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Event Notification Report for October 16, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/13/2000 - 10/16/2000

                              ** EVENT NUMBERS **

37426  37427  37428  37429  37430  37431  

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|General Information or Other                     |Event Number:   37426       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NATIONAL INSTITUTE OF HEALTH         |NOTIFICATION DATE: 10/13/2000|
|LICENSEE:  NATIONAL INSTITUTE OF HEALTH         |NOTIFICATION TIME: 16:04[EDT]|
|    CITY:  BETHESDA                 REGION:  1  |EVENT DATE:        10/13/2000|
|  COUNTY:                            STATE:  MD |EVENT TIME:             [EDT]|
|LICENSE#:  19-00296-10           AGREEMENT:  Y  |LAST UPDATE DATE:  10/13/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE DOERFLEIN   R1      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  ZOON                         |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE NATIONAL INSTITUTE OF HEALTH REPORTED A MISSING PHOSPHORUS - 32 SOURCE   |
|                                                                              |
| On September 22, 2000 a researcher and Authorized User within the NIH        |
| Radiation Safety Program reported to his area health physicist that          |
| approximately 600 microcuries of Phosphorus-32 labeled DCTP was missing from |
| a source vial.  The source vial of NEN Catalog Number BLU513Z had been first |
| opened the previous day, September 21, 2000, by another researcher who       |
| remembered removing only 400 microcuries of the total activity of 1000       |
| microcuries for an experiment.  This researcher then replaced the vial into  |
| the refrigerator, noting that 30 microliters (600 microcuries) were left.    |
|                                                                              |
| The research laboratory staff distinctly recalled locking the laboratory at  |
| the end of that day, in accordance with NIH policy for the security of       |
| radioactive materials, and also recalled having to unlock the laboratory the |
| next morning.                                                                |
|                                                                              |
| However, on September 22 at 11 A.M., when a third researcher went to use the |
| remaining P-32 DCTP from the same vial as was used the previous day, the     |
| vial was completely empty.                                                   |
|                                                                              |
| The researchers performed extensive contamination surveys to determine if    |
| the contents had spilled; no contamination was found. Following notification |
| of the Radiation Safety Branch, the area health physicist performed          |
| extensive contamination checks throughout the Department to ensure that the  |
| material had not been used to intentionally contaminate anything. Again, no  |
| contamination was found. The Authorized User notified the NIH Police of the  |
| missing material.                                                            |
|                                                                              |
| The Authorized User contacted everyone within the Department to determine    |
| the resolution of the missing P-32. The Department Chief has held meetings   |
| with his staff and interviewed all Authorized Users within the Department;   |
| to date no one has admitted using the F-32 DCTP.  However, it is the belief  |
| of everyone involved that the P-32 DCTP was borrowed by another researcher,  |
| who is not willing to admit it, for a legitimate research experiment.  This  |
| is based on the fact that the P-32 compound was within the locked            |
| laboratory; therefore, someone with a key to that laboratory, i.e. a member  |
| of the Department, is most likely to have used the P-32.                     |
+------------------------------------------------------------------------------+

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|General Information or Other                     |Event Number:   37427       |
+------------------------------------------------------------------------------+
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| REP ORG:  ITT INDUSTRIES                       |NOTIFICATION DATE: 10/13/2000|
|LICENSEE:  ITT INDUSTRIES                       |NOTIFICATION TIME: 16:20[EDT]|
|    CITY:  ST. GEORGE               REGION:  2  |EVENT DATE:        08/18/2000|
|  COUNTY:                            STATE:  SC |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/13/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KEN BARR             R2      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+DAVE LOVELESS        R4      |
| NRC NOTIFIED BY:  PATTON (BY FAX)              |MONTE PHILLIPS       R3      |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |LAWRENCE DOERFLEIN   R1      |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 INVOLVING POSSIBLE ITT INDUSTRIES TRANSDUCER FAILURES                |
|                                                                              |
|                                                                              |
| Since the date of discovery, design alternatives continue to be evaluated.   |
| The methods under investigation for corrective action will be mechanical in  |
| nature.  ITT Conoflow expects to conclude the analysis phase of their        |
| investigation by 12/15/00 and currently estimate that replacement units      |
| would be available by 2/15/01.                                               |
|                                                                              |
