| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/23/2005 - 11/24/2005 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42114 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE STRAUBMULLER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/03/2005
Notification Time: 15:05 [ET]
Event Date: 11/03/2005
Event Time: 10:30 [EST]
Last Update Date: 11/23/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
CLIFFORD ANDERSON (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text ECCS LEAKAGE OUTSIDE CONTAINMENT
"A 0.02 GPM leak was identified on the inlet valve (1CV89) to the 11 seal injection filter. This leak equates to 4500 cc/hour. The leakage is outside containment and quantified IAW Leakage Monitoring and reduction program procedure SC.RA-AP.ZZ-0051. This leakage exceeds the 3800cc/hour limit as stated in UFSAR section 6.3.2.11 and GDC-19 to ensure control room habitability. Therefore ECG section 11 section 11.2 specifically 11.2.2.b applies for being in a degraded or unanalyzed condition. The 1CV89 valve was recently replaced as a scheduled activity during the current 1R17 refueling outage. The 1CV89 packing has been adjusted and the leakage has stopped. The leakage was to the floor to the liquid waste system. There was no personnel contamination or injuries due to the leakage.
"Current Plant Conditions: RCS temperature is 340 degrees, RCS pressure is at 1400 PSIG and stable, plant heat-up and pressurization is in progress IAW integrated operating procedures."
The leakage occurred from 10:30 to 12:30 EST. The valve has been tested and declared operable. Primary coolant activity is 0.828 microCuries per cc. There is no known steam generator tube leakage.
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM LICENSEE (SAUER) TO HUFFMAN ON 11/23/05 AT 15:10 EST * * *
"On 11/03/05 at 1505, PSEG Nuclear made an 8 hour report in accordance with the 10CFR50.72(b)(3)(v) --(Event number 42114) - for ECCS leakage outside containment.
"Upon further investigation, it has been determined that the leak was within the guideline limits for the control room and off-site radiological exposure. Additionally, at the time of discovery, Salem Unit 1 was in Mode 4 coming out of its seventeenth refueling outage and 73 of the 193 fuel assemblies in the core were new fuel assemblies. Therefore, the actual core nuclide inventory would have been much less than the core nuclide inventory assumed in the design basis analysis. Therefore, the event of November 3, 2005 reported under 10CFR50.72(b)(3)(v) is being retracted."
The licensee will notify the NRC Resident Inspector. R1DO (Doerflein) notified. |
| General Information or Other | Event Number: 42154 | Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: USKH, INC.
Region: 4
City: SPOKANE State: WA
County:
License #: WN-I0409-1
Agreement: Y
Docket:
NRC Notified By: TERRY FRAZEE
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/18/2005
Notification Time: 19:53 [ET]
Event Date: 11/17/2005
Event Time: 17:45 [PST]
Last Update Date: 11/18/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
REBECCA NEASE (R4)
PATRICIA HOLAHAN (NMSS)
CANADA via fax ()
AARON DANIS (email) (TAS)
| Event Text AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER MOISTURE DENSITY GAUGE
The following information was received via email:
"Event Report # WA-05-062
"This is notification of an event in Washington State as reported to or investigated by the WA Department of Health, Office of Radiation Protection.
"STATUS: new
"Licensee: USKH, Inc.
"City and state: Spokane, Washington
"License number: WN-I0409-1
"Type of license: Portable Gauge
"Date of event: 17 November 2005, Called in 5:45 PM.
"Location of Event: Spokane, Washington
"ABSTRACT: The license's Radiation Safety Officer reported that sometime between 2 and 5 PM a Troxler, Model 3411B, moisture density gauge, Serial Number 5541, was stolen out of the operator's transport vehicle parked in a Diamond Parking lot adjacent to the 'Flour Mill' where the company's offices are located at 621 W. Mallon Avenue, Suite 309, Spokane, Washington. A police report was filed on 17 November 2005 but Spokane police declined to investigate the scene.
