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Event Notification Report for February 8, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/05/2016 - 02/08/2016

** EVENT NUMBERS **


51690 51691 51692 51693 51697 51698 51699 51703 51712 51715

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Agreement State Event Number: 51690
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: CHEVRON USA PRODUCTS COMPANY
Region: 4
City: PASCAGOULA State: MS
County:
License #: MS-413-01
Agreement: Y
Docket:
NRC Notified By: ROBERT SIMS
HQ OPS Officer: STEVEN VITTO
Notification Date: 01/28/2016
Notification Time: 09:33 [ET]
Event Date: 09/18/2015
Event Time: [CST]
Last Update Date: 01/28/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE OPEN/STUCK SHUTTER

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

"During Fall shutter checks and inventory, on 9/18/2015, an Ohmart-Vega fixed gauge, DEA-2102, device model no. SHLM-BR1, (housing serial no. 13530993) (source serial no. 8533CN), was discovered to have an open/stuck shutter, the source disconnected, and was unable to be moved into the closed position. The RSO [Radiation Safety Officer] contacted the manufacturer and arrangements for repair are in motion. DRH [Mississippi Division of Radiological Health] was notified on 1/15/2016 and recommended that RSO take surveys with a survey measurement of the source. On 1/22/2016, [the] RSO provided readings that did not exceed 0.02 mR/hr at the surface of the steel drum that encloses the gauge and the source. The gauge and source is sealed in the steel drum and is only accessible by the manufacturer. The source is not in a designated work area, and is not causing exposure limits beyond the limits for radiation control to the general public and occupational workers."

Isotope: Cs-137
Activity: 40mCi
Mississippi report # MS-16001

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Agreement State Event Number: 51691
Rep Org: COLORADO DEPT OF HEALTH
Licensee: CJAMS INC & HIGH COUNTRY AUTO ACCESSORIES
Region: 4
City: YAMPA/STEAMBOAT SPRINGS State: CO
County:
License #: CO GENERAL LI
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/28/2016
Notification Time: 13:09 [ET]
Event Date: 01/21/2016
Event Time: [MST]
Last Update Date: 01/28/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST/ABANDONED TRITIUM EXIT SIGN

The following Agreement State Report was received by the State of Colorado via email:

"[The licensee reported that,] according to the maintenance specialist for the property [located in Steamboat Springs, CO], an inspection of the property was conducted to complete the Radioactive Materials Unit annual report for 2015. They reported on 6/24/15, the exit sign was still in the space. Upon completing an audit of the general license files, contact was made to the current tenant who reported the building had been remodeled. A call was made to the reporting maintenance staff who completed the forms. During the discussion regarding the lost/abandoned exit sign, a request for further information would need to be submitted along with a corrective action should the sign not be found. [The maintenance specialist] conducted a site inspection and found the sign to be missing on 1/21/16. A detailed report was submitted with a corrective action letter received on 1/27/16.

"Tritium Exit Sign:
Model: SLX 60
Source Serial: #412078
Isotope: H-3, Activity
Activity: 7500 mCi
Date Shipped from Isolite Corporation: 6-18-2007

"The property management company is reviewing all properties to verify if a Tritium exit signs are still in use and providing the current tenants of regulatory requirements to correct and prevent any future displacement or loss of exit signs containing Tritium."

Colorado Event Report ID No.: CO16-I16-02

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: 51692
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: JL SHEPHERD & ASSOCIATES
Region: 4
City: SAN FERNANDO State: CA
County:
License #: 1777
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: DONG HWA PARK
Notification Date: 01/28/2016
Notification Time: 13:19 [ET]
Event Date: 01/14/2016
Event Time: [PST]
Last Update Date: 01/28/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - SHIPMENT EXCEEDED RADIATION LIMIT

The following Agreement State Report was received by the State of California via email:

"On January 14, 2016, the Southwest Research Institute (SRWI) notified the Texas radiation control program (TxRCP) of the receipt of an exclusive use shipment with package contact dose rates up to 1900 mrem/hr, which exceed the 1000 mrem/hr limit for exclusive use shipments in closed vehicles. The package contained a nominal 8.4 Ci Co-60 source. SWRI personnel verified that the dose rate limits in the cab of the vehicle and at other shipment locations did not exceed regulatory limits.

