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Event Notification Report for June 30, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/29/2016 - 06/30/2016

** EVENT NUMBERS **


51910 52027 52028 52032 52034 52035 52051 52053

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 51910
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID HECKMAN
HQ OPS Officer: BETHANY CECERE
Notification Date: 05/05/2016
Notification Time: 15:39 [ET]
Event Date: 05/05/2016
Event Time: 05:00 [MST]
Last Update Date: 06/29/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN KRAMER (R4DO)

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

Event Text

HIGH PRESSURE SAFETY INJECTION VALVE BONNET LEAKAGE IDENTIFIED DURING REFUELING OUTAGE

"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73.

"At 0500 MST on May 5, 2016, engineering personnel determined that leakage from the bonnet seal weld of the Train B High Pressure Safety Injection (HPSI) system loop 2A injection valve, SIBUV0616, constituted reactor coolant system pressure boundary leakage. This is being reported as a degradation of a principal safety barrier pursuant to 10 CFR 50.72(b)(3)(ii)(A).

"The leak was identified during a planned activity in which Operations was filling the refueling pool using HPSI pump B. Leakage was stopped when a plant operator closed SIBUV0616.

"PVNGS Unit 1 was shut down for its 19th refueling outage (1R19) on April 9, 2016, at 0000 MST and is in Mode 6.

"The NRC Resident Inspectors have been informed of this condition."

* * * RETRACTION PROVIDED BY JORGE RODRIGUEZ TO JEFF ROTTON AT 1732 EDT ON 06/29/2016 * * *

"Subsequent engineering evaluation of the leak condition concluded the leakage from the bonnet seal weld of SIBUV0616 was not reportable reactor coolant system pressure boundary leakage. This conclusion was based on further reviews of the PVNGS licensing bases, ASME Code requirements, and design features of the valve with vendor assistance, which determined that the body-to-bonnet threads provide the structural support for the mechanical joint and the seal weld is not required for structural integrity of the component.

"Based on the above information, PVNGS has determined the leakage did not represent a degraded condition of a principal safety barrier as defined by 10 CFR 50.72(b)(3)(ii)(A) and Event Notification No. 51910 is hereby withdrawn.

"The NRC Resident Inspectors have been informed."

Notified R4DO (Werner)

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Agreement State Event Number: 52027
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: MIDWEST INDUSTRIAL X-RAY, INC
Region: 3
City: ALBERTVILLE State: MN
County:
License #: 1186-89
Agreement: Y
Docket:
NRC Notified By: TYLER KRUSE
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/21/2016
Notification Time: 11:37 [ET]
Event Date: 06/20/2016
Event Time: 09:30 [CDT]
Last Update Date: 06/21/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA SOURCE DISCONNECT

The following was received from Minnesota via email:

"On June 20, 2016 at 0930 [CDT] Midwest Industrial X-Ray, Inc. (License number 1086-89) had a source disconnect event. Their Radiation Safety Officer notified the Minnesota Department of Health [MDH] of the event at 0925 [CDT] on June 21, 2016.

"Initial details:
- The event happened on a jobsite in Lakeville, MN.
- The Camera was a QSA 880 Delta.
- Source was 47.5 curies of I-192.
- The cause has been initially determined to be a worn drive cable. The licensee stated that the drive cable passed the go-no-go test prior to hooking up.
- They were able to retrieve the source and get it back in the shielded position.
- All equipment was inspected after the retrieval.
- The faulty drive cables were brought back to the licensee's corporate office in Fargo, ND for repair.
- Pocket dosimeter readings following the retrieval were: 41 mrem, 20 mrem, 11 mrem, and 10 mrem.

"The licensee is in the process of preparing a written report that will be submitted within 30 days as required. MDH will continue to investigate this event. MDH Inspectors will be on-site at the licensee's office in Albertville MN on June 23, 2016 to perform a follow-up inspection."

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Agreement State Event Number: 52028
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: NOVA ENGINEERING AND ENVIRONMENTAL
Region: 4
City: SAN DIEGO State: CA
County:
License #: 7732-37
Agreement: Y
Docket:
NRC Notified By: DONELLE KRAJEWSKI
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/21/2016
Notification Time: 14:28 [ET]
Event Date: 06/21/2016
Event Time: 10:00 [PDT]
Last Update Date: 06/21/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JESSE ROLLINS (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSNS (MEXICO) (FAX)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The following was received from California via email:

"The RSO of Nova Engineering and Environmental notified RHB [Radiologic Health Branch] in Brea that a Troxler yellow transport case containing a Troxler model 3411B # 18840 moisture density gauge containing 8 mCi of Cs-137 and 40 mCi of Am-241/Be was stolen from a technician's pickup truck today. The technician stated that he had loaded and secured the Type A case into his pick-up truck from a storage facility in Irvine, CA then stopped at a coffee shop before traveling to his work location. He went to unlock the gauge case and found that it had been stolen. He returned to the coffee shop, but was unable to find his gauge. He is contacting the Irvine Police Dept. to make a theft report. The RSO indicated that they lock and chain each side of the case to the truck independently and once again around the top of the case to prevent it from opening. Nova E&E does have contact information on the gauge and the case and they use a small padlock on the Cs-137 source rod handle to prevent accidental deployment."

