Event Notification Report for May 8, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/05/2000 - 05/08/2000
** EVENT NUMBERS **
36976 36977 36978 36979 36980 36981 36982 36983
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|Power Reactor |Event Number: 36976 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/05/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 12:40[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/05/2000|
+------------------------------------------------+EVENT TIME: 09:40[CDT]|
| NRC NOTIFIED BY: JOHN LECHMAIER |LAST UPDATE DATE: 05/05/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM DURING PLANNED INSTRUMENT MAINTENANCE |
| |
| "At 0940 hours on 5-5-00, Unit 2 scrammed while performing a scheduled |
| Instrument Maintenance surveillance that resulted in a Group 1 isolation. |
| The Unit 2 Emergency Diesel Generator received a spurious Auto Start signal |
| during the Auxiliary Power transfer. During the transient reactor water |
| level reached +8 inches and all Group 2 actuations occurred as expected. |
| Unit 2 is now in Mode 3 with reactor water level within its normal band." |
| |
| All rods fully inserted with the reactor scram and the plant is now stable |
| in normal plant configuration for Mode 3. Preliminary investigation |
| determined that a technician valved out one instrument then tripped a |
| different instrument causing the reactor scram. Investigation is still on |
| going and startup will not proceed until complete. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36977 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/07/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 03:01[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/06/2000|
+------------------------------------------------+EVENT TIME: 23:24[EDT]|
| NRC NOTIFIED BY: NICK CONICELLA |LAST UPDATE DATE: 05/07/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM SIGNAL WITH ALL CONTROL RODS INSERTED AND UNIT |
| DEFUELED |
| |
| "At the time of the event, the Hope Creek reactor was in a preplanned outage |
| with the core completely offloaded to the spent fuel pool, all control rods |
| inserted, and the control rod drive hydraulic system isolated. |
| |
| "Outage work required isolating air to the scram discharge volume vent and |
| drain valves which resulted in these valves being closed. Water inleakage |
| was identified to the scram discharge volume. Since there was no drain path, |
| water level continued to rise in the discharge volume until the high scram |
| discharge volume level scram signal was reached. No components repositioned |
| as a result of the scram signal since they were already in their fail safe |
| positions as a result of preplanned outage work. |
| |
| "Based on the condition of the reactor, the control rod drive hydraulic |
| system, and the reactor protection system at the time of the event, the |
| validity of the ESF signal is being evaluated." |
| |
| The licensee will inform the NRC resident inspector of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36978 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 05/07/2000|
| UNIT: [1] [] [] STATE: VA |NOTIFICATION TIME: 09:42[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/07/2000|
+------------------------------------------------+EVENT TIME: 07:57[EDT]|
| NRC NOTIFIED BY: JIM BLANKENSHIP |LAST UPDATE DATE: 05/07/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|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 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE/REACTOR TRIP DUE TO FAULT OF GENERATOR OUTPUT BREAKER |
| |
| "Unit 1 generator output breaker malfunction (G12) causing Unit 1 Reactor |
| Trip and AFW pump actuation." |
| |
| A generator lockout occurred after the generator output breaker (G12) |
| faulted. The generator lockout caused an automatic turbine trip/reactor |
| trip. All control rods inserted completely following the trip. The unit is |
| currently stable in Hot Standby with steam generators being fed by the |
| auxiliary feedwater system and decay heat being removed by the main |
| condenser. |
| |
| The licensee reported that smoke and flames were observed in the area of the |
| G12 breaker. The site fire brigade responded, and the fire and smoke |
| subsided within 10 minutes. The licensee plans to investigate the cause of |
| the breaker fault and any necessary repairs. The NRC resident inspector will |
| be informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36979 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/07/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 13:45[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/05/2000|
+------------------------------------------------+EVENT TIME: 11:25[EDT]|
| NRC NOTIFIED BY: QUENTIN HICKS |LAST UPDATE DATE: 05/07/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIAL FOR RESIDUAL HEAT REMOVAL SYSTEM NOT ABLE TO PERFORM SAFETY |
| FUNCTION |
| |
| "During the performance of the cold shutdown surveillance N1-ST-V 14 |
| (SERVICE WATER CHECK VALVE AND EMERGENCY SERVICE WATER PUMP AND CHECK VALVE |
| TEST) it was determined that ESW (EMERGENCY SERVICE WATER) check valves |
| 72-21 and 72-22 failed to isolate. The failure of these valves to close may |
| have resulted in ESW not being able to perform its safety function to |
| support residual heat removal (RHR)." |
| |
| The two check valves serve to isolate the non-safety loads of ESW. The |
| valves were serviced and the test was performed again successfully. It was |
| on 5/7/00 about 1230 CDT that the licensee recognized that a four hour |
