United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for January 7, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/04/2013 - 01/07/2013

** EVENT NUMBERS **


48630 48631 48632 48633 48634 48650 48651 48652 48653

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Agreement State Event Number: 48630
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: PHILLIPS 66
Region: 4
City: WESTLAKE State: LA
County:
License #: LA-2149-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/28/2012
Notification Time: 15:26 [ET]
Event Date: 11/09/2012
Event Time: [CST]
Last Update Date: 12/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER ON PROCESS GAUGE

The following information was received from the Louisiana Department of Environment Quality via facsimile:

"On 11/09/2012, the RSO for Phillips 66 called in a preliminary report about [stuck] shutters on fixed level gauges utilized in their processes in the chemical plant. There was no possible exposure to the plant workers because the gauges were still installed on a process [tank in a remote location] and the shutters remaining open was not a problem. . . . The gauges are Omart and Ronan Engineering devices. [A manufacturer service technician] was contacted to evaluate the source holders and determined which devices could be repaired and which ones needed to be replaced. All of the source holders, with the exception of two were able to be freed up for continual use. . . . Two source holders were damaged during the evaluation process. . . .These two sources in their holders will be replaced during the next turn-a-round to reduce down time. . . . The gauges have been in the elements for a prolonged period of time and the shutters malfunctioned due to corrosion in the mechanism of the source holder. All of the sources were evaluated and inspected . . .. The manufacturer's service tech stated that it appears the be from being in the elements. The manufacturer stated that they were looking into finding a modification to shield the shutter mechanism from the elements. The Louisiana Department of Environmental Quality considers this item closed and the records will be reviewed during the next inspection."

The gauges involved are:
1) Omart SHLG2-45
2) Omart SR 2
3) Ronan SA1-F37

Louisiana Incident Number T145023

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Agreement State Event Number: 48631
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: BASF CORPORATION
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2304-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/28/2012
Notification Time: 15:14 [ET]
Event Date: 11/27/2012
Event Time: [CST]
Last Update Date: 12/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER ON PROCESS GAUGE

The following information was received from the Louisiana Department of Environment Quality via facsimile:

"On 11/27/2012, the RSO for BASF called in a preliminary report about a shutter on a fixed level gauge utilized in their processes in the chemical plant. There is no possible exposure to the plant workers because the gauge [is] installed on a remote process [tank inaccessible by plant personnel] and, [consequently], the shutter remaining open and operating [should not be] a problem. . . . The gauge is a Berthold, model #LB-7440D loaded with 150 mCi of Cs-137. [A manufacturer service technician] has been contacted to repair the level gauge. The manufacturer's service tech stated that [the stuck shutter] appears [to be the result of exposure to] the elements. The Louisiana Department of Environmental Quality considers this item closed and the records will be reviewed during the next inspection."

Louisianan Incident Number: T145017

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Agreement State Event Number: 48632
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: ROCK TENN CP, LLC
Region: 4
City: HODGE State: LA
County:
License #: LA-2230-LO1
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/28/2012
Notification Time: 15:24 [ET]
Event Date: 11/01/2012
Event Time: [CST]
Last Update Date: 12/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER ON PROCESS GAUGE

The following information was received from the Louisiana Department of Environment Quality via facsimile:

"On 11/01/2012, the RSO for Rock Tenn called to report a stuck shutter on a [density] gauge utilized on a process [line] in the paper mill refinery. There was no possible exposure to the mill workers because the gauge is installed on a process [line in a remote location] and, [consequently,] the shutter remaining [open] is not a problem. The gauge is a Berthold, Model LB 7400 Series, loaded with a 50 mCi Cs-137 [source]. The gauge has been in the elements for a prolonged period of time and the shutter malfunctioned due to corrosion in the mechanism of the source holder. All of the sources were evaluated and inspected and only one needed repair. The manufacturer stated that it appeared to be from being in the elements. The manufacturer stated that they were looking into finding a modification to shield the shutter mechanism from the elements. The Louisiana Department of Environmental Quality considers this item closed."

