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Event Notification Report for September 15, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/14/2000 - 09/15/2000

                              ** EVENT NUMBERS **

37319  37320  37321  37322  37323  37324  

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|Power Reactor                                    |Event Number:   37319       |
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| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 09/14/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 10:32[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        09/14/2000|
+------------------------------------------------+EVENT TIME:        10:10[EDT]|
| NRC NOTIFIED BY:  MATEOSZEWSKI                 |LAST UPDATE DATE:  09/14/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION DUE TO A DEAD MANATEE FOUND IN ONE OF THE PLANT CANALS  |
|                                                                              |
| The licensee made a call to the U. S. Fish and Wildlife Agency and the       |
| Florida Fish and Wildlife Conservation Commission to notify them of a dead   |
| manatee found in canal C107, directly southwest of the plant.                |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
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|Fuel Cycle Facility                              |Event Number:   37320       |
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| FACILITY: HONEYWELL INTERNATIONAL, INC.        |NOTIFICATION DATE: 09/14/2000|
|   RXTYPE: URANIUM HEXAFLUORIDE PRODUCTION      |NOTIFICATION TIME: 11:35[EDT]|
| COMMENTS: UF6 CONVERSION (DRY PROCESS)         |EVENT DATE:        09/13/2000|
|                                                |EVENT TIME:        13:00[CDT]|
|                                                |LAST UPDATE DATE:  09/14/2000|
|    CITY:  METROPOLIS               REGION:  3  +-----------------------------+
|  COUNTY:  MASSAC                    STATE:  IL |PERSON          ORGANIZATION |
|LICENSE#:  SUB-526               AGREEMENT:  Y  |MARK RING            R3      |
|  DOCKET:  04003392                             |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HUGH ROBERTS                 |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 10 CFR 40.60 24-HOUR REPORT DUE TO FAILURE OF EDG TO START                   |
|                                                                              |
| The licensee reported that a Cummins model V12-500GS failed to start when    |
| tested. The licensee is investigating the cause of the failure to start. The |
| EDG was repaired as of 2045 CDT.                                             |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37321       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  IOWA DEPT OF RADIATION CONTROL       |NOTIFICATION DATE: 09/14/2000|
|LICENSEE:  MERCY HOSPITAL                       |NOTIFICATION TIME: 13:31[EDT]|
|    CITY:  IOWA CITY                REGION:  3  |EVENT DATE:        09/11/2000|
|  COUNTY:                            STATE:  IA |EVENT TIME:        11:00[CDT]|
|LICENSE#:  0013-1-52-M1          AGREEMENT:  Y  |LAST UPDATE DATE:  09/14/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK RING            R3      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  GEORGE JOHNS                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED EXPOSURE TO IRIDIUM-192 SOURCES                                   |
|                                                                              |
| An individual at Mercy Hospital thought that she had ordered both dummy      |
| seeds and real iridium-192 seeds.  A package containing seeds from Best      |
| Industries, Inc. was delivered to Mercy Hospital on 09/11/00.  The shipping  |
| papers for the package stated 1 each leader, and on the next line 1 each     |
| ribbon with six seeds.  The person thought that the 1 each leader was the    |
| dummy iridium-192 seeds and the 1 each ribbon with six seeds was the real    |
| iridium-192 seeds.  The individual did not realize that the package shipping |
| papers meant 1 each leader with 1 each ribbon with six seeds.  The           |
| individual did not make a routine radiation survey before removing a ribbon  |
| of iridium-192 seeds from a lead pig.  The individual carried the ribbon of  |
| seeds  in her hand to a room where a practice simulation of a upcoming       |
| operation was to be performed using dummy seeds.  The simulation was never   |
| performed because of some problems with loading the ribbon of seeds into a   |
| catheter.  The ribbon of  iridium-192 seeds was stored in a storeroom        |
| overnight at the foot of a bench.  That night, the individual realized that  |
| she may have handled iridium-192 seeds instead of dummy seeds.  The next     |
| morning, she discovered that she had handled actual iridium-192 seeds.       |
| Total activity of the iridium-192 seeds was 18.54 mCi.                       |
|                                                                              |
| The state of Iowa has calculated that the individual received 29 rem to her  |
| right hand and a whole body dose of 55 mrem (she had the ribbon of           |
| iridium-192 seeds in her hand for an estimated time of 20 minutes.) The      |
| doctor who was to have performed the simulated operation received a          |
| calculated whole body dose of 60 mrem.                                       |
|                                                                              |
| This event was initially reported to NRC Region 3 (Jim Lynch).               |
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|Power Reactor                                    |Event Number:   37322       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 09/14/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 17:52[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        09/14/2000|
+------------------------------------------------+EVENT TIME:        14:22[CDT]|
| NRC NOTIFIED BY:  GLENN KRAUSE                 |LAST UPDATE DATE:  09/14/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF STANDBY LIQUID CONTROL (SLC) SYSTEM  DECLARED INOPERABLE      |
