United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2003 > May 20

Event Notification Report for May 20, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           05/19/2003 - 05/20/2003



                              ** EVENT NUMBERS **



39680  39850  39857  39858  39859  39860  39861  39862  



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|Power Reactor                                    |Event Number:   39680       |

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

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

| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 03/19/2003|

|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 18:16[EST]|

|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/19/2003|

+------------------------------------------------+EVENT TIME:        11:04[CST]|

| NRC NOTIFIED BY:  E. HENSEN                    |LAST UPDATE DATE:  05/19/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |CLAUDE JOHNSON       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          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| HATCH MODIFICATION COULD HAVE IMPACTED COMPLETION OF A CONTROL ROOM          |

| EVACUATION                                                                   |

|                                                                              |

| "At 1104, 3/19/03, while operating at 100% power, Callaway Plant discovered  |

| that a modification performed on an equipment hatch impacted the ability to  |

| complete a Control Room evacuation in the event of a fire.  The modification |

| had installed a hatch in a floor penetration between elevations that had a   |

| latching mechanism installed on the bottom side of the hatch but the         |

| associated T-handle was not initially installed on top of the hatch.  The    |

| latch mechanism could still be operated from the top via a large opening in  |

| the hatch where a ladder passed through the hatch.  This modification could  |

| have resulted in the inability to access the area and valves below the hatch |

| that would require manipulation during a Control Room evacuation.   When     |

| this problem was identified, a T-handle was installed on top of the hatch    |

| for operating the latching mechanism and resolved the situation.             |

|                                                                              |

| "This event affects our commitment for the Control Room Fire Safe Shutdown   |

| analysis and is being reported as an unanalyzed condition per                |

| 10CFR50.72(b)(3)(ii)(B)."                                                    |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

|                                                                              |

| Notified R4DO (C. Johnson)                                                   |

|                                                                              |

| * * * RETRACTION ON 5/19/03 AT 1451 EDT FROM TIM HOLLAND TO E. THOMAS * * *  |

|                                                                              |

| "This event is being retracted.  Upon further Engineering evaluation, it was |

| determined that there was sufficient time to allow using an alternate route  |

| to access and operate the valve located on the elevation below the equipment |

| hatch.  Thus this event did not represent an unanalyzed condition and is not |

| reportable."                                                                 |

|                                                                              |

| Notified R4DO (T. Pruett)                                                    |

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



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

|General Information or Other                     |Event Number:   39850       |

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

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

| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 05/15/2003|

|LICENSEE:  BLAZER INDUSTRIAL RADIOGRAPHY        |NOTIFICATION TIME: 12:18[EDT]|

|    CITY:  PASADENA                 REGION:  4  |EVENT DATE:        05/14/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        18:48[CDT]|

|LICENSE#:  LO4619                AGREEMENT:  Y  |LAST UPDATE DATE:  05/16/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |WILLIAM JOHNSON      R4      |

|                                                |TOM ESSIG            NMSS    |

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

| NRC NOTIFIED BY:  HELEN WATKINS                |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| AGREEMENT STATE REPORT                                                       |

|                                                                              |

| The licensee reported a potential overexposure to a radiographer who was     |

| x-raying some pipes at a worksite.  After completing a section of piping,    |

| the radiographer should have cranked his source back in, but was interrupted |

| by another technician and left his work area.  When he returned, the         |

| radiographer changed out his film, and moved the guide tube to another       |

| section of piping to begin more x-rays.  At this point, he realized that his |

| survey meter had pegged high, and remembered that he had not cranked the     |

| source back in prior to moving it.  He proceeded to immediately crank the    |

| source back to its fully shielded position.  The exact time and distance     |

| from the source for the radiographer's exposure is unknown, and the licensee |

| is attempting to re-create the scenario.                                     |

|                                                                              |

| The source was 26 Curies of Iridium 192, model number INC-32.  The serial    |

| number is unknown at this time.  A preliminary investigation by the licensee |

| estimates the radiographer's exposure to 800-900 millirem whole body.  There |

| is currently no exposure estimate for his hands/extremities.                 |

|                                                                              |

| The radiographer's badge was sent off for processing.  Results will be       |

| reported on 5/16/03 to the NRC.  The Texas Department of Health is sending   |

| an additional inspector to the site to investigate.                          |

|                                                                              |

|                                                                              |

| * * * UPDATE ON 5/16/03  @ 1120 BY  WATKINS TO GOULD * * *                   |

|                                                                              |

| Blazer Industrial Radiography brought in a consultant to perform preliminary |

| dose calculations for the whole body and the right hand of the radiographer. |

| The results were 1.3R for the whole body and 37.1R for the right hand,       |

| neither of which exceeds the annual regulatory limit.                        |

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



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

|Power Reactor                                    |Event Number:   39857       |

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

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

| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/19/2003|

|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 05:57[EDT]|

|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/19/2003|

+------------------------------------------------+EVENT TIME:        04:24[EDT]|

| NRC NOTIFIED BY:  MARTIN MANPENFEL             |LAST UPDATE DATE:  05/19/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |BRIAN MCDERMOTT      R1      |

