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Event Notification Report for December 16, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/13/2013 - 12/16/2013

** EVENT NUMBERS **


49612 49626 49627 49628 49629 49630 49631 49632 49633 49634

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Agreement State Event Number: 49612
Rep Org: MISSOURI BAPTIST MEDICAL CENTER
Licensee: MISSOURI BAPTIST MEDICAL CENTER
Region: 3
City: SAINT LOUIS State: MO
County:
License #: 24-11128-02
Agreement: N
Docket:
NRC Notified By: TOM MOENSTER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/06/2013
Notification Time: 17:00 [ET]
Event Date: 12/06/2013
Event Time: [CST]
Last Update Date: 12/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
Person (Organization):
CHRISTINE LIPA (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

UNLABELED PACKAGE CONTAINING RADIOACTIVE MATERIAL

The Missouri Baptist Medical Center, in Saint Louis, MO, received an unlabeled package from a supplier in Valencia, CA, which contained 2 spot markers, each containing 50 microCi of Co-57. The package was an expected shipment; however, there was no labeling on the outside of the package indicating the presence of radioactive material. The radiation reading on the outside of the package was 1 mR/hr.

The package was opened to verify contents and the material is being maintained in a secure location. No personnel over exposures occurred. The supplier was notified by the licensee of the mislabeling.

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Power Reactor Event Number: 49626
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/12/2013
Notification Time: 12:44 [ET]
Event Date: 12/12/2013
Event Time: 04:36 [PST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GREG WERNER (R4DO)

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

Event Text

BOTH TRAINS OF PRIMARY CONTAINMENT HYDROGEN AND OXYGEN MONITORS OUT OF SERVICE FOR MAINTENANCE

"This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 0436 (PST), on 12/12/2013 the Division 1 sample rack for monitoring primary containment oxygen and hydrogen atmospheric concentrations was removed from service for planned maintenance activities. The Division 1 sample rack is expected to be out of service for 14 hours. The redundant Division 2 sample rack was previously removed from service for maintenance and remains out of service for repairs. Compensatory measures to monitor primary containment for hydrogen and oxygen are available via grab samples using chemistry procedures."

The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM QUOC VO TO HOWIE CROUCH AT 1705 EST ON 12/13/13 * * *

"Following completion of maintenance activities, the Division 1 sample rack for monitoring primary containment oxygen and hydrogen atmospheric concentrations was returned to operable status at 1150 PST on 12/13/2013, restoring its required emergency assessment capability.

"The NRC Resident Inspector has been notified."

Notified R4DO (Walker).

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Power Reactor Event Number: 49627
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: RON SIMS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/13/2013
Notification Time: 13:40 [ET]
Event Date: 12/13/2013
Event Time: 11:06 [CST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
WAYNE WALKER (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

OFFSITE NOTIFICATION DUE TO FUEL OIL SPILL TO THE ENVIRONMENT

"At 1106 [CST], the control room was informed that a diesel fuel spill to the environment was a reportable event. Earlier in the day, a container tipped over in the bed of a truck eventually spilling diesel fuel onto the ground inside the owner controlled area. Approximately 2 and one half gallons spilled out. The lid of the container was apparently defective.

"No fuel oil made contact with any surface water.

"The area was cleaned up.

"The Kansas Department of Health and Environment and the National Response Center were notified.

"The NRC Resident Inspector has been notified."

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Part 21 Event Number: 49628
Rep Org: TRIVIS INC.
Licensee: TRIVIS INC.
Region: 1
City: BIRMINGHAM State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID BLAND
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/13/2013
Notification Time: 14:37 [ET]
Event Date: 12/13/2013
Event Time: [CST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
PART 21 GROUPS (EMAI)

Event Text

PART 21 REPORT - NON-DESTRUCTIVE TESTING DID NOT MEET PROCEDURAL REQUIREMENTS

The following information was summarized from the report submitted by TriVis via facsimile:

David Bland, President of TriVis Inc. reported that two contract Non-Destructive Evaluation (NDE) Level II examiners, employed by TriVis, failed to meet NDE procedural requirements for weld testing on the Outer Top Cover Plate (OTCP) on six Transnuclear Model NUHOMS-61BTH Dry Shield Canisters (DSC) at the Monticello Nuclear Generating Plant.

