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
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|Power Reactor |Event Number: 38513 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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). |
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|Power Reactor |Event Number: 38531 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Fuel Cycle Facility |Event Number: 38533 |
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| 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| |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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." |
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|Power Reactor |Event Number: 38534 |
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| 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
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| 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021