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Event Notification Report for April 21, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           04/18/2003 - 04/21/2003



                              ** EVENT NUMBERS **



39754  39763  39770  39771  39772  39773  39774  39775  39776  



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

|Power Reactor                                    |Event Number:   39754       |

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

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

| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 04/13/2003|

|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 19:06[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/13/2003|

+------------------------------------------------+EVENT TIME:        16:56[CDT]|

| NRC NOTIFIED BY:  RON GIBBS                    |LAST UPDATE DATE:  04/18/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID LOVELESS       R4      |

|10 CFR SECTION:                                 |                             |

|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

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

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| REACTOR VESSEL BOTTOM HEAD DEGRADED CONDITION                                |

|                                                                              |

| "On 4/12/2003, during the Unit 1 11th (1RE11) refueling outage, an           |

| inspection was performed of the vessel bottom head. This bare metal          |

| inspection identified a potential leak indication at the head to penetration |

| interface for Bottom Mounted Instrumentation (BMI) penetrations 1 and 46.    |

| There was a small amount of residue around the outer circumference of the    |

| BMI penetrations. No wastage was observed. Samples of the residue were taken |

| and the area was cleaned with demineralized water. Chemical sample results   |

| available as of 1300 on 4/13/2003 are not conclusive; however, they have     |

| confirmed that the residue found at the Penetration 46 contains boron,       |

| indicating that this could be an RCS leak. The residue removed from          |

| Penetration 1 was characterized as 'gummy' and its composition is still      |

| under investigation. Additional exams are planned to confirm the likely      |

| origin of the residue and to determine the scope of any repairs. There has   |

| been no indication of RCS leakage observed at the BMI penetrations during    |

| previous operational cycles. This notification is being made in accordance   |

| with 10 CFR 50.72(b)(3)(ii)(A)."                                             |

|                                                                              |

| Unit 1 will remain in mode 5 until appropriate corrective actions are        |

| identified.  The licensee informed the NRC resident inspector.               |

|                                                                              |

| * * * * UPDATE 1151 EDT 04/18/03 FROM WAYNE HARRISON TO MIKE RIPLEY  * * *   |

|                                                                              |

| "STP Nuclear Operating Co. will be making a press release [at 12:00 pm       |

| 04/18/03] concerning the indications found on the Bottom Mounted             |

| Instrumentation penetrations on Unit 1. The release is being coordinated     |

| with NRC Region IV.                                                          |

|                                                                              |

| "STP has notified or will be notifying various federal, state and local      |

| agencies, including FEMA, the governors office, Matagorda County, Bay City.  |

| City of Palacios, state representatives and state senators, US               |

| representatives and US Senators."                                            |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

|                                                                              |

| Notified R3DO (C. Johnson), HQ PAO (W. Beecher)                              |

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



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

|General Information or Other                     |Event Number:   39763       |

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

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

| REP ORG:  MA RADIATION CONTROL PROGRAM         |NOTIFICATION DATE: 04/16/2003|

|LICENSEE:  AEA TECHNOLOGY QSA                   |NOTIFICATION TIME: 10:07[EDT]|

|    CITY:  BURLINGTON               REGION:  1  |EVENT DATE:        04/15/2003|

|  COUNTY:                            STATE:  MA |EVENT TIME:             [EDT]|

|LICENSE#:  12-8361               AGREEMENT:  Y  |LAST UPDATE DATE:  04/16/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |DAVID SILK           R1      |

|                                                |THOMAS ESSIG         NMSS    |

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

| NRC NOTIFIED BY:  BRUCE PACKARD                |                             |

|  HQ OPS OFFICER:  RICH LAURA                   |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| MASSACHUSETTS AGREEMENT STATE REPORT ON SHIPPING PACKAGE RADIOLOGICAL ISSUE  |

|                                                                              |

| "On April 15, 2003, a Yellow-III Package containing 30 millicuries (1.1 Gbq) |

| of Co-60 measured 400 millirem/hr on the surface. The Shipper was AEA        |

| Technology QSA GMBH, Giesilweg 1, D-38110 Braunschweig, Germany. The         |

| carriers included Federal Express Freight and Ground Control. Immediate      |

| reporting requirements means investigation is not complete at the time of    |

| report."                                                                     |

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



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

|Power Reactor                                    |Event Number:   39770       |

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

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

| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 04/18/2003|

|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 16:59[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/18/2003|

