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Event Notification Report for December 1, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/30/2000 - 12/01/2000

                              ** EVENT NUMBERS **

37557  37558  37559  37560  

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|Power Reactor                                    |Event Number:   37557       |
+------------------------------------------------------------------------------+
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| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 11/30/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 12:03[EST]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        11/30/2000|
+------------------------------------------------+EVENT TIME:        08:44[EST]|
| NRC NOTIFIED BY:  CHARLES MORRIS               |LAST UPDATE DATE:  11/30/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF SAFETY FUNCTION OF THE NUCLEAR SERVICES SEA WATER SYSTEM             |
|                                                                              |
| At 0843 on November 30, 2000, RWP-2B. Nuclear Services Sea Water Pump, was   |
| started and observed to develop low discharge pressure, rendering the pump   |
| INOPERABLE.  This condition was caused by diversion of flow via a failed     |
| open check valve upon shutdown of pump, RWP-1 which shares  a common         |
| discharge header with pump RWP-2B.                                           |
|                                                                              |
| RWP-2A, Nuclear Services Sea Water Pump, discharge is also common to RWP-2B. |
| Consequently, RWP--2A would likely not have developed adequate discharge     |
| pressure, and therefore, adequate flow could not have been provided by       |
| either Nuclear Services Sea Water Pump.                                      |
|                                                                              |
| Although allowed by design, this single failure defeats the safety function  |
| of the Nuclear Services Sea Water System.                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37558       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 11/30/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 17:42[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        11/30/2000|
+------------------------------------------------+EVENT TIME:        15:50[CST]|
| NRC NOTIFIED BY:  RICHARD GADBOIS              |LAST UPDATE DATE:  11/30/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL JORDAN       R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOAD REJECT - REACTOR SCRAM                                                  |
|                                                                              |
| The reactor scrammed at 1550 due to generator load reject.  The main         |
| generator ouput circuit breaker 2-7 was being closed after maintenance when  |
| a bus to phase differential trip was received causing both output circuit    |
| breakers 2-3 and 2-7 to open.  With both output circuit breakers open, the   |
| reactor scrammed due to load reject.                                         |
|                                                                              |
| The response to the reactor scram was normal, all rods inserted.  Steam is   |
| being dumped to the main condenser for decay heat removal.                   |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37559       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 11/30/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 20:55[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/30/2000|
+------------------------------------------------+EVENT TIME:        17:00[EST]|
| NRC NOTIFIED BY:  STEVE SAUER                  |LAST UPDATE DATE:  11/30/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANIELLO DELLA GRECA  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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SERVICE WATER ACCUMULATOR LEVEL HIGH OUT OF SPECIFICATION                    |
|                                                                              |
| At 1700 on 11/30/00, it was identified that the 11B service water            |
| accumulator level was higher than that allowed by technical specifications.  |
| This was identified following a level device calibration.  The service water |
| accumulators support containment integrity by ensuring the containment fan   |
| coils remain properly filled during a design basis accident.  Tech Spec      |
| 3.6.1.1 and 3.6.2.3 were entered for containment integrity and the           |
| inoperability of 11 and 12 containment fan coil units.  Actions were taken   |
| within the one hour time requirement to comply with the containment          |
| integrity LCO.  The service water accumulator was subsequently drained to    |
| within specification at 1742.  Tech Spec 3.6.11 was exited at this time.     |
| The 11 and 12 containment fan coils were restored to operable at 1745 and    |
| Tech Spec 3.6.2.3 was exited.  Actions are underway to calibrate the         |
| redundant instrumentation and to investigate the cause of the instrument     |
| drift.  All power plant parameters remained stable throughout this event and |
| no other safety systems were affected.                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.  |
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