Event Notification Report for November 16, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/15/2000 - 11/16/2000
** EVENT NUMBERS **
37524 37525 37526 37527
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|Power Reactor |Event Number: 37524 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 11/15/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 15:49[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/15/2000|
+------------------------------------------------+EVENT TIME: 14:22[EST]|
| NRC NOTIFIED BY: VERITA BELLAMY |LAST UPDATE DATE: 11/15/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE ERNSTES 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO FAILURE OF TURBINE RUNBACK ACTUATION CIRCUITS |
| |
| Unit 2 experienced a turbine runback at 1410 EST. The control room |
| operators noticed all status lights for overpower and overtemperature delta |
| T runback were illuminated. The operators decided to manually trip the |
| reactor from about 23 % rated thermal power. The reactor trip resulted in a |
| turbine trip as expected. Auxiliary feedwater pumps started due to low-low |
| steam generator levels. The unit is stable in Mode 3. |
| |
| The runback bistables are locked in without having the logic bistables |
| tripped that feed the trip circuit. The licensee is troubleshooting the |
| problem and the cause is unknown at this time. The plant will remain in |
| Mode 3 until the problem is corrected. |
| |
| The licensee notified the NRC Resident Inspector. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37525 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 11/15/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 19:04[EST]|
| RXTYPE: [1] GE-2 |EVENT DATE: 11/15/2000|
+------------------------------------------------+EVENT TIME: 17:50[EST]|
| NRC NOTIFIED BY: JERE FREEMAN |LAST UPDATE DATE: 11/15/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RICHARD BARKLEY 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 A/R Y 1 Startup |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR WATER LEVEL |
| |
| The plant received a low water level reactor scram during turbine |
| manipulation after 2 turbine bypass valves opened. All systems functioned |
| as designed. The actual cause is not fully understood and is under |
| investigation. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37526 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/15/2000|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 20:30[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/15/2000|
+------------------------------------------------+EVENT TIME: 19:30[EST]|
| NRC NOTIFIED BY: HARRY RUSSELL |LAST UPDATE DATE: 11/15/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE ERNSTES R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF PRIMARY METEOROLOGICAL TOWER INDICATIONS |
| |
| The licensee suffered a loss of all indications from the primary |
| meteorological tower and loss of backup meteorological tower delta |
| temperature in the control room and safety parameter display system. The |
| backup meteorological tower indications available are wind speed and |
| direction. This reduces the ability to perform prompt offsite dose |
| assessment. The cause is unknown and is being investigated. There were no |
| operations or work ongoing at the time. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37527 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/16/2000|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 05:10[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/16/2000|
+------------------------------------------------+EVENT TIME: 03:23[CST]|
| NRC NOTIFIED BY: BRAD MOORE |LAST UPDATE DATE: 11/16/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE ERNSTES 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP ON HIGH-HIGH STEAM GENERATOR WATER LEVEL FOLLOWING A |
| MASTER STEAM GENERATOR FEEDWATER PUMP CONTROLLER FAILURE AND SLUGGISH |
| CONTROLS AFTER SWITCHING TO MANUAL |
| |
| The master steam generator feedwater pump controller failed low and caused |
| feedwater pump speeds to slow down. (Both pumps dropped to 3,200 rpm.) In |
| an attempt to regain feedwater pump speed and steam generator water level in |
| manual, a high-high level was reached in the 2A steam generator. This |
| caused a turbine trip and subsequent reactor trip. All control rods fully |
| inserted. Auxiliary feedwater actuation and feedwater isolation occurred as |
| expected. All systems functioned as required. |
| |
| It was reported that the controller was sluggish after manual control was |
| taken and that operators were not able to terminate the rising level in the |
| 2A steam generator before the high-high level trip setpoint was reached. |
| The lowest steam generator water level attained was approximately 27%. The |
| low level trip occurs at 25%. The cause of the controller failure is |
| currently under investigation. |
| |
| The unit is currently stable in Hot Standby. Pressurizer heaters and |
| sprays, normal charging and letdown, and the reactor coolant pumps are |
| currently being utilized for primary system pressure, level, and transport |
| control. Secondary steam is being dumped to the main condenser, and |
| auxiliary feedwater is supplying water to the steam generators. All |
| containment parameters are normal. |
| |
| The licensee plans to notify the NRC resident inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021