Event Notification Report for December 4, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/01/2000 - 12/04/2000
** EVENT NUMBERS **
37560 37561 37562 37563 37564
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|Power Reactor |Event Number: 37560 |
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| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 12/01/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 07:30[EST]|
| RXTYPE: [1] CE |EVENT DATE: 12/01/2000|
+------------------------------------------------+EVENT TIME: 05:40[CST]|
| NRC NOTIFIED BY: ANTHONY CHRISTIANSON |LAST UPDATE DATE: 12/01/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KRISS KENNEDY R4 |
|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 DUE TO TECHNICAL SPECIFICATIONS |
| |
| The licensee reported that the unit has commenced a shutdown in accordance |
| with Technical Specification 2.1.4 due to an approximately 1 gpm reactor |
| coolant system (RCS) leak. The licensee stated that the leakage, as measured |
| by containment sump level, began suddenly this morning and increased to the |
| TS 2.1.4 threshold of 1 gpm. (The criterion for declaration of an Unusual |
| Event is 10 gpm.) The licensee is preparing to make a containment entry in |
| order to identify the location of the leak. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE ON 12/01/00 AT 1540 ET BY ERICK MATZKE TAKEN BY MACKINNON * * |
| * |
| |
| The leak has been identified and isolated, CVCS system isolated. The leak |
| is located on a socket weld to the CVCS Regenerative Heat Exchanger. The |
| crack on the socket weld is approximately 1.24" in length. The licensee has |
| an alternate charging path to the reactor coolant system. Technical |
| Specification 2.1.4 was exited at 0830 CST and the shutdown of the plant was |
| secured at about 0900 CST. Reactor power is about 86%. Options for repair |
| of the leak are being investigated at this time. R4DO (Kriss Kennedy) |
| notified. |
| |
| The NRC Resident Inspector was notified of this event update by the |
| licensee. |
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|Power Reactor |Event Number: 37561 |
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| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/01/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 12:46[EST]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/01/2000|
+------------------------------------------------+EVENT TIME: 10:15[CST]|
| NRC NOTIFIED BY: VERCELLI |LAST UPDATE DATE: 12/01/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERED THAT SHUTDOWN COOLING SYSTEM COULD NOT BE PLACED IN SERVICE. |
| |
| Logic for Shutdown Cooling System would have prevented placing Shutdown |
| Cooling in service (not currently required to be in service because Shutdown |
| cooling is above its cut in permissive temperature of 350 degrees F). A |
| component had high resistance simulating a high temperature condition |
| (thermocouples failed high). Maintenance is troubleshooting the problem at |
| this time. |
| |
| At the this time rods are being pulled to go critical. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 37562 |
+------------------------------------------------------------------------------+
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| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 12/01/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 14:34[EST]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 12/01/2000|
+------------------------------------------------+EVENT TIME: 11:10[CST]|
| NRC NOTIFIED BY: AL BAILEY |LAST UPDATE DATE: 12/01/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 30 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AUTOMATIC REACTOR SCRAM OF DUE TO HIGH REACTOR VESSEL WATER LEVEL. |
| |
| High reactor vessel water level occurred during feedwater manipulations to |
| place "2B" Turbine Driven Reactor Feedwater Pump online. The abnormally |
| high reactor vessel water level (level 8) initiated trips of the Main |
| Generator and all online feedwater pumps, resulting in a reactor scram. All |
| rods fully inserted into the core. Reactor vessel water level has been |
| restored to a normal level of 36 inches using their Motor Driven Reactor |
| Feedwater Pump. All equipment responded as expected. There were no ESF |
| actuations because of this event. Conditions are stable. An investigation |
| has been initiated to determine the cause of the abnormally high reactor |
| vessel water level. The licensee was coming out of a refueling outage when |
| the reactor scrammed from 30% reactor power due to the valid high reactor |
| vessel water level signal. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 37563 |
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| FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 12/01/2000|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 15:46[EST]|
| RXTYPE: [1] B&W-R-LP |EVENT DATE: 12/01/2000|
+------------------------------------------------+EVENT TIME: 14:50[EST]|
| NRC NOTIFIED BY: DOUG WHALEN |LAST UPDATE DATE: 12/01/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY TO A CONTRACTOR. IMMEDIATE |
| COMPENSATORY MEASURES TAKEN UPON DISCOVERY. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| See HOO Log Book for further details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37564 |
+------------------------------------------------------------------------------+
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| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/03/2000|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 18:08[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/03/2000|
+------------------------------------------------+EVENT TIME: 14:16[CST]|
| NRC NOTIFIED BY: DWAYNE JOHNSON |LAST UPDATE DATE: 12/03/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| ESF ACTUATION |
| |
| Today, 12/03/2000, at 1416 hours, 121 Spent Fuel Special & In-Service Purge |
| System tripped due to high radiation on lR-22, the Shield Building Stack gas |
| radiation monitor. This ventilation system operated for approximately 1-2 |
| minutes prior to the high radiation trip signal. Other diverse indications |
| aligned to the Shield Building Stack include 1R-11 and 1R-12, which showed |
| no increase in radiation. A gas sample taken in containment (concurrent to |
| the vent system startup) also revealed no activity above the normal |
| background level (.05 DAC). A post-trip gas sample taken on IR-22 also |
| revealed no elevated activity. |
| |
| The licensee notified the NRC resident inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021