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Event Notification Report for April 25, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/24/2013 - 04/25/2013

** EVENT NUMBERS **


48261 48481 48556 48917 48930 48931 48933 48955 48962 48963 48964 48965

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Agreement State Event Number: 48261
Rep Org: NV DIV OF RAD HEALTH
Licensee: UNIVERSITY OF NEVADA
Region: 4
City: LAS VEGAS State: NV
County:
License #: 03-13-0305-01
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/31/2012
Notification Time: 15:48 [ET]
Event Date: 10/01/2011
Event Time: [PDT]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - STUDENT RECEIVED POTENTIAL INHALATION OVEREXPOSURE

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

"A graduate student inhaled a mixture of U-233 and U-238 while working in the lab grinding a compound of Uranium Octoxide. [The graduate student] used a glove box instead of the hood with the HEPA filter, contrary to UNLV [University of Nevada Las Vegas] approved procedure.

"This happened twice and could have been between October 1, 2011 and April 1, 2012.

"The first bioassay, based on an inhalation date of October 1, 2011, showed 17.72 rem total. When the inhalation date was assumed to be April 1, 2012, the result was 5.52 rem.

"[U-233]*1.6 = [U-238] contribution.

"The student will be getting a third bioassay on September 5, 2012 at the Lawrence Livermore National Lab (LLNL). This will involve a low-energy chest count to detect Th-234 and an organ count, looking at the kidneys for Uranium.

"The student has been restricted from all lab work since April.

"The bioassay was done at Test America."

* * * UPDATE AT 1553 EDT ON 10/24/12 FROM SNEHA RAVIKUMAR TO S. SANDIN * * *

The following update was received from the State of Nevada via email:

"NMED Item No.: NV120022

"Preliminary results:

"1. September 5, 2012:

Low-energy lung count, kidney count and hand count were performed at LLNL.
The lung count was less than MDA for U-233, Th-234, U-234 & U-2235.
The detect/non-detect kidney & hand counts were both non-detect.

"2. September 12, 2012:

Third Bioassay results received.
U-238 - 0.66 dpm/sample
U-235 - less than CRDL
U-233/234 - 1.25 dpm/sample"

Notified R4DO (Hagar) and FSME Events Resource via email.

* * * UPDATE AT 1540 EDT ON 11/15/12 FROM RAVIKUMAR TO HUFFMAN * * *

The following update was received from the State of Nevada via email:

"All personnel having access to the UNLV lab where the original uptake occurred had bioassay samples taken. UNLV determined that 46 persons should be in this group, including the RSO and ARSO. From the data submitted thus far, an additional graduate student appears to have received an uptake. This student has been restricted from further RAM work and a dose assessment undertaken. The actual dose will be dependent on the time and source of the uptake. If the timeframe and source are the same as that of the original graduate student, the magnitude will be the same. Thirteen remaining bioassays remain to be analyzed. Three of the thirteen are yet to be collected. The RSO attributed his elevated uptake to previous DOD work. The latest ten bioassays were collected within the last three weeks and with expedited processing results, should be available by mid-December."

Notified the R4DO (Drake) and FSME Events Resource via e-mail.

* * * UPDATE AT 1411 EST ON 02/12/13 FROM RAVIKUMAR TO SNYDER * * *

The following update was received from the State of Nevada via email:

"Dependent on the particle size of the uptake the grad student's exposure could be either 6760 mrem for size M (medium) particles versus 154 mrem for size S (small) particles. UNLV has indicated a delay till March, 2013, for this analysis. It appears only the one Grad Student had an uptake.

"What corrective action(s) were taken to prevent a recurrence?

"Existing procedures were reviewed & rewritten, and additional new monitoring, controls, training and procedures are now in place to prevent a recurrence."

Notified the R4DO (Hagar) and FSME Events Resource via e-mail.

* * * UPDATE AT 1152 EDT ON 04/24/13 FROM SNEHA RAVIKUMAR TO CHARLES TEAL * * *

The following is excerpted from an email received from the State of Nevada:

"All of the activity ratios (especially the one from the ICP-MS [Inductively Coupled Plasma Mass Spectrometry], which has the lowest uncertainty) are consistent with that of natural uranium. This supports the conclusion that the student's observed bioassay results are the result of an intake of natural uranium form non-occupational sources and not a result of material she was handling at UNLV."

Notified R4DO (Whitten) and FSME Event Resource via email.

