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Event Notification Report for April 16, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/15/1999 - 04/16/1999 ** EVENT NUMBERS ** 35533 35592 35595 35596 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35533 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/30/1999| | UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 20:50[EST]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 03/30/1999| +------------------------------------------------+EVENT TIME: 20:15[EST]| | NRC NOTIFIED BY: ED BURCHFIELD |LAST UPDATE DATE: 04/15/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHARLES OGLE R2 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 | |3 N Y 100 Power Operation |100 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY OPERATING PROCEDURES (EOPs) AND ABNORMAL PROCEDURES (AP) DO NOT | | PROVIDE SPECIFIC GUIDANCE REGARDING NECESSARY OPERATOR ACTIONS SHOULD LOW | | PRESSURE INJECTION (LPI) HEADER FLOW INDICATION BE LOST. INTERIM GUIDANCE | | HAS BEEN PROVIDED TO ON-SHIFT OPERATORS TO ADDRESS THIS PROBLEM. | | | | During table top review and validation of EOPs, it was discovered that plant | | procedures did not provide that necessary guidance to ensure adequate | | operator action will occur during a certain scenario. A review of the EOPs | | has identified a scenario that is not adequately addressed in the procedure | | and therefore could place the Oconee Units outside their design basis. | | Specifically, the EOP requires throttling LPI header flow during a Large | | Break Loss of Coolant Accident (LOCA) to protect against potential pump | | runout. If flow cannot be maintained, the EOP directs the operator to | | Abnormal Procedures (AP) AP/1/A/1700/007, "Loss of LPI System." The EOP | | (EOP Section 505) and AP do not provide specific guidance regarding the | | necessary operator actions should LPI header flow indication be lost. This | | could occur on a subsequent loss of a specific power supply. Failure to | | take appropriate actions during a LOCA with this specific single failure | | could result in operators opening the LPI pump header cross connect valves | | (LP-9 and LP-10) per existing procedures, resulting in the potential loss of | | both LPI pumps due to runout. Interim guidance to close the valve of the | | affected Train (Train "A" is LP-17 and Train "B" is LP-18) so runout will | | not occur has been provided to the operators to address this potential | | deficiency, and the EOP is currently being revised. | | | | The NRC Resident Inspector was notified of this event by the licensee. | | | | * * * UPDATE at 1120 on 04/15/99 from Reene Gambrell to Jolliffe * * * | | | | After further investigation of this event, Duke Power Company has determined | | that there is no credible single failure that would result in the loss of | | the safety and non-safety flow instrumentation on an LPI header. Therefore, | | adequate instrumentation was available for the operators to successfully | | mitigate a Core Flood Line Break accident, and this event is not reportable | | under 10CFR50.72. Thus, the licensee desires to retract this event. | | | | The licensee notified the NRC Resident Inspector. The Operations Officer | | notified the R2DO Pierce Skinner. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35592 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/14/1999| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 06:50[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/14/1999| +------------------------------------------------+EVENT TIME: 04:33[CDT]| | NRC NOTIFIED BY: PAT HABEL |LAST UPDATE DATE: 04/15/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN JACOBSON 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 85 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO Rx TRIP FROM 85% POWER DUE TO MAIN GENERATOR FAULT FOR UNKNOWN | | REASONS - | | | | AT 0433 CDT ON 04/14/99, UNIT 2 AUTOMATICALLY TRIPPED FROM 85% POWER DUE TO | | A MAIN GENERATOR TRIP CAUSED BY A MAIN GENERATOR FAULT FOR UNKNOWN REASONS. | | ALL CONTROL RODS INSERTED COMPLETELY. BOTH TRAINS OF THE AUXILIARY | | FEEDWATER SYSTEM ACTUATED TO RESTORE STEAM GENERATOR WATER LEVELS TO NORMAL. | | NO SAFETY OR RELIEF VALVES LIFTED. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. ALL SYSTEMS FUNCTIONED AS DESIGNED. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). THE LICENSEE IS INVESTIGATING THE | | CAUSE OF THE MAIN GENERATOR FAULT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0408 ON 04/15/99 BY JOLLIFFE * * * | | | | THE AUTOMATIC REACTOR TRIP WAS CAUSED BY A PROBLEM WITH A MAIN GENERATOR GIX | | GROUND FAULT RELAY. THE LICENSEE HAS BYPASSED THE RELAY AND RESTARTED UNIT | | 2. THE LICENSEE IS CONTINUING TO INVESTIGATE THE ROOT CAUSE OF THE REACTOR | | TRIP. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35595 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/15/1999| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 14:47[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/1999| +------------------------------------------------+EVENT TIME: 13:01[CDT]| | NRC NOTIFIED BY: DAN ACKERMAN |LAST UPDATE DATE: 04/15/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN JACOBSON R3 | |10 CFR SECTION: | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 12 Power Operation |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A CONTROL BANK OVERLAP | | PROBLEM DURING UNIT 2 RESTART | | | | The following text is a portion of a facsimile received from the licensee: | | | | "[At 1301 CDT on 04/15/99, the] Unit 2 reactor was shut down from 12% power | | due to control bank overlap not meeting the requirements of Technical | | Specification 3.1.6. Unit 2 was in the process of starting up after a trip | | on 04/14/99 due to a generator problem." (Refer to event #35592 for | | additional information.) | | | | The licensee stated that all systems functioned as required and that there | | was nothing unusual or not understood about this event. The estimated | | restart date is currently unknown. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35596 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/15/1999| | UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 20:04[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/1999| +------------------------------------------------+EVENT TIME: 16:19[EDT]| | NRC NOTIFIED BY: PAUL SIMMONS |LAST UPDATE DATE: 04/15/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PIERCE SKINNER R2 | |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 +------------------------------------------------------------------------------+ | MANUAL STARTING OF THE STANDBY HIGH-HEAD CENTRIFUGAL CHARGING PUMP (CCP) DUE | | TO FAILURE OF OPERATING PUMP | | | | The following text is a portion of a facsimile received from the licensee: | | | | "[At approximately] 1619 on 04/15/99, the in-service 1B-B CCP was stopped | | after water was identified spraying from the outboard seal. The leak | | stopped when the pump was stopped. [The main control room unit operator] | | had observed increasing amps with decreasing charging flow indicating that | | the 1B-B CCP was not functioning [normally]. The 1A-A CCP was placed in | | service to maintain [pressurizer] level in the normal operating range and | | [to] prevent [pressurizer] level from decreasing to the letdown | | isolation/[pressurizer] heater lockout setpoint which could ultimately | | [have] lead to a [reactor] trip [and possibly a safety injection] on low | | [pressurizer] pressure." | | | | The licensee stated that there were no unusual occurrences that were not | | understood and that the 1A-A CCP has functioned correctly. The licensee | | also stated that the unit entered three 72-hour technical specification | | limiting conditions for operation as a result of this event. These LCOs | | were entered at 1619 EDT. | | | | The licensee reported that this event involved a manual actuation of an | | engineered safety feature component (1A-A CCP) in response to actual plant | | conditions and that this was not a system functional failure. | | | | The licensee plans to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+