| Advice to Customers                                                          |
|                                                                              |
| Each site location should analyze their system and corresponding potential   |
| for failure with regard to this notification.  In the absence of a seismic   |
| event resulting in radiation and/or a steam line break, they do not believe  |
| this unit will cause an operational problem.                                 |
|                                                                              |
| Please note that the product qualification was simulated for a ten, (10)     |
| year design life.  Those units with a service life of ten, (10) years or     |
| more should not be considered qualified.                                     |
|                                                                              |
| Individual customers will be advised by letter when replacement IEEE I/P     |
| transducers are available.                                                   |
|                                                                              |
| Nature of the Deviation                                                      |
|                                                                              |
| The nature of the deviation is to the test and performance requirements      |
| associated with IEEE 323 and IEEE 344. An inappropriate bonding process was  |
| utilized in the manufacture of the IEEE I/P Transducer. This process change  |
| began in 1986 and could, during a seismic event involving high radiation     |
| and/or high temperature steam, result in the potential failure of the        |
| transducer to perform its intended safety function.                          |
|                                                                              |
| Product Models involved                                                      |
| GT25CA1826     GT65CA1826    GT45CA1826                                      |
| GT25FA1826     GT45FA1826     GT65FA1826                                     |
|                                                                              |
| Identification of the Company                                                |
|                                                                              |
| ITT Conoflow                                                                 |
| ITT Conoflow, Division of ITT Grinnell Valve Company                         |
| ITT Conoflow, Division of ITT Fluid Technology Corporation                   |
| ITT Conoflow, ITT Industries                                                 |
|                                                                              |
| Location of Components in Use                                                |
|                                                                              |
| DUKE ENERGY CORPORATION, CATAWBA NUCLEAR STATION                             |
|                                                                              |
| FORT CALHOUN STATION                                                         |
|                                                                              |
| KOREA ELECTRIC POWER CORPORATION, KANONAM                                    |
|                                                                              |
| ERGYTECH INCORPORATED, HOUSTON, TEXAS                                        |
|                                                                              |
| PONTON INDUSTRIES, INCORPORATED, SANTA FE SPRINGS, CALIFORNIA                |
|                                                                              |
| ONTARIO POWER GENERATION, DNGD, BOWMANVILLE, ONTARIO LIC 3Z8 CANADA          |
|                                                                              |
| COMMONWEALTH EDISON, MAY WOOD, ILLINOIS                                      |
|                                                                              |
| COPES-VULCAN, INCORPORATED, LAKE CITY, PENNSYLVANIA                          |
|                                                                              |
| PETRO-CHEM EQUIPMENT COMPANY,  BATON ROUGE, LOUISIANA                        |
|                                                                              |
| ASIAM INTERNATIONAL (TAIWAN) INCORPORATED, TAIPEI 105 TAIWAN, R.O.C.         |
|                                                                              |
| NEW YORK POWER AUTHORITY, JA FITZPATRICK NUCLEAR PLANT                       |
|                                                                              |
| CONTROL COMPONENTS, INC., RANCHO SANTA MARGARITA, CALIFORNIA                 |
|                                                                              |
| NORTHEAST NUCLEAR ENERGY, HARTFORD, CONNECTICUT                              |
|                                                                              |
| These companies were also informed.                                          |
|                                                                              |
| OMAHA PUBLIC POWER DISTRICT, FORT CALHOUN STATION                            |
|                                                                              |
| DETROIT EDISON COMPANY                                                       |
|                                                                              |
| ALABAMA POWER COMPANY, SOUTHERN NUCLEAR OPERATING COMPANY                    |
|                                                                              |
| GPU NUCLEAR CORPORATION, C/O GPU SERVICE CORPORATION                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37428       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 10/13/2000|
