United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for August 22, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/21/2013 - 08/22/2013

** EVENT NUMBERS **


48863 49143 49273 49274 49277 49278 49290 49293 49294 49295

To top of page
Part 21 Event Number: 48863
Rep Org: INTEGRATED RESOURCES, INC.
Licensee: INVENSYS (FOXBORO METER CO.)
Region: 4
City: NEBRASKA CITY State: NE
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN F. BROSEMER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/28/2013
Notification Time: 15:53 [ET]
Event Date: 03/27/2013
Event Time: 15:30 [CDT]
Last Update Date: 08/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
GREG PICK (R4DO)
PAUL KROHN (R1DO)
PART 21 GROUP (EMAI)
DEBORAH SEYMOUR (R2DO)
JULIO LARA (R3DO)

Event Text

PART 21 REPORT - FOXBORO POWER SUPPLY POTENTIAL FAILURES DUE TO DEFECTIVE TIE WRAPS AND HOLDERS

Mr. John F. Brosemer, President of Integrated Resources, Inc., reported discovery of repeated defects in Foxboro Meter Company's N-2ARPS-A6, Style D power supplies. When manufactured, the power supplies utilized Thomas and Betts TC105A aluminum wire tie holders in random numbers and placements. As the power supplies age, the tie wrap holder adhesive degrades and the tie wraps embrittle resulting in the separation of the tie wraps and loss of holder adhesion to the power supply enclosure. This causes the wraps and holders to fall to the bottom of the enclosure which could result in shorts when the aluminum comes in contact with electronic components. In one particular power supply, all tie wrap holders in use failed and separated from the enclosure.

The power supplies are used in Foxboro SPEC-200 cabinetry that are used throughout the industry. At the time of this notification, Integrated Resources has one power supply from Three Mile Island and two power supplies from Ft. Calhoun undergoing refurbishment. Integrated Resources will be following up this telephonic notification with a written report once their internal investigation is done.

Recommended corrective actions are for affected facilities to open and inspect all power supplies and remove the aluminum tie wrap holders and replace the tie wraps and holders with Teflon types.

* * * UPDATE FROM BROSEMER TO SNYDER AT 1530 EDT ON 4/1/13 * * *

"Suspecting this to be a common mode failure IRI [Integrated Resources, Inc.] opened and inspected two Foxboro N-2ARPS-A6 power supplies which were sent to IRI for refurbishment by Fort Calhoun Nuclear Station. Examination revealed that both of the power supplies have the same failures of the tie wrap aluminum mounting plates adhesive with the majority of the plates being held on the wire bundles by age embrittled nylon wire ties.

"Confirmation of the common mode failure by inspection of the Fort Calhoun Nuclear Stations was on or about 1530 CDT on March 27, 2013.

"IRI is not the OEM or Original supplier for this power supply and cannot provide the number nor locations of these components. However, by searching the RAPID database IRI has found the power supplies at the following:

"Arizona Public Service - Palo Verde Nuclear Generating Station; Constellation Energy - Nine Mile Point Nuclear Power Plant; Detroit Edison - Fermi 2 Nuclear Power Plant; Dominion Nuclear - Millstone Nuclear Power Plant; Dominion Nuclear - Kewaunee Nuclear Power Plant; Eletronnuclear - Angra Nuclear Power Plant; Entergy Nuclear - Arkansas Nuclear One; Entergy Nuclear - Indian Point Energy Center; Entergy Nuclear - Pilgrim Nuclear Power Plant; Entergy Nuclear - J. A. Fitzpatrick Nuclear Power Plant; Exelon Corporation - Three Mile Island Nuclear Plant; Exelon Corporation - Peach Bottom Atomic Power Station; NextEra Energy - Point Beach Nuclear Power Plant; Progress Energy Florida - Crystal River Nuclear Power Plant; Southern California Edison - San Onofre Nuclear Generating Station.

"IRI suspects several other utilities and units are affected by this report.

Corrective action taken: "IRI's preliminary suggestion is inspection and removal of failed tie wrap mounting plates which are being held on to wire bundles by aging nylon tie wraps. IRI also suggests replacement of age embrittled nylon tie wraps with Tefzel tie wraps."

