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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 37558 |
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| 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. |
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|Power Reactor |Event Number: 37559 |
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| 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
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| 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. |
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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. |
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