|10 CFR SECTION:                                 |TERRY REIS           NRR     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|RICHARD WESSMAN      IRO     |

|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       3        Startup          |0        Startup          |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| AUTOMATIC REACTOR SCRAM RESULTING IN  PRIMARY CONTAINMENT AND REACTOR        |

| BUILDING ISOLATIONS                                                          |

|                                                                              |

| At 0424 EDT, during startup operations, the Main Turbine Bypass valves       |

| unexpectedly opened and depressurized the reactor vessel.  After             |

| depressurization, the reactor level increased due to swell and caused an     |

| automatic reactor scram.  Additionally, there was a Reactor Building         |

| Isolation Signal and Group I, II, and VI Primary Containment Isolation       |

| Signal generated.  Immediately after the automatic scram,  five control rods |

| failed to insert into the core.  Plant operations personnel performed        |

| actions in accordance with their Emergency Operating Procedures to drive the |

| control rods into the core.  According to the licensee, adequate shutdown    |

| margin was always maintained.                                                |

|                                                                              |

| The plant electrical system is stable with plant equipment being powered     |

| from offsite and the startup transformer.  Reactor pressure and level are    |

| being maintained via steam line drains to the main condenser.                |

|                                                                              |

| Troubleshooting of the Main Turbine Bypass valves/control system is in       |

| progress.                                                                    |

|                                                                              |

| The licensee will be notifying the NRC Resident Inspector.                   |

|                                                                              |

| * * * UPDATE ON 5/19/03 @ 0957 EDT FROM ERIC OLSON TO CROUCH * * *           |

|                                                                              |

| The following clarification of the above information was received from the   |

| licensee via facsimile:                                                      |

|                                                                              |

| "At 04:24 EDT, during startup operations, the Main Turbine Bypass Valves     |

| failed open.  At the beginning of the event reactor pressure was             |

| approximately 880 psig.  When the Main Turbine Bypass Valves opened, reactor |

| pressure lowered to approximately 820 psi and reactor water level swelled    |

| (due to voiding) from 28 inches to approximately 55 inches.  This resulted   |

| in a Group I PCIS [Primary Containment Isolation Signal] being generated as  |

| designed and automatically closing the MSIV's [Main Steam Isolation Valves]. |

| MSIV closure terminated the depressurization, however initiated an automatic |

| RPS [Reactor Protection System] signal as designed.  Termination of          |

| depressurization resulted in reactor level lowering to approximately 7       |

| inches which in turn initiated a Group II (Containment Isolation) and Group  |

| VI (Reactor Water Cleanup Isolation) PCIS signals.  All rods inserted during |

| the scram, however five control rods went beyond full in.  Actions were      |

| taken in accordance with EOP's [Emergency Operating Procedures] and plant    |

| operating procedures to verify the five control rods were beyond full in.    |

| This is an indication issue with control rods that can occur when a scram    |

| signal is present and the Control Rod Drive System charging water flow       |

| drives the control rods beyond the [zero] and full in reed switches.         |

|                                                                              |

| "The plant electrical system is stable with plant equipment being powered    |

| from offsite power via the startup transformer.  Reactor pressure is being   |

| maintained by steam line drains to the main condenser.   Reactor water level |

| is being maintained with normal feed and condensate system.                  |

|                                                                              |

| "Troubleshooting of the Main Turbine Bypass Valve/Control system is in       |

| progress.                                                                    |

|                                                                              |

| "The [NRC] Resident Inspector has been notified."                            |

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



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

|Power Reactor                                    |Event Number:   39858       |

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

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

| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 05/19/2003|

|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 09:43[EDT]|

|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        05/19/2003|

+------------------------------------------------+EVENT TIME:        05:18[CDT]|

| NRC NOTIFIED BY:  JONATHAN ROBB                |LAST UPDATE DATE:  05/19/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANNE MARIE STONE     R3      |

