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Event Notification Report for March 5, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/04/2014 - 03/05/2014

** EVENT NUMBERS **


49852 49853 49855 49867 49868 49869 49870 49871

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Agreement State Event Number: 49852
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: GEISINGER HEALTH SYSTEMS
Region: 1
City: DANVILLE State: PA
County:
License #: PA-0006
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: PETE SNYDER
Notification Date: 02/25/2014
Notification Time: 08:56 [ET]
Event Date: 03/01/2011
Event Time: [EST]
Last Update Date: 02/25/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANNE DeFRANCISCO (R1DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - EXTERNAL CONTAMINATION IDENTIFIED ON A PACKAGE

The following information was received from the Commonwealth of Pennsylvania via fax:

"Notifications: Licensee emailed notification to the Department's [Pennsylvania Department of Environmental Protection] South Central Regional Office on March 2, 2011. This was initially evaluated as not exceeding the limits of  71.47; however, further assessment determined it as an immediate reporting event under 20.1906(d)(1).

"Event Description: On March 1, 2011, a Nuclear Medicine Technologist from Geisinger logged in a package from Triad Isotopes radio pharmacy. Exposure on the surface of one of the containers labeled White I was measured to be 14 mR/hr. The contamination was found to be limited to the handle of the package. The inside of the container and its contents were not contaminated. The contents were removed and the empty contaminated package was double bagged and placed in decay storage.

"According to calculations provided by the licensee, the initial net wipe reading of the handle area on the suspect package was 10,670 dpm for an area of 6 [inch] x 1.5 [inch] or 15 cm x 3. 8 cm. Assuming a 10% wipe efficiency, the activity per unit area was 1,840 dpm/cm2 (0.8 mCi/cm2), which exceeded the maximum permissible limit of 220 dpm/cm2 as noted in  71.47.

"Cause Of The Event: Cross-contamination from the radio pharmacy.

"Actions: The Department called Triad Isotopes on March 2, 2011. It was stated that the driver, vehicle, and all other areas that the driver and the package came into contact with, were surveyed and no contamination was found. Triad Isotopes confirmed that the shipment met the requirements of the Radioactive White I when it left and only contained 20 mCi of Tc-99m. No further actions were taken."

PA Event Report ID No. PA110005

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Agreement State Event Number: 49853
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: TEI ANALYTICAL SERVICES
Region: 1
City: WASHINGTON State: PA
County:
License #: PA-1164
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: PETE SNYDER
Notification Date: 02/25/2014
Notification Time: 08:56 [ET]
Event Date: 04/05/2011
Event Time: [EST]
Last Update Date: 02/25/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANNE DeFRANCISCO (R1DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE FAILS TO RETRACT

The following information was received from the Commonwealth of Pennsylvania via fax:

"Notifications: This was originally reported to the NMED within 30-days per 10 CFR 34.101 (a)(2) on May 5, 2011 and was assigned NMED Number 110278; however, after further evaluation it was determined it should have also been reported under 10 CFR 30.50 which requires immediate reporting.

"Event Description: TEI Analytical Services was performing gamma radiography of pipe welds at its facility in Washington, PA. During the first exposure, the radiography source assembly was unable to be retracted to its shielded position due to excessive bend in the guide tube. When retraction of the source was attempted resistance was encountered within 1/4 turn of full retraction. The source was returned to the collimator and a second attempt was made to retract the source. Again, resistance was encountered at the same location. Additional attempts to retract the source were terminated and the RSO was notified.

"Equipment information:

Exposure Device: Make: Source Production and Equipment Company
Device Model: SPEC-150
Serial #:0418
Date Quarterly Inspection/Maintenance performed: 03/08/2011
Sealed Source: Isotope: Ir-192
Make: Source Production and Equipment Company
Model: G-60
Serial #: SB2506 .
Activity: 105 Ci (3885 GBq)

"Cause of the Event: Exceeding the maximum 6 [inch] radius bend for guide tube. A longer tube would have prevented the event.