CA 5010 # 062116

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 52032
Rep Org: COLORADO DEPT OF HEALTH
Licensee: PORTER ADVENTIST HOSPITAL - ENCORE ELECTRIC
Region: 4
City: DENVER State: CO
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/22/2016
Notification Time: 11:00 [ET]
Event Date: 12/31/2005
Event Time: [MDT]
Last Update Date: 06/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JESSE ROLLINS (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

This material event contains a "Category 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following was received from the State of Colorado via email:

"Event Report ID No.: CO16-I16-08

"Detail: The facility hired a contractor to remodel space within the hospital. During the construction pedestrian traffic was routed around the area. According to the facility environmental health safety office the Tritium exit signs were only in use during the project.

"Event Description: It is unknown due to the extensive passage of time and the departure of employees who were involved with the project. No further information is available related to the use or the disposition of the 6 Tritium exit signs, Model # SLXTUIGW10, Serial # 162229 to 162234, H-3, 7.3 CI."

THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL

Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 52034
Rep Org: COLORADO DEPT OF HEALTH
Licensee: VAIL MOUNTAIN SCHOOL
Region: 4
City: VAIL State: CO
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/22/2016
Notification Time: 13:28 [ET]
Event Date: 06/22/2016
Event Time: [MDT]
Last Update Date: 06/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JESSE ROLLINS (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following was received from Colorado via email:

"The facility manager completed the documentation for the 2016 Annual General License reports. During his inspection, only 2 of the 4 Tritium exit signs were reported. It is unknown as to what may have occurred with the other two signs as staff has changed since the signs were designated to be used at the facility.

"Pictures were submitted showing the labels on the existing two signs located within the modern fold doors at the school. No serial number was provided on the label from the manufacture Shield Source. The distributor, Isolite, did report serial numbers on the quarterly report to the state."

Colorado Report # CO16-I16-09

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 52035
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: ASPIRUS-WAUSAU HOSPITAL
Region: 3
City: WAUSAU State: WI
County:
License #: 073-1342-01
Agreement: Y
Docket:
NRC Notified By: KRISTA KUHLMAN
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/22/2016
Notification Time: 17:46 [ET]
Event Date: 06/17/2016
Event Time: [CDT]
Last Update Date: 06/22/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - CONTAMINATION OF BRACHYTHERAPY PATIENT

The following was received from Wisconsin via email:

"On Friday, June 17, 2016, a licensee discovered contamination on a package that was used to ship I-125 prostate brachytherapy seeds. The post procedure survey of the packaging revealed elevated levels of radiation. After wipes were taken, the licensee determined that there was I-125 contamination on the inside of the packaging. There was no other contamination in the operating room. The licensee had the patient return to the facility to perform a urine bioassay. The bioassay revealed elevated levels of I-125 in the patient's urine. However further analysis will be required to determine activity concentrations. The licensee has also administered Lugols solution to the patient to block the thyroid. The department and the licensee are still collecting data to determine if this is a medical event. Site visits and updates will be performed as needed."

Wisconsin Report ID # WI160004

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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Power Reactor Event Number: 52051
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STEPHEN W. REED
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/29/2016
Notification Time: 12:30 [ET]
Event Date: 05/09/2016
Event Time: 06:26 [EDT]
Last Update Date: 06/29/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
OMAR LOPEZ (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

INVALID ACTUATION OF PRIMARY CONTAINMENT ISOLATION VALVES (PCIVs)

"This 60-day telephone notification is being made in lieu of a Licensee Event Report (LER) submittal in accordance with 10 CFR 50.73(a)(1) to notify the NRC of an invalid actuation of PCIVs, reportable under 10 CFR 50.73(a)(2)(iv)(A).

"On May 9, 2016, at 0626 Eastern Daylight Time (EDT), an unexpected trip of the Unit 1 Reactor Protection System (RPS) Bus A occurred, resulting in closure of several PCIVs on loss of power, per design. In addition, the following actuations also occurred per design:

- insertion of a half reactor scram signal.
- initiation of the standby gas treatment (SBGT) system .
- isolation of the secondary containment.
- initiation of the control room emergency ventilation (CREV) system smoke and radiation mode.
- trip of the operating reactor water cleanup system (RWCU) pump due to closure of its isolation valve.

"The event resulted from a failed relay coil in the drive motor run logic for the RPS power supply motor-generator (MG) set. The failed relay blew a fuse, which de-energized the RPS drive motor contactor and MG set. This resulted in de-energizing the RPS power supply in the 'A' channel and produced the actuations listed previously, per design. Affected systems and components were restored to their normal configurations by 1000 EDT on May 9, 2016.

"Since no plant or process conditions existed that required the PCIV isolations (e.g., high drywell pressure or low reactor water level), this event is being reported per 10 CFR 50.73(a)(1) as an invalid actuation. This issue has been entered into the site Corrective Action Program (CR 2027653) for evaluation and implementation of further corrective actions.

This event did not result in any adverse impact to the health and safety of the public.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 52053
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARK DICKERSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/29/2016
Notification Time: 17:21 [ET]
Event Date: 06/29/2016
Event Time: 09:40 [CDT]
Last Update Date: 06/29/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
MICHAEL KUNOWSKI (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

SECONDARY CONTAINMENT INOPERABLE

"At 0940 CDT on 6/29/2016, both doors of a Secondary Containment Airlock were reported to be open simultaneously for a period of less than 5 seconds. The brief time that the doors were simultaneously open constituted an inoperable condition of Secondary Containment. Secondary Containment was immediately restored to operable by closing the airlock doors. The airlock interlock was repaired and verified to operate correctly.

"This event is being reported pursuant of 10 CFR 50.72(b)(3)(v)(C).

"The Senior Resident Inspector has been notified."

Page Last Reviewed/Updated Thursday, June 30, 2016
Thursday, June 30, 2016