Event Notification Report for June 21, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/20/2000 - 06/21/2000
** EVENT NUMBERS **
37096 37097 37098
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|Other Nuclear Material |Event Number: 37096 |
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| REP ORG: US STEEL, GARYWORKS |NOTIFICATION DATE: 06/20/2000|
|LICENSEE: US STEEL |NOTIFICATION TIME: 15:00[EDT]|
| CITY: GARY REGION: 3 |EVENT DATE: 06/20/2000|
| COUNTY: STATE: IN |EVENT TIME: 09:30[CST]|
|LICENSE#: 13-26104-02 AGREEMENT: N |LAST UPDATE DATE: 06/20/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ROGER LANKSBURY R3 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DEAN LARSON | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NDAM DAMAGED GAUGE/DEVICE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| POSSIBLE DAMAGED GAUGE ON PLATE LINE |
| |
| A Daystrom manufactured gauge, serial number 3014 with 20 curies of Cs-137, |
| the north gauge on the plate line was struck by a moving plate on the water |
| cooling jacket. There is no apparent damage to the gauge, radiation |
| monitoring did not indicate anything unusual. The service company, |
| Radiometry, has been contacted and will be at the plant tomorrow to check |
| the gauge for damage. |
| |
| US Steel intends to submit a written report to the NRC within thirty days. |
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|Power Reactor |Event Number: 37097 |
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| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 06/20/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 18:45[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 06/20/2000|
+------------------------------------------------+EVENT TIME: 16:31[EDT]|
| NRC NOTIFIED BY: MARK ELLINGTON |LAST UPDATE DATE: 06/20/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|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 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| MANUAL REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL DUE TO INADVERTENT |
| CLOSURE OF MAIN FEEDWATER ISOLATION VALVE |
| |
| The plant suffered an inadvertent closure of the 'A' Main Feedwater |
| Isolation Valve (MFIV) for an unknown reason, investigation in progress. |
| The licensee initiated a manual reactor trip before the automatic reactor |
| trip for low steam generator level could initiate, all rods fully inserted. |
| The three Auxiliary Feedwater (AFW) Pumps automatically started due to the |
| reactor trip and reduced feedwater flow. The plant has been stabilized in |
| Mode 3 pending completion of troubleshooting of the 'A' MFIV closure. Heat |
| removal is via the steam dumps to the main condenser with feed flow from the |
| AFW pumps. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37098 |
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| FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/21/2000|
| UNIT: [2] [] [] STATE: SC |NOTIFICATION TIME: 05:08[EDT]|
| RXTYPE: [2] W-3-LP |EVENT DATE: 06/21/2000|
+------------------------------------------------+EVENT TIME: 02:57[EDT]|
| NRC NOTIFIED BY: AL GARROU |LAST UPDATE DATE: 06/21/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KERRY LANDIS R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 M/R Y 68 Power Operation |0 Hot Standby |
| | |
| | |
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EVENT TEXT
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| - MANUAL REACTOR TRIP FROM 68% POWER DUE TO UNISOLABLE EHC SYSTEM OIL LEAK |
| - |
| |
| At 0257 on 06/21/00, control room operators manually tripped the plant from |
| 68% power due to an unisolable electrohydraulic control (EHC) system oil |
| leak which caused main turbine control valve oscillations. Two control rod |
| bottom lights, shutdown bank 'A' and control bank 'C' did not illuminate; |
| however, the control rod position indications showed that all control rods |
| were fully inserted into the core. The auxiliary feedwater system |
| actuated, as expected. Steam is being dumped to the main condenser. The |
| plant is stable in Mode 3 (Hot Standby). |
| |
| The licensee is repairing the oil leak and investigating the problem with |
| the control rod bottom lights. |
| |
| The licensee notified the NRC Resident Inspector. |
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