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 ¾ 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)." |
| |
| The Licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
