| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/02/2011 - 09/06/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47174 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: CARILLION CLINIC
Region: 1
City: ROANOKE State: VA
County:
License #: 770-051-1
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/19/2011
Notification Time: 15:42 [ET]
Event Date: 08/07/2011
Event Time: [EDT]
Last Update Date: 09/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES TRAPP (R1DO)
BRUCE WATSON (FSME)
| Event Text VIRGINIA AGREEMENT STATE REPORT - DOSE RECEIVED BY PATIENT GREATER THAN PRESCRIBED
The following information was obtained from the State of Virginia via fax:
"On August 7, 2011, the licensee's RSO received notification of an incident. A patient was treated for bronchial/trachea carcinoma using temporary brachytherapy employing a HDR delivery system. Subsequent to treatment, it was realized that dwell positions were misrepresented on the approved treatment plan. Reconstruction of the applicator position led to the conclusion that dose to organs or tissue other than the treatment site received more than 50 Rem and more than 50% of the expected dose. Licensee notified Virginia Department of Health on August 17, 2011. Referring physician was notified on August 17, 2011. Physician is meeting with patient on August 19, 2011. Licensee indicated organs at risk and health effects to patient are under development."
Virginia Report ID: VA-11-08
* * * UPDATE AT 1458 EDT ON 09/02/11 FROM MIKE WELLING TO S. SANDIN * * *
The following update was received from the State of Virginia via email:
"On August 31st the licensee report was received. The report indicated the cause was human error during data loading into the delivery system. An error was received and in order to clear the error the source position spacing was changed. The report detailed the licensee's dose calculations to the surrounding organs and tissue. The estimated maximum amount received by the larynx was 2.332 Gy which was 581% over the expected dose of 0.42 Gy.
"A subsequent licensee response on September 1st detailed the dose to the lungs. The dose to the lungs did not differ between expected and delivered.
"The patient has had two follow up visits and shows no adverse effects. A positive tumor effect was observed by the referring physician."
Notified R1DO (DiPaolo) and FSME (Hsueh).
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. |
| Power Reactor | Event Number: 47207 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: BRIAN HAYDEN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/27/2011
Notification Time: 21:06 [ET]
Event Date: 08/27/2011
Event Time: 19:15 [EDT]
Last Update Date: 09/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PAMELA HENDERSON (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY SIRENS OUT-OF-SERVICE
"Sirens in St. Mary's and Calvert counties are out of service exceeding the minimum required of 19. Currently 44 sirens are out of service due to local power outages caused by the storm. Compensatory measures are in place for the affected counties. Route alerting will be used if necessary."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1730 EDT ON 09/02/11 FROM TOM JONES TO S. SANDIN * * *
As of 1655 EDT on 9/2/11, all 72 emergency sirens have been returned to service.
The licensee informed the NRC Resident Inspector. Notified R1DO (DiPaolo). |
| Agreement State | Event Number: 47217 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: PATRIOT ENGINEERING AND ENVIRONMENTAL, INC
Region: 1
City: RADLIFF State: KY
County:
License #: 201-643-52
Agreement: Y
Docket:
NRC Notified By: CHRISTOPHER KEFFER
HQ OPS Officer: PETE SNYDER | Notification Date: 08/30/2011
Notification Time: 10:56 [ET]
Event Date: 08/06/2011
Event Time: 08:20 [CDT]
Last Update Date: 08/30/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
EUGENE DIPAOLO (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - GAUGE RUN OVER BY EXCAVATOR
"Kentucky Radiation Health Branch was notified on 08/08/2011, by a representative from Patriot Engineering and Environmental, Inc. of a vehicle running over a portable gauge on Saturday morning, 08/06/2011. The gauge was run over by an excavator during backfill operation. The gauge is identified as Humboldt Model 5001 EZ, serial no. 3260, containing 11 mCi of Cs-137 and 44 mCi of Am-241/Be. Surveys of the damaged gauge taken by the licensee indicated that the source had not been breached and that there was no leakage."
Kentucky Event Report ID No: KY110006 |
| Agreement State | Event Number: 47218 | Rep Org: NEW JERSEY DEPT OF ENVIRONMENT PROT
Licensee: TRINITAS HOSPITAL
Region: 1
City: Elizabeth State: NJ
County:
License #: 332163
Agreement: Y
Docket:
NRC Notified By: CATHY BIEL
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/30/2011
Notification Time: 11:09 [ET]
Event Date: 08/29/2011
Event Time: 03:00 [EDT]
Last Update Date: 08/30/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
EUGENE DIPAOLO (R1DO)
ANGELA MCINTOSH (FSME)
MATTHEW HAHN (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE - LOST GADOLINIUM CAMERA SOURCES
The following report was received via facsimile.
