Event Notification Report for January 15, 2003

                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/14/2003 - 01/15/2003



                              ** EVENT NUMBERS **



39507  



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|Power Reactor                                    |Event Number:   39507       |

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| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 01/14/2003|

|    UNIT:  [1] [] []                 STATE:  VA |NOTIFICATION TIME: 04:18[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/14/2003|

+------------------------------------------------+EVENT TIME:        01:37[EST]|

| NRC NOTIFIED BY:  ALISON MACKELLAR             |LAST UPDATE DATE:  01/14/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|10 CFR SECTION:                                 |TERRY REIS           NRR     |

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

|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   |

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

|1     M/R        Y       100      Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| MANUAL REACTOR TRIP DUE TO HIGH REACTOR COOLANT PUMP SHAFT VIBRATION         |

|                                                                              |

| "At 0137 hours, with Surry Power Station Unit 1 at 100% reactor power, a     |

| manual reactor trip was initiated due to elevated shaft vibrations (alert    |

| and danger) on 'C' Reactor Coolant Pump.                                     |

|                                                                              |

| "IRPI indication for one control rod indicated 25 steps following the trip.  |

| Borated as necessary to ensure adequate shutdown margin. All other control   |

| rods fully inserted into the core as designed.  The IRPI indication for this |

| rod is trending down at this time. The shutdown margin for Unit 1 was        |

| determined to be satisfactory.  Auxiliary feedwater automatically initiated  |

| as designed on low low steam generator level following the trip.  Primary    |

| RCS temperature decreased to approximately 541 degrees following the reactor |

| trip and was stabilized at 547 degrees.                                      |

|                                                                              |

| "No primary safety or power operated relief valves were actuated during the  |

| event. As a result of the loss of turbine load, the secondary power operated |

| relief valves actuated during the transient. No indication of primary to     |

| secondary leakage exists, therefore no adverse radiological consequences     |

| resulted from this event.                                                    |

|                                                                              |

| "All electrical busses transferred properly following the trip.  #1 EDG was  |

| T/O [tagged out] prior to unit trip.  All other emergency diesel generators  |

| are operable.  There were no radiation releases due to this event, nor were  |

| there any personnel injuries or contamination events.  The cause of the      |

| event is being investigated.                                                 |

|                                                                              |

| "Unit 1 is currently at Hot Shutdown with RCS temperature being maintained   |

| at approximately 547 degrees.  Unit 2 was not affected by this event and     |

| remains stable at 100% power operations.  This event Is being reported in    |

| accordance with 10CFR50.72(b)(2)(iv) and 10CFR50.72(b)(3)(iv)."              |

|                                                                              |

| The licensee notified the NRC resident inspector.                            |

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