U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/14/2003 - 01/15/2003
** EVENT NUMBERS **
39507
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39507 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
