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Event Notification Report for December 30, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/29/2011 - 12/30/2011

** EVENT NUMBERS **


47413 47554 47556 47557 47558 47561

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 47413
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: CHARLES TEAL
Notification Date: 11/03/2011
Notification Time: 23:26 [ET]
Event Date: 11/03/2011
Event Time: 18:00 [EDT]
Last Update Date: 12/29/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
NEIL PERRY (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

DIESEL GENERATOR STARTING AIR NOT COMPLIANT WITH APPENDIX R REQUIREMENTS

"During the conduct of a system vulnerability assessment by Engineering on the emergency diesel system. a discussion was held regarding the impact of a fire on the DG starting air system.

"Subsequently it was recognized that components of the system were vulnerable to damage during a fire. A review of the Appendix R analysis was conducted and it was determined that this vulnerability was not analyzed in the evaluation.

"This is reportable to Unit 2, as Unit 1 has a separate diesel building for the 1-Alpha emergency diesel."

The NRC Resident Inspector has been notified.

* * * RETRACTION ON 12/29/11 AT 1556 EST FROM GIOFFRE TO HUFFMAN * * *

"The Appendix R analysis was updated and no changes to the plant or procedures resulted. Therefore, no unanalyzed condition that significantly degraded plant safety existed. This event is being retracted. The NRC Resident Inspector has been notified."

R1DO (Joustra) notified.

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Agreement State Event Number: 47554
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: MIDAMERICAN ENERGY
Region: 3
City: MUSCATINE State: IA
County:
License #: 0040-1-70-FG
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/27/2011
Notification Time: 12:57 [ET]
Event Date: 12/27/2011
Event Time: 08:00 [CST]
Last Update Date: 12/27/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK RING (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - NUCLEAR GAUGE SHUTTER MISSING

The following information was received via email from the State of Iowa:

"The RSO of Louisa Generating Station/MidAmerican located at 8602 172nd Street, Muscatine, Iowa 52761 reported to IDPH [Iowa Department of Public Health] at 0930 CST that at approximately 0800 [CST], the courtyard operator was performing rounds and noticed that the shutter on a Texas Nuclear device (model # 5192, serial # B-2724, 50 mCi, Cesium 137) in crusher feeder / hopper 1B was detached from the device and laying on the grating directly underneath the device. [The RSO] suspects that the shutter vibrated off. The shutter is usually in the open position as the hopper is operational 24/7 measuring coal as it moves through the hopper. There were no employees in the hopper and the device sits 10-12 feet above the ground. After [IDPH spoke] with [the RSO] and considering their license conditions, [the RSO] is calling the service provider to come to their location and assess the repositioning of the shutter."

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Power Reactor Event Number: 47556
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TOM FOWLER
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/29/2011
Notification Time: 02:00 [ET]
Event Date: 12/28/2011
Event Time: 22:30 [EST]
Last Update Date: 12/29/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JUDY JOUSTRA (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

OFFSITE NOTIFICATION TO STATE OF NEW JERSEY DUE TO A DISCHARGE INTO THE DELAWARE RIVER

"At 2209 EST on 12/28/11 following a planned station service water (SSW) pump swap, a motor operated valve (MOV) failed to close in a water treatment system for the SSW pump that was secured. This was discovered shortly after the pump was removed from service by the field operators. The control room was notified at 2230 EST of the issue and ongoing efforts to troubleshoot and correct the malfunction. The release was terminated by closing a manual isolation valve at 2240 EST. This malfunction resulted in the discharge of approximately 17 gallons of 15% sodium hypochlorite (product) to the idle SSW pump intake which communicates with the Delaware river, The idle SSW pump was restarted at 2240 EST thus withdrawing all residual product from the intake and directing it to plant treatment systems (dechlorination on the cooling tower outfall). A sample was obtained from the Delaware river just outside the intake structure and there was no detectable chlorine in the sample and there were no abnormal conditions noted on the river. Based on Environmental Licensing review, this is reportable to the state of NJDEP [New Jersey Department of Environmental Protection] within 2 hours. The report to the state was initiated at 0017 EST on 12/29/11.

"The HC Senior NRC Resident has been informed. Affected systems are limited to the Station Service Water (SSW) system and the Sodium Hypochlorite water treatment system. There were no actuations or initiating signals. There was no impact on plant operations and these systems remain fully operable. The failure was limited to the MOV which has been isolated via a manual valve. There was nothing unusual or not understood. All safety related equipment continues to function as required. There were no injuries or reported wildlife impact."

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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
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
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
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

Event Text

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).

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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
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
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
ERIC DUNCAN (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

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.

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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
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
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
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

Event Text

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.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012