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Event Notification Report for October 27, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/26/2000 - 10/27/2000

                              ** EVENT NUMBERS **

37457  37458  37459  37460  37461  

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|General Information or Other                     |Event Number:   37457       |
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| REP ORG:  NATIONAL RESPONSE CENTER             |NOTIFICATION DATE: 10/26/2000|
|LICENSEE:  UNKNOWN                              |NOTIFICATION TIME: 00:25[EDT]|
|    CITY:  MISHAWAKA                REGION:  3  |EVENT DATE:        10/25/2000|
|  COUNTY:  ST. JOSEPH                STATE:  IN |EVENT TIME:        20:10[CST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTON VEGEL          R3      |
|                                                |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+GEOFFREY WRIGHT      R3      |
| NRC NOTIFIED BY:  CREWS                        |CINDY PEDERSON       R3      |
|  HQ OPS OFFICER:  STEVE SANDIN                 |LARRY CAMPER         NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| RECOVERY OF TROXLER MOISTURE DENSITY GAUGE FROM THE LOADING DOCK OF A        |
| DEPARTMENT STORE.                                                            |
|                                                                              |
| AT 2010 LOCAL TIME ON 10/25/00 A TROXLER MOISTURE DENSITY GAUGE [MODEL 3430, |
| S/N 29119] CONTAINING BOTH A CESIUM-137 AND AMERICIUM-241 SOURCE WAS         |
| DISCOVERED ON THE LOADING DOCK OF A DEPARTMENT STORE LOCATED IN MISHAWAKA,   |
| IN.  THE RESPONDING FIRE DEPARTMENT CONTACTED THE SOUTH BEND FIRE DEPARTMENT |
| FOR HAZMAT (RADIOLOGICAL) ASSISTANCE.  A PRELIMINARY RAD SURVEY SHOWED       |
| APPROXIMATELY 2mR/HR CONTACT.  THE INDIANA STATE DEPARTMENT OF HEALTH WAS    |
| INFORMED.  THE CONDITION OF THE TROXLER TRANSPORT CASE SUGGESTS THAT IT MAY  |
| HAVE BEEN STOLEN.  FIRE STATION #3 IN MISHAWAKA HAS TAKEN CUSTODY OF THE     |
| TROXLER AND IS STORING THE DEVICE IN A LOCKED SECURE AREA.  THE INITIAL      |
| REPORT FROM THE NATIONAL RESPONSE CENTER INDICATED THAT 75 MEMBERS OF THE    |
| PUBLIC WERE EVACUATED.  REGION 3 WILL FOLLOWUP IN THE MORNING.  SEVERAL      |
| FEDERAL AND STATE AGENCIES WERE INFORMED BY THE STATE OF INDIANA AND THE     |
| NATIONAL RESPONSE CENTER.                                                    |
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|Power Reactor                                    |Event Number:   37458       |
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| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 10/26/2000|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 15:54[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/26/2000|
+------------------------------------------------+EVENT TIME:        14:05[CDT]|
| NRC NOTIFIED BY:  JERRY GOSMAN                 |LAST UPDATE DATE:  10/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANTON VEGEL          R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| SINGLE FAILURE RESULTING IN BOTH SAFEGUARDS TRAINS BECOMING INOPERABLE       |
|                                                                              |
| Prairie Island has three safeguard vertical cooling (service) water pumps.   |
| These pumps are equipped with an air/vacuum valve that acts to expel air     |
| from the pump upon starting.  A ball float closes off the valve opening      |
| after the air is expelled, and is held closed by pump developed head.  It    |
| was postulated that the air/vacuum valve could fail to close and the flow of |
| water out of the valve could cause flooding.  Plant evaluation determined    |
| that documentation does not exist that conclusively demonstrates that the    |
| failure cannot occur or that the resultant flooding does not affect the      |
| opposite safeguards train pump.  Since the operability determination is      |
| indeterminate, both trains of safeguards pumps were declared inoperable.  A  |
| single failure resulting in both safeguards trains becoming inoperable is    |
| outside the plant design basis.                                              |
|                                                                              |
| Compensatory actions are being put into place to restore operability of the  |
| safeguards pumps.  The initial actions are to station a qualified individual |
| in the safeguard pump area.  The qualified individual will observe any start |
| of a safeguard pump and ensure no failure of the air/vacuum valve has        |
| occurred.  If a failure occurs such that flooding is an immediate concern,   |
| the qualified individual will contact the Control Room to secure the pump.   |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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|General Information or Other                     |Event Number:   37459       |
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| REP ORG:  GEORGIA RADIOACTIVE MATERIAL PGM     |NOTIFICATION DATE: 10/26/2000|
|LICENSEE:  UNKNOWN                              |NOTIFICATION TIME: 16:03[EDT]|
|    CITY:  EAST POINT               REGION:  2  |EVENT DATE:        10/24/2000|
|  COUNTY:                            STATE:  GA |EVENT TIME:        12:00[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  10/26/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANNE BOLAND          R2      |
|                                                |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM HILL                     |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| STRONTIUM-90 SOURCE FOUND IN SCRAP METAL.                                    |
