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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  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37560       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37561       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37562       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37563       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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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