Event Notification Report for January 20, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/19/1999 - 01/20/1999 ** EVENT NUMBERS ** 35178 35280 35281 35282 35283 35284 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35178 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/20/1998| | UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 06:19[EST]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 12/20/1998| +------------------------------------------------+EVENT TIME: 02:53[EST]| | NRC NOTIFIED BY: HILL |LAST UPDATE DATE: 01/19/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PAUL FREDRICKSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN ENGINEERED SAFEGUARDS ACTUATION DURING A SURVEILLANCE. | | | | WHILE PERFORMING IP/O/A/0310/012B(ENGINEERED SAFEGUARDS SYSTEMS LOGIC | | SUBSYSTEM 1 LOW PRESSURE INJECTION CHANNEL 3 ON LINE TEST) UNIT 2 RECEIVED A | | SPURIOUS/PARTIAL ACTION OF ES CHANNEL 3. THE "2A" LOW PRESSURE INJECTION | | PUMP AND THE "C" LOW PRESSURE SERVICE WATER PUMP STARTED AUTOMATICALLY. | | THESE COMPONENTS WERE SECURED WITHIN 2 MINUTES AND 4 MINUTES RESPECTIVELY AT | | THE DIRECTION OF THE CONTROL ROOM SRO. THE REASON FOR THE SPURIOUS ACTION | | IS UNKNOWN AT THIS TIME AND IS BEING INVESTIGATED. THERE WAS NO INDICATION | | OF HUMAN ERROR AND THEY SUSPECT IT MAY HAVE BEEN A FAULTY RELAY. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | ---------------------------UPDATE AT 1311 ON 1/19/99, BY OWENS RECEIVED BY | | WEAVER ------------------------------- | | | | "After further review of the circumstances of this event, it has been | | determined that a single ESF component actuation occurred as a result of the | | failure of the test logic of the ES actuation circuitry for this channel. | | The failed ES channel 3 test logic and the trip logic were replaced and the | | surveillance was satisfactorily completed. The removed ES channel 3 test | | logic was subsequently determined to have been operable during the test (as | | designed) and that the required ESF components (and other required non-ESF | | components) would have actuated during the test. These ESF components | | include the 2A LPI pump (which actuated), and the injection mode LPI suction | | isolation valve and discharge valve for this train of ESF (which did not | | actuate and should not have actuated per design of the test logic) . | | | | "NUREG-1022, Section 3.3.2 guidance, states that the NRC staff generally | | does not consider single component actuations, by themselves, to be | | reportable if they are part of complex systems (trains) used for accident | | mitigation. In addition, actuation of the LPI pump by itself would not be | | sufficient to mitigate the consequence of an accident. | | | | "As a consequence, Duke Energy has concluded that this event does not meet | | the report requirements of 10 CFR 50.72." | | | | The licensee informed the NRC resident inspector. The operations center | | informed the R2DO (Christensen). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35280 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 01/18/1999| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 21:46[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/18/1999| +------------------------------------------------+EVENT TIME: 20:17[CST]| | NRC NOTIFIED BY: CARL MOORE |LAST UPDATE DATE: 01/19/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNU |JIM GAVULA R3 | |10 CFR SECTION: |BRUCE BOGER NRR | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |FRANK CONGEL IRD | | |SULLIVAN FEMA | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT - LOSS OF APPROXIMATELY 50% OF CONTROL ROOM ANNUNCIATORS | | | | "Loss of redundant Annunciator Power Supplies has rendered a substantial | | number of safety related annunciators inoperable. This required a GSEP | | notification - Unusual Event, (MU-6 - Loss of Annunciators for >= 15 | | minutes). Backup indications are available and increased main control board | | monitoring has been implemented." | | | | The licensee has called in additional personnel to help with the increased | | monitoring. Troubleshooting on the power supplies is in progress. The NRC | | resident inspector has been notified. | | | | | | *** UPDATE ON 01/19/99 @ 0539 BY RAUSH TO GOULD *** | | | | THE PLANT TERMINATED THE NOUE AT 0407 WHEN TESTING VERIFIED THE SYSTEMS WERE | | FULLY OPERATIONAL. THE CAUSE OF THE POWER SUPPLY FAILURE WAS DUE TO A | | GROUND WHICH HAS BEEN REPAIRED. BOTH BACKUP AND MAIN POWER SUPPLY HAVE | | BEEN RETURNED TO SERVICE. | | | | THE NRC RESIDENT INSPECTOR AND THE STATE WAS NOTIFIED. | | | | THE REG 3 RDO(GAVULA) AND THE EO( BOGER )WERE NOTIFIED ALONG WITH FEMA | | (WRIGHT). