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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  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39952       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   39954       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

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

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39955       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                        |
+------------------------------------------------------------------------------+