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Event Notification Report for November 6, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/05/2013 - 11/06/2013

** EVENT NUMBERS **


49477 49479 49483 49500 49502 49503 49504 49505 49506 49507

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Agreement State Event Number: 49477
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: PDV MIDWEST REFINING, LLC
Region: 3
City: LEMONT State: IL
County:
License #: IL-01603-01
Agreement: Y
Docket:
NRC Notified By: GIBB VINSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/28/2013
Notification Time: 11:16 [ET]
Event Date: 10/23/2013
Event Time: [CDT]
Last Update Date: 10/28/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ROBERT DALEY (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - GAUGE DAMAGED IN A FIRE

The following report was received from the Illinois Emergency Management Agency, Bureau of Radiation Safety via e-mail:

"PDV Midwest Refining (CITGO) in Lemont, IL called on 10/26/13 to report a fixed gauge that was involved in a fire on 10/23/13. The gauge is an Ohmart/Vega gauge containing 37 GBq (1 Ci) of Cs-137. Their consultant had been on site and done a characterization of the area. The housing looked to be intact and radiation surveys at 35 feet from below the housing were 40 microR/hr. A contamination survey of material under the vessel indicated no contamination at this time. No one is able to get into the immediate area because of debris and a perimeter has been established. IEMA/BRS [Illinois Emergency Management Agency, Bureau of Radiation Safety] inspectors have been dispatched to the scene for further evaluation."

Item Number: IL13030

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Agreement State Event Number: 49479
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: AMEC ENVIRONMENT & INFRASTRUCTURE, INC.
Region: 4
City: IRVINE State: CA
County:
License #: CA5799-30
Agreement: Y
Docket:
NRC Notified By: K. HARKNESS
HQ OPS Officer: PETE SNYDER
Notification Date: 10/28/2013
Notification Time: 16:03 [ET]
Event Date: 10/28/2013
Event Time: 11:30 [PDT]
Last Update Date: 10/28/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENT RESOURCE (EMAI)
ILTAB (EMAI)
MEXICO (EMAI)

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

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The State of California submitted the following via email:

"At 1130 [PDT] on October 28, 2013, the RSO for AMEC called to report a stolen moisture density [M/D] gauge: Troxler, model 3440, S/N 36036 that contains 8 millicuries of Cs-137 and 40 millicuries of Am-241/Be.

"The stolen gauge was last seen on Friday, October 25, 2013 by the authorized user, who secured the M/D gauge in safe mode inside the locked yellow transportation box which was placed inside a locked metal box. The contractor's tools at the site in Mission Valley, CA was also burglarized and a police report was filed.

"The [metal] box's lock had been drilled out and the chain attaching it to the building was cut. RHB [Radiation Health Branch] advised the RSO to place a Lost/Found notice in the local paper offering a reward for return of the gauge to AMEC."

CA 5010 Number: 102813

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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Non-Agreement State Event Number: 49483
Rep Org: AIR FORCE MASTER MATERIAL LICENSE
Licensee: AIR FORCE MASTER MATERIAL LICENSE
Region: 1
City: FORT MEADE State: MD
County:
License #: 42-23539-01AF
Agreement: Y
Docket: 30-28641
NRC Notified By: MAJOR EDWARD KELLY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/29/2013
Notification Time: 13:50 [ET]
Event Date: 10/17/2013
Event Time: 08:00 [EDT]
Last Update Date: 10/29/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
JAMES DRAKE (R4DO)
MATTHEW HAHN (ILTA)
FSME EVENTS RESOURCE (EMAI)

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

Event Text

LOST GENERAL LICENSE DEVICE CONTAINING A NICKEL 63 SOURCE

"On January 20, 2012, leak tests were conducted on all [Air Force] BE's [Bioenvironmental Engineering] APDs [air particulate detectors] with the expectation of disposing them to AFRRAD [Air Force Radioactive Recycling and Disposal]. The APDs were placed in storage at the BE office (Bldg 3423) awaiting sample results and direction from AFRRAD. At the time, AFRRAD had a backlog in workload and were not receiving GLDs [general license devices]. During a GLD program review on Oct.17, 2013, BE determined that the GLD, a Smith's Detection APD-2000 (ECN: 0300069, SN: 4150) was missing and likely disposed via DRMO [Defense Reutilization and Marketing Office]. A records search commenced immediately.