"Actions: The device was operated by the RSO to retract the source conventionally and the resistance was significant. The RSO made one entry to the area to lower the stand height; thereby, decreasing the radius of the guide tube. Total time for the entry was 11 seconds including walking to the stand from the shieldwall and return. Time to lower stand was 2 seconds. The source was cranked back into the device and the event was terminated. The equipment was disassembled and inspected by the RSO. No physical damage was evident to the guide tube, or to the external/internal materials of the guide tube."

PA Event Report ID No. PA110010

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Agreement State Event Number: 49855
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSAL WELL SERVICES
Region: 1
City: LEMON State: PA
County: WYOMING
License #: PA-1446
Agreement: Y
Docket:
NRC Notified By: JOSEPH M. MELNIC
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/25/2014
Notification Time: 15:00 [ET]
Event Date: 02/23/2014
Event Time: [EST]
Last Update Date: 02/25/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANNE DeFRANCISCO (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - SHUTTER FAILURE ON BERTHOLD DENSITY GAUGE

The following information was received from the Commonwealth of Pennsylvania via fax:

"NOTIFICATIONS: Licensee notified the Department [PA DEP Bureau of Radiation Protection] via email and voice message after close of business on February 24, 2014. This event is reportable within 24-hours per 10 CFR 30.50(b)(2).

"EVENT DESCRIPTION: During the pressure pumping operations at a well fracturing job site, personnel observed an unexpected fluctuation in density readings. The density gauge was inspected and attempts to turn the shutter handle to the closed position caused it to separate from the body of the gauge. It was observed that the roll pin, which attaches the shutter handle to the shutter shaft, had come out causing the shutter handle to separate from the shield housing. The pin was replaced, the handle reattached, and the gauge shutter was closed and locked. No elevated exposure to personnel is anticipated. The gauge was then removed from service, placed into storage, and the manufacturer was notified.

Manufacturer: Berthold
Model: LB 8010
Serial Number: 10049
Isotope: Cs-137
Activity: 20 mCi
Source Serial Number: 0180/08

"CAUSE OF THE EVENT: The roll pin, which attaches the shutter handle to the shutter shaft, came out causing the shutter handle to be removed from the shield housing. More information will be forwarded upon receipt of final report.

"ACTIONS: The density gauge has been removed from operations and is in storage in a Williamsport, Pennsylvania facility. The licensee is working with the manufacturer to investigate the event, make repairs, and determine root cause. The Department plans to do a reactive inspection."

PA Event Report ID No: PA140006

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Power Reactor Event Number: 49867
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUGLAS LaMARCA
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/04/2014
Notification Time: 01:50 [ET]
Event Date: 03/04/2014
Event Time: 00:25 [EST]
Last Update Date: 03/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
FRED BOWER (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 N 0 Cold Shutdown 0 Cold Shutdown

Event Text

SECONDARY CONTAINMENT DECLARED INOPERABLE DURING SURVEILLANCE TESTING

"On March 4, 2014 at 0025 EST, Secondary Containment drawdown testing surveillance failed to meet acceptance criteria of SR 3.6.4.1.5 due to maximum flow rate exceeding the allowable value. Secondary Containment drawdown testing was being performed on Reactor Building Zone 1 and Zone 3 with Zone 2 HVAC shutdown.

"Upon failure of the surveillance, Secondary Containment ventilation was realigned to a previous successfully tested and known operable alignment for Zones 1, 2 and 3. This alignment consists of all Reactor Building Zones in service and Zone 3 aligned to the Railroad Bay.