"The (New Jersey) (Bureau of Emergency Response) BER received a call from the (Radiation Safety Officer) RSO at Trinitas Hospital at 1500 (EDT) on Monday August 29, 2011. This past Friday, while performing an inventory of their sealed sources, it was discovered that two (Gadolinium) Gd-153 camera sources were missing. These sources were dated March 2002, with an initial activity of 250 mCi apiece. (The half-life of Gd-153 is 241 days, therefore each source had decayed to ~0.01 mCi). The RSO stated that these sources were never used on the camera, and had been in storage since 2002. During the last routine inventory (July 2011) the sources were accounted for. Friday's inventory was being conducted as a result of a recent cleanup of the storage area. The RSO indicated that hospital staff conducted thorough searches of the hospital on Friday, as well as over the weekend, but have not found the sources. It was also indicated that the chief nuclear medicine technologist, who was involved in the cleanup, is currently overseas until September 7. When he returns, the RSO will discuss with him to see if he has knowledge of the location of these sources."
The search and investigation is still ongoing.
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 |
| Fuel Cycle Facility | Event Number: 47219 | Facility: AREVA NP INC RICHLAND
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION
FABRICATION & SCRAP
COMMERCIAL LWR FUEL
Region: 2
City: RICHLAND State: WA
County: PENTON
License #: SNM-1227
Agreement: Y
Docket: 07001257
NRC Notified By: CALVIN MANNING
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/30/2011
Notification Time: 12:01 [ET]
Event Date: 08/29/2011
Event Time: 09:20 [PDT]
Last Update Date: 09/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(4) - NAT PHENOM AFFECTING SAFETY
| Person (Organization):
MALCOLM WIDMANN (R2DO)
DAVID PSTRAK (NMSS)
| Event Text 24-HOUR REPORT DUE TO FAILURE OF A GAMMA MONITORING SYSTEM
"On 8/28/11 at 0920 hrs. PDT, electrical storms in the area caused power surges. The site backup power generators activated as designed. However, it was later discovered that a gamma monitor associated with the waste water treatment process was damaged. When the gamma monitoring system failed, the system interlocks shut the system down as designed. The system has remained down since that time and will remain down until repaired.
"This report is being made per the requirements of 10 CFR 70, Appendix A(b)(4), (24-hr. report criteria), 'Any natural phenomenon that has affected the availability or reliability of one or more Items Relied On For Safety (IROFS)'.
"An updated report with additional timeline information will be provided as the information becomes available.
"SAFETY SIGNIFICANCE OF EVENTS: Low. The waste water treatment system was shut down as designed.
"POTENTIAL CRITICALITY PATHWAYS INVOLVED: The only potential pathway is gradual accumulation of uranium in the waste water treatment equipment over an extended period of time.
"CONTROLLED PARAMETERS: Concentration is controlled. Maximum concentration in the equipment is estimated to be less than 1.5 grams of uranium per liter based on gamma monitor reading when the system shut down.
"ESTIMATED AMOUNT/ENRICHMENT, FORM OF LICENSED MATERIAL: Facility is licensed for 5 wt% U-235. Normal system clean out results in about 120 grams of uranium. A minimum critical mass assuming spherical geometry is [much greater than normal system content].
"CORRECTIVE ACTIONS: System automatically shut down as designed and will remain down until the equipment is repaired and returned to service.
* * * UPDATE AT 1214 EDT ON 09/02/11 FROM CALVIN MANNING TO S. SANDIN * * *
The following information was received via email:
"At approximately 0920 local time, 8/28/2011 and closely associated in time with both a thunderstorm and a test of various internal backup power generators, an operator at the Waste Water Treatment (WWT) facility noticed that the gamma monitors on two sand filters had ceased to function correctly. Apparently as an immediate result of this failure to function, the associated flows to the sand filters shut down automatically (normal fail-safe shutdown). The system has remained down since that time and will remain down until the gamma monitoring system is repaired.
"This plant condition was brought to the attention of the HRR EHS&L staff on Tuesday 8/30/2011 at 0800 by an engineer responsible for the gamma monitoring system who was soliciting potential options to restore the system to service.
"At 0901 local time AREVA's HRR EHS&L notified the NRC Operation's Center of this condition per the requirements of 10CFR70 Appendix A criterion (b) (4) (24 hour report) which requires reporting of any natural phenomenon that has or may have affected the intended safety function or availability or reliability of one or more items relied on for safety.
