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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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37322 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021