"In April 2013, a SSgt [Staff Sergeant] at 779 AMDS/SGPB began the equipment turn-in process on a GLD, a Smith's Detection APD-2000 (ECN: 0300069, SN: 4150). The GLD was turned over to 779 MDSS/MERC by another SSgt, via AF Form 601 and radiation leak sampling data for the item. Upon receipt of the GLD, MERC then turned it over to 779 MDSS/SGSM. On April 24, 2013, the GLD was removed from the BE Flight's Defense Medical Logistics Standard Support (DMLSS) account, and identified for 'turn-in to DRMO'.

"The SSgt [at 779 AMDS/SGPB], contacted the Defense Logistics Agency (DLA) warehouse at Ft. Meade on Oct. 23, 2013 [and] visited them in an effort to retrieve the missing GLD. DLA [Defense Logistics Agency] records management was overhauled shortly after the item was turned in, thus records relating to the GLD from the warehouse were unable to be furnished. Bioenvironmental Engineering's radiation detection equipment, a SAM940 & Victoreen 451P, were used but [the search] was unsuccessful in locating the GLD at the warehouse. DLA warehouse management has been instructed to immediately notify 779 AMDS/SGPB should the GLD be discovered at their location."

The licensee considers the device un-retrievable and has contacted NRC R4 (Cook).

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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Power Reactor Event Number: 49500
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID NELSON MADSEN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/04/2013
Notification Time: 17:01 [ET]
Event Date: 11/05/2013
Event Time: 01:00 [CST]
Last Update Date: 11/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES DRAKE (R4DO)

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 activity at Cooper Nuclear Station [CNS] will remove the TSC [Technical Support Center] ventilation system from service. The TSC ventilation system will be rendered non-functional during this maintenance period. The maintenance activity on the TSC ventilation is expected to last less than one day.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless uninhabitable due to ambient temperature, radiological, or other conditions. CNS Station procedures provide appropriate monitoring and compensatory measures to ensure habitability of the TSC and, if necessary, instructions for relocation of TSC personnel to alternate TSC facilities, should the need arise. Both of these alternate facilities are equipped with emergency ventilation systems and are currently fully functional. In the event of TSC activation, maintenance will be expedited to restore ventilation to service.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of an Emergency Response Facility (ERF). An update will be provided once the TSC ventilation system has been restored to normal operation.

"The licensee has notified the NRC Resident Inspector."

* * * NOTIFIED BY JEREMY SIMS TO JOHN SHOEMAKER AT 1736 EST ON 11/05/2013 * * *

"Cooper Nuclear Station Technical Support Center ventilation system has been restored to service following planned maintenance. The NRC Resident Inspector has been informed."

Notified R4DO (Drake).

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Power Reactor Event Number: 49502
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: GEORGE CURTIS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/05/2013
Notification Time: 05:00 [ET]
Event Date: 11/05/2013
Event Time: 00:41 [EST]
Last Update Date: 11/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ALAN BLAMEY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 0 Startup 0 Startup

Event Text

AUTOMATIC ACTUATION OF THE AUXILIARY FEEDWATER SYSTEM DUE TO MAIN FEED PUMP TRIP

"At 0041 hours [EST] on 11/05/2013, while placing the Condensate Polishers into service, a secondary side perturbation occurred, resulting in a loss of the one running Main Feedwater Pump ('A' Pump) on low suction pressure. At the time, the plant was in Mode 2 with Startup Low Power Physics Testing in progress. By design, this condition resulted in an automatic start of Auxiliary Feedwater. Both 'A' and 'B' Motor-Driven Auxiliary Feedwater (AFW) Pumps started as designed. Steam generator water levels were maintained by the Auxiliary Feedwater flow. The 'B' Motor Driven AFW pump was secured following its automatic start to stabilize steam generator water levels and reactor coolant system temperature. Plant conditions including steam generator water levels have been stabilized. At 0250 hours [EST] 'A' Main Feedwater Pump was restarted and at 0252 hours [EST], the 'A' Motor-Driven AFW pump was secured.