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Power Reactor Event Number: 48481
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DON SHEEHAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/06/2012
Notification Time: 03:56 [ET]
Event Date: 11/06/2012
Event Time: 00:06 [EST]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GLENN DENTEL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

HIGH PRESSURE COOLANT INJECTION ACTUATION SIGNAL

"On Tuesday, November 06, 2012, at 00:06 EST, during the application of a tag-out associated with feedwater level control, the 12 feedwater flow control valve (FCV-29-137) unexpectedly partially opened. As a result, reactor vessel water level rose to the high level turbine trip set point causing the main turbine to trip. The turbine trip signal then resulted in the initiation of High Pressure Coolant Injection (HPCI) channels 11 and 12 logic. No actual system component starts or actuations occurred as a result of the logic initiation and no actual HPCI injection occurred due to the system configuration, nor was injection required.

"Actions were taken to manually isolate the 12 feedwater flow control valve and reactor vessel water level was restored to normal.

"This meets NRC 8-Hour reporting criteria per 10 CFR 50.72(b)(3)(iv)(A) due to a valid actuation of the High Pressure Coolant Injection System."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM JERRY HELKER TO CHARLES TEAL ON 12/17/12 AT 1543 EST * * *

"This notification is being made to retract Event Notification (EN) #48481, which reported an automatic actuation of the High Pressure Coolant Injection (HPCI) system initiation logic.

"The HPCI system is automatically initiated based on conditions representing a small break loss of coolant accident (LOCA). The initiation signals are:

- Low reactor water level - This is a direct indication of a potential loss of adequate core cooling.
- Turbine trip - During a LOCA within the drywell, high drywell pressure due to the line break will cause a reactor scram, which causes a turbine trip, which then by design initiates the HPCI system.

"The event occurred with the reactor in the cold shutdown condition, with the main turbine and main turbine shaft-driven feedwater pump (#13) out of service. In the cold shutdown condition, the probability of a LOCA is low and the HPCI system is not required by the Technical Specifications to be operable. Neither of the conditions requiring actuation of the safety function of the HPCI system (high drywell pressure or low reactor water level) was present. Although the turbine trip signal was in response to an actual sensed high reactor water level condition, high reactor water level is not a plant condition satisfying the requirement for actuation of the safety function of the HPCI system. With reactor vessel water level high, the safety function of the HPCI system (i.e. to provide adequate core cooling) was already completed. Thus, the HPCI initiation signal was invalid, and the event is not reportable under 10 CFR 50.72(b)(3)(iv)(A)."

The NRC Resident Inspector has been informed. Notified the R1DO (Hunegs).

* * * UPDATE FROM JOHN APRIL TO VINCE KLCO ON 4/24/13 AT 0158 EDT * * *

"Upon further review, it has been determined the event did constitute a valid actuation of the HPCI system and is reportable per 10CFR50.72(b)(3)(4)(A)."

The licensee will notify the NRC Resident Inspector.

Notified the R1DO (Joustra).

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Power Reactor Event Number: 48556
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: MARK BROUSSARD
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/04/2012
Notification Time: 15:48 [ET]
Event Date: 12/04/2012
Event Time: 12:00 [EST]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ALAN BLAMEY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Defueled 0 Defueled

Event Text

TEMPORARY EMERGENCY OPERATING FACILITY ESTABLISHED FOR PLANNED OUTAGE

"In support of the planned upgrades to Crystal River Unit 3's Emergency Operations Facility's (EOF) heating, ventilation and air conditioning (HVAC) system, on Dec. 4, 2012, at 1200 hours Eastern Standard Time a temporary EOF has been established and declared operational. The temporary EOF is located adjacent to the primary EOF and remains outside the 10-mile Emergency Planning Zone. The temporary EOF meets the functional requirements of the primary EOF. During the establishment of the temporary EOF, there was no loss in the functionality of the EOF. If an emergency requiring EOF activation occurs, the temporary EOF will be staffed and activated using emergency planning procedures. The Emergency Response Organization has been briefed on the use of the temporary EOF. Readiness of the temporary EOF has been confirmed by a facility walkdown using existing procedures. This condition has no adverse affect on the public's or employees' health and safety. The EOF HVAC system is scheduled to be out of service for approximately four months.

"The NRC Resident Inspector has been notified."

