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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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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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