"Safety Significance of Event: The safety significance of this event is low. The feed and discharge to and from the waste water treatment sand filters were shut down as designed when the gamma detectors failed.
"Potential Nuclear Criticality Pathways Involved: The only potential pathway is for gradual build up / accumulation of uranium in the WWT equipment over an extended period of time (many years).
"Controlled Parameters (Mass, Moderation, Geometry, Concentration, Etc.): Uranium concentration is controlled. The maximum concentration of uranium in the equipment is estimated to be less than 1.5 g U/L based on gamma monitor readings just prior to the system being shut down.
"Estimated Amount, Enrichment, Form of License material (Includes process limit and % worst case critical mass): The facility is licensed for 5 wt.% U-235. Normal system clean out results in about 120 grams of uranium. A minimum critical mass of uranium at 5 wt.% U-235 assuming spherical geometry is about 38,000 grams.
"Nuclear Criticality Safety Control(s) or Control System(s) and description of the failures or deficiencies: No control system failures occurred.
"Corrective Actions to Restore Safety Systems and When Each Was Implemented: The system automatically shut down as designed and will remain down until the equipment is repaired, functionally tested, and returned to service."
Notified R2DO (Sykes) and NMSS (Pstrak). |
| Agreement State | Event Number: 47226 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: U.S. STEEL
Region: 1
City: WEST MIFFLIN State: PA
County:
License #: PA-G0309
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/31/2011
Notification Time: 14:41 [ET]
Event Date: 08/02/2011
Event Time: [EDT]
Last Update Date: 08/31/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAUL KROHN (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - SHUTTER MECHANISM FAILURE
The following information was obtained from the Commonwealth of Pennsylvania via facsimile:
"EVENT DESCRIPTION: Failure of the shutter mechanism on one of its generally licensed thickness gauges was identified immediately to operators through a computer based warning message and visually by a red status light adjacent to the gauge location. Adjustment of the air supply allowed the shutter to close but still not operate properly. Routine maintenance activities were not successful in allowing the shutter to return to operational status and Applied Health Physics were notified to provide radiological support. No radiation exposure to personnel ensued during this event. The device is identified as: Manufacturer (IRMS), Model (TG-2), Serial# (00M0397-I5), Isotope (Americium-241), Activity (3 Ci), Location (Cold Reduction Mill).
"CAUSE OF THE EVENT: A faulty actuator cylinder.
"ACTIONS: The shutter mechanism was replaced, tested, and confirmed as operating properly. The actuator cylinder will be placed on a preventive maintenance schedule following this event."
PA Report No.: PA110022 |
| Agreement State | Event Number: 47227 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: AURORA MEDICAL CTR. OF WASHINGTON CO., INC.
Region: 3
City: HARTFORD State: WI
County:
License #: 131-1024-01
Agreement: Y
Docket:
NRC Notified By: KRISTA KUHLMAN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/31/2011
Notification Time: 16:15 [ET]
Event Date: 08/30/2011
Event Time: [CDT]
Last Update Date: 08/31/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
GREG SUBER (FSME)
| Event Text AGREEMENT STATE REPORT - PATIENT RECEIVED WRONG ISOTOPE DURING A DIAGNOSTIC PROCEDURE
The following information was obtained from the State of Wisconsin via facsimile:
"The Wisconsin Department of Health Services (DHS) received a phone call from the Imaging Manager at Aurora Medical Center of Washington County on August 30, 2011, that a patient received a dose of 5 mCi of I-131 on February 2, 2011. The patient, according to the written directive, was to receive a dose of 5 mCi of I-123. This diagnostic procedure was ordered to evaluate whether any thyroid tissue remained following an iodine ablation dose one year earlier.
"DHS conducted an investigation on August 31, 2011 and the licensee will submit a 15-day written report concerning the medical event. At this time, the licensee is evaluating their process and is developing a new written directive form. The authorized user will discuss this with the referring physician to determine if the patient will be notified."
Wisconsin Report ID: WI110013
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: 47233 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: PDV REFINING, LLC
Region: 3
City: LEMONT State: IL
County:
License #: IL-01603-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/01/2011
Notification Time: 16:02 [ET]
Event Date: 08/31/2011
Event Time: [CDT]
Last Update Date: 09/01/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
KEVIN HSUEH (FSME)
| Event Text AGREEMENT STATE REPORT INVOLVING A FIXED NUCLEAR GAUGE SHUTTER THAT FAILED TO CLOSE
The following information was received from the State of Illinois via email:
"Late yesterday the Agency's [Illinois Emergency Management] W. Chicago office received a call from PDV Midwest Refining (IL-01603), 135th St and New Ave., Lemont, IL 60439. The caller reported that while his crew was performing routine shutter checks of fixed gauges in his area of the plant, a shutter failed to close. The vessel the gauge was on was in use as part of a sulfur unit and needed to remain in operation with the gauge 'on-line', so no other immediate action was taken other than to advise all shift supervisors of the gauge's status and to avoid performing any work in the area.
