Event Notification Report for August 13, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/12/2013 - 08/13/2013

** EVENT NUMBERS **


49235 49237 49238 49257 49265 49267 49270

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Non-Agreement State Event Number: 49235
Rep Org: COVANTA INDIANAPOLIS, INC.
Licensee: COVANTA INDIANAPOLIS, INC.
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-32836-01
Agreement: N
Docket:
NRC Notified By: BRIAN FOSTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/05/2013
Notification Time: 08:49 [ET]
Event Date: 08/02/2013
Event Time: [EDT]
Last Update Date: 08/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
STEVE ORTH (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

STUCK SHUTTER ON A LEVEL DETECTOR

One source holders for a Ronan Engineering, model GS-400, level detector had the shutter door seized in the open position which is the normal operating position. The licensee was unable to free up the shutter at their facility and has contacted the manufacturer (Ronan) for assistance. The source is secure and not leaking. The radiation levels are normal around the device. There is no possibility of exposure to individuals due to the active beam not being accessible.

Manufacturer: Ronan Engineering
Model: GS-400
Activity: 100mCi
Isotope: CS-137
S/N: 5134C0

* * * UPDATE FROM BRIAN FOSTER TO PETE SNYDER AT 1601 EDT ON 8/5/13 * * *

As of 1600 EDT on 8/5/13 the shutter door has been freed and now cycles normally. No further action is needed and Ronan's Engineering service has been canceled. Notified R3DO (Lara) and FSME Event Resource via email.

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Agreement State Event Number: 49237
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: IOWA HEALTH - DES MOINES
Region: 3
City: DES MOINES State: IA
County:
License #: 0310-1-77-HDR
Agreement: Y
Docket:
NRC Notified By: LEO WARDROBE
HQ OPS Officer: PETE SNYDER
Notification Date: 08/05/2013
Notification Time: 13:14 [ET]
Event Date: 08/01/2013
Event Time: [CDT]
Last Update Date: 08/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JULIO LARA (R3DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - WRONG FRACTIONAL DOSE ADMINISTERED TO PATIENT

The licensee reported the administration of a 700 cGy fractional dose instead of the 500 cGy prescribed fractional dose to a patient during GYN treatment on 8/1/13. The 700 cGy fraction was prepared for another patient. The isotope involved was Ir-192.

The fraction was the second of a three fraction total dose of 1500 cGy. The final fraction will be adjusted so that the total dose to the patient is 1500 cGy. The prescribing physician had been informed. The patient will be informed of the adjustment prior to administration of the final fraction on 8/8/13.

There are no anticipated adverse consequences to the patient. The cause is under investigation and the licensee is still discussing potential corrective actions.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Agreement State Event Number: 49238
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: OMAHA PUBLIC POWER DISTRICT
Region: 4
City: OMAHA State: NE
County:
License #: 01-39-04
Agreement: Y
Docket:
NRC Notified By: RANDY LAMBERT
HQ OPS Officer: PETE SNYDER
Notification Date: 08/05/2013
Notification Time: 15:52 [ET]
Event Date: 08/05/2013
Event Time: 09:50 [CDT]
Last Update Date: 08/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - SHUTTER STUCK ON A PROCESS GAUGE

The State of Nebraska submitted the following information via email:

"The licensee uses fixed industrial gauges for measuring levels in fly ash hoppers at the station's precipitator building. The industrial fixed gauges contain a Cesium 137 sealed source. The Cesium 137 sources were originally installed in April, 1984, and at the time contained 50 millicuries per source. The sources were manufactured and installed by Kay Ray Inc. The gauge that experienced the event was Kay Ray Gauge, Housing Model #7080 and housing serial number 16784H. The source capsule manufacture was Amersham model no. CDC 800 and K-R Ref. Number serial number 15095 V.

"In accordance with their license conditions two of the station's chemists were securing the Unit #5's precipitator sources in preparation for an inspection of the precipitator. The 'external' source closure mechanism for Unit #5 precipitator's 5FA-3E & 4E hoppers did not operate as designed and the shutter did not close when the handle on the floor was operated.

"The radiation sources, which are part of a hopper level sensor, are mounted between two fly ash hoppers 20 feet off the floor. The source closure mechanisms are connected to a handle located at the floor level by a flexible cable. These closure cables are secured to the structures so that when the handles are operated the control cables slide inside a sheath. On the 5FA-3E & 4E source, the shutter closure cable became loose up at the source which allowed the whole cable to slide back and forth when the handle was operated to try and close the shutter. This type of failure has been seen in the past and is easily fixed by tightening the screw which secures the end of the cable to the structure. This required a scaffold to be built up to the source level. A contractor came on site at 12:30 pm [CDT] on 8/5/2013 and erected a scaffold so repairs could be made."

