Event Notification Report for October 10, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/09/2001 - 10/10/2001
** EVENT NUMBERS **
38362 38366 38367 38368 38369
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|Power Reactor |Event Number: 38362 |
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| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/07/2001|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 13:02[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/2001|
+------------------------------------------------+EVENT TIME: 09:50[EDT]|
| NRC NOTIFIED BY: STEVE CHERBA |LAST UPDATE DATE: 10/10/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 8 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| UNEXPECTED REACTOR TRIP DURING PLANT STARTUP OPERATIONS |
| |
| ". . . . This event occurred at 0950 hours this morning (10-7-01). Currently |
| the Unit is in Mode 3 with all systems normal. At the time of the trip the |
| unit was at approximately 8 % power (by RCS AT indication, about 6 to 7 % on |
| Power Range Nuclear Instrumentation) in power ascension and was just |
| preparing to roll the main turbine. |
| |
| "RCS Tavg was noted to decrease below the normal 547 �F no-load post-trip |
| value to about 535 �F by the Reactor Operator monitoring the temperature. At |
| the time of the trip one main feedwater pump was supplying the Steam |
| Generators (SG), with low-flow feedwater pre-heating in service. Main |
| feedwater isolated on the trip with the SGs being supplied post trip by the |
| motor driven Auxiliary Feedwater (AFW) Pumps. The RCS cooldown was |
| attributed to the #4 SG AFW flow control valve not closing as expected on |
| high flow thus allowing too much flow to #4 SG, as well as steam that was |
| still being supplied to low flow feedwater preheating. Operator actions |
| taken in response to the cooldown were to close the main steam stop valves, |
| and review AFW valve positions so as to limit steam flow from, and feed flow |
| to, the SGs. These actions were completed by 0959 hours, and were sufficient |
| to maintain temperature control. RCS temperature shortly recovered to 547 �F |
| at about 1032 hours, 10-7-01. No other significant abnormalities were noted, |
| pressurizer pressure decreased in response to the temperature transient, and |
| the subsequent RCS shrink caused RCS letdown to isolate on low pressurizer |
| level. The plant is presently stable in Mode 3. No other RPS or SI setpoints |
| were exceeded due to the trip and subsequent temperature transient. All |
| other systems and equipment functioned normally. |
| |
| "The initiating RPS signal was a high Power Range Nuclear Instrument Rate |
| Trip on 2 out of 4 channels. Cause of this rate trip is not definitively |
| known at this time, rapid event teams to investigate and evaluate the trip |
| have been initiated. Suspected cause is a Rod Control System problem." |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| * * * UPDATE 0353EDT ON 10/10/01 FROM DALE TURINETTI TO S. SANDIN * * * |
| |
| The following information was received as an update to this report: |
| |
| "The cause of the Unit 2 reactor trip was a negative rate trip as a result |
| of a loss of Rod Control Motor Generator set voltage. The loss of voltage |
| was attributed to a failed open resistor on the North motor generator set |
| which caused a loss of voltage regulation. It is believed this loss of |
| voltage caused the north motor generator set to act as a load; and the south |
| motor generator set could not maintain the output voltage. The reduction in |
| voltage caused a collapse of field and the subsequent release of control |
| rods and resultant negative rate trip. |
| |
| "The motor generator set resistors have been replaced and associated relays |
| have been tested to ensure proper operation of the motor generator sets. |
| Plant power ascension is in progress with the unit in mode 1 and at 25%." |
| |
| The licensee informed the NRC resident inspector. Notified R3DO(Parker). |
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|Power Reactor |Event Number: 38366 |
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| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 10/09/2001|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 12:22[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 10/09/2001|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: JOHN SCHORK |LAST UPDATE DATE: 10/09/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CLIFF ANDERSON R1 |
|10 CFR SECTION: | |
|ACOM 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 Intermediate Shut|0 Intermediate Shut|
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LANCASTER COUNTY EMERGENCY SIRENS WERE FOUND INOPERABLE |
| |
| "At 11:30 AM on 10/9/01, TMI determined that the apparent inoperability of |
| emergency sirens in Lancaster County, Pennsylvania for approximately 3 days |
| met the criteria set forth in NUREG 1022, Rev. 2 for a major loss of |
| emergency offsite communications capability and that an immediate 8 hour |
| notification in accordance with 10 CFR 50.72(b)(3)(xiii) was required. |
| |
| "At approximately 8:55 am on Tuesday, October 9, 2001 the emergency sirens |
| in Lancaster County were inadvertently activated during routine maintenance |
| by Capitol Area Communications, the siren vendor. During the weekly |
| evaluation of system electronics on Tuesday, October 9, 2001, Capitol Area |
| Communications had discovered an anomaly with the system communications with |
| Lancaster County. Capitol Area Communications called Lancaster County and it |
| was found that apparently the transmitter for Lancaster County had been |
| incorrectly left turned off following recent maintenance performed on |
| Saturday, October 6, 2001 that occurred in the vicinity of the transmitter. |
| |
| "The transmitter was turned back on at approximately 8:55 am on Tuesday, |
| October 9, 2001. When the transmitter was turned on, a signal that had been |
| sent on Saturday, October 6, 2001 for the monthly Saturday test of the |
| sirens that had been received but not acted upon, was acted upon by the |
| transmitter which then activated the sirens. The sirens were silenced upon |
| recognition of the inadvertent actuation. Lancaster County is notifying |
| local media of the cause of the inadvertent siren actuation. |