"Bolt cutters were used to liberate the gauge/transport box from 2 separate chains with a padlock on each attaching the box to the rear of the operator's pick-up truck. The parking lot (of over 75 vehicles) has an attendant who did not observe the theft.
"The operator appears to have violated at least one DOH requirement that may have contributed to the theft to the device. Department of Health Order, dated 2 December 2002, requires that when the licensee's portable gauge is not physically under the control of the operator that the device must be covered or carried in such a way that the passer-by cannot see the device.
"Another potential contributing factor to the theft, is that the operator was planning on transporting the gauge to his residence to recharge and take it to the work site the next morning because the work site was halfway between the operator's residence and the primary storage location. Preliminary information indicates that the work site is within 50 miles of the primary storage location. This is still under investigation. The licensee will be cited for at least one violation as a result of the event, and corrective actions will be discussed with the licensee.
"The event is currently under investigation. This report will be updated to include any new findings. No media attention noted at present.
"What is the notification or reporting criteria involved? WAC 246-221-240 Reports of stolen, lost or missing radiation sources
"Activity and Isotope(s) involved: 296 megaBq (8 millicuries) Cesium-137 and 1480 megaBq (40 millicuries) Americium 241/Beryllium.
"Overexposures? (number of workers/members of the public; dose estimate; body part receiving dose; consequence) N/A
"Lost, Stolen or Damaged? STOLEN (mfg., model, serial number) noted above
"Disposition/recovery: pending
"Leak test? Unknown
"Vehicle: (description; placards; Shipper; package type; Pkg. ID number) pick-up truck with no cap
"Release of activity? N/A
"Activity and pharmaceutical compound intended: N/A
"Misadministered activity and/or compound received: N/A
"Device (HDR, etc.) Mfg., Model; computer program: N/A
"Exposure (intended/actual); consequences: N/A
"Was patient or responsible relative notified? N/A
"Was written report provided? Pending
"Was referring physician notified? N/A
"Consultant used? N/A"
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. |
| General Information or Other | Event Number: 42156 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: IRIS NDT
Region: 4
City: TULSA State: OK
County:
License #: OK30246-02
Agreement: Y
Docket:
NRC Notified By: MIKE BRODERICK
HQ OPS Officer: PETE SNYDER | Notification Date: 11/19/2005
Notification Time: 11:54 [ET]
Event Date: 11/18/2005
Event Time: 20:00 [CST]
Last Update Date: 11/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
REBECCA NEASE (R4)
PATRICIA HOLAHAN (NMSS)
| Event Text AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE OF A RADIOGRAPHER
At 2000 on 11/18/05 during a radiography job at P2S in Sand Springs, OK, a radiographer received a 23 Rem calculated dose. He went out to change the camera film when he thought his assistant had fully retracted the source. The radiographer was in front of the camera for approximately 3 minutes. The licensee stated that the cause of the overexposure was miscommunication.
When the radiographer was on his way to the camera he set down his radiation detection instrument and answered a cell phone call. At the same time the assistant who was responsible for retracting the source was sending a text message on his cell phone. The radiographer's alarming rate meter was turned off. The camera was a SPEC Model 150 with a 66 Curie Iridium-192 source. The camera was tested after the event and found to be in good operating condition.
