United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2007 > September 14

Event Notification Report for September 14, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/13/2007 - 09/14/2007

** EVENT NUMBERS **


43622 43626 43628 43630 43632 43636 43637 43641

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 43622
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: RICHARD THOMPSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/07/2007
Notification Time: 00:52 [ET]
Event Date: 09/06/2007
Event Time: 23:22 [CDT]
Last Update Date: 09/13/2007
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
TROY PRUETT (R4)
JIM DYER (NRR)
PAT GWYNN (R4)
TOM ANDREWS (R4)
FANGIE JONES (R4)
IRWIN (FEMA)
EVANS (DHS)
MICHELE EVANS (NRR)
JEFF CRUZ (IRD)

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

LEAKAGE FROM REACTOR COOLANT SYSTEM >10 GPM

A relief valve (BG 8117) in the letdown system opened and released about 650 - 700 gallons of water from the reactor coolant system into the pressurizer relief tank. The rate of release from the letdown was 119 gpm. It was estimated that the pressurizer level lowered about 2-3%. The letdown system was isolated by closing the letdown orifice block isolation valve. Licensee is investigating the reason for the spurious lifting of the relief valve. Due to leakage from the reactor coolant system, the licensee entered EAL 4R. Plant is stable and operating at full power.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM THOMPSON TO ABRAMOVITZ AT 0120 EDT ON 09/07/07 * * *

The licensee stated that the Unusual Event was exited at 0120 EDT.

The licensee notified the NRC Resident Inspector. Notified R4DO (Pruett) and NRR EO (Evans) and IRD MOC (Cruz).

* * * UPDATE AT 1635 EDT ON 09/13/07 FROM JOHN WEEKLEY TO S. SANDIN * * *

The licensee is retracting this report based on the following:

"This is a follow-up notification to inform the NRC that Callaway Plant is retracting an Unusual Event declaration reported on 09/07/2007 at 00:52 EDT. EAL 4R was entered and the declaration was made due to leakage from the reactor coolant system.

"The basis for EAL 4R indicates that the initiating condition for an Unusual Event would include failure of a relief valve to properly close following reduction of applicable pressure and NOT simply the actuation of the relief valve as designed.

"Based on troubleshooting efforts and upon review of the event, it has been determined that relief valve BG8117 functioned as designed to reduce pressure and therefore the declaration of the Unusual Event was not required. The relief valve did sense an over-pressurization and did perform its intended function. The relief valve reseated when the letdown line was isolated. Based on this, the Unusual Event declaration is retracted."

The licensee informed the NRC Resident Inspector. Notified R4DO (Cain), EO (MJ Ross) and IRD (Blount).

To top of page
General Information or Other Event Number: 43626
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: QSA GLOBAL, INC
Region: 1
City: BURLINGTON State: MA
County:
License #: 12-8361
Agreement: Y
Docket: 09-7304
NRC Notified By: MIKE WHALEN
HQ OPS Officer: JASON KOZAL
Notification Date: 09/10/2007
Notification Time: 12:46 [ET]
Event Date: 08/31/2007
Event Time: [EDT]
Last Update Date: 09/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES TRAPP (R1)
MICHELE BURGESS (FSME)
ILTAB (email) ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - AM-241 SOURCES LOST DURING SHIPMENT

The State provided the following information via facsimile:

"Licensee received routine shipment of Am-241 button sources from supplier in China - Shenzhen CIC in Shenzhen, China on August 15, 2007. Shipment was sent via China Air from China to New York, and then transported by air to Boston. In Boston, it is then trucked via Ground Control and arrived at the licensees facility in Burlington, MA. The licensee estimates the package was sent from China sometime after July 25, 2007.

"The excepted package (UN2911) was damaged when it arrived at the licensees' facility. At this time the licensee confirmed there was no contamination nor high radiation levels from the package. This package is normally not opened as it is forwarded to a customer for use in smoke detectors. On August 31, 2007, before forwarding the package, the licensee opened the package to verify its contents. The licensee discovered that 2 vials from the package were missing.

"Each plastic vial contains 500 Am-241 button sources, each 0.8 microCi nominal activity, for a total of 0.4 milliCi total in each vial.

"The licensee immediately notified their transport broker and their agent in China."