* * * UPDATE ON 4/24/13 AT 1757 EDT FROM WARREN DEAGLE TO BILL HUFFMAN * * *

"Primary Emergency Operating Facility Outage completed.

"This is a courtesy notification and provides an update to the information provided in Event Notification Number 48556 on December 4, 2012, Eastern Standard Time (EDT).

"The primary Emergency Operations Facility (EOF) at the Crystal River Nuclear Plant has been restored on April 24, 2013, with the completion of the planned maintenance activity on the EOF heating, ventilation and air conditioning (HVAC) system that commenced on December 4, 2012, EDT. The temporary EOF established to support this planned upgrade, previously identified in Event Notification Number 48556, is no longer in use. The primary EOF is currently operational and experienced no loss in functionality during the restoration activities. The Emergency Response Organization has been briefed on the restoration of the primary EOF. This condition has no adverse affect on the public's or employees' health and safety.

"NRC Region II has been notified."

The Licensee has also notified the NRC Resident Inspector.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Agreement State Event Number: 48917
Rep Org: U.S. ARMY
Licensee: U.S. ARMY
Region: 1
City: CAMP LEJEUNE State: NC
County:
License #: 21-32838-01
Agreement: Y
Docket:
NRC Notified By: THOMAS GIZICKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/12/2013
Notification Time: 11:46 [ET]
Event Date: 04/11/2013
Event Time: 13:00 [EDT]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(1) - UNPLANNED CONTAMINATION
Person (Organization):
DAVE PASSEHL (R3DO)
FSME EVENTS RESOURCE ()
JAMES TRAPP (R1DO)

Event Text

TRITIUM LAMP BROKEN DURING MAINTENANCE OF A MORTAR SIGHT

On 4/11/13 at 1300 EDT, a 1 Ci tritium lamp was broken during routine maintenance on a M64 mortar sight unit. The sealed source tritium lamp broke when a wrench hit the tritium module. Surveys were conducted, but the results will not be available until next week. Bioassays are being perform on 4 individuals and based on historic records, the RSO expects minimal intake of less than 5 mrem. The device was bagged, tagged and placed in a secure storage area for future disposal.

The licensee attempted to notify R3 (McCraw).

* * * RETRACTION FROM THOMAS GIZICKI TO VINCE KLCO ON 4/24/13 AT 1004 EDT * * *

The US ARMY is retracting this event due to a miniscule bio-assay indicated dose rate to the four workers (maximum dose of 0.9 mRem to an individual) and survey results of the maintenance shop indicating no contamination. The device has been secured and properly stored for future disposal.

The licensee notified R3 (McCraw).

Notified the R1DO (Joustra), R3DO (Hills) and FSME Events Resource via email.

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Agreement State Event Number: 48930
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: UNSPECIFIED
Region: 1
City:  State: NY
County:
License #: UNSPECIFIED
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/16/2013
Notification Time: 13:32 [ET]
Event Date: 03/25/2013
Event Time: [EDT]
Last Update Date: 04/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM COOK (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOACTIVE SEED MIGRATED DEEPER INTO TISSUE AND WAS NOT REMOVED

The following information was received by facsimile:

"A patient for axillary node dissection with radioactive seed localization had an 8.33MBq 123 I [Iodine] seed placed at tumor site under ultrasound guidance by radiologist. The surgeon successfully removed the tumor and lymph node, however the seed had migrated deeper into tissue and was not removed. The surgeon determined that the new seed location prevented safe extraction due to scarring from previous node removal, mastectomy and reconstructive, surgery. NYS DOH [The New York State Department of Health] received verbal notice within 24 hours and written notice within 15 days. The patient, referring physician, medical oncologist, and radiologist have all been notified. A localized dose at 0.5 cm from the seed of 22.9Gy was calculated, negligible dose at 6 cm. As a corrective action the facility will no longer use radioactive seed localization for axillary node lesions. [Licensee] Policy updates and staff notifications are to be evaluated during the next routine inspection."