|                                                                              |
| During the performance of a sample of the SLC storage tank, the chemistry    |
| technician discovered a small piece of foreign material in the sample.  Upon |
| further investigation several pieces of foreign material (appears to be      |
| plastic) were found floating on the top, and what appears to be 2 large      |
| plastic bags floating near the bottom of the tank.  At time 1422 CST the SLC |
| system was declared inoperable due to a potential for the bags to cause a    |
| loss of the SLC safety function.  Riverbend Station entered Limiting         |
| Condition of Operation for Technical Specification 3.3.1.7 action C to       |
| restore one SLC subsystem to OPERABLE within 8 hours.  Efforts are underway  |
| to remove all foreign material from the SLC system storage tank.  If one     |
| train of SLC system has not been restored within 8 hours the licensee has an |
| additional 12 hours to be in Hot Shutdown.  All other Emergency Core Cooling |
| Systems and the Emergency Diesel Generators are fully operable.              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * *  UPDATE ON 09/14/00 AT 2247 ET BY HUSTON TAKEN BY MACKINNON * * *      |
|                                                                              |
| The foreign material found in the SLC Tank has been removed to the extent    |
| possible.  Additional inspections with underwater camera and boroscopic      |
| equipment reveal no additional plastic.  Riverbend Station has declared the  |
| system operable and has exited the Technical Specification Limiting          |
| Condition of Operation for the system at time 2059 CT.  Safety function has  |
| been restored.   Foreign material removed appears to be two large thin       |
| plastic bags, light brown in color.   R4DO (G. Sanborn) notified.            |
|                                                                              |
| The NRC Resident Inspector was notified by the licensee of the update.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37323       |
+------------------------------------------------------------------------------+
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 09/14/2000|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 18:47[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        09/04/2000|
+------------------------------------------------+EVENT TIME:        14:24[CDT]|
| NRC NOTIFIED BY:  DALE BERRY                   |LAST UPDATE DATE:  09/14/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         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        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FEEDWATER ISOLATION                                                          |
|                                                                              |
| During Post Trip review, it was discovered that a second feedwater isolation |
| signal that occurred was not reported.  This second feedwater isolation      |
| signal occurred following the reactor trip, see event # 37287, previously    |
| reported on 09/04/00.   This notification is to report the additional        |
| feedwater isolation signal that occurred September 4, 2000 at 1424 hours.    |
|                                                                              |
| The feedwater isolation signal occurred when the steam dump valves that were |
| being used to control reactor coolant system temperature popped open .  This |
| caused "B" steam generator water level to swell above the feedwater          |
| isolation signal setpoint of 78%.                                            |
|                                                                              |
| All equipment operated as required.  The feedwater isolation valves closed   |
| due to the feedwater isolation signal.  These valves were the only equipment |
| not already in the feedwater isolation system required position.             |
|                                                                              |
| The effect of the feedwater isolation signal on the plant was minimal. The   |
| feedwater isolation valves were reopened at 1514 hours to allow feeding      |
| steam generators with the Motor Driven Startup Feedwater Pump.               |
|                                                                              |
| The plant is currently in Mode 1 at 100% power.                              |
|                                                                              |
| The NRC Resident Inspector will notified of this event by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37324       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 09/15/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 01:40[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        09/14/2000|
+------------------------------------------------+EVENT TIME:        23:33[EDT]|
| NRC NOTIFIED BY:  KERRY ALLEN                  |LAST UPDATE DATE:  09/15/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES TRAPP          R1      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION LOGIC RELAY COIL FAILED CAUSING SOME           |
| ISOLATIONS                                                                   |
|                                                                              |
| The primary containment isolation logic relay 16A-K61 coil apparently burned |
| out causing the relay to de-energize.  This caused valves 20 MOV-94 (DW      |
| equipment sump pump inboard isolation), 20 MOV-82 (DW floor sump pump        |
| inboard isolation), and 10 MOV-18 (RHR shutdown cooling inboard isolation)   |
| to receive a close signal. 20 MOV-94 and 82 went closed while 10 MOV-18 was  |
| already closed.  The drywell sumps can not be pumped down, this places the   |
| plant in the coolant leakage monitoring per technical specification 3.6.d    |
| which allows 24 hours for repair of the problem.  The problem is being       |
| worked on and investigated and it is expected to be completed within the 24  |
| hour limit.                                                                  |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
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