United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for September 28, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/27/2012 - 09/28/2012

** EVENT NUMBERS **


48212 48320 48322 48324 48326 48339 48350 48351 48352 48353

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48212
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ANDREW HESS
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/20/2012
Notification Time: 19:11 [ET]
Event Date: 08/20/2012
Event Time: 15:20 [CDT]
Last Update Date: 09/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ERIC DUNCAN (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

RWCU SYSTEM ISOLATION DIFFERENTIAL FLOW - HIGH FUNCTION INOPERABLE

"On 8-20-2012 during scheduled surveillance testing, the Reactor Water Cleanup (RWCU) System Isolation Differential Flow - High function was discovered to be inoperable at 1520 CDT. The high differential flow signal is provided to detect a break in the RWCU system when area or differential temperature would not provide detection (i.e. cold leg break). This instrumentation provides isolation signals to both inboard and outboard isolation valves and its loss is being reported pursuant to 10CFR50.72(b)(3)(v)(C).

"The NRC Resident Inspector was notified."

* * * RETRACTION AT 1513 EDT ON 9/27/2012 FROM BOB MURRELL TO MARK ABRAMOVITZ * * *

"Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the RWCU Differential Flow High instrument loop was, at all times, capable of performing its TS function. Specifically an engineering analysis of the impact of the instrument as-found and as-left values on the overall instrument loop setting was performed. The analysis determined that the instrument in question was set at a value which would have isolated the RWCU Primary Containment Isolation Valves prior to reaching the Technical Specification (TS) allowable value and therefore the instrument loop remained capable at all times of performing its TS function.

"This event is not considered a Safety System Functional Failure or a Condition Prohibited by TS and is not reportable to the NRC as a Licensee Event Report (LER) per 10CFR50.73.

"The NRC Senior Resident Inspector has been notified."

Notified the R3DO (Lipa).

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Agreement State Event Number: 48320
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: BAYER MATERIAL SCIENCE LLC
Region: 4
City: BAYTOWN State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/19/2012
Notification Time: 14:47 [ET]
Event Date: 09/19/2012
Event Time: [CDT]
Last Update Date: 09/19/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE SHUTTERS STUCK OPEN

State of Texas provided the following information via email:

"On September 19, 2012, the licensee notified the Agency [Texas Department of Health] that during a routine inspection it had discovered that the shutters on two Berthold LB-300L gauges were stuck in the open position. Both gauges contained cobalt-60 sources: one source was 1.9 milliCuries and the other was 1.68 milliCuries. Since these gauges normally operate in the open position, there was no increased risk of exposure to any individual. The licensee is making arrangements for a licensed vendor representative to make repairs as soon as possible. Information will be provided in accordance with SA-300 as it is obtained.

"Source holder/source information: 1.9 mCi cobalt-60 source holder/source SN: 1412/1-7-98; 1.68 mCi cobalt-60 source holder/source SN: 1771/2-11-00."

Texas Incident #: I-8990

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Agreement State Event Number: 48322
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: ENERGY SOLUTIONS LLC
Region: 4
City: CLIVE State: UT
County:
License #: UT2300249
Agreement: Y
Docket:
NRC Notified By: GWYNN GALLOWAY
HQ OPS Officer: PETE SNYDER
Notification Date: 09/19/2012
Notification Time: 17:34 [ET]
Event Date: 09/18/2012
Event Time: 14:00 [MDT]
Last Update Date: 09/19/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - SURFACE CONTAMINATION IDENTIFIED ON A SHIPMENT

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

"During the normal receipt process of a shipment #0870-09-0101 of LLRW [low level radioactive waste] on September 18, 2012, Energy Solutions personnel found one barrel in a shipment of five barrels that had removable beta contamination (tritium) which exceeded U.S. DOT limits. There was no visible damage to the barrel and no indication that the barrel had leaked during transport. Licensee personnel surveyed the other barrels in the shipment and the vehicle. No removable beta contamination was found and the vehicle was released on September 18, 2012.

"[Utah Division of Radiation Control] staff are investigating this incident."

Utah Incident No.: UT120002

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Agreement State Event Number: 48324
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNIVERSAL WELL SERVICES
Region: 1
City: MEADVILLE State: PA
County:
License #: PA-1446
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/20/2012
Notification Time: 13:21 [ET]
Event Date: 09/18/2012
Event Time: [EDT]
Last Update Date: 09/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - SHUTTER FAILURE

The following information was provided by the State of Pennsylvania via facsimile:

"On September 19, 2012, the licensee sent notification via email to the Department's Central Office regarding an event that took place on September 18, 2012. The event is reportable within 24 hours per 10CFR 30.50(b)(2).