"On 1/27/16 CDPH/RHB [California Department of Public Health/Radiologic Health Branch] was notified by NRC (R. Erickson) by email of the event being investigated by TxRCP inasmuch as a California licensee (JL Shepherd & Associates) had prepared the package for shipment from a Maryland licensee to SWRI. On 1/27/16, TxRCP requested that CDPH/RHB (CaRCP) take the lead in investigation of the event inasmuch as JL Shepherd & Associates had prepared the package for shipment, including performing the radiation surveys. CDPH/RHB agreed to take the investigation lead. At the request of NRC, the TxRCP retracted their event report to NRC HOO, and NRC requested that CDPH/RHB submit an event report to NRC."

California 5010 number: 012716

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Agreement State Event Number: 51693
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: MEMC PASADENA INC
Region: 4
City: PASADENA State: TX
County:
License #: 05129
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DONG HWA PARK
Notification Date: 01/28/2016
Notification Time: 17:30 [ET]
Event Date: 01/28/2016
Event Time: [CST]
Last Update Date: 01/28/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER

The following report was received from the Texas Department of State Health Services via email:

"On January 28, 2015, the licensee notified the Agency [Texas Department of State Health Services] that during routine leak test and shutter checks, it had discovered that the shutters on two Ohmart-Vega SH-F1 gauges were stuck in the open position. Open is the normal operating position for these two level gauges that are mounted on the sides of tanks. Each gauge contains a 120 millicurie cesium-137 source. Due to the location of the gauges, there is no risk of exposure to any individual. The licensee has contacted the manufacturer and is scheduling repairs. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident #: I 9376

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 51697
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TERRY BRANDT
HQ OPS Officer: DONG HWA PARK
Notification Date: 01/29/2016
Notification Time: 17:09 [ET]
Event Date: 01/29/2016
Event Time: 09:20 [CST]
Last Update Date: 02/05/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BILLY DICKSON (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

OFFSITE POWER DECLARED INOPERABLE DUE TO LOWERING GENERATOR VOLTAGE

"At 0920 CST on 1/29/16, while performing main generator voltage adjustments at the direction of the transmission operator, Duane Arnold Energy Center (DAEC) switchyard voltage lowered to the calculated point where offsite sources were considered inoperable. During this event, both onsite emergency diesel generators were fully operable and capable of performing their intended safety function.

"While no safety concerns arose, Technical Specification (TS) Limiting Condition for Operability (LCO) 3.8.1.a Condition C was entered due to two offsite electric power circuits being inoperable. Immediate actions were taken to adjust main generator voltage to restore switchyard voltage. In less than 10 minutes, both offsite circuits were declared operable and LCO 3.8.1.a Condition C was exited. This resulted in a reportable event pursuant to 10CFR50.72(b)(3)(v)(D).

"During the time of reduced grid voltage, no bus low-voltage alarms nor any equipment issues occurred. The cause of this event is under investigation, and there are not any current operability concerns with the offsite power circuits."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM ROBERT MURRELL TO DANIEL MILLS AT 1319 EST ON 02/05/2016 * * *

"The purpose of this notification is to retract a previous report made on 1/29/16 at 1709 (EST). NRC notification was initially made as a result of offsite power sources being declared inoperable due to the identification of a low voltage condition by the grid operator.

"Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the offsite power grid conditions were above the required limit and were therefore operable. It was determined that a trip of the DAEC turbine/generator would not have led to fluctuations in voltages in the DAEC switchyard below the trip setpoints for Loss of Power. Based on this, the safety-related buses and loads were fully capable of performing their intended design basis function. The degraded voltage relays setpoint were not reached; therefore, the essential electrical buses remained connected to offsite power.

"Therefore, the low voltage condition does not meet the reporting requirements of 10 CFR 50.72 or 10 CFR 50.73

"The Resident Inspector has been notified."

Notified R3DO (Kozak).

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Agreement State Event Number: 51698
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: PURCELL, RHOADES & ASSOC.
Region: 4
City: PLEASANT HILL State: CA
County:
License #: 2898
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/29/2016
Notification Time: 16:42 [ET]
Event Date: 01/28/2016
Event Time: 17:00 [PST]
Last Update Date: 01/29/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSNS (MEXICO) (FAX)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST/STOLEN NUCLEAR DENSITY GAUGE

The following report was received from the State of California via email:

"[The licensee] states that the nuclear density gauge was inside a box in company van parked in the public street on the side of the building. It was discovered missing once they needed to use it for a job. [The State] was notified that the item had been missing for approximately 24 hours.

