U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/02/2003 - 05/05/2003
** EVENT NUMBERS **
39631 39745 39811 39812 39817 39818 39819 39821 39822
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|Power Reactor |Event Number: 39631 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 03/02/2003|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 16:00[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 03/02/2003|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: CHARLES PIKE |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |WALTER RODGERS R2 |
|10 CFR SECTION: |DAVID AYRES R2 |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| OFFSITE NOTIFICATION TO STATE AGENCY OF EXPIRED GREEN SEA TURTLE FOUND AT |
| BARRIER NET |
| |
| "NRC notification [is] being made due to state notification to [the] Florida |
| Wildlife Commission regarding a Green Sea Turtle found dead at barrier net |
| pursuant to 10 CFR 50.72(b)(2)(xi)." |
| |
| The turtle was found on the surface at the barrier net with no injuries or |
| abnormalities except for fresh cuts common for turtles coming through pipes. |
| The cause of death is unknown at this time. A necropsy is planned. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| * * * UPDATE ON 3/15/03 @ 1033 EST FROM TEREZAKIS TO CROUCH * * * |
| |
| "On 3-15-03, a green sea turtle was retrieved from the plant's intake canal. |
| The turtle was determined to be in need of rehabilitation. The injuries to |
| the turtle are not causal to plant operation. Per the plant's turtle permit, |
| the Florida Fish and Wildlife Conservation Commission (FWCC) was notified at |
| 0920 EST. This non-emergency notification is being made pursuant to 10 CFR |
| 50.72(b)(2)(xi) due to the notification of FWCC." |
| |
| The NRC Resident Inspector will be notified by the licensee. |
| |
| * * * UPDATE ON 3/19/03 AT 1222 EST FROM E. SUMNER TO RIPLEY * * * |
| |
| "On 03/19/03 @ 1105 hrs., one loggerhead turtle was retrieved from the |
| plant's intake canal. The turtle was determined to be in need of |
| rehabilitation. The injury to the turtle is not causal to plant operation. |
| Per the plant's turtle permit, the Florida Fish and Wildlife Conservation |
| Commission (FWCC) was notified at 1115 EST." |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATED ON 3/31/03 AT 1159 EST FROM W.L. PARK TO A. COSTA * * * |
| |
| "On 3-31-03 [1105 EST], a loggerhead sea turtle was retrieved from the |
| plant's intake canal. The turtle was determined to be in need of |
| rehabilitation. The injuries to the turtle are not causal to plant |
| operation. Per the plant's turtle permit, the Florida Fish and Wildlife |
| Conservation Commission (FWCC) was notified at 1105 EST. This non-emergency |
| notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) due to the |
| notification of FWCC." |
| |
| The NRC Resident Inspector will be notified. |
| |
| * * * UPDATE 1235EST ON 4/9/03 FROM ANDY TEREZAKIS TO S.SANDIN * * * |
| |
| "On 4-9-03, a loggerhead sea turtle was retrieved from the plant's Intake |
| canal. The turtle was determined to be in need of rehabilitation. The |
| injuries to the turtle are not causal to plant operation. Per the plant's |
| turtle permit, the Florida Fish and Wildlife Conservation Commission (FWCC) |
| was notified at 1100 EST. This non-emergency notification is being made |
| pursuant to 10CFR50.72(b)(2)(xi) due to the notification of FWCC." |
| |
| The licensee informed the NRC resident inspector. Notified R2DO(Landis). |
| |
| *** UPDATE ON 5/2/03 AT 1826 FROM S. OEHRLE TO A. COSTA *** |
| |
| "On 5/2/03, a green sea turtle was retrieved from the intake canal. The |
| turtle required rehabilitation. The injuries were not causal to plant |
| operation. Per the plant's turtle permit, the Florida Fish and Wildlife |
| Conservation Commission was notified at 1445 EDT. This non-emergency |
| notification is being made pursuant to 10 CFR 50.72 (b)(2)(xi) due to |
| offsite notification." |
| |
| The Licensee will notify the NRC Resident Inspector. Notified R2DO |
| (Munday). |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39745 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 04/09/2003|
| UNIT: [] [] [3] STATE: AZ |NOTIFICATION TIME: 23:42[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/09/2003|
+------------------------------------------------+EVENT TIME: 19:43[MST]|