"This morning, the radiation safety officer was contacted for additional information and instructions regarding necessary actions on their part. The RSO advised that the gauge was an Ohmart model SH-F1-45, containing 15 milliCi of Cs-137 as of April 2002. It was one of two gauges on that vessel. The other gauge which was lower on the vessel showed no difficulties in its operation. However, he noted that a similar problem had occurred in the past with the same model gauge on a parallel sulfur unit in the same physical position. At that time, field notes prepared by the manufacturer's representative who inspected the device indicated that some corrosion was present on the device. Both vessels and thus all four gauges are exposed to the full range of seasonal cycles of weather. All site staff have been made aware of the gauge condition and to ensure all 'lock out - tag out' practices are in effect in the area to preclude any work on the vessel until such time the manufacturer's rep has repaired the device or removed it from the vessel.
"The radiation safety officer was advised of the need to file a written report within 30 days in keeping with Illinois regulations.
"Source/Radioactive Material: SEALED SOURCE GAUGE Radionuclide: CS-137
"Manufacturer: OHMART CORP. Activity: 0.015 Ci [or] 0.555 GBq
"Model Number: A-2102
"Serial Number: unk
Illinois Item Number: IL11117 |
| Power Reactor | Event Number: 47235 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEFFREY MIELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/01/2011
Notification Time: 17:54 [ET]
Event Date: 09/01/2011
Event Time: 10:50 [CDT]
Last Update Date: 09/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL KUNOWSKI (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 TECHNICAL SUPPORT CENTER DIESEL GENERATOR NON-FUNCTIONAL
"At 1050 (CDT), on September 1, 2011, the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was declared non-functional due its failure to start during routine testing. The plant is currently in the process of determining the cause of the failure. Normal power to the TSC is currently available. This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM JEFFREY MIELL TO MARK ABRAMOVITZ AT 1313 EDT ON 9/2/11 * * *
"The TSC Emergency Diesel Generator failure has been identified and corrected. The unit has been successfully tested, restoring the EDG and TSC to a functional status." The TSC was restored at 1145 CDT.
The licensee will notify the NRC Resident Inspector.
Notified the R3DO (Kunowski). |
| Non-Agreement State | Event Number: 47236 | Rep Org: COVIDIEN-MALLINCKRODT, INC
Licensee: COVIDIEN-MALLINCKRODT, INC
Region: 3
City: MARYLAND HEIGHTS State: MO
County:
License #: 02-04206-01
Agreement: N
Docket:
NRC Notified By: DAN HOFFMAN
HQ OPS Officer: JOE O'HARA | Notification Date: 09/02/2011
Notification Time: 10:59 [ET]
Event Date: 09/02/2011
Event Time: [CDT]
Last Update Date: 09/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
EUGENE DIPAOLO (R1DO)
MICHAEL KUNOWSKI (R3DO)
JIM WHITNEY (ILTA)
ANGELA MCINTOSH (FSME)
CANADA ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text LOST PRODUCT CONTAINING 18 MILLICURIES INDIUM - 111
The licensee shipped the radioactive imaging product to a customer in Rochester, NY on 8/7/11. The courier, Medical Delivery Services, called the licensee that evening to report that they had three bills of lading for the customer but only two packages to deliver.
The licensee has commenced an investigation to determine the root cause and develop corrective actions. Customers along the route have been contacted without success of finding the missing product. The calculated activity level now is 31 microcuries.
The licensee notified R3DO (Bob Gattone).
