United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2001

Event Notification Report for December 4, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/03/2001 - 12/04/2001

                              ** EVENT NUMBERS **

38513  38531  38533  38534  
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38513       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 11/23/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 12:30[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        11/23/2001|
+------------------------------------------------+EVENT TIME:        12:10[EST]|
| NRC NOTIFIED BY:  CHARLIE PIKE                 |LAST UPDATE DATE:  12/04/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO FLORIDA STATE INVOLVING RECOVERED SEA TURTLE
FROM    |
| UNIT 1 INTAKE STRUCTURE                                                      |
|                                                                              |
| "A sea turtle with no external injuries but appearing to be distressed was   |
| recovered from the Unit 1 Intake Structure.  The State Stranding Coordinator |
| for sea turtles has been contacted."                                         |
|                                                                              |
| * * * UPDATE 11/23/01 AT 1255EST FROM CHARLIE PIKE TO S. SANDIN * * *        |
|                                                                              |
| "Turtle has died."                                                           |
|                                                                              |
| The licensee informed both the State of Florida and the NRC Resident         |
| Inspector.                                                                   |
|                                                                              |
| * * * UPDATE 1413EST ON 12/3/01 FROM JACK BREEN TO FANGIE JONES * * *        |
|                                                                              |
| At approximately 1215 EST on 12/3/01, a report was made to the Florida       |
| Department of Fish and Wildlife concerning the recovery of an injured sea    |
| turtle from the plant's intake canal.  The turtle was a green sea turtle in  |
| the intake canal that appeared distressed and looked to have a wound from a  |
| boat motor on its back.  It will be transferred to the State for             |
| rehabilitation.                                                              |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  Notified           |
| R2DO(MacAlpine).                                                             |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38531       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 12/02/2001|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 18:17[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        12/02/2001|
+------------------------------------------------+EVENT TIME:        14:48[EST]|
| NRC NOTIFIED BY:  RESTUCCIO                    |LAST UPDATE DATE:  12/03/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM RULAND       R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       75       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 75% POWER                                          |
|                                                                              |
| On December 2, 2001 at 1448, Unit 2 manually scrammed from approximately     |
| 75% reactor power due to a low water level trip (159.3" - Level 3).          |
| Preliminary indications are an electrical fault/trip on feedwater Pump  "A"  |
| was the cause of the reactor low level condition.  The  "A"  Recirculation   |
| Flow Control Valve (FCV) ran back to minimum position as required on the low |
| level alarm at 178.3" -  Level 4.  The  "B"  FCV failed to fully run back as |
| required due to the electrical transient and the subsequent loss of          |
| hydraulic control units. The  "B"  FCV stabilized at 50% open.  The          |
| Operators were inserting cram rods in an attempt to lower power further when |
| the low water level trip alarm came in for Division 1.  The Control Room     |
| Supervisor (CRS) ordered the mode switch to shutdown.  All Control Rods      |
| inserted as required.  Reactor water level is being controlled in the normal |
| level band with Condensate Booster pumps.  Reactor pressure is being reduced |
| to place the shutdown cooling system in service by the use of the turbine    |
| bypass valves.                                                               |
|                                                                              |
| Additionally, indications show that the Neutron Monitoring System (NMS)      |
| scram setpoints were exceeded for the Average Power Range Monitoring (APRM)  |
| thermal power trip.  This trip signal was in close sequence to the mode      |
| switch being placed in the shutdown position.                                |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| HOO NOTE: see event # 38532                                                  |
|                                                                              |
| * * * UPDATED AT 1734 EST ON 12/3/01 BY TOM RESTUCCIO TO FANGIE JONES * * *  |
|                                                                              |
| "The purpose of this notification is to provide an update to Event #38531.   |
| From reviews of plant computer data and alarm printouts, it was determined   |
| that the Average Power Range Monitoring (APRM) Thermal Power trip was NOT    |
| exceeded. The only APRM scram signal received was the expected APRM neutron  |
| monitoring scram which occurred when the mode switch was taken out of the    |
| run position. With the mode switch not in run, the APRM neutron monitoring   |
| scram setpoint is 15% which was exceeded due to power being at 75%."         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (John Rogge) has |
| been notified.                                                               |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38533       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/03/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 23:13[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/03/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:34[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  12/03/2001|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |PATRICK HILAND       R3      |
|  DOCKET:  0707001                              |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM WHITE                    |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)        SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILURE                                                     |
|                                                                              |
| "At 1734 CST, on 12/3/2001, the Plant Shift Superintendent was notified that |
| the C-337 High Pressure Fire Water (HPFW) Sprinkler System 8-14 had been     |
| inspected and 4 sprinkler heads had visible corrosion on them. The system    |
| configuration and building configuration were evaluated using                |
| EN-C-822-99-047. Effects of impaired Sprinkler Heads on System Operability,  |
| and determined that with these heads impaired, a portion of the building     |
| would not have sprinkler coverage. The sprinkler system is required to be    |
| operable according to TSR LCO 2.4.4.5. HPFW Sprinkler System B-14 was        |
| declared inoperable and TSR LCO 2.4.4.5 Required Action B was implemented    |
| for the area without sprinkler coverage.                                     |
|                                                                              |
| "This event is reportable under 10 CFR 76.120(c)(2) as an event in which     |
| equipment required by the TSR is disabled or fails to function as designed.  |
|                                                                              |
| "The NRC Senior Resident Inspector has been notified of this event."         |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38534       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 12/04/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 04:58[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/03/2001|
+------------------------------------------------+EVENT TIME:        22:56[CST]|
| NRC NOTIFIED BY:  OLMSTEAD                     |LAST UPDATE DATE:  12/04/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       12       Power Operation  |1        Startup          |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER ACTUATION                                                |
|                                                                              |
| During a controlled plant shutdown, a vibration problem occurred on the Main |
| Turbine that required breaking condenser vacuum.  Since breaking condenser   |
| vacuum would cause a loss of the operating Main Feedwater pump and generate  |
| an Auxiliary Feedwater Actuation signal, both "A" and "B" Motor Driven       |
| Auxiliary Feedwater pumps were manually started prior to breaking condenser  |
| vacuum.  "A" Motor Driven Auxiliary Feedwater pump failed to develop proper  |
| flow, so the Turbine Driven Feedwater pump was placed in service. The "A"    |
| Motor Driven Auxiliary Feedwater pump was subsequently secured and declared  |
| inoperable.  A plan of action is being developed to troubleshoot and repair  |
| the inoperable "A" Motor Driven Auxiliary Feedwater pump.                    |
|                                                                              |
| Initially, Steam Generator Atmospheric Power Operated Relief Valves were     |
| being used to control Reactor Coolant System temperature.  Condenser vacuum  |
| has been restored and currently, Steam Generator water levels are being      |
| maintained using the Turbine Driven Auxiliary Feedwater pump with condenser  |
| steam dumps maintaining Reactor Coolant System temperature.                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+
.