+------------------------------------------------+EVENT TIME:        14:08[EDT]|

| NRC NOTIFIED BY:  MICHAEL HOWARD               |LAST UPDATE DATE:  04/18/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        R2      |

|10 CFR SECTION:                                 |SUSIE BLACK          NRR     |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |JOSEPH HOLONICH      IRO     |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|1     N          N       0        Refueling        |0        Refueling        |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| NON- WORK RELATED FATALITY TO CONTRACT EMPLOYEE PROMPTS OFFSITE              |

| NOTIFICATION                                                                 |

|                                                                              |

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

|                                                                              |

| "At approximately 1408 EDT on April 18, 2003, a non-work related medical     |

| emergency occurred at the Sequoyah Nuclear Plant (SNP).  Specifically, a     |

| contract laborer went into cardiac arrest.  The individual was attended to   |

| by SNP Emergency Medical Technicians (EMTs).  The individual was transported |

| off-site in a TVA ambulance and was subsequently transferred to a Hamilton   |

| County ambulance.  The individual was pronounced dead on arrival at the      |

| hospital.  The fatality was not related to the health and safety of the      |

| public or on-site personnel.                                                 |

|                                                                              |

| "The individual was outside of the Radiological Controlled Area and no       |

| radioactive material or contamination was involved.                          |

|                                                                              |

| "A notification was made to the Occupational Safety and Health               |

| Administration at 1555 EDT this date.  This ENS notification is in response  |

| to a notification to a other government agency in accordance with 10 CFR     |

| 50.72(b)(2)(xi)."                                                            |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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



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

|Fuel Cycle Facility                              |Event Number:   39771       |

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

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

| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 04/19/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 00:45[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/18/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:15[EDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/19/2003|

|    CITY:  PIKETON                  REGION:  3  +-----------------------------+

|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |

|LICENSE#:  GDP-2                 AGREEMENT:  N  |THOMAS KOZAK         R3      |

|  DOCKET:  0707002                              |JOHN GREEVES         NMSS    |

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

| NRC NOTIFIED BY:  KURT SISLER                  |                             |

|  HQ OPS OFFICER:  ARLON COSTA                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NONR                     OTHER UNSPEC REQMNT    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| OFFSITE NOTIFICATION TO OHIO EPA OF OPACITY EXCEEDANCE                       |

|                                                                              |

| "On 4/18/03 at 2315 hours, the high pressure blower overload tripped on      |

| X-600 [Steam Plant] #3 boiler.   This equipment failure caused two opacity   |

| readings (six minute average) to be above 20%.  This requires a verbal       |

| notification to the Ohio Environmental Protection Agency (OEPA).             |

|                                                                              |

| "At 2350 hours, the Plant Shift Superintendent notified OEPA of the X-600    |

| Steam Plant opacity exceedance.  UE-RA-RE1030, App. D, section P, requires a |

| 4 hour NRC event [notification] when other government agencies are           |

| notified."                                                                   |

|                                                                              |

| The high pressure blower overload breaker was reset and the #3 boiler is     |

| currently operational.  The Licensee is investigating the cause of the       |

| blower overload trip.                                                        |

|                                                                              |

| The Licensee informed both the NRC Resident Inspector and the DOE Site       |

| Representative.                                                              |

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



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

|Power Reactor                                    |Event Number:   39772       |

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

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

| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 04/19/2003|

|    UNIT:  [] [2] []                 STATE:  MD |NOTIFICATION TIME: 19:33[EDT]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/19/2003|

+------------------------------------------------+EVENT TIME:        15:30[EDT]|

| NRC NOTIFIED BY:  JAMES GROOMS                 |LAST UPDATE DATE:  04/19/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |DAVID SILK           R1      |

|10 CFR SECTION:                                 |                             |

|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     N          N       0        Hot Standby      |0        Hot Standby      |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| REACTOR PROTECTION SYSTEM ACTUATION                                          |

