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Event Notification Report for April 25, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           04/24/2003 - 04/25/2003



                              ** EVENT NUMBERS **



39777  39780  39789  39790  39791  39792  39793  39794  





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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|Power Reactor                                    |Event Number:   39777       |

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

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

| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 04/21/2003|

|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 12:35[EDT]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        04/21/2003|

+------------------------------------------------+EVENT TIME:        11:40[EDT]|

| NRC NOTIFIED BY:  A. HALLIDAY                  |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |HAROLD GRAY          R1      |

|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   |

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

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

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| DISCOVERY OF SAFEGUARDS INFORMATION.                                         |

|                                                                              |

| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY.                        |

|                                                                              |

| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE.   |

|                                                                              |

| CONTACT THE HOO FOR FURTHER DETAILS.                                         |

|                                                                              |

|                                                                              |

| * * * *  UPDATE ON 04/24/03 AT 1410 BY HALLIDAY TO GOULD * * * *             |

| RETRACTION                                                                   |

|                                                                              |

| The Security Manager, with personnel from Security and Regulatory Compliance |

| reviewed the incident using the guidance in USNRC Regulatory guide 5.62,     |

| Reporting of Safeguards Events, and USNRC Generic Letter 91-03, Reporting of |

| Safeguards events.  It was determined that although the document contained   |

| some low level safeguards information, the document could not have           |

| significantly aided an adversary in defeating a security barrier or in       |

| carrying out an act of radiological sabotage as the key piece of safeguards  |

| information, an encryption table, was not filled out.  Based on that         |

| determination JAF is withdrawing the one-hour telephone notification         |

| (EN-39777). The event remains a loggable event per 10 CFR 95.57(b).  It was  |

| entered into the Security Log at the time of notification. The event has     |

| also been entered into the licensee's corrective action program for apparent |

| cause determination.                                                         |

|                                                                              |

| The NRC Resident inspector was notified and the state will be notified.      |

|                                                                              |

| Notified the Reg 1 RDO(Gray)                                                 |

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



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

|General Information or Other                     |Event Number:   39780       |

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

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

| REP ORG:  MARYLAND DEPT OF THE ENVIRONMENT     |NOTIFICATION DATE: 04/22/2003|

|LICENSEE:  ENGINEERING CONSULTANT SERVICES      |NOTIFICATION TIME: 11:05[EDT]|

|    CITY:  FREDERICK                REGION:  1  |EVENT DATE:        04/22/2003|

|  COUNTY:  FREDERICK                 STATE:  MD |EVENT TIME:             [EDT]|

|LICENSE#:  MD2103701             AGREEMENT:  Y  |LAST UPDATE DATE:  04/22/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |HAROLD GRAY          R1      |

|                                                |TOM ESSIG            NMSS    |

+------------------------------------------------+MATT HAHN            IAT     |

| NRC NOTIFIED BY:  ALAN JACOBSON                |                             |

|  HQ OPS OFFICER:  MIKE RIPLEY                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| STOLEN MOISTURE DENSITY GAUGE                                                |

|                                                                              |

| The licensee reported that upon arriving at their work site in Bethesda, MD  |

| early in the morning of 04/22/03 they discovered that their construction     |

| trailer was broken into and a moisture density gauge stolen.  The gauge is a |

| CPN Model # MC1DR, S/N MD00305503 containing 10 millicuries Cs-137 and 50    |

| millicuries Am-241:Be.  The licensee notified the Montgomery County Police   |

| (Case # B03089862).                                                          |

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



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

|Power Reactor                                    |Event Number:   39789       |

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

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

| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 01:25[EDT]|

|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        04/23/2003|

+------------------------------------------------+EVENT TIME:        19:23[CDT]|

| NRC NOTIFIED BY:  MARK OKOPNY                  |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       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       67       Power Operation  |67       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| ACCIDENT MITIGATION                                                          |

|                                                                              |

| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or      |

| Condition that could have prevented fulfillment of a Safety Function needed  |

| to Mitigate the Consequences of an Accident. On 04/23/03, at 18:15 CDST, the |

| 1A Diesel Generator was made inoperable for a scheduled surveillance.        |

| Concurrent with this inoperability, the 0 Diesel Generator received a        |

| spurious CO2 actuation signal. This spurious CO2 partial logic actuation did |

| not result in an actual CO2 injection into the 0 Diesel Generator Room. The  |

| CO2 system partial actuation however resulted in several ventilation dampers |

| failing closed as designed. With these dampers closed, the ventilation       |

| support system for the 0 Diesel Generator became inoperable, the 0 Diesel    |

| Generator was declared inoperable at 1923 hours 04/23/03. This condition     |

| resulted in both the 1A and 0 Diesel Generators concurrently being           |

| inoperable. Actions were taken to terminate the 1A Diesel surveillance and   |

| restore the 1A Diesel Generator to an operable status. This was accomplished |

| at 1952 hours 04/23/03. The 1A and 0 Diesel Generators were simultaneously   |

| inoperable for 29 minutes. Due to the concurrent Diesel Generator            |

| inoperabilities which affect redundant trains required to mitigate the       |

| consequences of an accident, it has been determined that this event is       |

| reportable as an 8 hour ENS notification.                                    |

|                                                                              |

| "Corrective actions have been initiated to address the 0 Diesel Generator    |

| CO2 system and restore the ventilation dampers to an operable status. The    |

| spurious actuation of the 0 Diesel Generator CO2 system was determined to be |

| due to a Non-Licensed Operator opening the fire detection panel for          |

| inspection."                                                                 |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