|10 CFR SECTION:                                 |                             |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|1     N          Y       100      Power Operation  |97       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| PLANT COMMENCED TECH SPEC REQUIRED SHUTDOWN                                  |

|                                                                              |

| The following information was received from the licensee via facsimile:      |

|                                                                              |

| "At 0323 [CDT] on May 19th an Individual Rod Position Indication (IRPI) of   |

| control bank D exceeded 12 steps from its bank demand position.  At 0418 an  |

| additional IRPI of control bank D exceeded 12 steps from its bank demand     |

| position, at which time the two IRPI indications were declared inoperable.   |

| At 0518 the plant initiated a Standard Shutdown Sequence as required by the  |

| plant's Technical Specifications (TS 3.10.f.2) since two IRPI's in a group   |

| were out of service.  At 0530 the two IRPI were within 12 steps of the bank  |

| demand position and therefore the shutdown sequence was exited. Power is     |

| being held at 97% to investigate.                                            |

|                                                                              |

| "This is a 4-hour. Notification made in accordance with                      |

| 10CFR50.72(b)(2)(i)."                                                        |

|                                                                              |

| Initially, rod G-3 indication was greater than 12 steps from the bank demand |

| position.  Then rod G-11 indication drifted greater than 12 steps from the   |

| bank demand position.  Currently, power in stable at 97% with G-3 indicating |

| 198 steps and G-11 indicating 204 steps and bank demand position at 202      |

| steps.                                                                       |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

|                                                                              |

| * * * UPDATE AT 1540 EDT ON 5/19/03 FROM JONATHAN ROBB TO E.THOMAS * * *     |

|                                                                              |

| Mr. Robb called back to clarify that IRPI indication deviated gradually from |

| bank rod position as the bank was withdrawn, and as power and Tavg were      |

| increased.                                                                   |

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



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

|Power Reactor                                    |Event Number:   39859       |

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

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

| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 05/19/2003|

|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 10:32[EDT]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        05/19/2003|

+------------------------------------------------+EVENT TIME:        09:05[EDT]|

| NRC NOTIFIED BY:  GEORGE TULLIDGE              |LAST UPDATE DATE:  05/19/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|10 CFR SECTION:                                 |                             |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |

|NONR                     OTHER UNSPEC REQMNT    |                             |

|                                                |                             |

|                                                |                             |

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

|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          N       0        Refueling        |0        Refueling        |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| MANATEE TRAPPED IN THE INTAKE CANAL                                          |

|                                                                              |

| The following information was received from the licensee via facsimile:      |

|                                                                              |

| "Notification being made due to a State Notification (Florida Fish and       |

| Wildlife Commission - Bureau of Protected Species) at 0905 [EDT].  (10 CFR   |

| 50.72 (b)(2)).                                                               |

|                                                                              |

| "State notification made due to a Manatee trapped in the Intake Canal.  The  |

| animal appears to be in good condition and State personnel are [en route] to |

| assist in removal and release.                                               |

|                                                                              |

| "This notification includes requirements per St. Lucie Environmental         |

| Protection Plan Technical Specifications, Appendix B, section 4.1.  This is  |

| a 72-hr notification for unusual occurrence of any species protected by the  |

| Endangered Species Act of 1973."                                             |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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



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

|Other Nuclear Material                           |Event Number:   39860       |

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

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

| REP ORG:  GIBRALTAR PLASTIC CORPORATION        |NOTIFICATION DATE: 05/19/2003|

|LICENSEE:  GIBRALTAR PLASTIC CORPORATION        |NOTIFICATION TIME: 12:58[EDT]|

|    CITY:  LODI                     REGION:  1  |EVENT DATE:        05/19/2003|

|  COUNTY:                            STATE:  NJ |EVENT TIME:        09:30[EDT]|

|LICENSE#:  29-18454-02           AGREEMENT:  N  |LAST UPDATE DATE:  05/19/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |ANTHONY DIMITRIADIS  R1      |

|                                                |THOMAS ESSIG         NMSS    |

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

| NRC NOTIFIED BY:  JERRY WIZA                   |                             |

|  HQ OPS OFFICER:  ARLON COSTA                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BSUR 20.1906(d)(1)       SURFACE CONTAM LEVELS >|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| SURFACE CONTAMINATION LEVELS ON SOURCE IS GREATER THAN LIMITS                |

