Event Notification Report for January 3, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/02/2001 - 01/03/2001

                              ** EVENT NUMBERS **

37642  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37642       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/02/2001|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 22:05[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        01/02/2001|
+------------------------------------------------+EVENT TIME:        15:36[EST]|
| NRC NOTIFIED BY:  PHIL SANTINI                 |LAST UPDATE DATE:  01/02/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       6.5      Power Operation  |5        Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER PUMP AUTOMATIC START                                     |
|                                                                              |
| The plant sustained a main turbine trip on steam generator high level, cause |
| under review.  The turbine trip caused a main feedwater trip which caused an |
| automatic start of the 21 and 23 auxiliary feedwater pumps, as designed.     |
| The licensee review of the event determined, later in the evening, that the  |
| pump starts were reportable under 10 CFR 50.72(b)(2)(ii).                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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