"The licensee discovered during a routine maintenance inspection that the pin which allows the shutter handle to move was stuck in the closed position, rendering the shutter inoperable. No radiation exposure to personnel is believed to have occurred. The cause of the event was normal wear of gauge. The handle is in the closed position and the gauge has been taken out of service. A reactive inspection is planned by the Department's Western Regional Office.

"The device is identified as:
Manufacturer: Berthold Technologies USA, LLC
Model: LB8010
Serial #: 10055
Isotope: Cs-137
Activity: 20 mCi
Source Serial Number: 0800/08"

Event Report ID No: PA120031

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Agreement State Event Number: 48326
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: UNIVERSITY OF TENNESSEE MEDICAL CENTER
Region: 1
City: KNOXVILLE State: TN
County:
License #: R-47011
Agreement: Y
Docket:
NRC Notified By: JERRY BINGAMAN
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/20/2012
Notification Time: 16:38 [ET]
Event Date: 09/11/2012
Event Time: [EDT]
Last Update Date: 09/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - PATIENT RECEIVED UNDERDOSE OF Y-90 MICROSPHERES

The following information was provided by the State of Tennessee via facsimile:

"On September 11, 2012, the Division of Radiological Health received a report from the University of Tennessee Medical Center regarding a misadministration that occurred September 11, 2012. A patient was prescribed a dose of 20.0 mCi of Y-90 SirSphere microspheres, and only 15.32 mCi was administered. The administered dosage was 23% less than prescribed and will result in an absorbed dose of 40.1 Gy less than the calculated 171.3 Gy. The reason why this event occurred is not known.

"The residual activity was detectable in the SirSpheres waste container which contained the V-vial; tubing, catheters, and protective radioactive waste cloths. The administered dosage is still considered to be within therapeutic range, but less than that prescribed by the physician. The patient and the referring physician were both notified on September 11, 2012. Inspectors from the Knoxville Field Office will follow-up on this incident."

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: 48339
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GLENN GOELZER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/25/2012
Notification Time: 09:46 [ET]
Event Date: 09/25/2012
Event Time: 05:55 [PDT]
Last Update Date: 09/27/2012
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
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER REMOVED FROM SERVICE FOR MAINTENANCE

"On September 25, 2012, power was removed from various Technical Support Center (TSC) systems to perform planned system preventative maintenance (PM) and corrective maintenance (CM) activities. During these maintenance activities, the normal TSC and Operational Support Center (OSC) are unavailable for use during an emergency. The Plant Data Network (PDN) will not be available to the TSC. This will render the Safety Parameter Display System (SPDS), Emergency Response Facility Display System (ERFDS), Emergency Assessment and Response System (EARS) and the Post LOCA Sampling System in the TSC unavailable. System alarms and data displays will still be available to the plant operators in the Control Room. The expected duration of the power outage is approximately 39 hours.

"As compensatory measures, the backup emergency response facilities will be manned during an emergency. This compensatory measure has been communicated to the emergency response organization. It is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time that the normal TSC and OSC are unavailable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update message will be provided when the emergency response facilities are restored."

The licensee will notify the NRC Resident Inspector.

* * * UPDATE FROM GOELZER TO KLCO ON 9/27/12 AT 0025 EDT * * *

"This is an update to EN #48339 report on September 25, 2012, where Pacific Gas & Electric company (PG&E) reported that a planned maintenance power outage caused the normal Technical Support Center (TSC) and Operational Support Center (OSC) to be unavailable for use during an emergency.

"PG&E has completed all preventative maintenance (PM) and corrective maintenance (CM) activities that required the power outage to the TSC and OSC and has completed the restoration of these emergency response facilities. Plant personnel have been notified that the normal emergency response facilities have been restored.

"PG&E personnel have informed the NRC Resident Inspector."

Notified the R4DO (Werner).

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Part 21 Event Number: 48350
Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE PORTER
HQ OPS Officer: VINCE KLCO
Notification Date: 09/27/2012
Notification Time: 11:01 [ET]
Event Date: 09/27/2012
Event Time: 11:01 [EDT]
Last Update Date: 09/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
RONALD BELLAMY (R1DO)
REBECCA NEASE (R2DO)
CHRISTINE LIPA (R3DO)
GREG WERNER (R4DO)
PART 21 GROUP (EMAI)

Event Text

ERROR IN MAIN STEAM LINE HIGH FLOW CALCULATIONAL METHODOLOGY

The following information was received by facsimile:

"GEH [General Electric Hitachi] has recently discovered that calculations of choked flow rate in the Main Steam Line (MSL) of GEH BWRs may not be conservative, with the potential impacts to be evaluated for existing MSL high-flow setpoints and Analytical Limits (ALs).

