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Event Notification Report for June 23, 2003




                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           06/20/2003 - 06/23/2003



                              ** EVENT NUMBERS **



39952  39954  39955  



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|Power Reactor                                    |Event Number:   39952       |

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| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 06/20/2003|

|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 16:08[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/11/2003|

+------------------------------------------------+EVENT TIME:        22:00[EDT]|

| NRC NOTIFIED BY:  JAY WHITWORTH                |LAST UPDATE DATE:  06/20/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |LEONARD WERT         R2      |

|10 CFR SECTION:                                 |                             |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| OFFSITE NOTIFICATION TO STATE OF TENNESSEE MADE DUE TO LOSS OF POWER TO      |

| EMERGENCY SIRENS                                                             |

|                                                                              |

| The following information was obtained from the licensee via facsimile:      |

|                                                                              |

| "On June 11, 2003, 23 of the 108 emergency sirens were out of service        |

| because of a storm passing through the area, causing power outages.  The TVA |

| Operations Duty Specialist notified the State of Tennessee of the loss of    |

| the sirens. This report is being made to NRC in accordance with 10 CFR       |

| 50.72(b)(2)(xi) as a situation, related to the health and safety of the      |

| public or on-site personnel, or protection of the environment, for which a   |

| news release is planned or notification to other government agencies has     |

| been made.  As power was restored to the area, the sirens were returned to   |

| service.                                                                     |

|                                                                              |

| "This report is being made at this time since Sequoyah Operations personnel  |

| have become aware that the State of Tennessee was notified by the TVA        |

| Operations Duty Specialist on June 11, 2003."                                |

|                                                                              |

| The TVA Operations Duty Specialist is based in a location different from the |

| Sequoyah plant.                                                              |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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|Other Nuclear Material                           |Event Number:   39954       |

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| REP ORG:  NUCOR STEEL                          |NOTIFICATION DATE: 06/21/2003|

|LICENSEE:  NUCOR STEEL                          |NOTIFICATION TIME: 13:50[EDT]|

|    CITY:  CRAWFORDSVILLE           REGION:  3  |EVENT DATE:        06/21/2003|

|  COUNTY:                            STATE:  IN |EVENT TIME:        11:50[CST]|

|LICENSE#:  13-25975-01           AGREEMENT:  N  |LAST UPDATE DATE:  06/21/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |KENNETH RIEMER       R3      |

|                                                |C.W. (BILL) REAMER   NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  JEFF JORDAN                  |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|ISAF 30.50(b)(2)         SAFETY EQUIPMENT FAILUR|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| SOURCE HOLDER FRAME AND CONTROL SYSTEM DAMAGED                               |

|                                                                              |

|                                                                              |

| On 6/21/03 at approximately 1150 CST,  a source holder frame that houses a 1 |

| Curie Am-241 source was damaged.  The licensee, Nucor Steel, uses the source |

| to determine steel strip thickness.  The source holder and the source are    |

| intact and the source is retracted into the safe position.  Only the metal   |

| frame that supports the source holder and the source control system was      |

| damaged.  The manufacturer, Radiometric, has been contacted to repair the    |

| frame.  The source is exposed using an air signal which is currently locked  |

| and tagged out by the licensee.                                              |

|                                                                              |

| Informed R3DO (Riemer) and NMSS EO (Reamer).                                 |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39955       |

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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 06/22/2003|

|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 21:18[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        06/22/2003|

+------------------------------------------------+EVENT TIME:        17:42[EDT]|

| NRC NOTIFIED BY:  ANDY BARTLIK                 |LAST UPDATE DATE:  06/22/2003|

|  HQ OPS OFFICER:  BILL GOTT                    +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH JENISON      R1      |

|10 CFR SECTION:                                 |RICHARD WESSMAN      IRO     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|HERB BERKOW          NRR     |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|3     A/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| AUTOMATIC REACTOR TRIP WITH AFW ACTUATION                                    |

|                                                                              |

| The following information was obtained from the licensee via facsimile:      |

|                                                                              |

| "In order to support maintenance on feeder W-98 [Distribution Line], 345 KV  |

| Circuit Breaker #3 was opened.  Indian Point 3 remained in service utilizing |

| the feed via 345 KV Circuit Breaker #1.  After Con Edison completed          |

| maintenance on W-98, at 17:42 [EDT] an attempt was made to close 345 KV      |

| Circuit Breaker #3.  While attempting to close 345 KV Circuit Breaker #3, a  |

| fault occurred, resulting in an automatic Generator Trip, Reactor Trip and   |

| Turbine Trip.                                                                |

|                                                                              |

| "Automatic Safety Features operated as required, with all control rods       |

| inserting.                                                                   |

|                                                                              |

| "Decay heat is being removed by the Steam Generators, with make up provided  |

| by Auxiliary Feedwater with steam being relieved to the Main Condenser.      |

|                                                                              |

| "Off site power feeders remained available.  Off Site power is currently     |

| stable and providing power to all 480 Volt Safeguards Buses.  Automatic      |

| start and operation of the Emergency Diesel 'G' was not required."           |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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