Event Report Identification Number: NY-13-01

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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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State Event Number: 48931
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CUDD PUMPING SERVICES
Region: 4
City: CRYSTAL CITY State: TX
County:
License #: G02133
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/16/2013
Notification Time: 16:05 [ET]
Event Date: 04/16/2013
Event Time: [CDT]
Last Update Date: 04/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENTS RESOURCE (EMAI)
ERIC BENNER (NMSS)

Event Text

AGREEMENT STATE REPORT - TRUCK ACCIDENT INVOLVING A FIXED DENSITY GAUGE

The following information was provided by facsimile:

"On April 16, 2013, the Agency [Texas Department of State Health Services] was notified that one of the licensee's trucks had had a blowout on one of its tires which caused the vehicle to roll. The driver was killed in the accident. On the truck is a densitometer which includes a Thermo-Fisher Scientific Model 5192 fixed gauge that contains 200 millicuries of Cesium-137 (original activity). These devices are a USA DOT 7A Type A container. The licensee reported that the gauge is still [within] of the truck--there is no indication of radiation leakage or exposures to any individual. The licensee's Radiation Safety Officer is enroute and will make necessary radiation surveys and conduct an investigation. Local law enforcement responded to the accident. More information will be provided as it is obtained, per SA-300."

Texas State Report # I-9067

* * * RETRACTION FROM KAREN BLANCHARD TO JOHN SHOEMAKER ON 04/18/13 AT 1708 EDT * * *

The following retraction was received via email:

"This event does not meet the reporting criteria referenced in SA-300, specifically 49 CFR171.15 (b)(1) and (2), in that the individual's death in this incident was not the 'direct result of hazardous materials' as stated in the 171.15(b)(1)."

Notified R4DO (Drake), NMSS (Benner), and FSME EVENTS Resources via email only.

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Agreement State Event Number: 48933
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: HI-TECH TESTING SERVICE
Region: 4
City: SEILING State: OK
County:
License #: OK-32150-01
Agreement: Y
Docket:
NRC Notified By: MIKE BRODERICK
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/16/2013
Notification Time: 17:45 [ET]
Event Date: 04/15/2013
Event Time: [CDT]
Last Update Date: 04/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENTS RESOURCE (EMAI)
BRIAN MCDERMOTT (FSME)

Event Text

AGREEMENT STATE REPORT - CONTAMINATED RADIOGRAPHY CAMERA

The State of Oklahoma received a report from the licensee, that a new SPEC-150 Radiographer camera was giving an unexpected high radiation reading of 20 mrem. The State responded to the licensee's location to investigate. Contamination was detected on the exterior of the camera, guide tube, and cable. Contamination was also detected on the truck used to transport the camera. The camera had been used at a natural gas plant in Wheeling, Texas. There was no apparent damage to the camera and efforts to decontaminate the camera were unsuccessful. The licensee has placed the camera in a container and stored it in a secure location. It is believed the camera may have a manufacturer defect. The manufacturer has been notified. The truck has been decontaminated.

The State of Texas has been notified and they will determine if any contamination is present at the natural gas plant in Wheeling, Texas. The radiographer and his assistant were checked for contamination and none was found and no internal exposure is expected. The radiographer's dosimeter indicated 10 mrem and the assistant's dosimeter indicated 0 mrem. Both radiographer's film badges have been sent out for processing.

The States of Oklahoma and Texas will continue their investigations and provide additional information when it is available.

* * * UPDATE AT 1557 EDT ON 04/18/13 FROM KEVIN SAMPSON TO JOHN SHOEMAKER VIA EMAIL * * *

The following update was received from the State of Oklahoma by email:

"On Monday afternoon, April 15, 2013, radiographers of Hi-Tech Testing Service, (Oklahoma license OK-32150-01 located in Seiling, OK) were working at a natural gas plant near Wheeler, Texas. After doing their survey following retracting the source, they noted high levels of radiation coming from the right rear truck bed. The camera was not nearby, and there was no obvious source for the radiation. They contacted their RSO [Radiation Safety Officer] and after ensuring that the source was properly retracted and in the camera, and all known sources of radiation were accounted for, they still had the anomalous high reading. The RSO instructed them to return to the office. After some work, the RSO was able to remove the contamination with duct tape. He reported that using an ND-2000 radiation meter in near contact, the duct tape registered approximately 1 R/hour [Rem] (1000 mrem/hour). He reported that the bed was now showing no radiation, and that the radiography camera and associated equipment were showing no radiation. He secured the contaminated tape in his vault, and advised Oklahoma DEQ [Department of Environmental Quality] of this on Monday evening. On Tuesday [4/16/13] morning, DEQ inspectors arrived at the facility to investigate. As a courtesy, we [Oklahoma DEQ] had advised Texas DSHS [Department of State Health Services] radiation control of the report, and possible contamination concerns at the work site in Texas.

