| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/23/2012 - 02/24/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47680 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: AGRI-INDUSTRIAL PLASTICS COMPANY
Region: 3
City: FAIRFIELD State: IA
County:
License #: 3111151SEM
Agreement: Y
Docket:
NRC Notified By: RANDAL DAHLIN
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/21/2012
Notification Time: 09:13 [ET]
Event Date: 11/30/2011
Event Time: [CST]
Last Update Date: 02/21/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVE PASSEHL (R3DO)
DARYL JOHNSON (ILTA)
ANGELA MCINTOSH (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOSS OF ONE STATIC ELIMINATOR
The following information was received from the State of Iowa via email:
"Agri-Industrial Plastics Company, a general license registrant, reported the loss of one static eliminator, NRD model P-2021-8201, serial number A2HL930, containing 10 millicuries of Polonium-210. The device was used to eliminate static on plastic particles from the trimming of plastic parts. The device was last used on November 30, 2011. The registrant has spent several hours looking for the device. The registrant will be eliminating all remaining static eliminators and returning them to the manufacturer.
"Source/Radioactive Material: Sealed source ionizing
Manufacturer: NRD, INC.
Model Number: P-2021-8201
Serial Number: A2HL930
Radionuclide: PO-210, .010 Ci, 0.37 GBq
"Device Name: Static elimination device
Manufacturer: NRD, INC.
Model Number: P-2021-8201
Serial Number: A2HL930"
The state indicated the cause of the loss was due to inattention to detail.
Iowa Event Number IA120002
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 |
| Power Reactor | Event Number: 47687 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CURTIS DUNSMORE
HQ OPS Officer: VINCE KLCO | Notification Date: 02/22/2012
Notification Time: 23:36 [ET]
Event Date: 02/22/2012
Event Time: 20:14 [EST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
MIKE ERNSTES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 88 | Power Operation | 73 | Power Operation | | 2 | N | Y | 100 | Power Operation | 96 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABILITY OF EMERGENCY CORE COOLING SYSTEMS
"At 1859 hours EST, the Brunswick site experienced a loss of balance of plant (BOP) bus Common C. As a result, makeup pumps to the ECCS discharge line keepfill systems lost power. At 1905 on Unit 1, 'A' loop of the Core Spray (CS) system received a low discharge pressure alarm and was declared inoperable. At 1916 hours, 'B' loop of the Residual Heat Removal (RHR) system received a low discharge pressure alarm and was declared inoperable. With the loss of the second low pressure ECCS system, Condition J of Technical Specification 3.5.1, 'ECCS Operating,' was entered, which requires the Unit 1 to enter LCO 3.0.3 immediately. At 1931 hours, 'A' loop of RHR was declared inoperable due to low discharge pressure. Power reduction of Unit 1 was initiated at 2014 hours.
"At 2055 hours on Unit 2, 'A' loop of the Residual Heat Removal (RHR) system received a low discharge pressure alarm and was declared inoperable. At 2128 hours, 'B' loop of the Core Spray (CS) system received a low discharge pressure alarm and was declared inoperable. With the loss of the second low pressure ECCS system, Condition J of Technical Specification 3.5.1, 'ECCS Operating,' was entered, which requires the Unit 2 to enter LCO 3.0.3 immediately. Power reduction of Unit 2 was initiated at 2219 hours.
"This event reportability is in accordance with 10CRF50.72(b)(2)(i), Technical Specification Required Shutdown, due to inoperability of ECCS systems.
"The initial safety significance of this event is minimal. Offsite power and the Emergency Diesel Generators are operable. The High Pressure Coolant Injection (HPCI) system remains operable on both Unit 1 and Unit 2. The Reactor Core Isolation Cooling (RCIC) system remains operable on Unit 1 and is being restored following maintenance on Unit 2.
"Troubleshooting activities to determine the loss of the BOP Common C bus are in progress. Efforts are in progress to install temporary power to the keepfill makeup pumps."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM CURTIS DUNSMORE TO DONALD NORWOOD AT 0223 EST ON 2/23/2012 * * *
"Unit 1 - At 2315 hours, temporary power was provided to the ECCS keepfill makeup pump and the ECCS systems were restored. LCO 3.0.3 was exited on Unit 1 at 0041 hours with restoration of the 'A' and 'B' loops of the RHR systems. The 'A' loop of the Core Spray system was restored at 0058 hours on 2/23/2012."
During the shutdown, Unit 1 was manually scrammed due to high delta-pressure across the Circulating Water Pump traveling screens. See EN #47690 for details.
"Unit 2 - At 2315 hours, temporary power was provided to the ECCS keepfill makeup pump and the ECCS systems were restored. LCO 3.0.3 was exited on Unit 2 at 2354 hours with restoration of 'B' loop of the RHR system. The 'A' loop of the Core Spray system was restored at 0039 hours. Unit 2 was at 96% of Rated Thermal Power when the shutdown was terminated."