An NRC inspector observed part of this activity and questioned whether the dwell times for the penetrant and developer used by a NDE Level II employee of TriVis were sufficient to meet procedural requirements. Upon evaluating recorded video of the work location, it was determined that the dwell times for both the penetrant and the developer of the OTCP weld on DSC #16 were not in compliance with the TriVis NDE LPT [Liquid Penetrant Test] Procedure. An extent of condition review of previous LPT exams conducted on DSCs-11 through -16 revealed additional examinations that were not in compliance with the dwell times specified by the procedure as well as other procedural discrepancies.

All six DSCs were declared inoperable at the time of discovery. All work activities associated with dry fuel storage at Monticello were stopped. A timeline and corrective actions are being developed by TriVis and the licensee.

The two NDE Level II examiners were not previously employed by TriVis and did not perform any other NDE activities at Monticello.

Evaluations will be completed by January 31, 2014 or a follow-up interim report will be submitted.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49629
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: ROBERT PAGE
HQ OPS Officer: PETE SNYDER
Notification Date: 12/13/2013
Notification Time: 16:43 [ET]
Event Date: 12/13/2013
Event Time: 16:00 [EST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
STEVE ROSE (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

ELEVEN INDIVIDUALS NOT PROPERLY SUBJECTED TO THE RANDOM FITNESS FOR DUTY PROGRAM

"In 2010, changes within the Dominion FFD [Fitness for Duty] program resulted in currently 11 individuals not being subjected to random FFD testing although required. Two individuals are actively badged at Surry Power Station and North Anna Power Station (NAPS). Both individuals accessed the protected area at NAPS recently. The other nine individuals were not badged but perform duties that require them to be subject to the FFD program. The affected individuals are now within the random testing program.

"This event is reportable per 10CFR26.719(b)(4), 'Any programmatic failure, degradation, or discovered vulnerability of the FFD program that may permit undetected drug or alcohol use or abuse by individuals within a protected area, or by individuals who are assigned to perform duties that require them to be subject to the FFD program.'"

A work review will be conducted for the two actively badged individuals. The program error has been corrected.

The licensee has notified the NRC Resident Inspector and the Louisa County Administrator.

See similar Surry report EN #49630.

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Power Reactor Event Number: 49630
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TIM KEATING
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/13/2013
Notification Time: 17:51 [ET]
Event Date: 12/13/2013
Event Time: 16:00 [EST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
STEVE ROSE (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

ELEVEN INDIVIDUALS NOT PROPERLY SUBJECTED TO THE RANDOM FITNESS FOR DUTY PROGRAM

"In 2010, changes within the Dominion FFD [Fitness for Duty] program resulted in 11 supplemental personnel not being included in the current random FFD testing program. Two individuals are actively badged at Surry Power Station (SPS) and North Anna Power Station (NAPS). Both individuals accessed the protected area at SPS recently. The other nine individuals were not badged but perform duties that require them to be subject to the FFD program. The affected individuals are now included in the random testing program. An extent of condition was performed and no other contractor records were found to be affected.

"This event is reportable per 10CFR26.719(b)(4), 'Any programmatic failure, degradation, or discovered vulnerability of the FFD program that may permit undetected drug or alcohol use or abuse by individuals within a protected area, or by individuals who are assigned to perform duties that require them to be subject to the FFD program."

The error occurred when, in 2010, it was decided that contract employees would no longer be placed in a select labor pool. When this occurred, FFD personnel no longer monitored that particular labor pool in the belief that it no longer existed. Upon discovery that the labor pool did, in fact, still exist the licensee determined that the eleven personnel should have been included in the random testing program.

See similar North Anna report EN #49629. The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49631
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: PETE SNYDER
Notification Date: 12/13/2013
Notification Time: 19:44 [ET]
Event Date: 11/25/2013
Event Time: 15:00 [PST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GREG WERNER (R4DO)

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

Event Text

BREACH SIZES EXCEEDED FOR CONTROL ROOM ENVELOPE

"On December 13, 2013 it was determined that a reportable condition has existed at Columbia Generating Station since 1500 hours [PST] on November 25, 2013.

