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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