|                                                                              |

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

|                                                                              |

| "While performing STP [Surveillance Test Procedure] M-200-2, the RPS         |

| [Reactor Protection System] S/G [Steam Generator] Low Press[ure] Trip Units  |

| were bypassed using the S/G Low Press[ure] Bypass key.  The bypass was       |

| automatically removed early before the S/G Low Press[ure] trips were         |

| clear[ed].  This resulted in the RPS calling for the TCBs [Trip Circuit      |

| Breakers] to open.  The CEAs [control rods] were already in the core.  This  |

| is an 8 hr. report[able] per [10 CFR] 50.72(b)(3)(iv)(A).  S/G Press[ures]   |

| were [approximately] 700 psi."                                               |

|                                                                              |

| The surveillance test procedure was to allow time response testing on the    |

| trip circuit breakers by the Electrical department (which requires the TCBs  |

| to be closed).  The plant was also performing a plant heatup in preparation  |

| for plant startup.  During normal operations, the S/G Low Pressure Trip      |

| setpoint is 700 psi.  The surveillance test procedure allowed the S/G Low    |

| Pressure Trip to be bypassed via the bypass key.  If the S/G Low Pressure    |

| Trip is keyed to bypass and the S/G pressure increases to greater than 785   |

| psi,  then the 700 psi trip setpoint is automatically re-instated regardless |

| of bypass key position.  The licensee is investigating the reason that the   |

| S/G Low Pressure Trip was automatically re-instated with S/G pressure at     |

| approximately 700 psi.                                                       |

|                                                                              |

| The NRC Resident Inspector has been notified.                                |

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



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

|Power Reactor                                    |Event Number:   39773       |

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

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

| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 04/19/2003|

|    UNIT:  [1] [] []                 STATE:  VA |NOTIFICATION TIME: 23:23[EDT]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/19/2003|

+------------------------------------------------+EVENT TIME:        20:08[EDT]|

| NRC NOTIFIED BY:  BRAD BROWN                   |LAST UPDATE DATE:  04/19/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        R2      |

|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     M/R        Y       74       Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| MANUAL REACTOR TRIP WITH A SUBSEQUENT AUXILIARY FEEDWATER ACTUATION          |

|                                                                              |

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

|                                                                              |

| "A 4 hr. report due to a manual reactor trip (RPS actuation) due to an oil   |

| leak on the main turbine.                                                    |

|                                                                              |

| "An 8 hr. report due to Aux[iliary] Feedwater System initiation due to the   |

| reactor trip (expected response)."                                           |

|                                                                              |

| The manual reactor trip was due to a lube oil leak through the diaphragm on  |

| the EHC (Electro-Hydraulic Control) interface valve.  The leak caused the    |

| interface valve to close therefore isolating EHC hydraulic fluid to the      |

| turbine control system. During the trip, all rods inserted into the core.    |

| As a result of the transient,  a pressurizer power-operated relief valve     |

| lifted and indications show that it subsequently re-seated.  There are no    |

| indications that the blow-out plug on the pressurizer relief tank was        |

| damaged.  Pressurizer relief tank pressure has been reduced to normal.       |

| Additionally,  a secondary tube side relief lifted and was re-seated after   |

| the second running feedwater pump was secured.  Decay heat is being removed  |

| via the steam dump to condenser system operating in automatic.  The          |

| electrical grid is stable and supplying plant loads.  There was no affect on |

| the other operating unit.                                                    |

|                                                                              |

| As expected,  the Auxiliary Feedwater System initiated.  The system has been |

| returned to normal, standby configuration and steam generator level is being |

| controlled by the main feedwater system operating in manual control.         |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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



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

|Power Reactor                                    |Event Number:   39774       |

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

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

| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 04/20/2003|

|    UNIT:  [1] [2] [3]               STATE:  AZ |NOTIFICATION TIME: 05:40[EDT]|

|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        04/20/2003|

+------------------------------------------------+EVENT TIME:        00:00[MST]|

| NRC NOTIFIED BY:  RUSSELL STROUD               |LAST UPDATE DATE:  04/20/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |CLAUDE JOHNSON       R4      |

|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       98       Power Operation  |98       Power Operation  |