"Nuclear Gauge information:
Unit: CPN-Campbell Pacific Nuclear MC3 ; Serial # M37107962.
Additional information: Substance Type: Cesium -137, Amount: 10 mCi; Americium -241, Amount: 50 mCi."

The State of California, Department of Public Health Radiologic Health Branch received notification from the California's Governor's Office of Emergency Services. The licensee has contacted local law enforcement and a search for the gauge is still ongoing. Additional information will be provided when available.

California Report No. 012916

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: 51699
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: ISG & ASSOCIATES
Region: 4
City: OMAHA State: NE
County:
License #: 01-116-01
Agreement: Y
Docket:
NRC Notified By: JULIA SCHMITT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/29/2016
Notification Time: 17:06 [ET]
Event Date: 01/29/2016
Event Time: [CST]
Last Update Date: 01/29/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED NUCLEAR DENSITY GAUGE

The following report was received from the State of Nebraska via email:

"The Radiation Safety Officer for the Nebraska Radioactive Materials licensee reported that a Humboldt Model 5001, Serial Number 5624 industrial gauge had been damaged today (1/29/2016) at a temporary job site in Falls City, NE. The gauge contains 10 mCi of Cs-137 and 40 mCi of Am-241/Be. The user had left the gauge unattended for a brief time, and upon returning, found that a construction vehicle had run over the gauge. The gauge handle was broken and the case damaged. The source was able to be retracted, however the shutter was damaged and could not be completely closed. Wipe tests verified that there was no leakage from the source. Office of Radiological Health staff were dispatched to the scene."

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Agreement State Event Number: 51703
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: MORAVEK BIOCHEMICALS, INC
Region: 4
City: BREA State: CA
County:
License #: 2960
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: DONG HWA PARK
Notification Date: 01/30/2016
Notification Time: 13:11 [ET]
Event Date: 01/29/2016
Event Time: [PST]
Last Update Date: 01/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - CONTAMINATION FOUND ON RECEIPT INSPECTION

The following report was received from the State of California via email:

"Moravek received a package of tritium from Merck and Company (Rahway, New Jersey) on 1/29/16 by [common carrier] delivery (non-exclusive use). Upon performing the receipt radiological survey, Moravek personnel reported finding removable contamination of tritium on the external package surfaces up to 44.75 dpm/square cm. The applicable regulatory limit is 22 dpm/square cm based on wiping a 300 square cm area. Moravek personnel reported they estimate they wiped 100 square cm areas. The results of 5 wipes (approximately 500 square cm) performed by Moravek personnel of the package surfaces yielded an average of 26.4 dpm/square cm.

"The contamination regulatory limit is identical for all beta and gamma emitting radionuclides. However, the safety significance of the contamination is nuclide specific, and ranges up to a factor in excess of 10,000 for common beta/gamma emitting radionuclides. Tritium is on the very low end of the safety significance spectrum, with for example, the safety significance of tritium contamination being approximately a factor of 4000 less than the safety significance of a similar contamination level of Cs-137. The dose consequences of the highest wipe concentration of 44.75 dpm/square cm of tritium found on the package is therefore very minor.

"The [common carrier] RSO was notified of the contamination wipe results. The New Jersey radiation control program will also be notified."

California 5010 Number: 012916

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Power Reactor Event Number: 51712
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES SCHWER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/05/2016
Notification Time: 03:49 [ET]
Event Date: 02/05/2016
Event Time: 01:09 [EST]
Last Update Date: 02/05/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN ROGGE (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 Hot Standby 0 Hot Standby

Event Text

EXCESSIVE CONTROL ROOM IN-LEAKAGE IDENTIFIED

"On February 5, 2015 at 0109 EST, the Control Room Emergency Ventilation System (CREVS) was declared inoperable due to a higher than allowed identified in-leakage rate for the Control Room Envelope (CRE) when in the Normal Operating Mode. Unit 1 remains at 100 percent power and Unit 2 remains in Mode 3 for an unrelated planned maintenance outage. Unit 1 and Unit 2 share a common CRE.