"At this time, the cause of the secondary side perturbation is being investigated. The plant remains in Mode 2 and Startup Low Power Physics Testing has resumed.

"Due to the valid actuation of AFW, this event is being reported as an 8-hour non-emergency per 10CFR50.72(b)(3)(iv)(A). At no time during this occurrence was the public or plant staff at risk as a result of this event.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49503
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: JEFF SIMPSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/05/2013
Notification Time: 15:50 [ET]
Event Date: 11/05/2013
Event Time: 08:42 [CST]
Last Update Date: 11/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
CHRISTINE LIPA (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 91 Power Operation 91 Power Operation

Event Text

SECONDARY CONTAINMENT DECLARED INOPERABLE DUE TO FAILURE OF INTERLOCK MECHANISM

"At 08:42 [CST] on November 5, 2013, indication was received in the Control Room that two Secondary Containment doors, in one access opening, were opened simultaneously. The interlock mechanism preventing both doors from operating simultaneously did not operate as expected. A worker in the field reported that the Turbine Building side door was opened, and simultaneously the Reactor Building side door opened several inches and then quickly re-closed. This condition represents a failure to meet Surveillance Requirement 3.6.4.1.2. As a result, entry into Technical Specification 3.6.4.1, Condition A, was made momentarily due to Secondary Containment being inoperable. The doors were secured at 08:42 and Secondary Containment was declared Operable. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

See similar events 49153 and 49379. The licensee is tracking the failure as Incident Report 01581320.

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Non-Agreement State Event Number: 49504
Rep Org: US NAVY
Licensee: US NAVY
Region: 1
City: WASHINGTON State: DC
County:
License #: 42-23645-01NA
Agreement: N
Docket:
NRC Notified By: CAPT. DAVIS-URGO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/05/2013
Notification Time: 16:52 [ET]
Event Date: 11/05/2013
Event Time: [EST]
Last Update Date: 11/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JAMES NOGGLE (R1DO)
FSME EVENTS RESOURCE (EMAI)

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

Event Text

LOST STRONTIUM-90 SOURCE

The U.S. Navy reported the loss of an IBIS (In-flight Blade Inspection System) that contained 500 microCuries of Sr-90. The IBIS was attached to an USMC aircraft, when the co-pilot's window fell off and struck the blade resulting in the loss of the system. The incident occurred approximately 10 kilometers northeast of Naval Air Station Jacksonville.

The licensee has notified their project manager in Region 1 (Seeley).


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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Power Reactor Event Number: 49505
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: J A DAUGHERTY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/05/2013
Notification Time: 19:27 [ET]
Event Date: 11/05/2013
Event Time: 18:28 [EST]
Last Update Date: 11/05/2013
Emergency Class: UNUSUAL EVENT
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):
JAMES NOGGLE (R1DO)
DAVID SKEEN (NRR)
JANE MARSHALL (IRD)
WILLIAM DEAN (R1RA)
ERIC LEEDS (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 47 Power Operation 0 Hot Standby

Event Text

NOTIFICATION OF UNUSUAL EVENT DUE TO EXPLOSION AND FIRE IN THE TURBINE BUILDING

"On 11/5/13 at 1746 [EST], Beaver Valley Unit 1 Generator tripped on 'C' Transformer differential protection. The Unit was at 47%, so an automatic trip of the reactor was not expected. The reactor was tripped manually. Entered E-0 Reactor Trip Response. The Aux Feedwater Turbine Driven Pump automatically started as required and one motor driven pump was manually started.

"At 1748, the control room received report of fire in the Turbine building. The deluge system had actuated and extinguished the fire in the Turbine plant mezzanine. Off-site assistance was staged and available.

"At 1828, an Unusual Event was declared when fire brigade reports indications that an explosion and fire had occurred in a cable tray in the Unit 1 Turbine Mezzanine.

"The [NRC] Resident Inspector was notified of the events that occurred.

"At 1836, NRC [Resident Inspector] was notified of the Unusual Event.

"Cause of the cable tray explosion and fire is being investigated."