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

To top of page
General Information or Other Event Number: 43628
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: AMERICAN ENGINEERING AND TESTING
Region: 3
City: DEXTER State: MN
County:
License #: MN07005
Agreement: Y
Docket:
NRC Notified By: GEORGE JOHNS
HQ OPS Officer: JASON KOZAL
Notification Date: 09/10/2007
Notification Time: 15:53 [ET]
Event Date: 09/10/2007
Event Time: 03:00 [CDT]
Last Update Date: 09/10/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
SONIA BURGESS (R3)
MICHELLE BURGESS (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The State provided the following information via email:

"On Monday, September 10, 2007, the Minnesota Department of Health (MDH) was notified by American Engineering and Testing that a fire had destroyed a Troxler Model 3430 moisture density gauge. The fire occurred at a private residence, which was a farm, and spread to a pick-up truck that was parked beside the garage to that residence. The fire melted the plastic components of the gauge but did not effect the Cesium-137 source in the source rod or the Americium-241:Beryllium source that was in the lead shielding. Members of the Fire Department who responded to the fire were instructed to maintain a safe distance from the truck to avoid minimize radiation exposures.

"MDH completed radiation and contamination surveys of both sources. No contamination was detected and the radiation levels were as would be expected with the shielding intact. The sources were placed in containers filled with sand to provide shielding and removed to a secure permanent storage location. The RSO and the Corporate RSO will complete leak tests and arrange for the appropriate containers for shipment to the manufacturer.

"The gauge was a Troxler Model 3430, Serial Number 23279, which contained approximately 9 millicuries of Cesium-137 (Serial Number 75-5294) and 44 millicuries of Americium-241:Be (Serial Number 47-19161)."

Minnesota Report number: MN07005

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.

To top of page
Hospital Event Number: 43630
Rep Org: INDIANA UNIVERSITY MEDICAL CENTER
Licensee: INDIANA UNIVERSITY MEDICAL CENTER
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-02752-03
Agreement: N
Docket:
NRC Notified By: MAC RICHARD
HQ OPS Officer: JOE O'HARA
Notification Date: 09/11/2007
Notification Time: 16:03 [ET]
Event Date: 09/10/2007
Event Time: 11:20 [EDT]
Last Update Date: 09/13/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
SONIA BURGESS (R3)
JACK DAVIS (FSME)

Event Text

MEDICAL EVENT - PATIENT RECEIVED AN UNDERDOSE OF YTTRIUM-90

On Monday 9/10/07, the licensee was administering a 66 millicurie dose of Yttrium-90 microspheres to a patient for the treatment of liver cancer through a catheter. The patient only received a dose of 47 millicuries, a 27% underdose. The licensee is investigating the cause of the misadministration, but they believe the catheter used for the administration of the isotope failed or is leaking. The licensee believes there is no permanent functional damage to the patient. The physicians have been informed by the RSO that they need to notify the patient of the underdose and report that notification to the RSO. The treatment device is from MDS Nordion and a MDS Nordion company representative was on site during the administration of the isotope. The licensee intends to use the MDS Nordion representative for technical assistance in troubleshooting this problem once background radiation levels permit a closer inspection of the catheter.

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.

* * * UPDATE PROVIDED BY CINDY FLANNERY (FSME) TO JASON KOZAL ON 9/13/07 AT 1352 * * *

This event (EN43630) has been reviewed and determined to be a reportable medical event.

To top of page
General Information or Other Event Number: 43632
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TOLUNAY-WONG ENGINEERS, INC
Region: 4
City: HOUSTON State: TX
County:
License #: L-04848
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOE O'HARA
Notification Date: 09/11/2007
Notification Time: 18:24 [ET]
Event Date: 09/11/2007
Event Time: 15:11 [CDT]
Last Update Date: 09/12/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CLAUDE JOHNSON (R4)
JACK DAVIS (FSME)
MATTHEW HAHN ILTAB ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE RETURNED TO OWNER

On 9/7/07, Component Sales Company of Houston, Texas purchased a moisture density gauge for $400.00 from [DELETED], who stated that he got the gauge at a garage sale. The Component Sales Co. representative investigated the serial number of the gauge and notified the owner of the gauge. The owner, Tolunay-Wong Engineers of Houston, Texas recovered the gauge a CPN model serial number MD80204152 with 10 millicuries of Cs-137 and 50 millicuries of Am-241/Be. The Tolunay-Wong Company representative stated that the gauge had been used the day before but did not know it was missing. The company is trying to determine if the source rod had been properly locked in place. The state believes that [DELETED] may be a minor. The State has not notified law enforcement, and is unsure whether law enforcement will be involved at all "since the gauge has been recovered." The state is investigating this matter.

Texas Incident Number - I-8442

* * *UPDATE PROVIDED BY TUCKER TO KOZAL ON 9/12/07 AT 1645 * * *

The State provided the following update via email:

"The RSO informed the Agency on September 12, 2007, that the technician who inspected the gauge after its return confirmed that the source rod was locked in the stored position."