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35281 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/19/1999| | UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 08:41[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/19/1999| +------------------------------------------------+EVENT TIME: 08:25[EST]| | NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 01/19/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GENE KELLY R1 | |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 | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST CAPABILITY FOR EMERGENCY NOTIFICATION THROUGH THE WEATHER RADIOS. | | | | THE LICENSEE WAS INFORMED THAT THE AMES HILL TRANSMITTER IS OUT OF SERVICE. | | THIS FAILURE DEGRADES THE LICENSEE'S CAPABILITY FOR MAKING NOTIFICATIONS TO | | THE PUBLIC THROUGH WEATHER RADIOS DURING AN EMERGENCY. TECHNICIANS ARE ON | | THE WAY TO MAKE REPAIRS TO THE TRANSMITTER. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. STATE AND LOCAL AGENCIES WERE ALSO | | NOTIFIED. | | | | *** UPDATE ON 01/19/99 @ 1037 BY MAY TO GOULD *** | | | | THE AMES HILL TRANSMITTER WAS RETURNED TO SERVICE AT 1031. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED ALONG WITH THE STATE AND LOCAL | | AGENCIES. | | | | THE REG 1 RDO(KELLY) WAS NOTIFIED. | | | | HOO NOTE: SEE SIMILAR EVENT #35276 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35282 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/19/1999| | UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 14:43[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 01/19/1999| +------------------------------------------------+EVENT TIME: 14:20[EST]| | NRC NOTIFIED BY: JAMES GROOMS |LAST UPDATE DATE: 01/19/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 | |10 CFR SECTION: | | |AESS 50.72(b)(1)(v) EMERGENCY SIREN 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 +------------------------------------------------------------------------------+ | EMERGENCY SIRENS INOPERABLE | | | | The licensee reported that the sirens located in St. Mary's County failed | | their bi-weekly test today. The licensee has 17 of their total 72 sirens | | located within that county. Repair efforts are in progress. | | | | The licensee informed the NRC resident inspector and is working with St. | | Mary's County representatives to repair the problem. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35283 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 01/19/1999| | UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 16:46[EST]| | RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 01/19/1999| +------------------------------------------------+EVENT TIME: 14:20[EST]| | NRC NOTIFIED BY: TODD STRAYER |LAST UPDATE DATE: 01/19/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 | |10 CFR SECTION: | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) INOPERABLE | | | | The following text is taken from a licensee facsimile. | | | | "During a scheduled HPCI system test, the HPCI gland seal condenser lower | | gasket developed a leak (water leak) sufficient enough to warrant an | | immediate shutdown of HPCI. The HPCI auxiliary oil pump was placed in | | pull-to-lock. The HPCI suction paths from the torus and condensate storage | | tanks were isolated to stop the leak out of the gland seal condenser. The | | HPCI system is currently inoperable. Planned actions are to gather | | information from test participants, develop a root cause, and implement | | corrective actions in accordance with station procedures. Per our Technical | | Specification, the HPCI system is required to be returned to operable status | | within 14 days." | | | | The licensee will inform the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35284 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 01/20/1999| | UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 06:04[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/20/1999| +------------------------------------------------+EVENT TIME: [CST]| | NRC NOTIFIED BY: DAVE SCHUSSLER |LAST UPDATE DATE: 01/20/1999| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ROGER LANKSBURY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS | | | | The licensee commenced a unit shutdown in accordance with Technical | | Specification (TS) 3.8.1.7 after both standby diesel generators failed to | | reach required voltage and frequency within the required time (ten seconds). | | The licensee stated that the methodology for the test has been changed, and | | this was the first test performance using the new methodology. | | | | The old test procedure recorded the time for the diesel generators to start | | and reach required voltage and frequency, although the generator normally | | overshoots the targets slightly before reaching a steady state value. The | | revised test methodology records the time for the diesel generators to reach | | steady state voltage and frequency. The licensee reported that one diesel | | generator reached steady state within 15 seconds, and the other reached | | steady state within 22 seconds. | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+
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Page Last Reviewed/Updated Thursday, March 25, 2021