|                                                                              |

| The licensee was packaging eleven cesium sources for shipment to Adco        |

| Services Incorporated.  Upon surveying the sources, the contractor found     |

| that one Cs-137 source, Model No.S-4, Serial No.485 indicated field testing  |

| contaminations above 0.005 microcuries (exposure rate greater than 0.5       |

| mR/h).  The source activity is believed to be approximately 10.2             |

| millicuries.  This contaminated source will be packaged as dry waste in      |

| certified type A containers and will be shipped for disposal . The cabinet   |

| where the source was stored was contaminated and will also be packed and     |

| shipped for disposal.                                                        |

|                                                                              |

| The licensee contacted Region 1 (D. White).                                  |

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



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

|Other Nuclear Material                           |Event Number:   39861       |

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

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

| REP ORG:  ILLINOIS DEPARTMENT OF NUC. SAFETY   |NOTIFICATION DATE: 05/19/2003|

|LICENSEE:  NELSON LEASING                       |NOTIFICATION TIME: 16:30[EDT]|

|    CITY:  WHEELING                 REGION:  3  |EVENT DATE:        05/17/2003|

|  COUNTY:                            STATE:  IL |EVENT TIME:        18:45[CDT]|

|LICENSE#:  IL-01828-01           AGREEMENT:  Y  |LAST UPDATE DATE:  05/19/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |ANNE MARIE STONE     R3      |

|                                                |                             |

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

| NRC NOTIFIED BY:  JOE KLINGER                  |                             |

|  HQ OPS OFFICER:  ARLON COSTA                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE               |

|                                                                              |

| "On Saturday, May 17, at approximately 1845 hrs a Troxler moisture/density   |

| gauge Model # 3440, serial no. 21948, was stolen from a licensee's locked    |

| truck while it was parked in a parking lot at 105 N. Des Plaines, in         |

| Chicago.  The licensee's technician stopped on his way home from work at     |

| this location and noticed, upon returning to his vehicle, that the rear hard |

| cover, locked hatch had been broken into.  Upon further inspection, the      |

| technician noticed that the locked and chained nuclear gauge had been taken. |

| Immediately following this discovery, the Chicago Police Department was      |

| notified along with the licensee's Radiation Safety Officer/President, Scott |

| R. Nelson.  Scott Nelson mobilized to the crime scene.  En route he notified |

| the Illinois Department of Nuclear Safety's Radiological Duty Officer, Larry |

| Haskell.  Upon arrival at the scene, Mr. Nelson informed the police of the   |

| gauges operations, potential health issues and completed filing a police     |

| report.  It apparently was evident that the truck was broken into.  The      |

| police report number is HJ-369907.  The station is Area 4."                  |

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



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

|Power Reactor                                    |Event Number:   39862       |

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

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

| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 02:47[EDT]|

|   RXTYPE: [1] GE-2                             |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        00:30[EDT]|

| NRC NOTIFIED BY:  JEFF DOSTAL                  |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY DIMITRIADIS  R1      |

|10 CFR SECTION:                                 |MICHAEL CASE         NRR     |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |RICHARD WESSMAN      IRO     |

|                                                |SAM COLLINS          NRR     |

|                                                |JIM WIGGINS          R1      |

|                                                |NEAL PERRY           R1      |

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

|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                                   

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

| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                          |

|                                                                              |

| The plant experienced a trip of the "C" 4160 V electrical bus.  This         |

| condition required entry into multiple technical specifications the most     |

| limiting being 3.3.D.5.B due to the loss of the capability to determine the  |

| rate of identified containment leakage.  This required the reactor to be     |

| placed in a shutdown condition within the next 12 hours.                     |

|                                                                              |

| The licensee believes that the cause of the "C" bus trip is a fault on the   |

| bus that is indicated as a lockout, however, the specific fault is unknown   |

| at this time and is under investigation.  Due to the faulted bus, the        |

| station's emergency diesel generator did not start and will not be able to   |

| power any equipment on the "C" bus until the fault is repaired.  Significant |

| safety equipment lost due to loss of the bus is as follows:                  |

|                                                                              |

| Emergency Service Water pump and Containment spray system #1                 |

| Service Water pump #1                                                        |

| Reactor Building Closed Cooling pump #1                                      |

| Standby Gas Treatment system #1                                              |

| Core spray and Core spray booster pumps "A" & "D" (4 pumps total)            |

| Standby Liquid Control pump #1                                               |

| Control Rod Drive pump #1                                                    |

|                                                                              |

| The plant is commencing the required shutdown and expect to be at 60%        |

| reactor power by 0430 EDT.                                                   |

|                                                                              |

| The licensee will be notifying the NRC Resident Inspector.                   |

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