Event Notification Report for January 06, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/05/2000 - 01/06/2000
Power Reactor
Event Number: 36567
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FRANK SOENS
HQ OPS Officer: LEIGH TROCINE
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FRANK SOENS
HQ OPS Officer: LEIGH TROCINE
Notification Date: 01/06/2000
Notification Time: 19:16 [ET]
Event Date: 01/06/2000
Event Time: 16:11 [EST]
Last Update Date: 01/06/2000
Notification Time: 19:16 [ET]
Event Date: 01/06/2000
Event Time: 16:11 [EST]
Last Update Date: 01/06/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
LAWRENCE DOERFLEIN (R1)
LAWRENCE DOERFLEIN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
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.
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.
Power Reactor
Event Number: 36566
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAN BOYLE
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAN BOYLE
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/06/2000
Notification Time: 11:16 [ET]
Event Date: 01/06/2000
Event Time: 09:23 [EST]
Last Update Date: 01/06/2000
Notification Time: 11:16 [ET]
Event Date: 01/06/2000
Event Time: 09:23 [EST]
Last Update Date: 01/06/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
Person (Organization):
JIMI YEROKUN (R1)
JIMI YEROKUN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
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.
"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.