|2     N          Y       98       Power Operation  |98       Power Operation  |

|3     N          N       0        Refueling        |0        Refueling        |

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

                                   EVENT TEXT                                   

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

| PALO VERDE SPURIOUS ACTUATION OF OFFSITE EMERGENCY NOTIFICATION SIREN        |

|                                                                              |

| "At 0000 MST on April 20, 2003, the Palo Verde Unit 1 Control Room was       |

| notified of a spurious actuation of an emergency warning siren in the        |

| vicinity of 348th avenue and Buckeye Road.  While not confirmed at this      |

| time, the siren is believed to be siren #17 which is approximately five      |

| miles to the Northeast of Palo Verde.  At approximately 0035 MST, the Unit 1 |

| Control Room was informed [that] the siren was no longer actuating.  This    |

| siren provides emergency notification to approximately 89 members of the     |

| public.                                                                      |

|                                                                              |

| "No press release is planned at this time, however, the event is being       |

| reported due to the inquiry of a citizen to the Energy Control Center (ECC)  |

| and a subsequent notification to the Maricopa County Sheriff's Office.       |

|                                                                              |

| "There is no event in progress and no risk to the health and safety of the   |

| public.  Members of the public within audible range of the siren may have a  |

| concern for their radiological health and safety.                            |

|                                                                              |

| "Unit 1 is at approximately 98% power in Mode 1 at normal operating          |

| temperature and pressure.                                                    |

|                                                                              |

| "Unit 2 is at approximately 98% power in Mode 1 at normal operating          |

| temperature and pressure.                                                    |

|                                                                              |

| "Unit 3 is at 0% [power] in a refueling outage.                              |

|                                                                              |

| "The NRC Sr. Resident Inspector has been informed of the siren actuation and |

| [of] this ENS notification.                                                  |

|                                                                              |

| "Note: The checkbox below for 'OTHER GOV AGENCIES' is referring to the       |

| Maricopa County Sheriff's Office."                                           |

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



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

|Power Reactor                                    |Event Number:   39775       |

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

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

| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 04/20/2003|

|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 16:28[EDT]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        04/20/2003|

+------------------------------------------------+EVENT TIME:        15:13[CDT]|

| NRC NOTIFIED BY:  ROBERT TEMPLE                |LAST UPDATE DATE:  04/20/2003|

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

+------------------------------------------------+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       18       Power Operation  |18       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| LEAK  DISCOVERED ON HIGH PRESSURE CORE INJECTION PIPING DURING SURVEILLANCE  |

| TESTING                                                                      |

|                                                                              |

| "During the performance of STP [Surveillance Test Procedure] 3.5.1-09, HPCI  |

| [High Pressure Core Injection] System Post-Startup Operability Test, on      |

| 4/20/03, a small leak was detected on a  inch pipe nipple on the seal water |

| line on the main HPCI pump. Engineers determined that the leak is from a     |

| small crack at a threaded connection. This piping is ASME class 2 piping.    |

| This leak constitutes a loss of structural integrity of a Class 2 component  |

| as required by section 3.7.3 of the Technical Requirements Manual [TRM].     |

|                                                                              |

| "At 1337 CDT, on 4/20/03, entered T[TRM] LCO [Limiting Condition of          |

| Operation] T3.7.3 condition A, Structural Integrity of Class 1 or Class 2    |

| components not maintained in MODES 1, 2 and 3.                               |

|                                                                              |

| "At 1513 CDT on 4/20/03, the HPCI system was isolated and declared           |

| Inoperable. Entered [Technical Specification] LCO 3.5.1 Condition F, HPCI    |

| System Inoperable, 14 days to restore HPCI. This unplanned HPCI System       |

| inoperability is reportable under 10CFR50.72(b)(3)(v)(d) as a single train   |

| failure that could have prevented the fulfillment of a safety function of    |

| structures or systems designed to mitigate the consequences of an            |

| accident."                                                                   |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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



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

|Power Reactor                                    |Event Number:   39776       |

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

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

| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 04/20/2003|

|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 17:21[EDT]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/20/2003|

+------------------------------------------------+EVENT TIME:        12:35[EDT]|

| NRC NOTIFIED BY:  JOHN DUFF                    |LAST UPDATE DATE:  04/20/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        R2      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

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

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FOR GREATER THAN 1 HOUR       |

|                                                                              |

| "At 1235 hours EDT on 04/20/03, the Safety Parameter Display System (SPDS)   |

| portion of the Emergency Response Facility Computer System (ERFCS) was noted |

| to be inoperable due to all outputs being displayed in 'magenta' color.  At  |

| the time of the failure, the ERFCS computer was being re-initiated by        |

| Instrumentation & Controls personnel and failed to restart following the     |

| re-initiation sequence.                                                      |

|                                                                              |

| "As of 1335 hours EDT on 4/20/03, SPDS has been out of service for greater   |

| then 1 hour. which is considered a major loss of emergency assessment        |

| capability.                                                                  |

|                                                                              |

| "Troubleshooting of the ERFCS by Instrumentation & Controls personnel        |

| identified a software problem.  At 1600 hours EDT on 04/20/03,               |

| Instrumentation & Controls personnel were able to restore the 'A' train      |

| ERFCS and at 1630 hours EDT on 04/20/03 the ERFCS and SPDS were declared     |

| operable [efforts to restore the 'B' train are ongoing].                     |

|                                                                              |

| "This report is being made in accordance with I0CFR50.72(b)(3)(xiii)."       |

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| The Licensee has notified the NRC Resident Inspector.                        |

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