| notification should have been made on 5/5/00. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36980 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 05/07/2000|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 13:53[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 05/07/2000|
+------------------------------------------------+EVENT TIME: 11:25[CDT]|
| NRC NOTIFIED BY: TERRY GENCIUS |LAST UPDATE DATE: 05/07/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRUCE BURGESS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED LOAD SHED OCCURRED DURING ELECTRICAL MAINTENANCE TESTING |
| |
| "On May 7, 2000 at 0933, electrical testing was being performed on the |
| emergency diesel generator A load sequencer. The diesel generator was |
| out-of-service at the time [for annual maintenance]. An unexpected load |
| shed signal was developed, which removed charging pump C, service water pump |
| A2, containment fan coil A, and residual heat removal (RHR) pump A from the |
| train A emergency safeguards bus (Bus 5). In response to the load shed, |
| equipment was manually restarted from the control room. RHR pump A was |
| restarted in 90 seconds, restoring shutdown cooling. The cause of the load |
| shed was the post modification testing of the load sequencer, and is |
| continuing to be investigated." |
| |
| There was no increase in reactor coolant temperature during the 90 seconds |
| without RHR flow. Also, the RHR B pump was available if it had been |
| needed. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36981 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/08/2000|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 00:44[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/08/2000|
+------------------------------------------------+EVENT TIME: 00:15[EDT]|
| NRC NOTIFIED BY: STEVE MYERS |LAST UPDATE DATE: 05/08/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA 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 N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DIESEL GENERATOR STARTED DURING TESTING |
| |
| The 'A' emergency diesel generator (EDG ) automatically started due to a bus |
| undervoltage signal that was inadvertently caused when a procedural step was |
| misinterpreted. The EDG was secured. The licensee has informed the NRC |
| resident inspector of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36982 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/08/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 01:37[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 05/07/2000|
+------------------------------------------------+EVENT TIME: 22:43[EDT]|
| NRC NOTIFIED BY: NICK CONICELLA |LAST UPDATE DATE: 05/08/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP ISOLATION DUE TO INADVERTENT STANDBY LIQUID CONTROL |
| SIGNAL |
| |
| "On 5/7/00 at 2243 hours, a Reactor Water Cleanup System (RWCU) isolation |
| occurred due to an inadvertent Standby Liquid Control System (SLC) |
| initiation. At the time of the event, Hope Creek was in Operational |
| Condition 5, Refueling, with core reload activities recently initiated and |
| with all control rods fully inserted. SLC was not required to be operable |
| and was removed from service (injection line check valves were closed) when |
| the SLC initiation signal occurred. No sodium pentaborate was injected into |
| the Reactor Coolant System. Preliminary investigation into the event |
| determined that the SLC initiation signal resulted from activities |
| supporting required surveillance testing of SLC along with surveillances of |
| the Redundant Reactivity Control System (RRCS). The RRCS provides automatic |
| SLC initiation. Although the RWCU isolation instrumentation was also not |
| required to be operable at the time of the event, it was not removed from |
| service. The RWCU isolation due to a SLC initiation signal is an ESF |
| actuation. Both SLC pumps actuated as designed in response to the initiation |
| signal, however, a crack was observed in a weld in the 'A' SLC injection |
| line when the SLC pump was removed from service. Event investigation is |
| continuing and repairs to SLC are being initiated. The RWCU isolation signal |
| was reset and the RWCU was placed back in service. Core reload activities |
| are continuing." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36983 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/08/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 05:25[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/08/2000|
+------------------------------------------------+EVENT TIME: 03:56[EDT]|
| NRC NOTIFIED BY: RANDY HAISLET |LAST UPDATE DATE: 05/08/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |NIEL DELLA GRECA 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POST-ACCIDENT SAMPLING SYSTEM ISOLATION DURING TAGOUT |
| |
| While performing a tagout on the 'A' train of the post-accident sampling |
| system (PASS) H2/O2 sampling system, solenoid isolation valve SV-5065-20B, |
| which is a 'B' train valve, closed unexpectedly. The licensee restored the |
| 'A' train of PASS H2/O2 monitoring to service and closed the redundant |
| solenoid isolation valve in the 'B' train. The licensee declared valve |
| SV-5065-20B inoperable. |
| |
| After review of system electrical diagrams, the licensee determined that the |
| closure of valve SV-5065-20B was appropriate, although its closure was not |
| anticipated in the tagout procedure. The NRC resident inspector has been |
| informed of this event by the licensee. |
+------------------------------------------------------------------------------+
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