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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|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.                            |
+------------------------------------------------------------------------------+