Both the radiographer and the assistant have been suspended pending further investigation. The dosimeters of the individuals have been sent to be read and readings should be available on 11/21/05. The licensees radiation safety officer made the report to the state after taking both individuals to the hospital for blood tests as a precautionary measure. On 11/21/05 the state will investigate this incident further at the jobsite. |
| General Information or Other | Event Number: 42160 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: FAGEN, INC
Region: 4
City: MINDEN State: NE
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/21/2005
Notification Time: 15:16 [ET]
Event Date: 05/22/2003
Event Time: [CST]
Last Update Date: 11/21/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA SMITH (R4)
GREG MORELL (NMSS)
AARON DANIS (EMAIL) (TAS)
| Event Text AGREEMENT STATE REPORT - STOLEN TRITIUM EXIT SIGNS
The State provided the following information via facsimile:
"Safety Light shipped 15 self illuminating exit signs to Fagen, Inc. on April 14, 2003 with serial numbers 220369 - 220383. The signs were [Safety Light Corp] model SLX-60 with 11.5 curies each. Fagen, Inc. was the contractor for Kaapa Ethanol, LLC In Minden, Nebraska. Fagen, Inc. staff suspect that five signs were stolen on May 22 or 23, 2003 from a trailer that they kept supplies in. They [Fagen, Inc] then ordered six additional signs (five for the ones suspected stolen and one needed for an additional area needing a sign). Safety Light shipped the six signs on June 17, 2003 with serial numbers 211313-211318. Kaapa Ethanol, LLC took over the plant in January of 2004. When Kaapa did a complete inventory of the signs in 2005 they could not locate all of the signs. After a number of emails and phone calls it was determined that in addition to the unreported five signs that were missing in May of 2003, one additional sign from the April 14, 2003 order and three from the June 17, 2003 order were also missing. They believe that the signs were taken/stolen the first week of January 2004. Kappa Ethanol staff does not believe that the nine missing signs were ever installed."
Serial numbers of stolen exit signs: 220369, 220370, 220371, 220372, 220373, 220380, 211315, 211316, 211317.
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. |
| General Information or Other | Event Number: 42168 | Rep Org: NUCLEAR LOGISTICS INC
Licensee: NUCLEAR LOGISTICS INC
Region: 4
City: FORT WORTH State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ARON SEIKEN (VIA FAX)
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/23/2005
Notification Time: 15:54 [ET]
Event Date: 11/23/2005
Event Time: [CST]
Last Update Date: 11/23/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
LINDA SMITH (E-MAIL) (R4)
LAWRENCE DOERFLEIN (R1)
| Event Text PART 21 FROM NUCLEAR LOGISTICS INC CONCERNING POTENTIALLY DEFECTIVE MICROLOGIC TRIP UNITS
The following information is provided on a potential defect in accordance with 10CFR Part 21, paragraph 21.21(b). NLI [Nuclear Logistics Inc] does not have the capability to perform the evaluation to determine if a defect exists. NLI has supplied safety related breakers with the Micrologic trip units only to First Energy-Beaver Valley and PSEG-Hope Creek. Both of these plants are aware of the issue and the corrective actions described below.
The basic component that contains a potential defect is the Micrologic trip device installed in Square D series NT and NW low voltage switchgear breakers. The nature of the potential defect is as follows:
- Under certain combinations of operating conditions, the trip unit spuriously trips the breaker. The conditions that cause the spurious trip are starting a motor directly by breaker closure (no starter in the circuit) and system transients that have not been defined.
The reported spurious trips are as follows:
- PSEG-Hope Creek has Square D NW series breakers installed. One spurious trip was identified in over 1000 motor starts using these breakers in 7 safety related applications that start motors directly.
- First Energy-Beaver Valley has Square D NT and NW series breakers installed. One NT breaker installed in a non-safety application had multiple spurious trips upon motor starting.
- There are no other reported spurious trips of breakers at PSEG-Hope Creek or First Energy-Beaver Valley. Spurious trips in other facilities have been reported to Square D.
- NLI is not aware of the installation of Micrologic trip devices in safety related applications in other nuclear plants in the United States.
The following actions and corrective action that has been taken:
- Root cause analysis and testing has been performed by Square D and NLI. It was determined that the spurious trip was due to a combination transient voltages during motor start and a breaker configuration that lasts approximately 100ms during breaker closure.
- The NT breaker was determined to be more sensitive to the spurious trip than the NW breaker.
- The reported spurious trip rate for the Micrologic trip units installed worldwide is estimated at approximately 0.05%.
- A modification was developed and tested to prevent the susceptibility of the trip unit. This modified design will be implemented on the existing breakers and all future units.
NLI is working with the impacted utilities to replace the existing trip units. | |