Louisiana Incident Number: T144358

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Agreement State Event Number: 48633
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: PACIFIC NORTHWEST NATIONAL LABS
Region: 4
City: RICHLAND State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SEAN MURPHY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/28/2012
Notification Time: 17:27 [ET]
Event Date: 12/04/2012
Event Time: [PST]
Last Update Date: 12/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)
JACK GUTTMANN (NMSS)

Event Text

AGREEMENT STATE REPORT - OPEN TRANSPORT VEHICLE WITH RAD LEVELS EXCEEDING LIMITS

The following information was received from the Washington State Division of Radiation Protection via e-mail:

"A shipment of waste from the 325 building on the Hanford reservation, prepared for shipment by Pacific Northwest National Laboratories, was received at Perma-Fix Northwest waste (PFNW) -Richland. During the unloading evolution, PFNW noted that the dose rate on the bottom of 2 drums exceeded the manifested value, and one drum exceeded 200 mr/hr on contact. (See limits in 49CFR173.221 (b)). PFNW notified Washington Department of Health (WDOH). A [WDOH] inspector came to the site on December 6, 2012 and measured the dose rate with an Ludlum M-9 and measured 350 mr/hr. [WDOH] has routinely used an Eberline RO2 type of meter to determine compliance - this reading be taken again with an RO2. PFNW had an RO20 which measured 220 mr/hr. This is the reading that was used as the 'actual' dose rate. [WDOH] is attempting to get a measurement with an RO2. The dose rate value may change, as [WDOH] takes additional reading with other instruments after the new year.

"The dose rate at the drivers area and the outside of the shipment vehicle were within the limits for transportation. No material was detected to have leaked from the containers. There is not expected overexposure caused by this incident.

"Actions taken by State: Suspend all shipment to PFNW by PNNL

"Sr90 (in drums with errant dose rates.) Total activity in 2 drums: 2.4 e 5 MBq."

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Agreement State Event Number: 48634
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: GE HEALTHCARE
Region: 4
City: ARLINGTON HEIGHTS State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SEAN MURPHY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/28/2012
Notification Time: 17:27 [ET]
Event Date: 12/13/2012
Event Time: [PST]
Last Update Date: 12/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)
JACK GUTTMANN (NMSS)

Event Text

AGREEMENT STATE REPORT - OPEN TRANSPORT VEHICLE WITH RAD LEVELS EXCEEDING LIMITS

The following information was received from the Washington State Division of Radiation Protection via e-mail:

"Shipment number GE-IL-120712-USEW arrived at the US Ecology waste site on the morning of December 11, 2012. The shipment manifest listed Zn-65 and Co60 as the isotopes. The material is NARM material. Total activity 3.02E6 MBq. Total volume 6.07 m3. Total weight 15,082 Kg. Waste class A- stable. The drums were accelerator targets from GE Healthcare in Illinois and New Jersey, loaded in boxes, which were again loaded in drums and cemented in place. The outer drums were DOT 7A containers. The entity signing the shippers certification on the manifest was GE Healthcare in Illinois.

"US Ecology staff conducted surveys of the shipping vehicle, and reported to Washington State Department of Health that the dose rate on the bottom of the truck was greater than 200 mr/hr with a side wall GM detector. Washington State Department of Health inspector used an Eberline RO2 ion chamber to get a more accurate measurement, and found that the dose rate measured with the meter bottom flush with the bottom of the floor I beams was 250 mr/hr.

"The shipment shifted in transportation, and was not braced to withstand conditions of normal transportation. The shipment contained drums strapped to small pallets. Upon inspecting the shipment, the drums were not tightly contained in the trailer, noted by gaps between the toe boards and the drums, loose straps in the rear of the drums, and large spaces between the load locks and the drums. The driver was asked if his trip was normal, without any abnormal stops, turns, stops or bumps, and he said it was a very smooth ride, all on interstate, but he picked the load up in Iowa after the 1st truck had mechanical issues. One large drum in the center of the shipment had lead shielding blankets underneath the pallet it was on, and this drum could be rocked back and forth a few inches, while it was still strapped in the truck.

"A more detailed inspection of the packages occurred on the December 12th and 13th, including using the RO2 on the bottom of drums that exhibited higher than manifested dose rates. Two drums were found to have external, on contact dose rates of 1.5 R/hr.

"One drum's lid was not correctly installed. While there was no evidence of leakage, nor did the lid come off, it was not properly installed. The shipment required the use of 7A containers.

"One drum could not be correlated to the manifest, as there was a transposition error in the drum number. A call to the generator corrected the problem.

"The dose rate at the drivers area and the outside of the shipment vehicle were within the limits for transportation. No material was detected to have leaked from the containers. There is no suspected overexposures caused by this incident."


Washington State Report WA-12-081

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Power Reactor Event Number: 48650
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: PAUL HERMANN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/04/2013
Notification Time: 13:20 [ET]
Event Date: 12/29/2012
Event Time: [CST]
Last Update Date: 01/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
BINOY DESAI (R2DO)
PART 21 GRP (EMAI)

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

PART 21 - ANTI-ROTATION PIN FAILURE IN 10-INCH ANCHOR DARLING (FLOWSERVE) DOUBLE DISC GATE VALVE

The following is a summary of the information received from TVA - Browns Ferry via facsimile:


On December 29, 2012 it was determined that sufficient data existed to determine a defect existed in a 10-inch Anchor Darling double disc gate valve installed in Browns Ferry Unit 1.