Contact Information:
John F. Brosemer; President
Integrated Resources, Inc.
113 South 9th Street
Nebraska City, NE 68410

Notified R1DO (Dwyer), R2DO (Seymour), R3DO (Daley), R4DO (Kellar) and Part 21 Reactors (Email).

* * * UPDATE FROM JOHN BROSEMER (VIA EMAIL) ON 8/21/13 AT 1628 EDT * * *

"IRI's final recommendations are to remove all Thomas and Betts Co. model TC105A wire tie holders and to replace any embrittled wire ties with TEFZEL wire ties in all of the affected Foxboro Co. power supplies.

"IRI also discovered during the course of the investigation that Thomas and Betts Co. supplied these wire tie holders through normal distribution to all of the manufacturers. IRI recommends that the industry, during normal inspections, inspect for the these types of wire tie holders in all other installed equipment and to remove the failed wire tie holders."

Notified R1DO (Schmidt), R2DO (Haag), R3DO (Kozak), R4DO (Werner) and Part 21 Reactors (via email).

To top of page
Power Reactor Event Number: 49143
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ADAM PECK
HQ OPS Officer: VINCE KLCO
Notification Date: 06/24/2013
Notification Time: 04:35 [ET]
Event Date: 06/23/2013
Event Time: 21:20 [PDT]
Last Update Date: 08/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
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
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF 230 KV OFFSITE POWER RESULTS IN THE AUTOMATIC START OF EMERGENCY DIESEL GENERATORS

"At 2120 PDT, Diablo Canyon Power Plant experienced a loss of the offsite 230 kV startup power source due to an offsite transmission system relay actuation, resulting in valid anticipatory starts of Units 1 and 2 three emergency diesel generators on each unit. All diesels successfully started but were not loaded. All systems operated as designed with no problems observed.

"The 230 kV startup power source is the only offsite power system designed to be immediately available following an accident. However, the safety related onsite emergency diesel system would have provided power to mitigate the consequences of an accident while the 230 kV was unavailable.

"Restoration of the 230 kV offsite power system is in progress."

The licensee will notify the NRC Resident Inspector.

* * * UPDATE FROM MICHAEL KENNEDY TO HOWIE CROUCH AT 1618 EDT ON 8/21/13 * * *

"230 kV was restored to Operable on 06/24/13 at 0200 PDT. Normal 500 kV Offsite Power remained operable and was unaffected by this event.

"Following further review, Diablo Canyon Power Plant (DCPP) has determined that the loss of the 230 kV system was not a condition that could have prevented fulfillment of the safety function of a system credited to mitigate the consequences of an accident. This power source is not considered to be a safety-related system that is credited to mitigate any accident as described in the DCPP UFSAR, Chapters 6 and 15 accident analyses. PG&E concludes that the emergency diesel generators are the only power source needed to fulfill the accident mitigation function, and they did not become inoperable as a result of this event."

The licensee will be notifying the NRC Resident Inspector. Notified R4DO (Werner).

To top of page
Agreement State Event Number: 49273
Rep Org: MAINE RADIATION CONTROL PROGRAM
Licensee: RUMFORD PAPER COMPANY
Region: 1
City: RUMFORD State: ME
County:
License #: ME-17203
Agreement: Y
Docket:
NRC Notified By: JEAN GESLIN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/13/2013
Notification Time: 09:34 [ET]
Event Date: 03/25/2013
Event Time: [EDT]
Last Update Date: 08/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
FSME EVENT RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - SHUTTER STUCK ON FIXED PROCESS GAUGE

The following event report was received from the State of Maine Radiation Control Program via e-mail:

"Rumford Paper Company reported that the shutter on a fixed nuclear gauge (Ohmart model SH-F1-A45, serial #13520085) was stuck in the open position on 3/25/2013. The gauge contained a 370 MBq (10 mCi) Cs-137 source (model A-2100, serial #3133CM). Restrictions were put into place so no personnel could enter the vessel until repairs could be completed. The manufacturer was contacted and performed the necessary repairs and the shutter now operates properly."

