Event Notification Report for May 1, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/30/2001 - 05/01/2001
** EVENT NUMBERS **
37953 37954 37955
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|Power Reactor |Event Number: 37953 |
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| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/30/2001|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 02:24[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/29/2001|
+------------------------------------------------+EVENT TIME: 22:50[CDT]|
| NRC NOTIFIED BY: DAVE HANKS |LAST UPDATE DATE: 04/30/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BILL JONES R4 |
|10 CFR SECTION: | |
|*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| EXPECTED LOSS OF SPDS FOR GREATER THAN 8 HOURS |
| |
| Planned maintenance removed safety parameters display system (SPDS) from |
| service for greater than 8 hours. This requires a notification per 10 CFR |
| 50.72(b)(3)(xiii) for loss of assessment capabilities. |
| |
| The licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37954 |
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| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/30/2001|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 11:38[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 04/30/2001|
+------------------------------------------------+EVENT TIME: 11:00[EDT]|
| NRC NOTIFIED BY: MILLER |LAST UPDATE DATE: 04/30/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 46 Power Operation |48 Power Operation |
| | |
| | |
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EVENT TEXT
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| PLANT LOST BOTH COMMERCIAL AND ENS PHONE SYSTEMS |
| |
| The plant lost both their commercial and ENS phone systems due to a fiber |
| optics cable cut. Ameritech is currently troubleshooting and they do not |
| know at this time when service will be restored. The licensee has microwave |
| communication available. They have verified communications with other |
| agencies. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE 1702EDT ON 4/30/01 FROM MILLER TO S. SANDIN * * * |
| |
| "At 1100 on 4/30/01 The Emergency Notification System (ENS) and the |
| commercial telecommunications capability to dial offsite was found to be |
| non-functioning. Communications with outside agencies has been verified |
| through the microwave transmission lines (RERP Lines). The cause is being |
| attributed to a problem with an offsite fiber optics cable and an |
| investigation is underway by the local telecommunications company. The ENS |
| and commercial telecommunications lines were verified functional at 1650." |
| |
| The licensee informed the NRC resident inspector. Notified R3DO(Leach) |
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|Power Reactor |Event Number: 37955 |
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| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/30/2001|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 12:54[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/08/2001|
+------------------------------------------------+EVENT TIME: 08:45[EDT]|
| NRC NOTIFIED BY: PETE ORPHANOS |LAST UPDATE DATE: 04/30/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|*INV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 88 Power Operation |88 Power Operation |
| | |
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EVENT TEXT
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| INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION CAUSED BY SETPOINT |
| DRIFT |
| |
| "This 60-day optional report, as allowed by 10 CFR 50.73(a)(1), is being |
| made under the reporting requirement in 10CFR50.73(a)(2)(iv)(A) to describe |
| an invalid actuation of a specific system, namely Primary Containment |
| Isolation System (PCIS). |
| |
| "On March 8, 2001 at 08:45 hours the main control room received a 2A |
| Uninterruptible Power Supply (UPS)/Reactor Protection System (RPS) trouble |
| alarm and verified the following Engineered Safety Features (ESF) |
| isolations: Drywell Chilled Water (DWCW), Reactor Enclosure Cooling Water |
| (RECW), Instrument Gas and Containment Leak Detector. |
| |
| "The control room also received an electro-hydraulic control (EHC) |
| electrical malfunction alarm with a loss of cooling fans and inaccurate |
| indication of stop valve and combined intercept valves. Additionally, some |
| cabinet fans, 60 Hz solenoid valves and the bypass jack were also lost. |
| |
| "These expected isolations were bypassed by procedure for the given |
| condition, and were subsequently restored to their normal operating |
| position. The isolations were due to an invalid signal resulting from the |
| failure of a circuit board trim potentiometer for the undervoltage relay |
| (27-AY24801) of the 2A RPS breaker (2A-C248-52). Failure analysis of the |
| undervoltage relay (ABB Model No. 211T4175F) identified that the trim |
| potentiometer was heat sensitive (manufacturing defect) which caused the |
| relay setpoint to drift up to the actual line voltage, tripping the |
| breaker. |
| |
| "The 2A RPS undervoltage relay was replaced and the isolations were reset at |
| 15:39 hours. |
| |
| "The impact on the plant from this event was minimal. The selective |
| isolations and equipment losses during the transient did not result in a |
| plant transient, and the equipment performed as expected. |
| |
| "This event has been entered into the site-specific corrective action |
| program for resolution and generic implications. Industry operational |
| experience (CE) and vendor database searches identified no related issues |
| for this model relay. |
| |
| "The NRC site resident has been informed." |
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