| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/06/2008 - 11/07/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44307 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: CARDINAL HEALTH
Region: 1
City: WOBURN State: MA
County:
License #: 42-0146
Agreement: Y
Docket:
NRC Notified By: BOB GALLAGHAR
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/19/2008
Notification Time: 14:11 [ET]
Event Date: 06/13/2008
Event Time: 04:00 [EDT]
Last Update Date: 11/06/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE SCHMIDT (R1)
MICHELE BURGESS (FSME)
| Event Text AGREEMENT STATE REPORT INVOLVING A VEHICLE TRANSPORTING RADIOACTIVE MATERIAL
On 6/13/08, a Cardinal Health vehicle transporting Tc-99m and I-131 was involved in a vehicle accident on Route 495N. The vehicle overturned spilling eleven (11) shipping containers onto the roadway. The containers were not damaged and no radioactive material was released on the roadway or to the surrounding environment. The rad material was returned to the Cardinal Health facility in Woburn, MA. The licensee notified the National Response Center and the Commonwealth of Massachusetts.
* * * UPDATE FROM ROBERT GALLAGHER TO DONALD NORWOOD 11/06/2008 AT 0916 HRS * * *
"The following is submitted as additional information for NMED Item No. 080358 (EN44307):
"The licensee, Cardinal Health Nuclear Pharmacy, provided the Massachusetts Radiation Control Program with corrective actions they have taken to preclude a recurrence of this event. The corrective actions include retraining all delivery personnel (performed on June 18, 2008) on the importance of remaining alert while transporting radioactive materials. Delivery personnel were instructed not to work longer hours prior to the start of their delivery route."
Notified R1DO (Caruso) |
| General Information or Other | Event Number: 44619 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: OKLAHOMA STATE UNIVERSITY
Region: 4
City: STILLWATER State: OK
County:
License #: OK-00237-03
Agreement: Y
Docket:
NRC Notified By: MIKE BRODERICK
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/31/2008
Notification Time: 16:52 [ET]
Event Date: 10/30/2008
Event Time: 10:45 [CDT]
Last Update Date: 10/31/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4)
CHRISTIAN EINBERG (FSME)
| Event Text AGREEMENT STATE REPORT - ACCIDENTIAL EXPOSURE TO I-131
"A veterinarian was exposed to Iodine-131 after administering a dose to a cat. The incident occurred on Thursday, October 30, at about 10:45 AM. The (19 millicuries of I-131) dose had been given to the cat, and the user accidentally poked his left index finger with the syringe which contained a residue of I-131. The user's protective glove was penetrated by the needle, but the needle did not appear to have penetrated the skin. The user contacted the RSO a few minutes after the incident. Efforts were made to remove or displace the radioactive Iodine with partial success, reducing the beta measurements about 50%. The licensee estimated that about 20 nanocuries of I-131 were remaining after efforts to decontaminate. Finger swabs show a very small amount (.5 nanocuries or less) of removable contamination. The contamination is concentrated on an area less than 1 mm square on the user's left index finger near the tip. The user's fingertip is being kept bandaged to prevent spread of contamination.
"The licensee contacted DEQ promptly after the initial response. The exposed individual was taken to the University Medical Center where the physician is giving treatment based on NCRP 65. Nonradioactive iodine is being administered in an attempt to block absorption by the thyroid.
"Since the skin did not appear to be penetrated, the licensee believed that there would be no internal dose, but the exposed individual was directed to collect his urine for analysis. This report to NRC was held up in anticipation of the results. Analysis of the exposed individual's urine (about 2 liters collected overnight) shows a distinct I-131 peak that the licensee preliminarily estimated at about 90 picocuries/liter. A longer count with more precision is being made. The exposed individual will continue to collect all urine for analysis for at least five days.
"The situation has been complicated by the death of an immediate relative of the RSO. A Certified Health Physicist who is on the University Radiation Safety Committee is now acting for the RSO." |
| Power Reactor | Event Number: 44632 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILLY JOHNSON
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/06/2008
Notification Time: 00:59 [ET]
Event Date: 11/05/2008
Event Time: 22:54 [EST]
Last Update Date: 11/06/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
BINOY DESAI (R2)
|
| 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 BOTH TRAINS OF CONTROL ROOM EMERGENCY AIR TEMPERATURE CONTROL DECLARED INOP
"WBN Unit 1 initiated a Tech Spec required shutdown at 2254 on 11/05/08. The plant entered TS 3.0.3 at 2135 on 11/05/08 due to both trains of Control Room Emergency Air Temperature Control (CREATCS) being declared inoperable. Initially Train 'B' CREATCS was inoperable due to the scheduled maintenance of Train 'B' auxiliary air system. With one train of Aux Air inoperable this renders that respective train of CREATCS inoperable. During this planned maintenance the 'A' train CREATCS chiller lost ability to cool the Main Control Room due to a failure in the control circuitry. This rendered 'A' train inoperable which led to entry into TS 3.0.3 for both trains CREATCS being inoperable. The plant exited TS 3.0.3 at 2345 on 11/05/08 upon completion of Post Maintenance Testing on the train 'B' Aux Air system and return to operability of the 'B' train Aux Air and therefore the 'B' train of CREATCS. The planned plant shutdown was stopped upon exit of TS 3.0.3 at 2345 11/05/08 and Rx power restored to 100%."