| NRC NOTIFIED BY: JAMES BLAZEK |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVE LOVELESS R4 |
|10 CFR SECTION: | |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Refueling |0 Refueling |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNATTENDED SECURITY HANDGUN FOUND IN THE PROTECTED AREA |
| |
| Immediate compensatory measures taken upon discovery. |
| |
| The Licensee has notified the NRC Resident Inspector. |
| |
| *** RETRACTION FROM D. MARKS TO A. COSTA AT 1858 ON 5/2/03 *** |
| |
| Upon further review of 10 CFR 73, Appendix G, Paragraph 1(a)(3), the |
| Licensee is retracting this event notification. Contact the NRC |
| Headquarters Operations Officer for additional details. |
| |
| The Licensee notified the NRC resident inspector. Notified the R4DO (Pick). |
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|General Information or Other |Event Number: 39811 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 04/30/2003|
|LICENSEE: ALBEMARLE CORPORATION |NOTIFICATION TIME: 13:18[EDT]|
| CITY: PASADENA REGION: 4 |EVENT DATE: 04/28/2003|
| COUNTY: STATE: TX |EVENT TIME: 07:00[CDT]|
|LICENSE#: LO4072-000 AGREEMENT: Y |LAST UPDATE DATE: 04/30/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GREG PICK R4 |
| |DOUG BROADDUS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JAMES OGDEN | |
| HQ OPS OFFICER: RICH LAURA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TEXAS AGREEMENT STATE REPORT ON DISABLED GAUGE FOR OIL CRACKING PLANT |
| |
| "Licensee immediately suspended operations in the affected "reactor" (oil |
| cracking plant) due to loss of measurement caused by loss of level/density |
| measurements from an Ohmart Corporation (OC) Model SH-F2, source holder, |
| containing 1 curie of Cs-137, Serial # 68526, located on the exterior |
| surface of the SAS Sodium reactor, vessel # R-7202. Operators noted a loss |
| of measurement at approximately 7:00 a.m. When investigating the outside of |
| the reactor vessel, on-site personnel noted that the fixed gauge had broken |
| free of its mounting bracket and fallen, face-down, approximately 10 feet to |
| the ground. Plant personnel immediately notified Techstar, a subsidiary of |
| Ohmart/Vega Corporation, for field service. A service technician arrived on |
| scene, surveyed the gauge for radiation leakage, checked for contamination, |
| and checked the functional operation of the gauge. The shutter was closed |
| and locked by service personnel, until damage could be assessed. No damage |
| was sustained by the gauge. The mechanism was fully functional and has been |
| reinstalled on the reactor vessel. A set screw (a 3/4 to 1 inch bolt) had |
| failed on the mounting bracket, due to suspected structural fatigue and |
| vibration over 11 years since the gauge was installed (December 1992). The |
| gauge was reinstalled in a bracket modified to fit on the welded beam |
| (2-inch pipe), that will not allow the gauge to fall if the set screw fails |
| in the future. All other gauges on site were checked by service personnel |
| for security and possible deterioration on mounting hardware. This gauge was |
| unique in this plant due to it's mounting which has now been upgraded to |
| allow for fail-safe operation without loss of function should the bracket |
| fail. Problem has been corrected by the service company. Modification to the |
| mounting bracket and replacement of the set screw has rectified the cause of |
| this incident and returned the reactor to operation." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39812 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/30/2003|
| UNIT: [] [2] [] STATE: FL |NOTIFICATION TIME: 21:52[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/30/2003|
+------------------------------------------------+EVENT TIME: 14:20[EDT]|
| NRC NOTIFIED BY: CHARLES PIKE |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOEL MUNDAY R2 |
|10 CFR SECTION: |FRANK GILLESPIE NRR |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEGRADED CONDITION DUE TO DEFECT IN REACTOR VESSEL HEAD PENETRATION |
| |
| "On April 30, 2003, at 1420 hours, with St. Lucie Unit 2 in a refueling |
| outage, FPL discovered a defect in reactor vessel head penetration 72. This |
| flaw was found during the ongoing reactor vessel head inspection being |
