U.S. Nuclear Regulatory Commission
                             Operations Center
 
                             Event Reports For
                            11/29/96 - 12/02/96
 
                             ** EVENT NUMBERS **
 
31391  

+----------------------------------+              +-----------------------+     
|POWER REACTOR                     |              |EVENT NUMBER:  31391   |     
+----------------------------------+              +-----------------------+     
+------------------------------------------------+-----------------------------+
|FACILITY: SALEM                      REGION:  1 |NOTIFICATION DATE: 12/01/96  |
|UNIT:     [ ] [2] [ ]                 STATE: NJ |NOTIFICATION TIME: 13:07 [ET]|
|RX TYPE: [1] W-4-LP,[2] W-4-LP                  |EVENT DATE:        12/01/96  |
+------------------------------------------------+EVENT TIME:        11:49[EST]|
|NRC NOTIFIED BY: JOHN ROBERTSON                 |LAST UPDATE DATE:  12/01/96  |
|HQ OPS OFFICER:  JOHN MacKINNON                 +-----------------------------+
+------------------------------------------------+       NOTIFICATIONS         |
|EMERGENCY CLASS: NOT APPLICABLE                 +-----------------------------+
|10 CFR SECTION:                                 |JIM JOYNER            RDO    |
|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          N        0     REFUELING       |     0    REFUELING       |
|     |                                             |                          |
+-----+---------------------------------------------+--------------------------+

                                   EVENT TEXT
+------------------------------------------------------------------------------+
| DURING SURVEILLANCE TESTING, THE "2C" EMERGENCY DIESEL GENERATOR             |
| AUTOMATICALLY STARTED AND ENERGIZED THE "2C" 4-KV BUS WHEN THE PRIMARY       |
| SUPPLY BREAKER FAILED TO CLOSE TO THE BUS.  THE REACTOR VESSEL IS DEFUELED.  |
|                                                                              |
| DURING SURVEILLANCE TESTING OF THE "2C" 4-KV VITAL BUS, STATION POWER        |
| SUPPLY BREAKER 23CSD FAILED TO CLOSE AS EXPECTED.  THIS CAUSED THE "2C"      |
| 4-KV BUS TO DE-ENERGIZE AND CAUSED THE SUBSEQUENT AUTOMATIC START OF THE     |
| "2C" EMERGENCY DIESEL GENERATOR.  THE "2C" 4-KV BUS WAS ENERGIZED BY THE     |
| EMERGENCY DIESEL GENERATOR FROM 1149 EST UNTIL 1255 EST.  THE ALTERNATE      |
| POWER SUPPLY BREAKER FOR THE "2C" 4-KV VITAL BUS WAS CLOSED, OFFSITE POWER   |
| WAS RESTORED TO THE BUS, AND EMERGENCY DIESEL GENERATOR "2C" WAS SECURED.    |
|                                                                              |
| POWER TO THE SPENT FUEL POOL COOLING PUMPS WAS NEVER INTERRUPTED BECAUSE     |
| THE POWER TO THE PUMPS WAS BEING SUPPLIED FROM THE "2B" 4-KV VITAL BUS. THE  |
| LICENSEE STATED THAT TWO SOURCES OF OFFSITE POWER WERE ALWAYS AVAILABLE.     |
| THE LICENSEE IS INVESTIGATING WHY THE 23CSD BREAKER DID NOT CLOSE.           |
|                                                                              |
| THE LICENSEE NOTIFIED THE LOWER ALLOWAYS CREEK TOWNSHIP OF THIS EVENT.  THE  |
| NRC RESIDENT INSPECTOR WAS ALSO NOTIFIED OF THIS EVENT BY THE LICENSEE.      |
+------------------------------------------------------------------------------+