"[Oklahoma] DEQ inspectors checked the area and equipment, including the radiography camera and associated equipment, the radiography truck used during the event, and the shop area where the camera and equipment had been worked on by the RSO. Contamination was found on the bed of the truck in a location where radiographers reportedly assemble and disassemble the camera and associated equipment. Removable contamination was found on the collimator that had been used during the exposures. Radiation was measured from the guide tube and from the crank cable. The radiation in the crank cable extended for several feet from the end of the cable that attaches to the radiography camera, consistent with contamination of the cable from contact with the (presumably contaminated) interior of the guide tube. Other than the bed of the truck, no contamination of the truck was found in this survey. The exterior of the camera was wiped, but no removable contamination was found. Analysis with a portable gamma spec showed that all contamination was Ir-192. Measured radiation levels in near contact on the equipment and truck varied, but were in the hundreds of microR/hour, with the highest being about 800 microR/hour on the collimator. It is important to note that none of this contamination was detectable with the radiography company's instrument, an ND-2000.

"Separately, we [Oklahoma DEQ] verified the licensee RSO's measurements of the contaminated duct tape that he had used to remove the bulk of the contamination from the truck bed. The tape was under lead shielding in an ammo box that had been used as a transport container, and we did not remove the tape from the container, but got readings in the hundreds of milliR/hour, consistent with the one R in contact figure reported by the company RSO.

"The radiographers involved live a long distance from the licensee office and were not available to be surveyed or interviewed in person while we were on site. The licensee reports this was the first time that the camera, guide tube, and crank cable had been used (see dates below). We are told that this equipment had been used only together, and had not been used with other equipment, and that it had only been used at the Wheeler, TX. job site.

"[Oklahoma] DEQ staff worked with the company RSO to remove the remaining contamination from the bed of the pickup truck. Contamination appeared to be in discrete spots on the bed, and removal appeared to be an all or nothing matter Attempts to remove the contamination with duct tape would fail repeatedly, then after another attempt it appeared that all contamination associated with that spot had been removed. Some of the people participating claimed to be able to see a small dark spot on the tape after the successful removal, consistent with a small chip of Ir-192 remaining on the tape. When we concluded our work, all levels we could find on the truck bed were 10 microR/hour or less in near contact.

"The contaminated guide tube, crank cable, collimator, and all wastes associated with the decontamination efforts were placed in plastic bags where possible, placed in a large trash can, and secured in the licensee's vault for removal. The work bay where all surveys had taken place was surveyed and found to be uncontaminated.

"[Oklahoma] DEQ staff and the licensee RSO called SPEC, manufacturer and distributor of the equipment, and advised them of the situation. DEQ requested that SPEC arrange for packaging and shipment of all contaminated material back to SPEC. SPEC representatives were at the licensee facility on Wednesday, April 17, 2013 and packaged all contaminated material and equipment for shipment to SPEC. To our knowledge, the actual shipment has not occurred yet. We were advised verbally that the SPEC staff found very low (no further information is available at this time) contamination on the truck, and that they surveyed the two radiographers and the clothes they had worn during the incident, and found low (no further information available at this time) contamination on one radiographer's shirt sleeve. The radiographer estimates he wore the shirt for about 13 hours on the day of the incident, and had not worn it since. SPEC has taken custody of the contaminated shirt. We were told that SPEC personnel surveyed the homes and privately-owned vehicles of the radiographers last night and found no contamination. We are expecting a written report from SPEC.

"The tentative opinion of the [Oklahoma] DEQ inspectors and the licensee RSO is that our findings are consistent with the presence of a limited number of particles of Ir-192 that had been present on the outside of the source. How the contamination came to be there is unclear. However present, it seems likely that the contamination was deposited inside the guide tube during the initial exposures, and some contamination fell out of the guide tube during assembly and disassembly of the camera. The 'all-or-nothing' removal of contamination from each area suggests that the contamination was in the form of relatively sizable chips, not in the form of a very fine particulate.

"[Oklahoma] DEQ will continue to investigate. We have cooperated with Texas [DSHS] staff as described above, and have informed the state of Louisiana. We were told that Texas staff visited the job site in Texas, and were guided to a single location of use by facility staff, where Texas staff found no contamination. In interviews with the radiographers, Oklahoma DEQ staff were told by the radiographers that radiography had been conducted at several sites in the plant over several days. We informed Texas of this discrepancy and the possibility of additional sites that might need to be checked for contamination. We understand that Texas staff are meeting at the job site this afternoon with the licensee RSO, one of the radiographers, and SPEC staff to check for contamination at all sites where radiography was performed.

