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Event Notification Report for October 19, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/18/2005 - 10/19/2005

** EVENT NUMBERS **


42055 42059 42062 42063

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General Information or Other Event Number: 42055
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: CHICAGO TESTING LABORATORY
Region: 3
City: BLUE ISLAND State: IL
County:
License #: IL-02065-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: BILL GOTT
Notification Date: 10/14/2005
Notification Time: 11:31 [ET]
Event Date: 10/14/2005
Event Time: 06:00 [CDT]
Last Update Date: 10/14/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVE PASSEHL (R3)
TOM ESSIG (NMSS)

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

"The Radiation Safety Officer at Chicago Testing Laboratory's (IL-02065-01) Elk Grove facility reported the theft of a Troxler gauge. The gauge is a model 3440 with s/n 16643. It contains 8 milliCuries of Cs-137 and 40 milliCuries of Am-241:Be. The construction gauge was stolen from the bed of a company truck early this morning between 0400 and 0630 while it was parked at the residence of the operator in Blue Island, IL. Blue Island police have investigated the reported theft. Several other pieces of construction equipment were stolen from the truck as well. The gauge was stored in its manufacturer's large yellow DOT Type A container. The gauge is designed to be used in the construction industry to determine compaction and density of soil, roadbeds, asphalt and concrete. The sealed sources have withstood direct impact from compactors and were designed with that possibility in mind.

"Local police have been advised to be aware of the theft and to notify the Agency's dispatch center should the gauge be located. They were cautioned that should the gauge appear to be damaged, crushed or dismantled to not approach the device and to secure the scene pending our notification/arrival."

Illinois Report number: IL050051

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Power Reactor Event Number: 42059
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JANET NOVAK
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/18/2005
Notification Time: 14:14 [ET]
Event Date: 10/18/2005
Event Time: 09:30 [EDT]
Last Update Date: 10/18/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN KINNEMAN (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Refueling 0 Refueling

Event Text

UT EXAMINATION DISCOVERED AN UNACCEPTABLE SPRAY LINE TO PRESSURIZER WELD

Ultrasonic Testing (UT) during the current refueling outage revealed three (3) indications unacceptable to ASME Section XI code on the 4 inch line "3RCS-004-224-1" Reactor Coolant System Pressurizer Nozzle to safe end weld. Two indications are circumferential, 6.4 inches and 7.7 inches in length, and the third is .25 inches long axis. This condition has existed since construction, i.e., circa 1984. There is no indication of any past RCS leakage from any of these weld defect indications. A weld overlay repair is currently in progress with five of seven passes completed which will meet ASME code requirements for all modes of operation.

The licensee will inform state/local agencies and has informed the NRC Resident Inspector.

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General Information or Other Event Number: 42062
Rep Org: IVEYCOOPER SERVICES, LLC
Licensee: INDUSTRIAL NUCLEAR COMPANY
Region: 1
City: CHATTANOOGA State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID W. IVEY
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/18/2005
Notification Time: 17:43 [ET]
Event Date: 10/17/2005
Event Time: [EDT]
Last Update Date: 10/18/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JOHN KINNEMAN (R1)
MICHAEL MARKLEY (NMSS)

Event Text

PART 21 REPORT INVOLVING A RADIOGRAPHIC SEALED SOURCE WITH A POTENTIAL SAFEY CONCERN

The following information was provided via fax:

"On October 17, 2005 I became aware of a condition involving a radiographic sealed source that may prove to be a safety concern to users of the sources. The manufacturer was promptly notified of the condition and a resolution was provided to IveyCooper via memo. The attached supplier corrective action has been generated and transmitted to Industrial Nuclear for 'Root Cause' and 'Action to Prevent Recurrence' dispositions. It provides details of the discovered condition. I am providing this notification in accordance with the requirements of 10CFR21.

"Date: 10/17/05

"Supplier: Industrial Nuclear Company, 35 Flagship Dr., North Andover, MA 01845

"Due Date: 12/17/05

"Material: Model 702 Radiographic Source

"Quantity: 8 at IveyCooper, unknown quantity at other licensees

"Description of Nonconformance: Roll pins of source connectors protrude from the source connector bodies on sources purchased from Industrial Nuclear Company in North Andover, MA. The protruding pins may increase risk of disconnect or source hanging in guide tube. Per the manufacturer roll pins should not extend past the outer plane of the connector barrel. A dial caliper was used to determine the amount of stick-out. Note: Two of the sources had been in use since January 05. No operational problems had occurred during use.

"Corrective Action Taken: Per memo from Industrial Nuclear Company the roll pins were filed to a flush condition using a hand file. Sources were secured and locked within the exposure device during the operation.

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Power Reactor Event Number: 42063
Facility: BYRON
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ED BANDIS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/19/2005
Notification Time: 02:39 [ET]
Event Date: 10/19/2005
Event Time: 00:57 [CDT]
Last Update Date: 10/19/2005
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):
ERIC DUNCAN (R3)

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

Event Text

AUTOMATIC REACTOR TRIP DUE TO LOW 2 STEAM GENERATOR WATER LEVEL


"Unit 2 reactor trip on low 2 S/G level. 2A CD/CB (condensate and condensate booster pump set is driven by a single motor) tripped while 2D CD/CB was out of service. The auto turbine runback was unsuccessful and turbine was runbacked manually. ESF actuations: AF (Auxiliary Feedwater) activation and FWI (Feedwater Isolation)." Only indication on the condensate and condensate booster pump trip was an over current flag.

All rods fully inserted into the core. Both the motor driven and the diesel driven auxiliary feedwater pumps are operating. All Emergency Core Cooling systems and the Emergency Diesel Generators are fully operable if needed.

The NRC Resident Inspector was paged by the licensee.

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