The licensee notified the NRC Resident Inspector. Notified R2DO (Ernstes). |
| Power Reactor | Event Number: 47688 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ALLAN BRIESE
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/23/2012
Notification Time: 00:45 [ET]
Event Date: 02/22/2012
Event Time: 18:45 [MST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RICK DEESE (R4DO)
|
| 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 | Y | 100 | Power Operation | 100 | Power Operation | Event Text SUSPICIOUS PACKAGE DISCOVERED ON SITE
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73
"At 1852 hours, Palo Verde Unit 1 was notified of a suspicious package located in the Owner Controlled Area outside the Protected Area. Maricopa County Sheriff's Office was contacted for assistance with a bomb disposal unit. Local media has become aware of this event and expressed interest by dispatching helicopters and television crews.
"There are no safety systems impacted by the package and operations personnel are not hampered in their ability to operate safety related equipment. There is no release of radioactivity to the environment as a result of this package and it has not adversely affected the safe operation of the plant or health and safety of the public. All three Palo Verde units are being maintained stable at approximately 100% power.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 47689 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARVIN GOLD
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/23/2012
Notification Time: 01:29 [ET]
Event Date: 02/23/2012
Event Time: 01:22 [EST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MIKE ERNSTES (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 | Event Text OFFSITE NOTIFICATION TO LAW ENFORCEMENT
Offsite notification to law enforcement agencies was made by the licensee due to an individual making threats against personnel and security at the site. The licensee notified the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details. |
| Power Reactor | Event Number: 47690 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CURTIS DUNSMORE
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/23/2012
Notification Time: 02:55 [ET]
Event Date: 02/22/2012
Event Time: 23:19 [EST]
Last Update Date: 02/23/2012 | 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
| Person (Organization):
MIKE ERNSTES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 73 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO HIGH DELTA-P ACROSS CIRCULATING WATER PUMP TRAVELING SCREENS
"At 2319 hours EST, a manual Reactor Protection System (RPS) actuation was inserted on Unit 1 in anticipation of a loss of condenser vacuum. Shortly before the manual RPS actuation, Circulating Water Intake Pump (CWIP) 1B tripped due to high delta-pressure across the intake traveling screen. This caused the trip of the remaining pumps. Previously, at 1859 hours, balance of plant (BOP) bus Common C unexpectedly de-energized. This caused loss of power to the CWIP traveling screen motors which, in turn, lead to the high delta-pressure across the traveling screen(s).
"All control rods inserted properly. As a result of the scram, reactor water level reached the Low Level 1 actuation set point and Primary Containment (i.e., Group 6) isolation occurred. All systems functioned as designed. The High Pressure Coolant Injection (HPCI) system is being used, as needed, for pressure control. The Reactor Core Isolation Cooling (RCIC) system is being used, as needed, for level control. No Safety/Relief Valves (SRVs) actuated as a result of the manual RPS actuation.
"The manual RPS actuation is reportable in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). The actuation of the HPCI and RCIC systems and the Group 6 isolation are reportable in accordance with 10CFR50.72(b)(3)(iv)(A)."
The unit is currently in Mode 3 with a cooldown in progress.
The licensee notified the NRC Resident Inspector. Notified R2DO (Ernstes).
* * * UPDATE FROM STEWART BYRD TO CHARLES TEAL AT 0741 EST ON 2/23/12 * * *
"At 2319 hours EST, a loss of all Circulating Water Intake Pumps caused a lowering vacuum on Unit 1. As previously reported (i.e. Event Notification 47690), a manual Reactor Protection System (RPS) actuation was inserted on Unit 1 at this time. In addition, a valid actuation of the RPS, High Pressure Coolant Injection (HPCI), Reactor Core Isolation Cooling (RCIC), and a Group 6 isolation was reported in accordance with 10CFR50.72(b)(3)(iv)(A). At 2342, Main Condenser vacuum was 15 in. Hg and lowering. All Main Steam Isolation Valves were slow closed in anticipation of Group 1 isolation at this time. This follow-up notification is being made to report the manual actuation of the Group 1 isolation valves in accordance with 10 CFR 50.72(b)(3)(iv)(A). The Group 1 isolation was discussed with the NRC during initial notification of EN 47690, and this follow-up is providing written notification of the MSIV closure."
