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Event Notification Report for May 5, 2003






                    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  





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

|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                                   

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

| 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).                                                                    |

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



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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|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). |

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



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

|General Information or Other                     |Event Number:   39811       |

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

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

| 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                          |

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