Event Notification Report for December 16, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/13/2002 - 12/16/2002
** EVENT NUMBERS **
39303 39381 39443 39444 39445 39446 39447 39448
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39303 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/19/2002|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 05:27[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/18/2002|
+------------------------------------------------+EVENT TIME: 21:30[CDT]|
| NRC NOTIFIED BY: JOHN LECHMAIER |LAST UPDATE DATE: 12/13/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(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
+------------------------------------------------------------------------------+
| RCIC HIGH STEAM FLOW ISOLATION INSTRUMENTATION INOPERABLE DUE TO BEING OUT |
| OF TOLERANCE |
| |
| "At 2130 hours CDT on 10/18/2002, the U1 RCIC High Steam Flow Isolation |
| Instrumentation was determined to have been inoperable. Both U1 RCIC High |
| Steam Flow switches were found to be outside their Technical Specification |
| Allowable Value during a calibration surveillance. Both U1 RCIC High Steam |
| Flow switches were subsequently recalibrated back to within their Technical |
| Specification Allowable Value. |
| |
| "This notification is being made in accordance with 10CFR50.72(b)(3)." |
| |
| The NRC Resident Inspector has been notified. |
| |
| * * * UPDATE 1145EST ON 12/13/02 FROM RON RUSTICK TO S. SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| "The purpose of this notification is to retract the ENS report made on |
| 10/19/2002 at 05:27 EDT (Event #39303). The initial report concerned the |
| Reactor Core Isolation Cooling (RCIC) system high steam flow isolation |
| function. On 10/18/2002, both required high steam flow isolation instruments |
| were found to be outside of their Technical Specifications Allowable Value |
| (AV); therefore, a notification was made under 10CFR50.72(b)(3)(V)(D). |
| However, a subsequent review of this event has determined that only one of |
| the two required channels actually exceeded the AV and thus one channel was |
| OPERABLE and capable of initiating the isolation function (i.e., there was |
| no loss of safety function). For this reason, Quad Cities Station has |
| concluded that the RCIC high steam flow isolation function was preserved." |
| |
| The licensee informed the NRC resident inspector. Notified R3DO(Hiland). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39381 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/17/2002|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 15:38[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/17/2002|
+------------------------------------------------+EVENT TIME: 13:06[EST]|
| NRC NOTIFIED BY: RICHARD STONE |LAST UPDATE DATE: 12/13/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LEONARD WERT R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(3)(v)(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
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE DURING QUARTERLY SURVEILLANCE TESTING |
| |
| "Unit 1 High Pressure Coolant Injection (HPCI) flow controller indicates 512 |
| GPM with system in standby. Found when aligning system for surveillance. |
| Cannot assure system will achieve rated flow automatically. HPCI is a |
| single train system." |
| |
| HPCI was declared inoperable placing Unit 1 in a 14-day LCO A/S 3.5.1. The |
| licensee intends to troubleshoot the problem including a fill/vent of the |
| applicable flow transmitter. The licensee will inform the NRC resident |
| inspector. |
| |
| * * * RETRACTION ON 12/13/02 AT 0958 EST FROM HARRY RUSSELL TO GERRY WAIG * |
| * * |
| |
| The investigation of the problem noted in Report 39381 reported 11/17/2002 |
| was determined to be setpoint drift of transmitter 1E41N008 and not an |
| inoperable controller. Because this transmitter receives an input of |
| differential pressure and the milliamp output is converted to flow using a |
| square root function the amount of error in the flow rate measurement is not |
| linear throughout the span of the transmitter. The plant has confirmed that |
| the "as found" setpoint drift of this single flow measuring device would |
| still have allowed the affected flow controller to perform its safety |
| function and control flow negligibly lower than the design flowrate (4220 |
| versus 4250 gpm), thereby continuing to allow HPCI to fulfill its safety |
| function. It did not involve a failure of the flow measuring device and |
| would therefore not be indicative of a generic failure problem with similar |
| flow measuring devices on other systems. The HPCI system was operable in its |
| "as found" condition. Based on the guidance in NUREG 1022, Revision 2, this |