"Upon restoration of Secondary Containment ventilation to a known operable alignment, operability was restored and Secondary Containment LCO 3.6.4.1 was cleared at 0128 EST on March 4, 2014.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG-1022, Rev. 3, Section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 49868
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL M. JONES
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/04/2014
Notification Time: 05:05 [ET]
Event Date: 03/04/2014
Event Time: 01:43 [EST]
Last Update Date: 03/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
FRED BOWER (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

UNIT 2 MANUAL REACTOR SCRAM FOLLOWING LOSS OF A UNINTERRUPTIBLE POWER SUPPLY [UPS]

"At 0137 EST Nine Mile Point Unit 2 experienced a loss of an uninterruptible power supply 2VBB-UPS3B which resulted in a half scram and half isolations. This caused a loss of cooling water to the Reactor Recirculation Pumps and other indications for the loss of power.

"At 0143 EST a Manual Reactor Scram was inserted due to the rise of temperatures on the Reactor Recirculation Pump seal cavity temperature and motor winding temperature.

"The reactor building ventilation radiation monitor went non-functional when the reactor building isolated on the loss of UPS power. The standby gas treatment system was started as required and restored the reactor building differential pressure.

"This is a 4-Hour report for 10CFR50.72(b)(2)(iv)(B) RPS Actuation and 8-Hour report for 10CFR50.72(b)(3)(xiii) Loss of Emergency Assessment Capability.

"The NRC Resident inspector has been notified."

All systems functioned as required following the manual scram. All control rods fully inserted.

The cause of the loss of the UPS is under investigation.

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Power Reactor Event Number: 49869
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JIM RITCHIE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/04/2014
Notification Time: 06:04 [ET]
Event Date: 03/04/2014
Event Time: 05:02 [EST]
Last Update Date: 03/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
FRED BOWER (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

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED MAINTENANCE

"A planned maintenance evolution at the Oyster Creek Nuclear Generating Station has removed the Technical Support Center (TSC) ventilation system from service. The TSC ventilation system will be rendered non-functional during the course of the work activities. The TSC ventilation is expected to be out of service for approximately twenty hours from 0500 [EST] to 2400, today, March 4, 2014.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.

''This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to potential loss of the TSC. An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49870
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEVIN HOLLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/05/2014
Notification Time: 01:37 [ET]
Event Date: 03/04/2014
Event Time: 19:17 [CST]
Last Update Date: 03/05/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
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
2 N Y 95 Power Operation 95 Power Operation

Event Text

MOMENTARY LOSS OF SECONDARY CONTAINMENT

"At 1917 hours [CST] on March 4, 2014, the Unit 1B fuel pool radiation monitor spiked high due to an invalid actuation which caused the U1 and U2 reactor building ventilation system to isolate (the control room ventilation system also isolated as designed). The Standby Gas Treatment system was already in operation for a scheduled surveillance as of 1900 hours on March 4, 2014. During the ensuing pressure transient, the Reactor Building differential pressure momentarily went positive. As a result, Secondary Containment was declared inoperable.

"Given the temporary loss in secondary containment, this event is reportable under 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

After the transient, the reactor building ventilation system was shutdown for scheduled maintenance and the control room ventilation system was returned to its normal configuration. The Standby Gas Treatment system was operating to support planned reactor building ventilation system maintenance. Troubleshooting of the radiation monitor spike is underway.

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Power Reactor Event Number: 49871
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAN WILLIAMSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/05/2014
Notification Time: 02:26 [ET]
Event Date: 03/04/2014
Event Time: 23:34 [EST]
Last Update Date: 03/05/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
FRED BOWER (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

UNIT 1 MANUALLY SCRAMMED DURING A RAPID SHUTDOWN IN RESPONSE TO A TURBINE EHC FAILURE

"At 2334 EST on 3/4/14 Unit 1 was manually scammed during a Rapid Plant Shutdown. The Rapid Plant Shutdown was initiated due to an Electro Hydraulic [Control] [EHC] System failure resulting in all Low Pressure Turbine lntercept Valves failing closed.

"The shutdown was normal and the plant is stable in Hot Shutdown with normal pressure control via the Main Steam Bypass Valves to the Main Condenser and normal level control using Feedwater."

The licensee informed both State and local agencies and the NRC Resident Inspector. A press release will be issued by the licensee.

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014