Maine Report Number: ME130002

To top of page
Agreement State Event Number: 49274
Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: ACS TESTING, INC.
Region: 4
City: SHERWOOD State: OR
County:
License #: ORE 90987
Agreement: Y
Docket:
NRC Notified By: KEVIN SIEBERT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/13/2013
Notification Time: 14:22 [ET]
Event Date: 08/02/2013
Event Time: 02:30 [PDT]
Last Update Date: 08/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - STOLEN AND RECOVERED TROXLER MOISTURE DENSITY GAUGE

The following information was obtained from the State of Oregon via email:

"A Troxler portable moisture density gauge was stolen out of the back of a worker's truck around 2:30 AM [PDT] on August 2nd, 2013. The gauge was recovered by the Sherwood police within the hour and returned to worker. The gauge handle and case remained locked. The only locks breached were the locks securing the device in the back of the truck. The licensee was just informed of the theft and reported it to Oregon RPS [Radiation Protection Services] at 10:00 AM on August 13th, 2013. The licensee will conduct further investigation and develop corrective actions. This information will be reported to Oregon RPS within 30 days.

"Device: Troxler 3430
SN: 38580
Sources: 9 mCi Cs-137 and 44 mCi Am-241/Be"

Oregon Incident #: 13-0029

To top of page
Non-Agreement State Event Number: 49277
Rep Org: R&M ENGINEERING - KETCHIKAN
Licensee: R&M ENGINEERING - KETCHIKAN
Region: 4
City: KETCHIKAN State: AK
County:
License #: 50-29259-01
Agreement: N
Docket:
NRC Notified By: GUY OWEN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/13/2013
Notification Time: 20:03 [ET]
Event Date: 08/12/2013
Event Time: 08:15 [YDT]
Last Update Date: 08/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

TROXLER 3450 MOISTURE DENSITY GAUGE DAMAGED DURING ROAD CONSTRUCTION

The licensee reports that a Troxler 3450 moisture density gauge was damaged at a construction site on Prince Wales Island, Alaska. The gauge had been left at the side of a road and was run over by a pickup truck. The operating handle and source rod were bent, however the gauge sources were in the safe position. The gauge was surveyed by the licensee and there is no indication of leakage or personnel exposure. The licensee has stored the gauge in a secure location until the gauge can be returned to the manufacturer for repair.

The Troxler 3450 gauge is serial #540 and contains a 8 mCi Cs-137 and a 40 mCi Am-241/Be source.

To top of page
Agreement State Event Number: 49278
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: STANFORD UNIVERSITY
Region: 4
City: STANFORD State: CA
County:
License #: NOT PROVIDED
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/13/2013
Notification Time: 21:56 [ET]
Event Date: 08/13/2013
Event Time: [PDT]
Last Update Date: 08/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - CONTAMINATION LIMITS ON PACKAGE EXCEEDED

The following Agreement State report was received via email.

"[The California Department of Public Health / Radiation Health Branch was notified that Stanford University received a package containing Radium 223 from Cardinal Health in Denver, Colorado and the package indicated removable contamination of 400 DPM of technetium 99 on the package. The following information was provided:

"The caller stated, that a package was received at the Nuclear Medicine Department and the package had a reading of 400 DPM which exceeds the Dept. of Transportation limits. Caller stated the package has been isolated and secured in the appropriate area and the carrier notified. Caller stated that the package will be at normal readings tomorrow.

"Cardinal Health, in Denver, was notified and will investigate this issue. RHB California will report additional information."

To top of page
Power Reactor Event Number: 49290
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: MICHAEL STODICK
HQ OPS Officer: PETE SNYDER
Notification Date: 08/19/2013
Notification Time: 17:23 [ET]
Event Date: 08/19/2013
Event Time: 10:13 [PDT]
Last Update Date: 08/21/2013
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

INCREASING BACKGROUND NOISE IN STACK RADIATION MONITOR RENDERS IT NON-FUNCTIONAL

"At 1013 hours PDT on August 19, 2013 the Reactor Building Stack Radiation Monitor High Range Detector was declared nonfunctional due to increasing background noise. The Reactor Building Stack Radiation Monitor Intermediate Range Detector remains functional and shows no increase in effluent radioactivity.

"To compensate for the loss of assessment capability due to the nonfunctioning radiation monitoring equipment, an additional Health Physics (HP) Technician trained to acquire offsite dose assessment information on offsite releases will be available. The additional personnel will be pre-staged in support of the Radiation Monitoring System outage and will be mobilized in accordance with guidance in the compensatory measure instructions.

