Event Notification Report for June 20, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/19/2001 - 06/20/2001
** EVENT NUMBERS **
38079 38080
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|Power Reactor |Event Number: 38079 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 06/19/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 12:13[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 06/19/2001|
+------------------------------------------------+EVENT TIME: 09:15[CDT]|
| NRC NOTIFIED BY: PEDERSON |LAST UPDATE DATE: 06/19/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE |
| |
| HPCI system was declared inoperable due to all alarm functions not |
| operating. The local undervoltage alarms did not annunciate in the control |
| room. This condition was discovered during a normal routine test. They |
| were attempting to send a signal from the local HPCI panel in the plant to |
| the control room, but the control room did not receive it. They verified |
| that the local panel is operable. An operator was locally stationed at the |
| subject panel to verify current alarm status and call the control room. |
| Therefore, in this mode of operation, the HPCI system has been declared |
| operable. They are still investigating the problem with signal |
| transmission. |
| |
| The NRC Resident Inspector was notified. |
| |
| The State and local agencies will be informed. |
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|Power Reactor |Event Number: 38080 |
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| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 06/20/2001|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 04:07[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 06/20/2001|
+------------------------------------------------+EVENT TIME: 00:11[CDT]|
| NRC NOTIFIED BY: GEORGE RUITER |LAST UPDATE DATE: 06/20/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 96 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO FEEDWATER REGULATING VALVE FAILING SHUT. |
| |
| At 0011 CDT feedwater regulating valve to steam generator "B" failed to the |
| closed position and manual control was not effective. The reactor/turbine |
| tripped on steam flow greater than feed flow coincident with low steam |
| generator water level. Following the trip, the rod bottom light for rod D4 |
| (interior rod) was off and valve LD-2 indicated mid-position (letdown |
| isolated on low pressurizer water level). Individual Rod Position |
| Indication for rod D4 indicates zero, however, emergency boration was used |
| to inject the required amount of boric acid for one stuck rod. Excess |
| letdown was established at 0028 CDT hours, since normal letdown was not |
| available due to the failure of valve LD-2. All emergency core cooling |
| systems, emergency diesel generators are fully operable if needed and the |
| electrical grid is stable. |
| |
| Both Motor Driven and the Turbine Driven Auxiliary Feedwater Pumps |
| automatically started. The Turbine Driven Auxiliary Feedwater pump was |
| secured per procedure and steam generator water is being maintained by the |
| Motor Driven Auxiliary Feedwater Pumps. |
| |
| At this time the licensee thinks that rod bottom light for rod D4 is burned |
| out. The licensee is also investigating why letdown isolation valve, LD-2, |
| indicates mid-position and the unexpected closure of feedwater regulating |
| valve for steam generator "B". The steam dump bypass control system is |
| operating properly. |
| |
| 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