| setpoint drift of 1E41N008 is not reportable. |
| |
| Notified R2DO (Mike Ernstes). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39443 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/13/2002|
| UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 10:25[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 12/13/2002|
+------------------------------------------------+EVENT TIME: 08:30[EST]|
| NRC NOTIFIED BY: LOUIS NOWELL |LAST UPDATE DATE: 12/13/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MIKE ERNSTES R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF MORE THAN 25% OF THE STATIONS ALERT SIRENS |
| |
| "Loss of more than 25% of the stations total alert sirens have been disabled |
| for more than one hour (0830-0930) due to a loss of power. This was due to |
| severe weather." |
| |
| The loss of alert sirens affects offsite response/notification. Efforts to |
| restore power to the sirens are in progress at this time. |
| |
| The licensee has notified the NRC Resident Inspector of this event. |
| |
| **** UPDATE on December 13, 2002 at 1500 Hours by Louis Nowell taken by |
| MacKinnon **** |
| |
| Less than 25% of the stations total alert sirens are disabled due to a power |
| loss. NRC R2DO (Mike Ernstes) notified. |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39444 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 12/13/2002|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 17:04[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/13/2002|
+------------------------------------------------+EVENT TIME: 14:50[EST]|
| NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 12/13/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID LEW R1 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO DIESEL FUEL SPILL |
| |
| "At 1450 EST on 12/13/2002, Susquehanna LLC Main Control Room received a |
| request for additional information from the Pennsylvania Emergency |
| Management Agency (PEMA). PEMA received rumors that a HAZMAT team had been |
| dispatched to Susquehanna in response to a spill associated with a potential |
| sabotage event. |
| |
| "At 1158 EST a delivery truck at the owner controlled entrance gate was |
| identified to have a saddle tank leak which resulted in a spill of |
| approximately 10 gallons. The diesel fuel was contained by site personnel, |
| and is in the process of being cleaned by site personnel. None of the oil |
| reached a waterway, and therefore does not meet the requirements for a |
| reportable spill. The delivery company contacted their contracted spill |
| response team, and they responded to the site. They were subsequently |
| released without performing any of the cleanup activities. The minor spill |
| was not due to sabotage. This information has been provided to PEMA. |
| |
| "This report is being issued due to the involvement of other government |
| agencies, and reportable under 10CFR50.72(b)(2)(xi)." |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39445 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 12/14/2002|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 09:11[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/14/2002|
+------------------------------------------------+EVENT TIME: 04:20[CST]|
| NRC NOTIFIED BY: DAVID LANTZ |LAST UPDATE DATE: 12/14/2002|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP ON OTDT DURING DOWNPOWER |
| |
| "At 0420 on 12/14/02, a valid actuation signal was generated that caused an |
| Overtemperature Delta T (OTDT) Reactor Trip. The cause of the OTDT trip was |
| a downpower at 1% per minute due to an oil leak on the 'C' Condensate Pump. |
| A valid actuation signal was generated for the Auxiliary Feedwater Actuation |
| System (AFAS), the Feedwater Isolation System (FWIS) and the Steam Generator |
| Blowdown System Isolation System (SGBSIS) due to Steam Generator Low Levels. |
| After the Turbine Driven Auxiliary Feedwater Actuation Signal (AFAS) was |
| reset, a second AFAS was received and the Turbine Driven Auxiliary Pump |
| failed to start. All other systems functioned as expected. |
| |
| "An Event Review Team (ERT) has been assembled to determine the cause of the |
| event. Additional corrective action to be taken will be based upon |
| recommendations provided by the ERT. |
| |
| "The Senior NRC Resident Inspector has been notified of the event." |
| |
| Both motor driven Auxiliary Feedwater Pumps are in service currently |
| maintaining SG levels. The Main Condenser is available for removal of |
| decay heat via the Main Steam Dump Bypass. All rods fully inserted. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39446 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 12/15/2002|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 06:28[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 12/15/2002|