In November, 2012 during a scheduled refueling, the High Pressure Coolant Injection valve, 1-FCV-073-0002 failed its local leak rate test with gross leakage identified on the upstream (reactor side) disc. The downstream side of the discs showed acceptable leakage.

When maintenance was performed on the valve, the disc retainer bolt was found sheared. Further investigation revealed that the anti-rotation pin had failed. A review of work order history determined that this valve was installed during the Unit 1 recovery in 2007.

The cause of the anti-rotation pin failure was determined to be that the stem was not adequately torqued to the upper wedge at the manufacturing plant. This cause was confirmed by internal inspections of the valve that were performed at Browns Ferry. Flowserve Corporation is also conducting an investigation.

The licensee identified 15 other applications of this particular 10-inch valve in all three Browns Ferry units. For all those valves except 2-FCV-073-0002, documentation exists demonstrating that the stem to upper wedge was torqued to manufacturer requirements, determined through MOVATS [Motor-Operated Valve Analysis and Test System] testing that the anti-rotation pin is not sheared, or determined through visual inspection that the anti-rotation pin remains intact. 2-FCV-073-0002 is considered to be non-conforming and will be inspected during the next scheduled Unit 2 refueling.

The licensee has notified the NRC Resident Inspector of this notification.

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Power Reactor Event Number: 48651
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES AYALA
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/04/2013
Notification Time: 14:19 [ET]
Event Date: 01/04/2013
Event Time: 09:41 [CST]
Last Update Date: 01/04/2013
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):
RAY AZUA (R4DO)

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

Event Text

UNIT 2 MANUALLY TRIPPED AFTER TWO SHUTDOWN CONTROL RODS UNEXPECTEDLY DROPPED DURING SURVEILLANCE TESTING

"On January 4, 2013, at 0941 hours [CST], Unit 2 was manually tripped after 2 shutdown rods unexpectedly dropped during monthly control rod surveillance testing. Shutdown Bank C rods were being inserted in accordance with the surveillance procedure, when 2 rods in Shutdown Bank E (D-8 and M-8) unexpectedly dropped. This met the criteria for a manual reactor trip, which was immediately performed.

"The appropriate procedures were entered to mitigate the transient and all systems responded as designed.

"Unit 2 is currently in Mode 3 and the cause of the 2 dropped rods is under investigation."

All three (3) motor-driven and the steam-driven Auxiliary Feedwater Pumps started as required and have since been secured. Decay heat is being removed using normal startup feedwater with steam discharge to the main condenser via the bypass valves. Unit 2 is in a normal post trip electrical lineup.

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 48652
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: HARDY FARRIS
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/05/2013
Notification Time: 03:09 [ET]
Event Date: 01/04/2013
Event Time: 23:37 [CST]
Last Update Date: 01/05/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RAY AZUA (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 94 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO A TURBINE/GENERATOR TRIP

"Actuation of RPS with reactor critical. Reactor Scram occurred at 2337 CST 01/04/13 from 94% CTP (Core Thermal Power). The cause of the scram appears to be a Generator/Turbine trip.

"Appropriate off normal event procedures were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached and no ECCS or Diesel Generator initiation occurred.

"MSIVs remained open and SRVs lifted and reseated as designed. Currently, reactor water level is being maintained by the Condensate and Feedwater system in normal band and reactor pressure is being controlled via bypass valves to the condenser."

The NRC Resident Inspector has been informed. See similar EN #48637.

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Power Reactor Event Number: 48653
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/06/2013
Notification Time: 13:32 [ET]
Event Date: 01/06/2013
Event Time: 20:00 [EST]
Last Update Date: 01/06/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES NOGGLE (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 Y 100 Power Operation 100 Power Operation

Event Text

PLANNED CORRECTIVE MAINTENANCE ON THE TECHNICAL SUPPORT CENTER (TSC) HVAC POWER SUPPLY

"This ENS [report] is being issued in advance of planned corrective maintenance on a TSC HVAC power supply.

"On 1/6/13 at 2000 [EST], the Technical Support Center Emergency Ventilation system will be removed from service to perform corrective maintenance on the load center that supplies power to the TSC HVAC system. The emergency ventilation system will not be available and cannot be restored within the time period required to staff and activate the Emergency Response Organization (ERO). The work is scheduled to complete on Friday 1/11/13 at 1500 [EST].

"If an emergency is declared and the TSC activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological or other conditions. The Station Emergency Director would assess habitability in accordance with station procedures. TSC relocation of personnel would be directed as required until such time that the TSC ventilation system is returned to service.

"An update will be sent upon TSC HVAC restoration."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, January 07, 2013
Monday, January 07, 2013