|                                                                              |
| Environmental Radiation Program (ERP) personnel were notified by South       |
| Carolina DHEC of a shipment of scrap metal returning to Newell Recycling;    |
| East Point, Georgia; from SMI Steel in Caycese, South Carolina.  October 25, |
| 2000 ERP staff surveyed the exterior of the truck and located the area with  |
| elevated radiation levels in the front left corner of the trailer.           |
| Personnel from Newell and the ERP began unloading scrap until a Sr-90 source |
| was located lying on the floor of the trailer.  The source was removed,      |
| bagged up and isolated approximately 30 yards away from the trailer in       |
| another trailer that could be locked and secured as a temporary storage area |
| until remedial actions can be taken by Newell.  Source markings were as      |
| follows 3F1L, 100mCi, SR-90, 3M1389, 7-84. Note: Based on the information on |
| the source, the Registry of Radioactive Sealed Sources and Devices registry  |
| number for this source is NR-460-S-921-S.                                    |
|                                                                              |
| Initial radiation measurements on the outside of the trailer in the area of  |
| the front corner were as high as 300 micro-R/hour.  Levels in the immediate  |
| area of the source inside the trailer were greater than 3R/hour (beta/gamma) |
| unshielded and in contact with the source.  After isolating the source, the  |
| remaining scrap metal was surveyed by ERP personnel using Ludlum Micro-R     |
| Meter and Eberline ESP-2 with HP-260 probe.  No radiation levels above       |
| background were noted.  General radiation levels inside the trailer ranged   |
| from 5 to 15 micro-R/hour while background radiation levels outside of the   |
| trailer were 15 to 20 micro-R/hour.  26 smears were taken on various pieces  |
| of scrap removed from the trailer and the floor in the vicinity of where the |
| source was found.  No removable or fixed contamination was noted once the    |
| source had been removed and isolated                                         |
|                                                                              |
| State of Georgia event number is GA-2000-20I.                                |
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|Power Reactor                                    |Event Number:   37460       |
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| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 10/26/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 16:40[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/26/2000|
+------------------------------------------------+EVENT TIME:        14:45[CDT]|
| NRC NOTIFIED BY:  K .  EHRHARDT                |LAST UPDATE DATE:  10/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREG PICK            R4      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| KAOWOOL ISSUE                                                                |
|                                                                              |
| During a plant walkdown to identify specific raceway configurations as part  |
| of their plan to address Kaowool issues, a condition was found that may      |
| affect both divisions of ESF switchgear room coolers.  This condition is     |
| conservatively being reported pursuant to 10CFR50.72(b)(1)(ii).   These      |
| areas were already under fire watch in accordance with their fire protection |
| program, as a precautionary response to issuance of SECY-99-0204 - Kaowool.  |
| Fire detection and fires suppression are available in the affected area.     |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector will be informed of the event by the Licensee.    |
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|Power Reactor                                    |Event Number:   37461       |
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| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 10/26/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 18:57[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        10/26/2000|
+------------------------------------------------+EVENT TIME:        14:15[CDT]|
| NRC NOTIFIED BY:  MACLENNAN                    |LAST UPDATE DATE:  10/26/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANTON VEGEL          R3      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N                Refueling        |0        Refueling        |
|2     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| SAFE SHUTDOWN MAKEUP PUMP (SSMP) DECLARED INOPERABLE.                        |
|                                                                              |
| At approximately 1415 hours on 10/26/00, the Safe Shutdown Makeup Pump       |
| (SSMP) tripped unexpectedly during quarterly operability testing.  At the    |
| time of the trip, the in-plant operator was transferring the flow controller |
| to automatic from the manual position to obtain proper IST flows.  At 1525   |
| hours, during a second attempt, the pump again tripped under the same        |
| circumstances.  The SSMP was run a third time, this time using the flow      |
| controller in manual without transferring to automatic.  On this attempt,    |
| the SSMP obtained the proper pressure and flow but the local controller      |
| indications remained erratic. The SSMP was declared inoperable from the time |
| of the first trip.  The licensee entered Technical Specification 3.8.(j) a   |
| 14 day Limiting Condition of Operation. All other Emergency Core Cooling     |
| Systems for Unit 2 are fully operable.                                       |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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