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: 47237 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MARK ROELIKE
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/02/2011
Notification Time: 22:15 [ET]
Event Date: 09/02/2011
Event Time: 16:00 [CDT]
Last Update Date: 09/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
MICHAEL KUNOWSKI (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 INTAKE STRUCTURE FIRE SUPPRESSION SYSTEM FAILED SURVEILLANCE TEST
"During intake structure fire suppression sprinkler system surveillance testing, Operations identified that a portion of the sprinkler system was not able to pass flow. A 14-day fire protection system impairment was entered and a continuous compensatory fire watch with backup suppression was stationed prior to removing the system from service for testing. Upon failure of the surveillance test, the impairment remained in effect and the continuous fire watch remained stationed pending investigation/repair by Maintenance. On 9/2/2011 at approximately 1600 [CDT], Mechanical Maintenance personnel informed Operations that the sprinkler suppression piping was found to be fouled and not capable of passing flow. The intake sprinkler system is relied upon in part to satisfy an exemption for the station to 10CFR50 Appendix R, Section III.G.2.B concerning separation of components in the intake structure. Based upon the intake sprinkler system being non-functional, this condition is being reported under 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition affecting plant safety systems."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 47238 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL PLETCHER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/03/2011
Notification Time: 03:28 [ET]
Event Date: 09/03/2011
Event Time: 02:35 [EDT]
Last Update Date: 09/03/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
EUGENE DIPAOLO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 99 | Power Operation | 96 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO RHR/CS ROOM COOLER BEING INOPERABLE
"Technical specification required shutdown due to reactor recirculation unit #7 [RHR/CS Room Cooler] inoperable. This cooling unit impacts the operability of 'A' Low Pressure Coolant Injection (LPCI) and 'A' Core Spray (CS).
"Entered TS 3.5.A.6. Commenced reducing power for 24 hour cold shutdown LCO."
The licensee has initiated repairs to the cooling unit.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1432 EDT ON 09/03/11 FROM JAMES KRITZER TO S. SANDIN * * *
The licensee exited TS 3.5.A.6 at 1000 EDT and declared CS operable after implementing compensatory measures. They are currently in a 7-day LCO Action Statement and expect to complete repairs within the time allowed. The Unit is currently holding power at 98%.
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 47239 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: KEN HAJNAL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/03/2011
Notification Time: 15:35 [ET]
Event Date: 09/03/2011
Event Time: 15:30 [EDT]
Last Update Date: 09/03/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
EUGENE DIPAOLO (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 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO "A" TRAIN SERVICE WATER LEAK
A leak in the "A" train of the service water system was identified on August 17, 2011. The leak is in the auxiliary building at the minus 5' elevation and the water is being collected in the waste drain tank. At 1530 on September 3, 2011, the leak was quantified as being less than 15 gpm and the service water system was declared inoperable in accordance with Technical Specification (TS) 3.7.4.1 for the Service Water System and the Technical Requirements Manual 3.4.10 for Structural Integrity. The leak is on a 10" flange between two bolt holes in a welded area of the flange. Maintenance has been able to reduce the leakage to approximately 3 gpm.
The plant is in a 72 hour Tech Spec and is making preparations to shutdown to mode 5 for repairs.
The licensee notified the NRC Resident Inspector and will notify state and local authorities. |
| Power Reactor | Event Number: 47240 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL G. BRILL
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/04/2011
Notification Time: 13:27 [ET]
Event Date: 09/04/2011
Event Time: 10:20 [EDT]
Last Update Date: 09/04/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARVIN SYKES (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 | 95 | Power Operation | 95 | Power Operation | Event Text TECHNICAL SUPPORT CENTER LOST DUE TO FAILED BACKUP DIESEL GENERATOR SURVEILLANCE TEST
"A condition is being reported per Technical Requirements Manual 13.13.1 Emergency Response Facilities Action B.2. The Functionality of the Technical Support Center (TSC) has been lost due to a failure to pass a required surveillance of the backup diesel generator for TSC Support Systems. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to FUNCTIONAL status with high priority.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 47241 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES KRITZER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/05/2011
Notification Time: 09:40 [ET]
Event Date: 09/05/2011
Event Time: 04:03 [EDT]
Last Update Date: 09/05/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
EUGENE DIPAOLO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 98 | Power Operation | 98 | Power Operation | Event Text LOSS OF METEROLOGICAL TOWER VERTICAL TEMPERATURE DIFFERENCE INSTRUMENTATION DUE TO LIGHTNING STRIKE
"On 9/5/11 at 0403 EDT, Vermont Yankee Nuclear Power Station experienced a lightning strike which resulted in a loss of all vertical temperature difference instrumentation.
"This condition is being reported as a loss of emergency assessment capability in accordance with 10CFR50.72(b)(3)(xiii)
"Procedure OPOP-PHEN-3127, Natural Phenomena, was entered and the lightning damage indicator walkdown checklist was performed with no additional damage found. Several other spurious alarms were received at the time of the lightning strike and are being investigated. None of these alarms indicate any other potentially reportable conditions.
"The plant is continuing normal power operation at approximately 98 percent rated thermal power.
"The NRC Resident Inspector has been informed."
The licensee reports that repairs are currently underway. | |