"GEH has not completed the evaluation of this condition to determine reportability under 10CFR Part 21 and is therefore issuing this 60-day Interim Notification. GEH will close or issue an update on this matter on or before December 12, 2012. Given the early status of the evaluation, GEH has no recommended actions at this time. This 60-day Interim Notification is issued in accordance with 10CFR Part 21.21(a)(2), and will be sent to all GE
BWR/2-6 plants and ABWR plants."

Affected plants include the following: Nine Mile 1-2, Fermi 2, Columbia, Grand Gulf, River Bend, FitzPatrick, Pilgrim, Vermont Yankee, Clinton, Dresden 2-3, LaSalle 1-2, Limerick 1-2, Oyster Creek, Peach Bottom 2-3, Quad Cities 1-2, Perry 1, Duane Arnold, Cooper, Susquehanna 1-2, Brunswick 1-2, Hope Creek, Hatch 1-2, Browns Ferry 1-3, and Monticello.

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Power Reactor Event Number: 48351
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN FINLAY
HQ OPS Officer: PETE SNYDER
Notification Date: 09/27/2012
Notification Time: 13:55 [ET]
Event Date: 09/27/2012
Event Time: 09:30 [CDT]
Last Update Date: 09/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
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 Y 100 Power Operation 100 Power Operation

Event Text

FITNESS FOR DUTY - CONTRABAND MATERIAL IDENTIFIED IN THE PROTECTED AREA

A licensee contractor discovered contraband material concealed above ceiling tiles in a locker room during a renovation of the area. Contact the Headquarters Operations Officer for details.

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 48352
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RAUL MARTINEZ
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/27/2012
Notification Time: 14:08 [ET]
Event Date: 09/27/2012
Event Time: 12:54 [CDT]
Last Update Date: 09/27/2012
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
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

PARTIAL LOSS OF EMERGENCY ASSESSMENT DURING PLANNED MODIFICATIONS

"On September 27, 2012, Comanche Peak Nuclear Power Plant began a cyber security related modification to the Unit 1 and 2 Plant Computer Systems (PCS) and associated network infrastructure. The entire PCS for each unit will be out of service for approximately 6 hours. During that time, the PCS satellite display systems (SDSs) in the TSC and EOF will be inoperable. After approximately 8 hours, the PCS will be restored to service along with the SDSs in the TSC. The SDSs in the EOF will remain out of service until the modification and related site acceptance testing is complete, currently scheduled for October 5, 2012. During this period. the remote display of Radiation Monitoring System (RMS) information in the EOF and OSC will be unavailable.

"The loss of EOF SDS terminals will be compensated by use of an alternate plant parameter display system, and loss of EOF/OSC RMS remote display will be compensated by means of the status board recorder telephone loop. Therefore, it is expected that appropriate assessment of plant conditions. notifications, dose projections, and communications could still be made, if required, during the time that the SDSs and RMS remote displays are inoperable.

"The extended loss of the EOF SDSs and EOF/OSC remote RMS data is being reported in accordance with 10.CFR.50.72(b)(3)(xiii). which is any event that results in a major loss of emergency assessment capability, offsite response capability, or off site communications capability. The NRC Resident Inspector has been notified. A follow-up ENS communication will be made when the EOF SDSs and EOF/OSC remote RMS remote displays are fully restored to service."

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Power Reactor Event Number: 48353
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JORGE O'FARRILL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/27/2012
Notification Time: 22:17 [ET]
Event Date: 09/27/2012
Event Time: 12:12 [EDT]
Last Update Date: 09/27/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
RONALD BELLAMY (R1DO)
PART 21 GROUP ()

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 92 Power Operation 100 Power Operation

Event Text

PART-21 REPORT - FAULTY MASTER TRIP UNITS, SLAVE UNITS, AND RESISTANCE TEMPERATURE DETECTORS

"On September 27, 2012, the Site Vice President was notified that a 10CFR21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.

"Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification. Specifically, epoxy was not applied under certain resistors as required. In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10CFRPart 21 condition involving a defect in a basic component.

"As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions. Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.

"JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation. The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF.

"This notification is made pursuant to 10CFR21.21(d)(3)(i)."

Page Last Reviewed/Updated Friday, September 28, 2012
Friday, September 28, 2012