"This is an interim report based on initial investigations and phone conversations with many of the actors, and has not undergone substantial review. More information will be provided later of further actions, or of any corrections or clarifications needed.

"Camera was used for shooting at the job site from April 8-12, 2013 and on April 15, 2013.

"Areas of interest that appear to [Oklahoma] DEQ at this time include:

"1) The licensee RSO was not able to detect contamination remaining on the truck bed, and had never identified any contamination on the associated equipment. [Oklahoma] DEQ found contamination at levels of definite concern present on both of these. The RSO was using an NDS-2000, a very common industrial radiography survey meter that is optimized for measuring high levels of radiation. Based on this experience, this model (and possibly similar instruments optimized for radiographer use) may not be sensitive enough to reliably detect contamination of this sort. [Oklahoma] DEQ was readily able to detect the contamination with a MicroR meter, portable gamma spec, and with a pancake probe.

"2) How the source came to be contaminated with Iridium is of interest, especially how the source was shipped with external contamination present, if that was indeed the case."

* * * UPDATE FROM KEVIN SAMPSON TO CHARLES TEAL ON 4/19/13 AT 1208 EDT * * *

The following update was received from the State of Oklahoma via email:

"On Thursday afternoon, Texas radiation control and SPEC personnel met with the licensee RSO and one of the radiographers involved in the incident at the Wheeler, TX job site. We are told they did surveys of all locations where radiography had been performed, and no contamination was detected."

Notified R4DO (Drake) and FSME Event Resource via email.

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Power Reactor Event Number: 48955
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: ALBERT MARTIN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/22/2013
Notification Time: 23:23 [ET]
Event Date: 04/22/2013
Event Time: 16:23 [CDT]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JACK WHITTEN (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling Shutdown 0 Refueling
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

EMERGENCY OPERATIONS FACILITY NOT AVAILABLE

"On 4-22-13, at 1623 [CDT], the ANO Unit 2 control room was notified of a loss of ventilation capability to the Emergency Operations Facility (EOF). The main control boards associated with the variable speed drives on both air handling units at the EOF have failed. Therefore, there are no means to filter air for the EOF. If the EOF is staffed, the EOF will be required to relocate to the Alternate EOF in the event of a release that causes the EOF evacuation criteria to be exceeded, as directed by approved emergency response procedures.

"The on-site Operations Support Center, on-site Technical Support Center and off-site Alternate EOF remain fully functional to perform emergency assessment activities. Efforts are underway to expedite repairs.

"This notification is required by 10CFR50.72(b)(3)(xiii)."

The licensee has notified the NRC Resident Inspector.

* * * UPDATE ON 4/24/13 AT 1003 EDT FROM STEVE COFFMAN TO DONG PARK * * *

At 1637 EDT on 4/23/13, the EOF ventilation has been restored and the EOF has full functionality.

The licensee has notified the NRC Resident Inspector.

Notified R4DO (Whitten).

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Research Reactor Event Number: 48962
Facility: RHODE ISLAND ATOMIC ENERGY COMM
RX Type: 2000 KW POOL
Comments:
Region: 1
City: NARRANGANSETT State: RI
County: WASHINGTON
License #: R-95
Agreement: Y
Docket: 05000193
NRC Notified By: ANDREW KADAK
HQ OPS Officer: VINCE KLCO
Notification Date: 04/24/2013
Notification Time: 10:58 [ET]
Event Date: 04/24/2013
Event Time: 10:00 [EDT]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
Person (Organization):
JUDY JOUSTRA (R1DO)
XIAOSONG YIN (NRR)
CRAIG BASSETT (NRR)
ALEXANDER ADAMS (NRR)

Event Text

UNQUALIFIED RADIATION SAFETY OFFICER AT A NON-POWER REACTOR

Based on a review of qualifications of the current RSO (Radiation Safety Officer) at the Rhode Island Nuclear Science Center, it was determined that the individual did not meet the licensee's Technical Specification 6.2.2 for education or experience requirements. This review is a follow-up to an NRC inspection report dated March 25, 2013.

