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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021