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Event Notification Report for January 7, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/06/2000 - 01/07/2000

                              ** EVENT NUMBERS **

36566  36567  

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|Power Reactor                                    |Event Number:   36566       |
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| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 01/06/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 11:16[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/06/2000|
+------------------------------------------------+EVENT TIME:        09:23[EST]|
| NRC NOTIFIED BY:  DAN BOYLE                    |LAST UPDATE DATE:  01/06/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LICENSEE UNABLE TO ESTABLISH AN ERDS CONNECTION FOR > 1 HOUR DURING          |
| SURVEILLANCE TESTING.                                                        |
|                                                                              |
| "ON JANUARY 6, 2000, [HOPE CREEK PERSONNEL] MADE [A] PROCEDURAL NOTIFICATION |
| TO [THE] NRC OF THE COMMENCEMENT OF THE QUARTERLY EMERGENCY RESPONSE DATA    |
| SYSTEM (ERDS) TEST AT 0855 [HOURS].  THE TEST IS PERFORMED IN ACCORDANCE     |
| WITH [THE] EMERGENCY PLAN IMPLEMENTING PROCEDURE - EPIP 1008.  DURING THE    |
| PERFORMANCE OF THE TESTING, THE PREVIOUSLY NOTIFIED NRC CONTACT CALLED THE   |
| HOPE CREEK CONTROL ROOM AT 0923 HOURS AND STATED THAT THEY WERE NOT          |
| RECEIVING ANY DATA, BUT [THEY] DID VERIFY [THAT THE] SYSTEM WAS ATTEMPTING   |
| TO CONNECT.                                                                  |
|                                                                              |
| "[THE] HOPE CREEK EMERGENCY CLASSIFICATION GUIDE DETAILS [THAT THE] LOSS OF  |
| THE NRC PHONE LINE OR MODEM USED FOR ERDS DATA TRANSMISSION FOR GREATER THAN |
| 1 HOUR AS A                                                                  |
| 1-HOUR REPORT.  TROUBLESHOOTING IS IN PROGRESS.                              |
|                                                                              |
| "NO OTHER SIGNIFICANT ISSUES EXIST AT STATION HOPE CREEK."                   |
|                                                                              |
| * * * UPDATE AT 1138 EST ON 01/06/2000 FROM BOYLE TO S. SANDIN * * *         |
|                                                                              |
| THE ERDS LINK WAS ESTABLISHED AT 1130 EST.  TESTING IS CURRENTLY IN          |
| PROGRESS.                                                                    |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
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|Power Reactor                                    |Event Number:   36567       |
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 01/06/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 19:16[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/06/2000|
+------------------------------------------------+EVENT TIME:        16:11[EST]|
| NRC NOTIFIED BY:  FRANK SOENS                  |LAST UPDATE DATE:  01/06/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| MANUAL REACTOR TRIP DUE TO LOSS OF A FEEDWATER PUMP AND DEGRADED FEEDWATER   |
| PUMP SUCTION WHICH RESULTED FROM THE ISOLATION OF THE LOW PRESSURE FEEDWATER |
| HEATER STRINGS                                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 1611, a manual reactor trip was performed due to loss of [the #]12 steam |
| generator [feedwater] pump (SGFP) and degraded SGFP suction pressure.  At    |
| approximately the same time, [the #]11 SGFP also tripped.  The secondary     |
| transient was due to isolation of the low pressure feedwater heater strings. |
| An [auxiliary] feedwater (AFW) [automatic] start signal was received due to  |
| low [steam generator] level due to normal shrink.  All safety systems        |
| performed as designed except for [the #]12 AFW [pump] and source range N-31. |
| No flow was observed from [the #]12 AFW [pump,] and operators manually       |
| initiated flow from the control room by depressing [the] low pressure        |
| override defeat.  [The #]13 AFW pump started and fed all four [steam         |
| generators] as designed, and [the #]11 AFW [pump] started and delivered flow |
| to [two] steam generators as designed.  Source range N-31 was erratic when   |
| it automatically energized.  At this time, the unit is stable in Mode 3."    |
|                                                                              |
| The licensee stated that all control rod fully inserted as a result of the   |
| manual reactor trip, and none of the primary or secondary safety relief      |
| valves lifted.  There were no related maintenance or surveillance activities |
| ongoing at the time of the event.  The causes of the issues mentioned above  |
| are currently under investigation.   The licensee stated that (with the      |
| exception of the items previously mentioned) all systems functioned as       |
| required and that there was nothing unusual or misunderstood.                |
|                                                                              |
| The unit is currently stable in Mode 3 (Hot Standby).  Normal charging and   |
| letdown, pressurizer heaters and sprays, and the reactor coolant pumps are   |
| currently being utilized to maintain primary system inventory, pressure, and |
| transport control.  Secondary steam is being dumped to the condenser, and    |
| AFW is being supplied to the steam generators.                               |
|                                                                              |
| The licensee notified the NRC resident inspector, and the Lower Alloways     |
| Creek Township.  The licensee plans to notify the State of New Jersey and    |
| also plans to issue a media/press release.                                   |
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