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Research Reactor Event Number: 49257
Facility: NATIONAL INST OF STANDARDS & TECH
RX Type: 20000 KW TEST
Comments:
Region: 1
City: GAITHERSBURG State: MD
County: MONTGOMERY
License #: TR-5
Agreement: Y
Docket: 05000184
NRC Notified By: SEAN O'KELLY
HQ OPS Officer: CHARLES TEAL
Notification Date: 08/09/2013
Notification Time: 14:29 [ET]
Event Date: 08/08/2013
Event Time: 14:30 [EDT]
Last Update Date: 08/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
ALEXANDER ADAMS (PRLB)
XIAOSONG YIN (PM)
PATRICK ISAAC (IR L)

Event Text

TECHNICAL SPECIFICATION VIOLATION DURING CORE RELOAD

While the reactor was shut down for planned maintenance, the licensee was performing a core reload in accordance with procedure. This procedure requires control rods elements to be withdrawn to get a count rate. As expected, the reactor became critical at some point.

It was noted on 8/8/13 that this criticality was a violation of Technical Specification (TS) 3.1.3 which prohibits operating the reactor with any grid position empty.

This procedure has been used multiple times in the past. A core reload is performed approximately every 4 years.

The licensee plans on either modifying their procedure or TS to prevent this in the future.

* * * UPDATE FROM SEAN O'KELLY TO HOWIE CROUCH AT 1624 EDT ON 8/12/13 * * *

Further investigation determined that two other technical specifications were violated during the core reload experiment being conducted.

Technical specification 3.3.1(1) requires reactor water level to be no more than 25" below the overflow standpipe during critical operations. This TS was violated because the experiment was being conducted with the water level at refueling level which is lower than 25" below the standpipe and the reactor became critical, as expected.

Technical specification 3.9.2.1 prohibits critical operation until all fuel elements handled are locked into their grid positions. By the very nature of the experiment, this TS was violated.

The licensee will be notifying their NRC Project Manager. Notified NRR (Yin, Adams, Isaacs).

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Power Reactor Event Number: 49265
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DONALD DETTMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 08/12/2013
Notification Time: 09:23 [ET]
Event Date: 08/12/2013
Event Time: 08:59 [EDT]
Last Update Date: 08/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MEL GRAY (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 VENTILATION REMOVED FROM SERVICE FOR PLANNED MAINTENANCE

"This condition does not affect the health and safely of the public or the operation of the facility.

"At 0859 EDT on August 12, 2013, pre-planned maintenance commenced which affects the Technical Support Center (TSC) ventilation. The scope of the maintenance is to replace the TSC ventilation charcoal filters and sampling canisters. This maintenance is currently scheduled to be completed by August 20, 2013.

"TSC emergency functionality during a radiation release event requires TSC ventilation be maintained. The actual TSC ventilation emergency function for iodine removal will be lost for the duration of the pre-planned maintenance. If an emergency should occur and a radioactive release occurs, the ventilation system will not provide iodine removal capability.

"If an emergency is declared and the TSC facility activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological or other conditions. If relocation of the TSC staff becomes necessary, the staff will be directed to relocate to the alternate TSC location. The alternate TSC has been verified to have electrical power and communication capability. The Technical Support Center Directors have been notified.

"This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49267
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE WEISE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/12/2013
Notification Time: 14:56 [ET]
Event Date: 08/12/2013
Event Time: 13:35 [EDT]
Last Update Date: 08/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY POWELL (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

LOSS OF ACCIDENT ASSESSMENT CAPABILITY DUE TO PLANNED MAINTENANCE ON THE PLANT STACK RADIATION MONITOR

The licensee will be removing the station stack radiation monitor, RM-8169, from service for planned maintenance. This constitutes a loss of assessment capability under 10CFR50.72(b)(3)(xiii).

The licensee notified the State of Connecticut, the city of Waterford and the NRC Resident Inspector.

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Power Reactor Event Number: 49270
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KEVIN ABELL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/12/2013
Notification Time: 20:56 [ET]
Event Date: 08/12/2013
Event Time: 15:50 [EDT]
Last Update Date: 08/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT SHAEFFER (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

Event Text

TECHNICAL SUPPORT CENTER (TSC) VENTILATION OUT OF SERVICE DUE TO DISCOVERED CONDITION

"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility. There is no impact to public health and safety due to this condition.

"On August 12, 2013 at 1550 [EDT], during routine testing of the HVAC [Heating Ventilation Air Conditioning] system, the TSC Emergency filtration Fan, MUF-1, was observed to have high vibration levels. Maintenance is working to determine the cause of the high vibrations and to make necessary repairs.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. If the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions, the Site Emergency Coordinator - TSC will relocate the TSC staff to an alternate TSC in accordance with applicable site procedures. The Emergency Response Organization team has been notified of the condition and the possible need to respond to or relocate to an alternate TSC during an emergency.

"An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Wednesday, March 24, 2021