| performed in accordance with the requirements of NRC Order EA-03-009. The |
| defect is OD surface connected, extends into the nozzle and penetrates into |
| the J-groove weld between the nozzle and reactor vessel head. The defect is |
| described as an axial flaw, 0.28 inches deep X 0.96 inches long, on the |
| downhill side of the penetration. Per the inspection guidance, surface flaws |
| located in the attachment weld area are not acceptable. |
| |
| "There had been no indication of RCS leakage during the previous cycle's |
| operation. This notification is being made in accordance with 10 CFR |
| 50.72(b)(3)(ii)(A)." |
| |
| The Licensee notified the NRC Resident Inspector. |
| |
| *** UPDATE ON 5/2/03 AT 1337 EDT FROM R.WELLER TO A. COSTA *** |
| |
| "This report is a supplement to original event report #39812 dated April 30, |
| 2003. On May 2, 2003 at 1240 hours, with St. Lucie Unit 2 in a refueling |
| outage, FPL discovered a defect in reactor vessel head penetration #18. This |
| is the second flaw found during the current ongoing reactor vessel head |
| inspection being performed in accordance with the requirements of NRC Order |
| EA-03-009. The defect is OD surface connected, extends into the nozzle and |
| through the J-groove weld between the nozzle and reactor vessel head. The |
| defect is described as an axial flaw, 0.39 inches deep X 2.98 inches long, |
| on the downhill side of the penetration. Per the inspection guidance, |
| surface flaws located in the attachment weld area are not acceptable. There |
| had been no indication of RCS pressure boundary leakage during the previous |
| cycles operation. This notification is being made in accordance with 10 CFR |
| 50.72(b)(3)(ii)(A)." |
| |
| The Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39817 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/02/2003|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 02:40[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/02/2003|
+------------------------------------------------+EVENT TIME: 02:14[EDT]|
| NRC NOTIFIED BY: A. YODER |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOEL MUNDAY R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN DUE TO BOTH HYDROGEN IGNITER TRAINS DECLARED |
| INOPERABLE. |
| |
| "A" and "B" Hydrogen igniter trains are inoperable requiring a plant down |
| power per Tech Spec 3.0.3. Tech Spec 3.0.3 requires the plant to be in Hot |
| Standby in 7 hours (clock started at 0115 EDT). "B" Train was inoperable to |
| repair a cable and a cable was mistakenly cut on "A" Train. |
| |
| All Emergency Core Cooling Systems are operable, electrical grid is stable, |
| and the Emergency Diesel Generators are fully operable as needed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
| |
| |
| **** UPDATE on 05/02/03 at 0809 EDT by L. Brown taken by MacKinnon **** |
| |
| Train "A" Hydrogen igniters declared operable and Tech Spec 3.0.3 exited at |
| 0741 EDT after its cable was repaired. |
| NRC R2DO (Joel Munday) notified. |
| |
| The NRC Resident Inspector was notified of this update by the licensee. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39818 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/02/2003|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 08:45[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/02/2003|
+------------------------------------------------+EVENT TIME: 06:32[CDT]|
| NRC NOTIFIED BY: ROBERT SCHREIFELS |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD GARDNER R3 |
|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 N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION |
| |
| At 0632 CDT on 5/2/03, there was a small fire in Control Room Alarm Panel |
| C-8-C. The fire was immediately extinguished with a hand held halon |
| extinguisher. Two alarmed (tagged) cards were found to be damaged. The |
| cause of the fire is under investigation, and there was no effect on plant |
| operations. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| *** RETRACTION ON 5/2/03 AT 1549 FROM R. SCHREIFELS TO A. COSTA *** |
| |
| "NMC [Nuclear Management Company] is retracting the notification made at |
| 0745 on 5/2/03 based on the small fire not being related to or affecting the |
| health and safety of the public or site personnel. The alarm functions |
| affected by the circuit board fire were confined to those associated with |
