Event Notification Report for November 30, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/29/2011 - 11/30/2011
EVENT NUMBERS
47492476804749047629
Power Reactor
Event Number: 47492
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GRACIA
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/30/2011
Notification Time: 22:09 [ET]
Event Date: 11/30/2011
Event Time: 17:47 [EST]
Last Update Date: 11/30/2011
Notification Time: 22:09 [ET]
Event Date: 11/30/2011
Event Time: 17:47 [EST]
Last Update Date: 11/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WAYNE SCHMIDT (R1DO)
WAYNE SCHMIDT (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 |
HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE
"On November 30, 2011, at 1747 hours [EST], with the reactor at 100% core thermal power and steady state conditions, Pilgrim Nuclear Power Station (PNPS) declared the High Pressure Coolant Injection (HPCI) system inoperable due to the HPCI turbine control valve (HPCI-24) failing to go open during planned post-maintenance testing. The HPCI-24 is a hydraulically operated control valve and its normal position is closed. The HPCI-24 valve has a safety function to open on a demand signal during certain event mitigation scenarios requiring the HPCI system operation.
"Based on the turbine control valve failing to open during post-maintenance testing and a subsequent check out run per PNPS Procedure 8.5.4.1, the HPCI system was declared inoperable at 1747 hours and the appropriate LCO was entered. An investigation of the event is underway and continuing.
"This event had no impact on the health and/or safety of the public.
"The NRC Resident Inspector bas been notified.
"This is an 8-hour notification made in accordance with 50.72(b)(3)(v)(D)."
"On November 30, 2011, at 1747 hours [EST], with the reactor at 100% core thermal power and steady state conditions, Pilgrim Nuclear Power Station (PNPS) declared the High Pressure Coolant Injection (HPCI) system inoperable due to the HPCI turbine control valve (HPCI-24) failing to go open during planned post-maintenance testing. The HPCI-24 is a hydraulically operated control valve and its normal position is closed. The HPCI-24 valve has a safety function to open on a demand signal during certain event mitigation scenarios requiring the HPCI system operation.
"Based on the turbine control valve failing to open during post-maintenance testing and a subsequent check out run per PNPS Procedure 8.5.4.1, the HPCI system was declared inoperable at 1747 hours and the appropriate LCO was entered. An investigation of the event is underway and continuing.
"This event had no impact on the health and/or safety of the public.
"The NRC Resident Inspector bas been notified.
"This is an 8-hour notification made in accordance with 50.72(b)(3)(v)(D)."
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
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: 00:00 [CST]
Last Update Date: 02/21/2012
Notification Time: 09:13 [ET]
Event Date: 11/30/2011
Event Time: 00:00 [CST]
Last Update Date: 02/21/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAVE PASSEHL (R3DO)
DARYL JOHNSON (ILTA)
ANGELA MCINTOSH (FSME)
DAVE PASSEHL (R3DO)
DARYL JOHNSON (ILTA)
ANGELA MCINTOSH (FSME)
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
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: 47490
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK GILBERT
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK GILBERT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/30/2011
Notification Time: 11:39 [ET]
Event Date: 11/30/2011
Event Time: 09:35 [CST]
Last Update Date: 11/30/2011
Notification Time: 11:39 [ET]
Event Date: 11/30/2011
Event Time: 09:35 [CST]
Last Update Date: 11/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (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 |
PLANT PROCESS COMPUTER OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"A planned maintenance evolution at the Duane Arnold Energy Center (DAEC) to replace power supplies in the plant process computer will result in a loss of some Safety Parameter Display System (SPDS) indications for a duration of less than 5 hours. No other indicators or annunciators will be unavailable during this maintenance to affect the plant's ability to assess or monitor an accident or transient in progress.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)."
The NRC Resident Inspector has been notified.
* * * UPDATE ON 11/30/11 AT 1442 EST FROM GILBERT TO HUFFMAN * * *
The licensee reports that the plant process computer work has been completed and SPDS has been functionally tested and returned to an operable status.
The licensee will notify the NRC Resident Inspector. R3DO (Riemer) notified.
"A planned maintenance evolution at the Duane Arnold Energy Center (DAEC) to replace power supplies in the plant process computer will result in a loss of some Safety Parameter Display System (SPDS) indications for a duration of less than 5 hours. No other indicators or annunciators will be unavailable during this maintenance to affect the plant's ability to assess or monitor an accident or transient in progress.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)."
The NRC Resident Inspector has been notified.
* * * UPDATE ON 11/30/11 AT 1442 EST FROM GILBERT TO HUFFMAN * * *
The licensee reports that the plant process computer work has been completed and SPDS has been functionally tested and returned to an operable status.
The licensee will notify the NRC Resident Inspector. R3DO (Riemer) notified.
Power Reactor
Event Number: 47629
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMANN
HQ OPS Officer: JOHN KNOKE
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: GENE DAMMANN
HQ OPS Officer: JOHN KNOKE
Notification Date: 02/01/2012
Notification Time: 12:49 [ET]
Event Date: 11/30/2011
Event Time: 07:58 [CST]
Last Update Date: 02/01/2012
Notification Time: 12:49 [ET]
Event Date: 11/30/2011
Event Time: 07:58 [CST]
Last Update Date: 02/01/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO UNMONITORED RELEASE OF TRITIUM (HEATING STEAM CONDENSATE)
"Heating Steam condensate containing 9,430 picocuries per liter [pCi/L] of tritium overflowed from the Main Warehouse between November 22, 2011 and November 29, 2011. The US EPA drinking water limit for tritium is 20,000 pCi/L.
"The Warehouse Condensate Return system failed to operate which resulted in the overflow of the Heating Steam condensate. There was a potential for the condensate to enter the environment where it could reach groundwater. The released volume for this event was conservatively calculated to be up to 3,900 gallons. The 122 Condensate Return Pump was replaced and the system was restored to service.
"This voluntary report is in accordance with the Nuclear Energy Institute's Industry Ground Water Protection Initiative."
The licensee has notified the NRC Resident Inspector and will inform state and local agencies of this event.
"Heating Steam condensate containing 9,430 picocuries per liter [pCi/L] of tritium overflowed from the Main Warehouse between November 22, 2011 and November 29, 2011. The US EPA drinking water limit for tritium is 20,000 pCi/L.
"The Warehouse Condensate Return system failed to operate which resulted in the overflow of the Heating Steam condensate. There was a potential for the condensate to enter the environment where it could reach groundwater. The released volume for this event was conservatively calculated to be up to 3,900 gallons. The 122 Condensate Return Pump was replaced and the system was restored to service.
"This voluntary report is in accordance with the Nuclear Energy Institute's Industry Ground Water Protection Initiative."
The licensee has notified the NRC Resident Inspector and will inform state and local agencies of this event.