Event Notification Report for December 29, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/28/2011 - 12/29/2011
Power Reactor
Event Number: 47561
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JEFF MIELL
HQ OPS Officer: JOHN KNOKE
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JEFF MIELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/30/2011
Notification Time: 02:34 [ET]
Event Date: 12/29/2011
Event Time: 20:09 [CST]
Last Update Date: 12/30/2011
Notification Time: 02:34 [ET]
Event Date: 12/29/2011
Event Time: 20:09 [CST]
Last Update Date: 12/30/2011
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):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (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 |
LPCI INSTRUMENTATION REQUIRED REPAIR AND RECALIBRATION
"Surveillance testing on Low Pressure Coolant Injection (LPCI) Loop Select logic yielded results requiring repairs to 3 of the 4 Recirculation Riser Differential Pressure instruments and calibration of all four. The instrument conditions were such that there was not reasonable assurance that the safety function of LPCI could be fulfilled during a design basis Loss Of Coolant Accident (LOCA). As such, this condition is reportable under 10 CFR 50.72(b)(3)(v)(D).
"The four instruments support the LPCI Loop Select logic by providing input that successfully identifies and directs LPCI flow to the unbroken recirculation loop so that core reflooding is accomplished in time to ensure that the fuel peak cladding temperature remains below the limits of 10CFR50.46. The instruments are arranged in a one-out-of-two-twice logic.
"The instruments were last calibrated September 26-29, 2011. At that time, pre-planned maintenance was performed to improve instrument reliability. Current testing indicates a repetitive issue with instrument drift. Repair and recalibration of each degraded instrument has been completed as the surveillance test has progressed such that the current status supports fulfillment of the safety function.
"The instrument type (Barton) is used in several safety systems, but there has been no notable degradation in other applications."
The licensee has notified the NRC Resident Inspector.
"Surveillance testing on Low Pressure Coolant Injection (LPCI) Loop Select logic yielded results requiring repairs to 3 of the 4 Recirculation Riser Differential Pressure instruments and calibration of all four. The instrument conditions were such that there was not reasonable assurance that the safety function of LPCI could be fulfilled during a design basis Loss Of Coolant Accident (LOCA). As such, this condition is reportable under 10 CFR 50.72(b)(3)(v)(D).
"The four instruments support the LPCI Loop Select logic by providing input that successfully identifies and directs LPCI flow to the unbroken recirculation loop so that core reflooding is accomplished in time to ensure that the fuel peak cladding temperature remains below the limits of 10CFR50.46. The instruments are arranged in a one-out-of-two-twice logic.
"The instruments were last calibrated September 26-29, 2011. At that time, pre-planned maintenance was performed to improve instrument reliability. Current testing indicates a repetitive issue with instrument drift. Repair and recalibration of each degraded instrument has been completed as the surveillance test has progressed such that the current status supports fulfillment of the safety function.
"The instrument type (Barton) is used in several safety systems, but there has been no notable degradation in other applications."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 47557
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: SCOTT AREBAUGH
HQ OPS Officer: JOHN KNOKE
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: SCOTT AREBAUGH
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/29/2011
Notification Time: 10:59 [ET]
Event Date: 12/29/2011
Event Time: 09:10 [CST]
Last Update Date: 12/29/2011
Notification Time: 10:59 [ET]
Event Date: 12/29/2011
Event Time: 09:10 [CST]
Last Update Date: 12/29/2011
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):
MARK RING (R3DO)
MARK RING (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 |
PLANNED MAINTENANCE ON PLANT PROCESS COMPUTER
"A planned maintenance evolution at the Duane Arnold Energy Center (DAEC} to replace power supplies in the plant process computer (Link 2) will result in a loss of some SPDS indications for a duration of less than 5 hours. No other indications or annunciators will be unavailable during this maintenance to affect the plant's ability to assess or monitor an accident of transient in progress."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM SCOTT AREBAUGH TO JOHN KNOKE AT 1146 EST ON 12/29/11 * * *
At 1006 CST on 12/29/11 the plant process computer (Link 2) was successfully restored and SPDS is functioning properly and returned to service.
The licensee has notified the NRC Resident Inspector. Notified R3DO (Duncan).
"A planned maintenance evolution at the Duane Arnold Energy Center (DAEC} to replace power supplies in the plant process computer (Link 2) will result in a loss of some SPDS indications for a duration of less than 5 hours. No other indications or annunciators will be unavailable during this maintenance to affect the plant's ability to assess or monitor an accident of transient in progress."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM SCOTT AREBAUGH TO JOHN KNOKE AT 1146 EST ON 12/29/11 * * *
At 1006 CST on 12/29/11 the plant process computer (Link 2) was successfully restored and SPDS is functioning properly and returned to service.
The licensee has notified the NRC Resident Inspector. Notified R3DO (Duncan).
Non-Agreement State
Event Number: 47558
Rep Org: ST. VINCENT HOSPITAL
Licensee: ST. VINCENT HOSPITAL
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-00133-02
Agreement: N
Docket:
NRC Notified By: ED WROBLEWSKI
HQ OPS Officer: BILL HUFFMAN
Licensee: ST. VINCENT HOSPITAL
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-00133-02
Agreement: N
Docket:
NRC Notified By: ED WROBLEWSKI
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/29/2011
Notification Time: 11:50 [ET]
Event Date: 12/29/2011
Event Time: 09:00 [EST]
Last Update Date: 12/29/2011
Notification Time: 11:50 [ET]
Event Date: 12/29/2011
Event Time: 09:00 [EST]
Last Update Date: 12/29/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
ERIC DUNCAN (R3DO)
ANGELA MCINTOSH (FSME)
ERIC DUNCAN (R3DO)
ANGELA MCINTOSH (FSME)
RADIOPHARMACEUTICAL PACKAGE RECEIVED WITH EXTERNAL CONTAMINATION
The Radiation Safety Officer of St. Vincent Hospital reported that the facility received a radiopharmaceutical shipment of I-131 with excess surface contamination on the outside of the shipping container. When the surface of the shipping container was initially swipe tested, the contamination was measured at 734 dpm per 100 sq centimeters. A follow-up swipe survey pinpointed the contamination to just one side of the shipping container and was found to be 581 dpm per 100 sq centimeters. Additional isotopic analysis determined that the radioactive contaminant was I-131. Integrity of the package was not compromised. The inside of the shipping container was tested and found to be clean. The two I-131 vials in the container were also verified to be intact and clean. The hospital called the radiopharmaceutical supplier, Cardinal Health Systems of Indianapolis, to notify them of the contamination found on the package. The shipping container has been isolated in a controlled area at St. Vincent Hospital.
The Radiation Safety Officer of St. Vincent Hospital reported that the facility received a radiopharmaceutical shipment of I-131 with excess surface contamination on the outside of the shipping container. When the surface of the shipping container was initially swipe tested, the contamination was measured at 734 dpm per 100 sq centimeters. A follow-up swipe survey pinpointed the contamination to just one side of the shipping container and was found to be 581 dpm per 100 sq centimeters. Additional isotopic analysis determined that the radioactive contaminant was I-131. Integrity of the package was not compromised. The inside of the shipping container was tested and found to be clean. The two I-131 vials in the container were also verified to be intact and clean. The hospital called the radiopharmaceutical supplier, Cardinal Health Systems of Indianapolis, to notify them of the contamination found on the package. The shipping container has been isolated in a controlled area at St. Vincent Hospital.