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Event Notification Report for March 3, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           02/28/2003 - 03/03/2003



                              ** EVENT NUMBERS **



39627  39628  39629  39630  39631  



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|Power Reactor                                    |Event Number:   39627       |

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| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 02/28/2003|

|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 14:10[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/28/2003|

+------------------------------------------------+EVENT TIME:        08:57[CST]|

| NRC NOTIFIED BY:  PETER DONAHUE                |LAST UPDATE DATE:  02/28/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID GRAVES         R4      |

|10 CFR SECTION:                                 |                             |

|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |

|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          N       0        Cold Shutdown    |0        Cold Shutdown    |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| LESS THAN THE REQUIRED NUMBER OF OPERABLE EMERGENCY DIESEL GENERATORS        |

|                                                                              |

| "While the plant was in cold shutdown, the division number 2 onsite          |

| emergency power (diesel generator) was made inoperable when it was           |

| discovered that the time delay relay, which energizes to cause the           |

| associated room cooling system to start when the diesel generator            |

| automatically initiates or the temperature in the room reaches 104 degrees   |

| F, was not replaced before exceeding it's analyzed service life. The         |

| division number 1 onsite emergency power (diesel generator) was already      |

| inoperable when the fuel oil transfer pump flow was found to be less than    |

| required while performing a technical specification surveillance test.       |

|                                                                              |

| "Technical Specification Limiting Condition of Operation (LCO) [3.8.2] for   |

| AC Sources during shutdown was entered. This LCO is required to be entered   |

| when one diesel generator is not capable of supplying one division of the    |

| onsite Class 1E AC electrical power distribution subsystem(s) to support     |

| equipment required to be operable. The following actions were immediately    |

| taken in accordance with this LCO and will remain in place until the LCO can |

| be met:                                                                      |

|                                                                              |

| 1. Core alterations are not allowed.                                         |

| 2. Movement of irradiated fuel assemblies iii secondary containment is not   |

| allowed.                                                                     |

| 3. Operations with the potential to drain the reactor vessel are not         |

| allowed.                                                                     |

| 4. Replacement of the subject relay was initiated.                           |

|                                                                              |

| "No fuel movement, core alterations or operations with the potential to      |

| drain the reactor vessel were in progress.                                   |

|                                                                              |

| "All offsite power sources are available and operable. No maintenance will   |

| be conducted which could potentially affect the availability of these        |

| offsite sources or the associated distribution systems."                     |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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|Hospital                                         |Event Number:   39628       |

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| REP ORG:  THOMAS JEFFERSON UNIV HOSPITAL       |NOTIFICATION DATE: 02/28/2003|

|LICENSEE:  THOMAS JEFFERSON UNIV HOSPITAL       |NOTIFICATION TIME: 15:52[EST]|

|    CITY:  PHILADELPHIA             REGION:  1  |EVENT DATE:        01/28/2003|

|  COUNTY:                            STATE:  PA |EVENT TIME:        13:00[EST]|

|LICENSE#:  37-00148-06           AGREEMENT:  N  |LAST UPDATE DATE:  02/28/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |JOHN KINNEMAN        R1      |

|                                                |FRED BROWN           NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  JOHN KEKLAK                  |                             |

|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BLO2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| 1.3 MILLICURIES SULPHUR-35 SOURCE INADVERTENTLY DISCARDED AS REFUSE          |

|                                                                              |

| On 1/20/03 a package was delivered from PerkinElmer Lifesciences located in  |

| Boston, MA to the Thomas Jefferson University Hospital.  The package         |

| included two (2) medical isotopes used in research; 1.3 millicuries          |

| Sulphur-35 (Half-life 87.4 days) and 250 microcuries Tritiated Thymidine.    |

| The package was shipped as excepted quantity not subject to external         |

| labeling.  A lab worker sometime between 1/23 and 1/24 discarded the package |

| containing the two sources as trash which was collected on 1/27 at           |

| approximately 0500 hours and taken to the landfill.                          |

|                                                                              |

| The licensee conducted interviews emphasizing prompt handling, good          |

| communication and individual responsibility to prevent recurrence.           |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39629       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 03/01/2003|

|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 05:39[EST]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/01/2003|

+------------------------------------------------+EVENT TIME:        01:54[CST]|

| NRC NOTIFIED BY:  SCHAEFER                     |LAST UPDATE DATE:  03/01/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID GRAVES         R4      |

|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   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     M/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| REACTOR MANUALLY TRIPPED FROM 100% POWER                                     |

|                                                                              |

| The Operators manually trip the reactor from 100% power following a loss of  |

| condensate flow in the secondary system.  The cause is unknown and being     |

| investigated.  All rods fully inserted and no relief valves lifted.          |

| However, the auxiliary feedwater and feedwater actuations were received      |

| following the trip as expected.  The reactor is in hot standby.              |

|                                                                              |

|                                                                              |

| The NRC resident Inspector was notified.                                     |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39630       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 03/02/2003|

|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 10:43[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        03/02/2003|

+------------------------------------------------+EVENT TIME:        03:35[CST]|

| NRC NOTIFIED BY:  LONG                         |LAST UPDATE DATE:  03/02/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID GRAVES         R4      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| PRIMARY CONTAINMENT MEASURED LEAKAGE EXCEEDS THE ALLOWED LEAKAGE.            |

|                                                                              |

| During routine scheduled LLRT (Local Leak Rate Testing) of Penetration       |

| X-214,  HPCI (High Pressure Coolant Injection) Exhaust Discharge to the      |

| Torus, leakage was unable to be quantified.   Additionally, of the two       |

| isolation check valves in the line, which one was leaking was unable to be   |

| determined.   As such, Primary Containment Allowed Leakage (La) is unable to |

| be verified to be less than allowed.                                         |

|                                                                              |

| The plant was in Mode 4 (Cold S/D) for a scheduled refueling outage with     |

| temperature being maintained between 130 and 145 degrees Fahrenheit and      |

| Primary Containment not required at the time of discovery.  The plant will   |

| remain in cold shutdown until repairs are completed.                         |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39631       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 03/02/2003|

|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 16:00[EST]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        03/02/2003|

+------------------------------------------------+EVENT TIME:        14:30[EST]|

| NRC NOTIFIED BY:  CHARLES PIKE                 |LAST UPDATE DATE:  03/02/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |WALTER RODGERS       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  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| OFFSITE NOTIFICATION TO STATE AGENCY OF EXPIRED GREEN SEA TURTLE FOUND AT    |

| BARRIER NET                                                                  |

|                                                                              |

| "NRC notification[is] being made due to state notification to [the] Florida  |

| Wildlife Commission regarding a Green Sea Turtle found dead at barrier net   |

| pursuant to 10 CFR 50.72(b)(2)(xi)."                                         |

|                                                                              |

| The turtle was found on the surface at the barrier net with no injuries or   |

| abnormalities except for fresh cuts common for turtles coming through pipes. |

| The cause of death is unknown at this time. A necropsy is planned.           |

|                                                                              |

| The NRC Resident Inspector will be notified by the licensee.                 |

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