The reactor trip was uncomplicated and Unit 1 is stable in mode 3 with decay heat being released to the main condenser. Normal offsite power is available. Unit 2 continues to operate at 100% and there is no impact on the health and safety of the public.

* * * UPDATE FROM J. A. DAUGHERTY TO JOHN SHOEMAKER AT 2005 EST ON 11/05/13 * * *

At 1959 on 11/5/13, the licensee terminated the Unusual Event.

The licensee has notified the NRC Resident Inspector.

Notified the R1DO (Noggle), NRR EO (Skeen), IRD (Marshall). Notified the DHS SWO, FEMA, DHS NICC, and Nuclear SSA via e-mail.

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Power Reactor Event Number: 49506
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: WARREN WONKA
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/05/2013
Notification Time: 21:31 [ET]
Event Date: 11/05/2013
Event Time: 18:00 [EST]
Last Update Date: 11/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ALAN BLAMEY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 19 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO MOMENTARY LOSS OF 4 KV BUSES AND SAFETY SYSTEM ACTUATION

"At 1800 hours EST on 11/05/2013, with the unit in Mode 1 at 19% power, an automatic reactor trip occurred. Operators were transferring loads from the Startup Transformer to the Unit Auxiliary Transformer in accordance with normal operating procedures. When breaker 52/7, Unit Aux to 4KV Bus 1 Breaker, was taken to the close position, indication on the Reactor Turbine Generator Board (RTGB) went from 'Open' to 'No' indication. Breaker 52/12, Incoming Line Startup Transformer No. 2, cycled open and then re-closed. This resulted in a momentary loss of power to 4KV Bus 2 and 4KV Bus 1. The reactor trip signal was based on a loss of 4KV bus voltage to 2 of the 3 required 4KV buses. The cause of the loss of 480V bus E-1 was a result of loss of power to 4KV Bus 2. As a result of the loss of 480V bus E-1, the 'A' Emergency Diesel Generator (EDG) auto started. The required loads sequenced onto the 'A' EDG with the exception of the 'A' Service Water (SW) pump. The cause of the failure of the 'A' SW pump is under investigation.

"The one running Main Feedwater Pump ('A' Pump) tripped on the resulting under voltage of 4 kV Bus 1. By design, this condition resulted in an automatic start of Auxiliary Feedwater due to both Main Feed pump breakers being opened. Both 'A' and 'B' Motor-Driven Auxiliary Feedwater (AFW) Pumps started as designed. Steam generator water levels were maintained in the normal operating band.

"Currently, the unit is stable in Hot Standby (Mode 3).

"This event is being reported as a 4 hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B) due to the valid Reactor Protection System Actuation

"This event is being reported as an 8 hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A) due to the valid actuation of AFW and EDG auto-start and subsequent starting of required under voltage loads.

"At no time during this occurrence was the public or plant staff at risk as a result of this event.

"The [NRC ] Resident Inspector has been notified."

The reactor trip was uncomplicated and the is plant is stable in mode 3 with decay heat being released to the main condenser. Normal offsite power is available with the exception of the 480V bus E-1 being supplied by the "A" Emergency Diesel Generator.

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Power Reactor Event Number: 49507
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: PETE SNYDER
Notification Date: 11/06/2013
Notification Time: 03:26 [ET]
Event Date: 11/06/2013
Event Time: 00:58 [CST]
Last Update Date: 11/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (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 N 0 Defueled 0 Defueled

Event Text

R-21 CIRCULATING WATER DISCHARGE RADIATION MONITOR PLANNED OUTAGE

"When transferring power supplies to a non-safety related cooling tower bus for planned outage maintenance, R-21, the Circulating Water Discharge Radiation Monitor was removed from service at 0058 [CST] and returned to service at 0111 [CST]. There is no installed backup for R-21 which has an emergency response function to provide indication of gaseous liquid effluent release to the environment. This monitor has no compensatory measure that will allow timely classification of two NUE (Notification of Unusual Event) and Alert classifications when out of service. This resulted in a loss of emergency assessment capability while R-21 was out of service.

"There are no radioactive leaks that impact the Circulating Water System.

"The licensee notified the NRC Resident Inspector."

Page Last Reviewed/Updated Wednesday, November 06, 2013
Wednesday, November 06, 2013