The NRC Resident Inspector has been notified. Notified R2DO (Ernstes). |
| Part 21 | Event Number: 47693 | Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DUYEN PHAM
HQ OPS Officer: VINCE KLCO | Notification Date: 02/23/2012
Notification Time: 11:08 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
MEL GRAY (R1DO)
MIKE ERNSTES (R2DO)
PATTY PELKE (R3DO)
RICK DEESE (R4DO)
PART 21 GRP - EMAIL ()
| Event Text PART 21 REPORT - ROSEMOUNT PRESSURE TRANSMITTERS WITH NONZERO BASED CALIBRATIONS
The following information was received by facsimile:
"During the course of qualification testing to replace certain diodes identified for obsolescence, RNII [Rosemount Nuclear Instruments, Inc.] has determined that Model 1154 Series H range code 4-8 pressure transmitters with a significantly elevated or suppressed 4 mA point may not meet the published steam pressure/temperature accuracy specification.
"The out of tolerance condition observed during steam pressure/temperature qualification testing is not related to the replacement diode changes. It is an inherent performance characteristic related to large zero elevation or suppression.
"The steam pressure/temperature accuracy specification will be revised to account for nonzero based calibrations with a significantly elevated or suppressed 4 mA point.
"This revised specification supersedes the published steam pressure/temperature accuracy specification for all Model 1154 Series H pressure transmitters affected by this notification.
"RNII recommends that users review the application where 1154 Series H range code 4-8 pressure transmitters are used to determine if there are safety considerations related to the revised steam pressure/temperature specification."
Rosemount Nuclear has provided instruments to the following list of domestic U.S. customers: Alabama Power; American Electric Power; Arizona Public Service/Pinnacle West; Bechtel Power; Constellation Energy; Dominion Nuclear Connecticut/Dominion Generation; Duke Energy; ECFS MCS; Edison Material Supply; Electro Mechanics; Entergy; Exelon Generation; Florida Power and Light; FPL Energy; Georgia Power; Northern States Power-Minnesota DBA XCEL Energy; Pacific Gas and Electric; Progress Energy Florida; Progress Energy Carolinas; PSEG Nuclear; South Carolina Electric and Gas; Southern California Edison; Southern Nuclear Operating Company; STP Nuclear Operating; Tennessee Valley Authority; TXU/Luminant; Westinghouse Electric. |
| Power Reactor | Event Number: 47694 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: VINCE KLCO | Notification Date: 02/23/2012
Notification Time: 12:52 [ET]
Event Date: 02/23/2012
Event Time: 09:00 [CST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RICK DEESE (R4DO)
|
| 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 OFFSITE NOTIFICATION DUE TO AN INTAKE STRUCTURE OIL SPILL
"On February 23, 2012, at 0900 CST, an oil leak was identified from a gear box in the intake structure that had leaked into the circulating water cell. Prompt action was taken to stop the leak. Less than or equal to 1 pint of oil was spilled into the circulating water cell and, subsequently, to the Missouri River. The spill has been stopped and clean up of the oil sheen in the intake cell is proceeding. A visible oil sheen was noted on the Missouri River downstream of the station's intake structure near the station's outfall. The gear box has been drained to prevent any further leakage. Notifications will be made per Fort Calhoun Nuclear Station's National Pollutant Discharge Elimination System (NPDES) permit. Samples will be taken for off site analysis to determine the quantity of oil discharged. The State of Nebraska, Department of Environmental Quality and National Response Center will be notified.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi), 4 hour non-emergency notification due to a notification being made to a Government Agency (State of Nebraska, Department of Environmental Quality and National Response Center)."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47695 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHAD EURAY
HQ OPS Officer: VINCE KLCO | Notification Date: 02/23/2012
Notification Time: 14:28 [ET]
Event Date: 02/24/2012
Event Time: 05:00 [EST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MIKE ERNSTES (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 | Event Text PLANNED MAINTENANCE WILL RESULT IN THE TECHNICAL SUPPORT CENTER BEING UNAVAILABLE
"The Technical Support Center will be unavailable for approximately 10 hours due to planned maintenance on motor control center SMXE."
Maintenance is expected to begin at 0500 on February 24, 2012.
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 47696 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: DAVID SPARGO
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/24/2012
Notification Time: 04:24 [ET]
Event Date: 02/23/2012
Event Time: 22:00 [CST]
Last Update Date: 02/24/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICK DEESE (R4DO)
|
| 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 LOSS OF 21 OUT OF 101 EMERGENCY SIRENS
"Communications has been lost to 21 sirens out of 101. The loss of communications does not allow the activation of the sirens. Almost all of Harrison County and Pottawattamie county in Iowa are without communications to the sirens. There are compensatory measures in place to ensure notification by local law enforcement in case of an actual emergency to inform the public in these areas.
"This is being reported per 10CFR50.72(b)(3)(xiii) for 'Any event that results in a major loss of emergency assessment capability, off site response capability, or communications capability'.
"An attempt is being made to reboot the siren's communication system in order to restore the sirens. During the reboot, sirens in Washington County, Nebraska, will also lose communications and therefore will not be functional. Local Law Enforcement has been notified in Washington County to perform compensatory measures in case of an emergency."
The NRC Resident Inspector has been informed. | |