"This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). A follow-up notification will be made when the equipment has been returned to service.

"The licensee will notify the NRC Resident Inspector."

* * * UPDATE FROM MICHAEL STODICK TO PETE SNYDER AT 2028 EDT ON 8/19/13 * * *

"Initial investigation into the cause of the malfunction of the Reactor Building Stack Radiation Monitor High Range Detector revealed that the condition also affected the Reactor Building Stack Radiation Monitor Intermediate Range Detector. Therefore, this monitor has also been declared non-functional as of 1633 hours PDT on August 19, 2013. Compensatory measures remain in effect to provide emergency response capability for assessing and monitoring actual or potential offsite consequences of a radiological release through this pathway. Corrective actions are being pursued to restore the affected monitors to functional status."

The licensee notified the NRC Resident Inspector. Notified R4DO (Werner).

* * * UPDATE FROM MOT HEDGES TO HOWIE CROUCH AT 1236 EDT ON 8/21/13 * * *

"The cause of the increased background noise for the Reactor Building Stack Radiation Monitor-High Range was due to failing cooling components for the instrumentation, resulting in increased electronic background noise in the instrumentation. There has been no change in the radiation levels at the plant.

"The NRC Resident Inspector has been notified."

Notified R4DO (Werner).

To top of page
Power Reactor Event Number: 49293
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT CHRISTOS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/21/2013
Notification Time: 22:20 [ET]
Event Date: 08/21/2013
Event Time: 20:00 [CDT]
Last Update Date: 08/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
LAURA KOZAK (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

UNANALYZED CONDITION FOR EMERGENCY DIESEL GENERATOR FUEL OIL PUMPS TRAIN SEPARATION

"On August 21, 2013 at 2000 CDT, it was determined following receipt and review of an NRC position document, that the design of the Monticello Nuclear Generating Plant diesel fuel oil supply system is not consistent with current and historical licensing and design basis documents. This condition affects fuel oil supply from the diesel fuel oil storage tank to both emergency diesel generators and is being reported pursuant to 10CFR50.72(b)(3)(ii) as an unanalyzed condition that could significantly degrade plant safety.

"Actions are in progress to address the unanalyzed condition. The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 49294
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: SCOTT CIESLEWICZ
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/22/2013
Notification Time: 01:11 [ET]
Event Date: 08/21/2013
Event Time: 21:00 [CDT]
Last Update Date: 08/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
LAURA KOZAK (R3DO)

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

Event Text

INADVERTENT SIREN ACTUATION

"On 08/21/2013, the Kewaunee Power Station was notified by Kewaunee County Emergency Management of the inadvertent actuation of siren K-005 at 2100 [CDT]. At the time of the actuation, there was severe weather in the area. The siren stopped actuating at 2125. Kewaunee Power Station requested maintenance crews remove power from the siren to prevent additional actuation until repairs can be made. The resulting loss of siren coverage is 4%. Siren K-005 is a shared siren with Point Beach Nuclear Power Plant. Point Beach control room has been notified."

The licensee has notified the NRC Resident Inspector.

To top of page
Power Reactor Event Number: 49295
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: KILE HESS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 08/22/2013
Notification Time: 01:28 [ET]
Event Date: 08/21/2013
Event Time: 21:00 [CDT]
Last Update Date: 08/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
LAURA KOZAK (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

INADVERTENT SIREN ACTUATION

"Point Beach was notified via our EP [emergency plan] manager that emergency plan siren K 5 actuated inadvertently at 2100 [CDT] on 8/21/13, during severe weather. Initial notification of this occurrence was made by Kewaunee County Emergency Management to the Kewaunee Nuclear Plant EP manager. The Kewaunee EP manager in turn notified the Point Beach EP manager. The siren stopped sounding at 2125 on 8/21/13, and was removed from service to prevent additional inadvertent actuations before it is repaired. The loss of coverage for siren K-5, which is the only Point Beach siren out of service at this time, is 1.9%, which is below the 50% loss of coverage requiring additional notifications."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, August 23, 2013
Friday, August 23, 2013