"This in-leakage was detected during additional testing following the event documented in EN #51584.

"At the time of discovery, there is a reasonable expectation this condition could prevent the fulfillment of the safety function of a system that is required to mitigate the consequences of an accident, thus satisfying the reporting criteria for 10CFR50.72(b)(3)(v)(D).

"Actions to implement mitigating actions were immediately initiated in accordance with Technical Specification 3.7.10. CREVS has been placed in Recirculation Ventilation Mode, isolating the control room from outside air.

"The NRC Senior Resident Inspector has been notified of the condition."

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Power Reactor Event Number: 51715
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SAMI JAZIRI
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/07/2016
Notification Time: 13:46 [ET]
Event Date: 02/07/2016
Event Time: 13:26 [EST]
Last Update Date: 02/07/2016
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RANDY MUSSER (R2DO)
SCOTT MORRIS (NRR)
BERNARD STAPLETON (IRD)
CATHY HANEY (R2RA)
JOHN LUBINSKI (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 88 Power Operation 0 Hot Shutdown

Event Text

MANUAL SCRAM AND ALERT DECLARATION DUE TO ELECTRICAL FAULT RESULTING IN FIRE/EXPLOSION

At 1346 EST the licensee reported that at 1326, Brunswick Unit 1 declared an Alert under EAL HA 2.1 due to an explosion/fire in the Balance of Plant 4 kV switchgear bus area. Prior to the Alert declaration, the operators initiated a manual SCRAM due to an unexpected power decrease from 88% to 40%. The licensee has visually verified that there is no ongoing fire and is investigating the initial cause of the event. Offsite power is available to the site, but EDGs 1 and 2 are running and supplying Unit 1 loads. The MSIVs shut and HPCI/RCIC are being used to maintain vessel level. At 1412 EST, NRC decided to remain in Normal Mode.

At 1704 EST the licensee reported the following:

"At 1313 hours Eastern Standard Time (EST) a manual reactor scram was initiated due to loss of both recirculation system variable speed drives as a result of an electrical fault. At this time, a Startup Auxiliary Transformer (SAT) experienced a lockout fault; interrupting offsite power to emergency buses 1 and 2. Emergency Diesel Generators (EDGs) 1, 2, 3, and 4 automatically started and EDGs 1 and 2 synchronized to emergency buses 1 and 2 per design. The power interruption resulted in closure of the Main Steam Isolation Valves, per design. The manual scram also resulted in closure of Group 2, 6, and 6 Containment Isolation Valves.

"The Reactor Core Isolation Cooling (RCIC) system was manually started and is being used to control reactor water level. The High Pressure Coolant Injection (HPCI) system was manually started and is being used for pressure control.

"The Plant response to the event was per design.

"Unit 2 is not directly affected by the event, however, due to the shared electrical distribution system is in a Technical Specification Action statement due to the Inoperable Unit 1 SAT.

"The public health and safety is not impacted by this event."

At 1751 EST, the licensee reported that the emergency declaration had been downgraded to an Unusual Event at 1730 because the plant no longer meets the criteria for an Alert, but does meet the criteria for an Unusual Event due to a "loss of all offsite power to Emergency 4 kV buses E1 (E3) and E2 (E4) for greater than or equal to 15 minutes."

The NRC Resident Inspector has been notified.

The licensee has notified the State and Local governments.

Notified DHS, FEMA, USDA, HHS, DOE, DHS NICC, EPA EOC, FEMA NWC (via email), FDA EOC (via email) and Nuclear SSA (via email).


* * * UPDATE FROM MARTY IRWIN TO DANIEL MILLS AT 1825 ON 2/07/16 * * *

At 1814 EST the emergency declaration was terminated because offsite power was restored.

The NRC Resident Inspector has been notified.

The licensee has notified the State and Local governments.

Notified R2DO (Musser), NRR EO (Morris), IRD MOC (Stapleton), R2RA (Haney), NRR ET (Lubinski), NRR ET (Dean), DHS, FEMA, USDA, HHS, DOE, DHS NICC, EPA EOC, FEMA NWC (via email), FDA EOC (via email) and Nuclear SSA (via email).

Page Last Reviewed/Updated Monday, February 08, 2016
Monday, February 08, 2016