The licensee notified the NRC Resident Inspector |
| Power Reactor | Event Number: 44633 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: WILLIAM STANG
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/06/2008
Notification Time: 14:47 [ET]
Event Date: 11/06/2008
Event Time: 11:15 [CST]
Last Update Date: 11/06/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMNES CAMERON (R3)
|
| 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 OFFSITE NOTIFICATION OF A DISCHARGE TO THE MISSISSIPPI RIVER
"On November 6, 2008 at 11:15, Operations was notified that results of an October 20, 2008 oil and grease weekly sample from a plant sump discharge to the Mississippi River exceeded the National Pollution Discharge Elimination System (NPDES) daily maximum allowable value of 15ppm. The October monthly average oil and grease NPDES of 10ppm was also exceeded. The Minnesota Pollution Control Agency is being notified."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44634 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID NELSON MADSEN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/06/2008
Notification Time: 16:27 [ET]
Event Date: 11/06/2008
Event Time: 08:56 [CST]
Last Update Date: 11/06/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
VIVIAN CAMPBELL (R4)
VERN HODGE (E-MAIL) (NRR)
JOHN THORP (E-MAIL) (NRR)
|
| 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 DEFECT FOUND IN BUSSMAN FUSES
"On November 6, 2008, Nebraska Public Power District (NPPD) completed a reportability determination which concluded that a batch of Bussmann fuses with a date code of J47 contained an underlying fabrication vulnerability that could result in a premature failure of the fuse. NPPD has concluded this condition is reportable per 10 CFR Part 21, since the underlying vulnerability could create a substantial safety hazard. The fuses are Commercial Grade items dedicated by NPPD for use at the Cooper Nuclear Station (CNS). The fuses are shipped directly from an authorized Bussmann facility to CNS. The fuse purchasing description is as follows: FUSE ; 10 AMP ; 250VAC ; ONE-TIME ; 50KA I.R. ; GENERAL PUPOSE ; Manufacturer Part Number NON-10. These fuses, with batch code of J47, have been determined by independent analysis to contain a poor solder joint internal to the fuse.
"These fuses are authorized by NPPD for use in both safety related and non safety related applications. The applicable dedication package identifies one of the safety functions as 'Fuses are required to conduct the design basis load current without interruption.' If the fuses were installed without the condition being detected and failed upon valid demand of associated circuit, the mission of the associated safety related equipment may not have been accomplished. However, since the fuses were found, the safety function of the installed fuses is maintained and the associated equipment remains operable based on specific instructions for maintaining the fuses in place until replacement. Therefore, this condition is NOT reportable under 10 CFR 50.72 or 50.73. However, installation could have occurred and remained undetected, thus introducing a common mode failure in certain applications, thus fulfilling the definition of a Substantial Safety Hazard as defined by 10 CFR Part 21. Based on independent analysis of fuse mode of failure, the defect may not be necessarily detected upon installation. Since the fuses were stocked in unrestricted spares for essential applications, 10 CFR Part 21 applies, and the condition is reportable under 10 CFR 21.21. The Responsible Corporate Officer has been notified of this condition per 10 CFR 21.21 (d)(3)(i) on November 6, 2008 at 08:56 AM, CST. Pursuant to 10 CFR 21.21 (d)(3)(ii) written notification is due to the NRC within 30 days of this notification."
Forty fuses were in the defective lot of which 15 are still installed in plant systems: Circ Water, RCIC, Emergency Diesel Generator 2, air removal and 4160 VAC diesel start breaker circuitry.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44635 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: QUENTIN J. HICKS
HQ OPS Officer: JASON KOZAL | Notification Date: 11/06/2008
Notification Time: 21:49 [ET]
Event Date: 11/06/2008
Event Time: 20:27 [EST]
Last Update Date: 11/06/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
JOHN CARUSO (R1)
|
| 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 TECH SPEC REQUIRED SHUTDOWN REQUIRED DUE TO FAILED SURVEILLANCE TEST
"Nine Mile Point (NMP) Unit 1 initiated a Technical Specification (TS) shutdown at 2027.
"During a normal Instrumentation Surveillance Test, a relay for Emergency Condenser (ECCS) Initiation failed to meet its acceptance criteria (at 1245). This placed the plant in an action statement that required placing a channel trip in for the affected relay channel in 24 hours.
"To perform the relay replacement NMP Unit 1 entered 1 hour TS shutdown Limiting Condition of Operation at 1928. At 2027 Shutdown of the plant was initiated by lowering reactor recirculation flow and thus reactor power. At 2031, relay replacement was completed, [at] 2038 plant returned to full power operations.
"The plant remained in 24 hour action statement until post maintenance testing was completed at 2124."
The licensee notified the NRC Resident Inspector. | |