update Date: 06/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
|
| 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 AUTOSTART OF "B" EDG DUE TO LOSS OF OFFSITE POWER CIRCUIT 767
"At approximately 0239 hours on June 3, 2012 the 'B' Emergency Diesel Generator (EDG) automatically started when offsite power circuit 767 was de-energized. The EDG started and re-energized Safe Guards busses 16 and 17. The selected Service Water (SW) pump 'B' automatically started to supply cooling to the EDG.
"The operators responded to the loss of circuit 767 using abnormal operating procedure AP-ELEC.1 'Loss of 12A and/or 12B Busses'.
"Offsite power was restored to 12B bus using ER-ELEC.1 'Restoration of Offsite Power' on circuit 7T at 0318 hours. The 'B' EDG was shutdown at 0445 hours.
"The initial investigation of the loss of circuit 767 indicates that the likely cause was due to wildlife, e.g., raccoon."
The licensee informed the NRC Resident Inspector. | |