| power supplies to non-safety bus which was previously de-energized. Plant |
| operations was not otherwise affected." |
| |
| The Licensee notified the NRC Resident Inspection. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39819 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 05/02/2003|
| UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 09:37[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/02/2003|
+------------------------------------------------+EVENT TIME: 06:10[CDT]|
| NRC NOTIFIED BY: WAYNE VANLANDINGHAM |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOEL MUNDAY R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 4 Startup |2 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MAIN FEEDWATER PUMP "B" MANUALLY TRIPPED CAUSEING AUXILIARY FEEDWATER PUMP |
| ACTUATION. |
| |
| "The 1A and 1B Motor Driven Aux Feed Water Pumps auto started due to trip of |
| the 1B Steam Generator Feed Pump (SGFP). |
| |
| "The pump was providing feed water to the steam generators and a local watch |
| was established to trip the pump should an overspeed condition be observed. |
| The watch was established due to the overspeed test not having yet been done |
| on the SGFP. The watch observed speed increasing on the SGFP and tripped |
| the pump locally when speed was observed to be 5000 rpm and rising. The |
| pump had previously been running at a stable 3600 rpm. |
| |
| "Control room staff entered AOP-13, Los of Feed, reduced nuclear power to 2% |
| and stabilized the plant. (1A & 1B Motor Driven Aux Feedwater pumps can only |
| handle 3% thermal rated power) |
| |
| "Plans are to investigate and correct the cause of the 1B SGFP speed |
| increase. |
| |
| "The trip of SGFP occurred during plant startup from refueling with 1A SGFP |
| Out of Service" |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39821 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 05/02/2003|
| UNIT: [] [] [3] STATE: SC |NOTIFICATION TIME: 19:57[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 05/02/2003|
+------------------------------------------------+EVENT TIME: 16:45[EDT]|
| NRC NOTIFIED BY: STEVE CAPPS |LAST UPDATE DATE: 05/02/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOEL MUNDAY R2 |
|10 CFR SECTION: |FRANK GILLESPIE NRR |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEGRADED CONDITION DUE TO POSSIBLE THROUGH WALL LEAKAGE ON CRDM |
| PENETRATIONS |
| |
| "During a walkdown of the Unit 3 reactor vessel [RV] head and CRDM [Control |
| Rod Drive Mechanism] nozzle penetrations prior to RV head retirement, |
| evidence of possible through wall leakage was observed on two CRDM |
| penetrations. The locations are nozzle 4 and nozzle 7. Nozzle 7 had been |
| previously repaired. Review of past outage video tape could not disposition |
| as either new or old leakage. Several additional nozzle to head |
| penetrations were masked by chromated water leakage deposits. |
| |
| "Initial Safety Significance: Any RCS [Reactor Coolant System] leakage from |
| these penetrations would have been below the threshold of measurability by |
| the reactor coolant system leakage measurement process. |
| |
| "The Reactor Vessel Head is scheduled for replacement during the present |
| refueling outage. Therefore, there are no plans at this time to perform |
| additional inspections or repairs on the current head." |
| |
| The Licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39822 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/03/2003|
| UNIT: [] [2] [3] STATE: IL |NOTIFICATION TIME: 06:27[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/02/2003|
+------------------------------------------------+EVENT TIME: 23:40[CDT]|
| NRC NOTIFIED BY: PAUL WOJTKIEWICZ |LAST UPDATE DATE: 05/03/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RONALD GARDNER R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 56 Power Operation |56 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF ERDS SYSTEM |
| |
| At 2340 CDT on 5/2/03, the licensee discovered that Dresden Station's |
| Emergency Response Data System (ERDS) computer was not functioning. |
| Technicians performed troubleshooting and the ERDS computer was restored at |
| 0440 CDT on 5/3/03. |
| |
| The licensee will notify the NRC Resident Inspector |
+------------------------------------------------------------------------------+