R4DO (Shannon), FSME EO (Bubar) and ILTAB (via e-mail) notified.

To top of page
Power Reactor Event Number: 43636
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: KEVIN BOSTON
HQ OPS Officer: PETE SNYDER
Notification Date: 09/13/2007
Notification Time: 06:48 [ET]
Event Date: 09/13/2007
Event Time: 06:01 [EDT]
Last Update Date: 09/13/2007
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
MICHAEL SHANNON (R4)
PAT GWYNN (R4)
JARED WERMIEL (NRR)
JEFF CRUZ (IRD)
HASELTON (DHS)
DUNKER (FEMA)

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

NOTICE OF UNUSUAL EVENT FOR A HYDRAZINE SPILL IN THE TURBINE BUILDING

"A Notification of an Unusual Event was declared at 06:01 EDT due to a chemical leak in the Turbine Building truck dock area near a roll-up door. The leak was discovered at 05:40 EDT coming from a line connecting two vertically stacked Hydrazine Metal chemical storage totes located inside a ventilated enclosure. The Hazmat Response Incident Team was formed to address the spill. Approximately 10 gallons is inside the enclosure berm. A small amount of liquid has leaked outside the enclosure berm but has been contained. Containment activities are in progress. Leak rate appears to be significantly less. Additional plant staff has been called in to support and are arriving on site at the time of this notification. The area has been roped off and plant announcements to warn personnel of this hazard have been made. (EAL-11.4, Plant Conditions Warrant Increased Awareness by Plant Staff)"

The licensee notified the NRC Resident Inspector, state and local government agencies.

* * * UPDATE AT 0742 ON 9/13/07 FROM CHLADIL TO ROTTON * * *

The licensee terminated the Notice of Unusual Event. The termination criteria was that the spill was stopped and the licensee has established limited personnel access restrictions to the turbine building truck bay and the service building elevator. The licensee is continuing to clean the area.

The licensee notified the NRC Resident Inspector and will be notifying state and local government agencies.

Notified R4DO (Shannon), NRR (Ross-Lee), IRD (Blount), DHS (Haselton) and FEMA (Laforty).

To top of page
Fuel Cycle Facility Event Number: 43637
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: PETE SNYDER
Notification Date: 09/13/2007
Notification Time: 09:41 [ET]
Event Date: 09/12/2007
Event Time: 11:30 [EDT]
Last Update Date: 09/13/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
Person (Organization):
JOEL MUNDAY (R2)
MICHELE BURGESS (FSME)

Event Text

MODERATION CONTROL ITEM RELIED ON FOR SAFETY DEGRADATION

"During an investigation of an unusual sinter test measurement result, it was determined that one of the Items Relied On For Safety (IROFS), as documented in the [Integrated Safety Analysis] (ISA) summary, had degraded. This report is submitted for administrative reporting pursuant to 10 CFR 70.50 Appendix A (b)(2).

"The IROFS described for the moderation control of the powder additive at the Dry Conversion Process (DCP) blender operation did not function as required because of an error that occurred at the Dry Scrap Recycle (DSR) container transfer station. At no time did an Unsafe condition exist. The existing criticality safety analysis of the operation bounded the situation, was effective and was not challenged.

"The container transfer station operation is shut down pending completion of an investigation and implementation of corrective actions."

To top of page
Power Reactor Event Number: 43641
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JAMES RUSSELL
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/14/2007
Notification Time: 02:18 [ET]
Event Date: 09/13/2007
Event Time: 23:04 [EDT]
Last Update Date: 09/14/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
RANDY MUSSER (R2)

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

Event Text

POTENTIAL REACTOR PRESSURE BOUNDARY LEAKAGE

"During an investigation in response to a low megger reading, a small amount of water was discovered in the environmental qualification boundary of the 22B RCS Thot thermowell (TE-3-422B2). Analysis of the water on 9/13/07 at 2304 showed Cesium 137 and 134, and Magnesium 54 indicating that the source of water intrusion into the thermowell was likely reactor coolant system (RCS) fluid. We are continuing the investigation for potential causes of water intrusion other than the Reactor Coolant System. This report is being made based on the previous indication of RCS leakage into 23A, RCS Tcold thermowell (TE-3-420) [see EN #43627 from 09/10/07] and similar discovery in our preliminary investigation.

"PTN Unit 3 Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.6.2.a permits no reactor coolant pressure boundary leakage in Modes 1-4. This report to the NRC is pursuant to the requirements of 10 CFR 50.72 (b)(3)(ii)(A) as a degraded condition."

Turkey Point Unit 3 is presently defueled.

The licensee will notify the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012