|    UNIT:  [1] [] []                 STATE:  CA |NOTIFICATION TIME: 22:18[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/13/2000|
+------------------------------------------------+EVENT TIME:        17:14[PDT]|
| NRC NOTIFIED BY:  NORTHNESS                    |LAST UPDATE DATE:  10/13/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT HAD AUTO START OF THE ONE COMPONENT COOLING WATER PUMP             |
|                                                                              |
| During testing of vital bus "F" components,(first and second level           |
| undervoltage relays) with the emergency diesel generator 1/3 parallel to the |
| aux. Power(bus "F"), a signal was generated which tripped the aux feeder     |
| breaker and that separated bus "F" from the PG&E system or auxiliary power.  |
| This event picked up a safety relay which started the third component        |
| cooling water(CCW) pump 1/1, which is an ESF component.  They do not need    |
| three pumps running, so they secured pump 1/2.                               |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37429       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 10/14/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 05:14[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/14/2000|
+------------------------------------------------+EVENT TIME:        03:24[CDT]|
| NRC NOTIFIED BY:  WILLIAM GREEN                |LAST UPDATE DATE:  10/14/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO A MAIN GENERATOR TRIP FOR UNKNOWN REASONS     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0324 [CDT], a reactor scram occurred due to a main generator trip.       |
| Group isolations 2, 3[, and] 6 occurred due to low reactor water level.  The |
| lowest [reactor water] level recorded was -20 inches on [the] wide range     |
| level recorder.  Reactor water level recovered, and both reactor [feedwater] |
| pumps tripped on high reactor water level.  Group isolations have been       |
| verified and reset.  [The] 'A' reactor [feedwater] pump has been returned to |
| service and is being used to control water level.  [High pressure coolant    |
| injection] and [reactor core isolation cooling] did not inject and were not  |
| needed to control reactor water level.  The plant will be placed in Cold     |
| Shutdown.  The electrical grid is stable."                                   |
|                                                                              |
| The licensee stated that all control rods fully inserted and that all        |
| systems functioned as required.  The licensee also stated that alternate rod |
| insertion initiated as a result of high pressure due to the transient.  The  |
| highest pressure observed was 1,085 psi.  None of the relief valves lifted,  |
| and the main steam isolation valves remained open throughout the event.      |
| Steam is currently being dumped to the condenser.                            |
|                                                                              |
| In addition, the licensee stated that the cause of the main generator trip   |
| is currently under investigation.  There were no related surveillance or     |
| maintenance activities ongoing at the time of the event.                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37430       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 10/14/2000|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 18:50[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        10/14/2000|
+------------------------------------------------+EVENT TIME:        18:30[EDT]|
| NRC NOTIFIED BY:  THOMAS O'QUINN               |LAST UPDATE DATE:  10/14/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|AAEC                                            |BELCHER              FEMA    |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |JOHN JOLICOEUR       RCT     |
|                                                |C. MILLER            IRO     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED AT 1830 HOURS DUE TO FIRE IN THE PROTECTED AREA       |
| LASTING GREATER THAN 10 MINUTES.                                             |
|                                                                              |
| "2A" Heater Drain Pump motor fire reported.  Fire reported at 1815 hours,    |
| the area was secured and  the fire was extinguished using carbon dioxide by  |
| the onsite fire brigade at 1831 hours.  No injuries.  Offsite fire           |
| department assistance was initially requested by the licensee but was not    |
| needed to extinguish the fire. Damage caused by the fire was the top back of |
| the heater drain pump motor.  Plant operation was not affected by the fire.  |
| Emergency facilities on site were not activated. State and local counties    |
| were notified by the licensee.                                               |
|                                                                              |
| After "2A" Heater Drain Pump tripped "2C" Heater Drain Pump was started.     |
|                                                                              |
| The NRC Residence Inspector was notified of this event by the licensee.      |
|                                                                              |
| * * * UPDATE on 10/14/00 at 1912ET by Schall taken by MacKinnon * * *        |
|                                                                              |
| Unusual Event terminated at 1908 ET. R2DO (Ken Barr), FEMA (Belcher),  IRO   |
| (C. Miller).                                                                 |
|                                                                              |