+------------------------------------------------+EVENT TIME: 02:30[EST]|
| NRC NOTIFIED BY: ALLEN RABENOLD |LAST UPDATE DATE: 12/15/2002|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY - LICENSED OPERATOR UNFIT FOR SCHEDULED WORK |
| |
| Licensed employee was determined to be under the influence of alcohol during |
| a 'for cause' test, did not assume any shift duties and his plant access has |
| been terminated. Contact HOO for additional details. |
| |
| Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Transportation |Event Number: 39447 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: SYNCOR INTERNATIONAL CORP. |NOTIFICATION DATE: 12/15/2002|
|LICENSEE: SYNCOR INTERNATIONAL CORP. |NOTIFICATION TIME: 08:40[EST]|
| CITY: GLASTONBURY REGION: 1 |EVENT DATE: 12/15/2002|
| COUNTY: STATE: CT |EVENT TIME: 05:00[EST]|
|LICENSE#: 04-26507-01MD AGREEMENT: N |LAST UPDATE DATE: 12/15/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID LEW R1 |
| |TOM ESSIG NMSS |
+------------------------------------------------+CREWS DOT |
| NRC NOTIFIED BY: MATT SVEJK | |
| HQ OPS OFFICER: ARLON COSTA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Tc-99m CANISTERS UNDAMAGED DURING TRANSPORTATION ACCIDENT |
| |
| The NRC Operations Center was notified by the Connecticut Department of |
| Environmental Protection (CT DEP) that an vehicle accident involving a |
| Syncor delivery to local hospitals and pharmacies had occurred. A follow-up |
| discussion with the Radiation Safety Officer (RSO) for Syncor International |
| Corporation located at 628 Hebron Avenue, Bldg.4, Glastonbury, CT 06033, |
| provided detailed information related to the incident. The company vehicle |
| (pickup truck) accidentally rolled over after encountering a patch of black |
| ice. Eight canisters (ammo box style) were ejected from the vehicle bed |
| during the accident at Route 6 and State Road 384 in Coventry, Connecticut. |
| The company driver was in the process of picking up and delivering the |
| canisters which house Tc-99m syringes (unit dose) that are enclosed in lead |
| pigs. Both the local police and fire departments and the CT DEP responded |
| to the accident which happened at approximately 0500 EST on 12/15/02. The |
| driver was taken to a local hospital for routine x-rays and treatment. The |
| initial assessment of the incident was that the canisters were not breached. |
| No contamination was detected by the first responders. Syncor will follow |
| up with measurements of the swipes using Multi-Channel Analyzer |
| methodology. |
| |
| |
| * * * UPDATE AT 10:18 ON 12/15/02 FROM MATT SVEJK TO ARLON COSTA * * * |
| |
| The test results of the wiped canisters using a Multi-Channel Analyzer did |
| not indicate any counts above background. The total Tc-99m activity of the |
| five active canisters (the other three were return canisters) was |
| approximately 1,137 millicuries (assay estimate as of 0500 EST on 12/15/02). |
| Notified R1DO(Lew) and NMSS(Essig). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39448 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 12/15/2002|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 21:18[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/15/2002|
+------------------------------------------------+EVENT TIME: 18:08[CST]|
| NRC NOTIFIED BY: GREG JANEK |LAST UPDATE DATE: 12/15/2002|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO HIGH MAIN TURBINE VIBRATIONS |
| |
| "At 18:08 on 12/15/02, the reactor was manually tripped due to high |
| vibrations on the Main Turbine. Investigation into the cause of the Main |
| Turbine high vibrations is in progress. |
| |
| "This is being reported under 10CFR50.72(b)(2)(iv)(b). |
| |
| "During the reactor trip, all control rods fully inserted. Auxiliary |
| Feedwater System automatically actuated as expected on low-low steam |
| generator water level, Main Condenser Vacuum was secured to reduce Main |
| Turbine speed quicker, Main Steam isolation was manually actuated, and the |
| Steam Generator Power Operated Relief Valves automatically opened to |
| maintain primary system temperature. |
| |
| "Primary System temperature and pressure is being maintained at 573 |
| degrees/2235 psig. |
| |
| |
| "Technical Specification 3.7.1.3 was entered at 18:11 due to Auxiliary |
| Feedwater Storage Tank level less than the minimum required level of 485,000 |
| gallons. This requires the level to be restored to above required limit |
| within 4 hours or be in Hot Standby within the next 6 hours. Currently |
| makeup to the storage tank is in progress." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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