| |
| "Subsequent discussions between Exelon Emergency Management personnel and |
| the siren vendor determined that the sirens for Lancaster County had |
| apparently been inoperable from sometime on Saturday, October 6 until today, |
| Tuesday, October 9. |
| |
| "The sirens in Lancaster County were reactivated when the transmitter [was |
| turned] back on. |
| |
| "The Lancaster County 911 dispatcher number 41 called the TMI Control Room |
| at approximately 9:00 AM. The Control notified a duty public information |
| representative of the siren malfunction. The duty Public Information |
| Representative spoke with Lancaster County Emergency Management at 9:13 am |
| who confirmed the information received from the 911 dispatcher. |
| Subsequently, at 9:15 am Exelon emergency management reconfirmed the |
| information received. |
| |
| "The site Sr. Resident Inspector has been informed of the event and the 8 |
| hour report. TMI Communications contacted the Lancaster County Commissioners |
| and PEMA to inform them of the event." |
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|Power Reactor |Event Number: 38367 |
+------------------------------------------------------------------------------+
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| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 10/09/2001|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 14:42[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 10/09/2001|
+------------------------------------------------+EVENT TIME: 09:00[CDT]|
| NRC NOTIFIED BY: GARY HARRINGTON |LAST UPDATE DATE: 10/09/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| DISCOVERY THAT ANTICIPATED FLOW MAY RESULT IN ENGINEERED SAFETY FEATURE |
| EQUIPMENT BEING INCAPABLE OF PERFORMING DESIGN FUNCTIONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Prior to entering the scheduled refueling outage and while the plant was |
| removed from service on 09/23/01, operating flow and temperature data for |
| the Turbine Building Service Water (SW) system header was obtained. The |
| Turbine Building SW header is a branch connection off the Engineered |
| Safeguards (ESF) SW header, which is manually selected to either 'A' or 'B' |
| train ESF SW header. Preliminary reviews of the data indicate that |
| anticipated flows under accident conditions, using existing analysis limits, |
| result in ESF equipment being incapable of performing design functions. The |
| current accident analyses for the SW ESF equipment only assumes a Turbine |
| Building demand on the selected ESF header of 2000 gallons per minute (gpm). |
| The gathered data, when projected to accident temperature limits for design |
| basis cooling requirements, shows the Turbine Building header flow to be |
| significantly greater than 2000 gpm. The data indicates that a lake water |
| temperature of 55 degrees F would be the maximum that would support the |
| previously assumed ESF operation Turbine Building header flow at 2000 gpm. |
| Current accident analysis assumes that ESF equipment will remain operable up |
| to 80 degrees F lake water while supplying the Turbine Building header." |
| |
| "Kewaunee will continue to review available and previously assumed |
| analytical data to determine what plant operational limitations may apply |
| and or what changes may be necessary to support a return to power operation. |
| The current schedule for the refueling outage includes a return to power |
| operation on December 5, 2001." |
| |
| The licensee stated that the unit is currently defueled as part of the |
| ongoing refueling outage. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 38368 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 10/09/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 15:25[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 10/09/2001|
+------------------------------------------------+EVENT TIME: 13:15[CDT]|
| NRC NOTIFIED BY: JAMES McKAY |LAST UPDATE DATE: 10/09/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| OFFSITE NOTIFICATION DUE TO GASOLINE SPILL OUTSIDE THE PROTECTED AREA |
| |
| The licensee was filling a company minivan with gasoline when the automatic |
| shut-off valve stuck and an uncontained spill occurred of greater than 5 |
| gallons and less than 50 gallons. This occurred outside of the protected |
| area. The licensee is conducting cleaning efforts in accordance with proper |
| procedures. |
| |
| The licensee notified the state and local authorities concerning the spill, |
| making this notification necessary. The licensee notified the NRC Resident |
| Inspector. |
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|Power Reactor |Event Number: 38369 |
+------------------------------------------------------------------------------+
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/09/2001|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 21:27[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 10/09/2001|
+------------------------------------------------+EVENT TIME: 18:20[EDT]|
| NRC NOTIFIED BY: BRYAN FERGUSON |LAST UPDATE DATE: 10/09/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN BONSER, REG 2 IRC |
|10 CFR SECTION: | |
|AMED 50.72(b)(3)(xii) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| TRANSPORT OF A RADIOACTIVELY CONTAMINATED PERSON TO AN OFFSITE MEDICAL |
| FACILITY FOR TREATMENT |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On October 09, 2001, a contract worker injured his leg while working in the |
| Reactor Building at Crystal River Unit 3. The injury required the worker to |
| be transported offsite to a local medical facility. A Health Physics |
| technician accompanied the individual to the medical facility since he was |
| potentially contaminated. The subsequent survey found radioactive |
| contamination on the individual's clothing and on the backboard used for |
| transport. The Health Physics technician took custody of the contaminated |
| material and returned it to Crystal River Unit 3." |
| |
| "This is reportable as an 8-hour report under 10 CFR 50.72(b)(3)(xii), 'any |
| event requiring the transport of a radioactively contaminated person to an |
| offsite medical facility for treatment.' " |
| |
| The licensee notified the NRC resident inspector. |
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