| The NRC Resident Inspector was notified by the licensee.                     |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37431       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 10/15/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 01:42[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/14/2000|
+------------------------------------------------+EVENT TIME:        16:40[EDT]|
| NRC NOTIFIED BY:  PAUL McINTYRE                |LAST UPDATE DATE:  10/15/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|AAIR 50.72(b)(2)(iv)(A)  AIRBORNE RAD RELEASE   |JOSEPH GIITTER       IRO     |
|                                                |ROGER PEDERSON       HP      |
|                                                |STU BAILEY           DOE     |
|                                                |MIGUEL CRUZ          HHS     |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNPLANNED, MONITORED, RADIOACTIVE RELEASE OF NOBLE GASES THROUGH THE UNIT    |
| VENT DURING ALIGNMENT FOR SAMPLING OF THE REACTOR COOLANT SYSTEM PRESSURIZER |
| STEAM SPACE WHILE ENTERING A REFUELING OUTAGE                                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[Based on preliminary data, the licensee reported that an] airborne         |
| radioactive release that may have exceeded the reportability limits in       |
| Appendix 'B' of 10 CFR [Part] 20, Table 2.  Preliminary results from data    |
| available as of 2200 hours on 10/14/00 appear to indicate that the release   |
| has exceeded the reportability criterion.  Additional review and calculation |
| of preliminary results are in progress to determine the actual release.      |
| Followup notification will be made to validate or retract this               |
| notification."                                                               |
|                                                                              |
| The licensee reported that this unplanned, monitored, gaseous, offsite       |
| release occurred at 1640 on 10/14/00 and that it was terminated within       |
| approximately 20 minutes.  The weather conditions were very stable at the    |
| time.  The site boundary dose and noble gas release rate were not available  |
| at the time of the event notification.  However, the available data          |
| indicated the dose at the unit vent.  Two radiation monitors exceeded their  |
| Trip II setpoints.                                                           |
|                                                                              |
| Plant Stack                                         Other                    |
| EMF 36                                            EMF 41                     |
|                                                                              |
| Radiation Monitor Readings                                           3.63 E3 |
| cpm                                    2.24 E4 cpm                           |
| Alarm Setpoints: Trip II                                                     |
| 2.71 E3 cpm                                    4.54 E3 cpm                   |
| Percent of Technical Specification Limit                        Not          |
| Available                                   Not Available                    |
|                                                                              |
| The licensee stated that there is no direct correlation between the          |
| radiation monitor setpoints or readings and the technical specification      |
| limits.  The technical specification limits are based upon dose at the site  |
| boundary, and determination of the site boundary dose requires extensive     |
| calculations and review.  The licensee currently anticipates that this       |
| information will be available in the followup notification.  At this time,   |
| the licensee believes that the release was well below the technical          |
| specification limits.  The licensee stated that nothing was unusual or       |
| misunderstood and that all systems functioned as required.                   |
|                                                                              |
| The licensee plans to notify the NRC resident inspector, the States of North |
| Carolina and South Carolina, and the applicable counties (York, Gaston, and  |
| Mecklenburg).  The licensee does not plan to issue a press release, and      |
| media interest is not anticipated at this time.                              |
|                                                                              |
| HOO NOTE:  At 0735 and 0818 on 10/15/00, representatives from the            |
| Environmental Protection Agency (Paul Wagner) and the South Carolina         |
| Department of Health and Environmental Control (John Jesse), respectively,   |
| called the NRC Operations Center for information regarding this event.       |
| (Call the NRC operations officer for contact information.)                   |
|                                                                              |
| * * * UPDATE ON 10/15/00 @ 1438 BY FRITZ TO GOULD * * * RETRACTION           |
|                                                                              |
| The Radiation Protection staff have evaluated the release and determined     |
| that it did not exceed any limits and also did not meet any reporting        |
| requirements of 10 CFR 50.72(b)(2)(iv)(A).  Therefore, the licensee is       |
| retracting this event.                                                       |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| The following individuals have been notified of this update:                 |
| Reg 2 RDO Barr    NRR EO Boger   IRO Giitter   DOE Stambaugh   EPA(NRC)      |
| Crews   FEMA Stinederf                                                       |
| USDA Conley   NMSS Holahan   HHS Cruz   HP Pederson   SCDHEC Jesse           |
+------------------------------------------------------------------------------+