"At 1500 hours on November 25, 2013, the Control Room Envelope (CRE) was declared inoperable based on the inability to ensure that the Control Room Emergency Filtration (CREF) System would be able to maintain a positive differential pressure with all areas surrounding the CRE boundary. Columbia does not have the installed instrumentation to directly monitor the differential pressure between the Main Control Room (MCR) and certain areas adjacent to the MCR. The pressure in the adjacent areas is controlled by placing conservative limits on allowed breach size for these adjacent areas.

"On November 25, 2013, it was identified that the combined breach size associated with several doors in these adjacent spaces resulted in exceeding the allowed limit. Based on exceeding the allowed breach size limit to the adjacent areas, the Control Room Envelope was declared inoperable, and Technical Specification Action Statement 3.7.3.B.1 was entered.

"An additional breach was discovered on 12/05/13 from a hole in ductwork passing through the cable spreading room, which is one of the adjacent areas to the CRE boundary, and that condition was added to the existing action statement 3.7.3.B.1. These are conditions that could have prevented fulfillment of a safety function of structures that are needed to mitigate the consequences of an accident and are reportable under 10 CFR 50.72(b)(3)(v)(D)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49632
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MARK DODDS
HQ OPS Officer: PETE SNYDER
Notification Date: 12/13/2013
Notification Time: 20:07 [ET]
Event Date: 12/13/2013
Event Time: 17:57 [CST]
Last Update Date: 12/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 18 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR TRIP DURING FEED PUMP SWAP

"During a feed pump shift from the motor driven reactor feed pump to the 'A' turbine driven reactor feed pump during power ascension, reactor pressure vessel (RPV) water level was approaching the Reactor Protective System (RPS) automatic scram set point when a manual reactor scram was inserted.

"All control rods fully inserted. RPV water level is being maintained by the normal condensate booster / feedwater systems. RPV pressure is being maintained via normal main steam system. There were no actuations of any Emergency Core Cooling System and no Safety Relief Valves actuations. All systems responded as expected."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49633
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: BRYAN EAGAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/14/2013
Notification Time: 06:57 [ET]
Event Date: 12/14/2013
Event Time: 03:37 [EST]
Last Update Date: 12/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
WAYNE SCHMIDT (R1DO)
MELANIE GALLOWAY (NRR)
WILLIAM GOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

MANUAL SCRAM DUE TO RISE IN REACTOR PRESSURE DURING TURBINE VALVE TESTING

"Today at approximately 0337 [EST], during quarterly turbine valve testing with reactor power at 100% of rated thermal power, the plant experienced reactor pressure control abnormalities. Reactor pressure rose to 1042 psig [at which point] the Operators inserted a manual SCRAM. The cause of the rise in reactor pressure is currently under investigation.

"All control rods inserted into the core. Main steam isolation valves remained open, [however], bypass valves did not open as expected. The plant is in its normal electrical lineup and decay heat is being removed via isolation condensers. No electronic (EMRVs) or safety valves lifted during the transient. The plant is currently shutdown and all parameters are stable.

"This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'"

The licensee notified the NRC Resident Inspector and will be notifying the State.

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Power Reactor Event Number: 49634
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL QUITTER
HQ OPS Officer: DANIEL MILLS
Notification Date: 12/14/2013
Notification Time: 19:32 [ET]
Event Date: 12/14/2013
Event Time: 15:03 [PST]
Last Update Date: 12/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GREG WERNER (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

UNANALYZED CONDITION AFFECTING UNIT 1 EMERGENCY DIESEL GENERATOR

"At 1503 PST on December 14, 2013, Pacific Gas and Electric Company identified that, if atmospheric conditions were to develop that had both sustained high winds exceeding 60 miles per hour from the NW to NNE direction, and ambient air temperature exceeding 97 degrees Fahrenheit, the combination of these conditions could result in inadequate heat removal to support continuous operation of the Unit 1 emergency diesel generators. Upon identification of this condition, shift orders were issued requiring implementation of existing procedural guidance to open plant doors to allow additional air flow that would provide adequate emergency diesel generator cooling to support continuous operation of the U1 emergency diesel generators.

"This report addresses a condition as described in 10 CFR 50.72(b)(3)(ii)(B).

"The NRC Resident Inspector has been notified of this condition."

This condition was discovered during a license basis verification review.

Page Last Reviewed/Updated Monday, December 16, 2013
Monday, December 16, 2013