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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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38368       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38369       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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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