This non-compliance is reportable in accordance with licensee Technical Specifications 1.25, item 8, which delineates administrative and procedural requirements. Immediate actions was to shut down operations until such time that inadequacies can be remedied.

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Power Reactor Event Number: 48963
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/24/2013
Notification Time: 16:50 [ET]
Event Date: 04/24/2013
Event Time: 16:00 [EDT]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
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
2 N Y 100 Power Operation 100 Power Operation

Event Text

NON-LICENSED EMPLOYEE SUPERVISOR CONFIRMED POSITIVE FOR ALCOHOL

"A non-licensed, supervisory employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been restricted."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48964
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RANDY ROSE
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/24/2013
Notification Time: 17:15 [ET]
Event Date: 04/24/2013
Event Time: 14:11 [EDT]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID HILLS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Defueled 0 Defueled
2 N Y 100 Power Operation 100 Power Operation

Event Text

VALID ACTUATION OF AN EMERGENCY DIESEL GENERATOR DUE TO A LOSS OF TRAIN A RESERVE FEED TO THE SITE

"On 4/24/13 at 1411 EDT, a fault occurred on the Unit 1 101 CD Reserve Auxiliary Transformer causing the 12 CD 34kV Reserve Feed Breaker to open resulting in a loss of Train A Reserve Feed to Unit 1 and Unit 2. The cause of the fault is still under investigation.

"Unit 2 remains stable in 100% power. Unit 2 entered LCO 3.8.1, AC Source - Operating, Condition A, one required offsite circuit inoperable Restore Unit 2 reserve feed to operable status within 72 hours.

"Unit 1 is currently in a refueling outage and offline. Unit 1 CD Emergency Diesel Generator (EDG) automatically started and loaded as expected.

"North Spent Fuel Pit Cooling Train lost power due to a load shed, which resulted in a 2 degree Fahrenheit rise in the Spent Fuel Pool Temperature. The North Spent Fuel Pit Cooling Pump was restarted on 1 CD EDG at 1447 EDT. South Spent Fuel Pool Cooling Train remained in-service the entire time.

"The licensee has notified the NRC Resident Inspector."

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Independent Spent Fuel Storage Installation Event Number: 48965
Rep Org: DIABLO CANYON
Licensee: PACIFIC GAS & ELECTRIC CO.
Region: 4
City: AVILA BEACH State: CA
County: SAN LUIS OBISPO
License #: SNM-2511
Agreement: Y
Docket: 72-26
NRC Notified By: DAN STERMER
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/24/2013
Notification Time: 18:15 [ET]
Event Date: 04/24/2013
Event Time: 09:02 [PST]
Last Update Date: 04/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION
Person (Organization):
JACK WHITTEN (R4DO)
ALLEN HOWE (NRR)
GORDON BJORKMAN (NMSS)
SCOTT MORRIS (IRD)

Event Text

LOADING PROCEDURE FOR ISFSI MULTI-PURPOSE CANISTERS PLACED THEM IN AN UNANALYZED CONDITION

"On April 24, 2013, at 09:02 PDT, Diablo Canyon Power Plant (DCPP) determined that the loading procedure for the independent spent fuel storage installation (ISFSI) multi-purpose canisters (MPCs) placed the MPCs in an unanalyzed condition. The procedure (approved for use in 2009) contained steps to install vent caps on the MPC vents while the MPC contained an air/water mixture. This placed the MPC in an isolated condition without any relief path while water was in the MPC (a condition previously not analyzed in the DCPP ISFSI FSAR).

"The MPC vents that prevent MPC over pressurization were disabled while the vent caps were installed with no alternative over pressurization protection provided, therefore the condition is a 24-hour reportable event under 10 CFR 72.75(d)(1).

"This process was used for 23 casks, beginning in 2009. The amount of time each cask was isolated was approximately 40 - 60 minutes. DCPP expects that no appreciable MPC pressure increase occurred, since the MPC contains an air void, and the activity is performed expeditiously. Based on engineering judgment, a conservative evaluation of the potential pressure rise during this period shows an increase of less than 2 psig. Since the MPC is vented prior to isolation, a 2 psig increase does not challenge the MPC design pressure of 100 psig. Therefore, there is no reason to believe that the integrity of any of the 23 previously loaded MPCs has been challenged at the DCPP ISFSI.

"This evaluation will be confirmed and documented in a formal calculation as part of issue resolution."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, April 25, 2013
Thursday, April 25, 2013