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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37098       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - 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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