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



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

|Power Reactor                                    |Event Number:   39790       |

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

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

| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 04:40[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/24/2003|

+------------------------------------------------+EVENT TIME:        03:48[EDT]|

| NRC NOTIFIED BY:  STUART SCHUETTPELZ           |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

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

|EMERGENCY CLASS:          ALERT                 |MONTE PHILLIPS       R3      |

|10 CFR SECTION:                                 |JAMES LYONS          NRR     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |MICHELE EVANS        IRO     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|CHUCK CAIN           R4      |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|CHARLIE BAGWELL      FEMA    |

|                                                |JOHN FLACH           NRC     |

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

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

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

|1     M/R        Y       100      Power Operation  |0        Hot Standby      |

|2     M/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| ALERT DECLARED                                                               |

|                                                                              |

| At 0348 EDT on 4/24/03, the plant experienced an influx of fish on the       |

| intake screens for the circwater and essential service water (ESW) systems.  |

| This resulted in a loss of vacuum to Units 1 and 2 main turbines, which led  |

| operators to manually trip both reactors.  Following the trip, operators     |

| noted that ESW flow to all 4 emergency diesel generators (EDGs) was severely |

| degraded.  This resulted in the licensee declaring all 4 EDG's inoperable.   |

| An alert was declared at 0348 EDT, and the NRC entered Monitoring Mode at    |

| 0506 EDT.                                                                    |

|                                                                              |

| * * * UPDATE AT 0600 ON 4/24/03 FROM LICENSEE TO H. CROUCH * * *             |

|                                                                              |

| All EDG's have adequate flow to be used in an emergency, but remain          |

| inoperable.                                                                  |

|                                                                              |

| The licensee is assessing damage to intake screens and strainers in the ESW  |

| system, and manually backwashing ESW screens.                                |

|                                                                              |

| * * * UPDATE AT 0718 ON 4/24/03 FROM DEAN BRUCK TO E. THOMAS * * *           |

|                                                                              |

| The licensee made a 4-hour ENS notification under 10 CFR 50.72(b)(2)(iv)(B)  |

| to inform the NRC of the manual reactor trips inserted on Units 1 and 2 at   |

| 0328 and 0329 on 4/24/03 for the reasons listed above.  Post-trip response   |

| of the plant was normal.  Main Steam Isolation Valves were manually closed   |

| on both units due to lowering Reactor Coolant System temperature and         |

| lowering vacuum.  Both units remain in Mode 3.                               |

|                                                                              |

| * * * UPDATE AT 1020 ON 4/24/03 FROM TODD CASPER TO E. THOMAS * * *          |

|                                                                              |

| The licensee made an 8-hour ENS notification under 10 CFR 50.72(b)(3)(iv)(A) |

| to inform the NRC of the Auxiliary Feedwater System (AFW) actuations in      |

| Units 1 and 2 following the reactor trips.  The heat removal path for both   |

| units is via AFW to the steam generator pressure operated relief valves.     |

|                                                                              |

| * * * UPDATE AT 0532 ON 4/25/03 FROM R3 IRC TO E. THOMAS * * *               |

|                                                                              |

| The licensee terminated the Alert at 0521 EDT.  The Alert was terminated     |

| based on having one train of ESW and one EDG declared OPERABLE for each      |

| Unit.  The NRC exited the Monitoring Mode of normal operations at 0532 EDT.  |

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



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

|Fuel Cycle Facility                              |Event Number:   39791       |

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

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

| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 04/24/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 05:42[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/24/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:             [CDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/24/2003|

|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+

|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |

|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MONTE PHILLIPS       R3      |

|  DOCKET:  0707001                              |DANIEL GILLEN        NMSS    |

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

| NRC NOTIFIED BY:  TOM WHITE                    |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| CRITICALITY CONTROL 24-HOUR REPORT (RESPONSE BULLETIN 91-01)                 |

|                                                                              |

| The following information was obtained from the regulatee via facsimile:     |

|                                                                              |

| "At 1320 [CDT] on 4/23/03, the Plant Shift Superintendent (PSS) was notified |

| that the trap media replacement activities for C-337 #4 Seal Exhaust (SX)    |

| trap were performed on 4/6/03 through 4/8/03 and the trap media and the      |

| bottom screen were replaced.  Contrary to the requirements of NCSA CAS-007,  |

| 'independent verification of no trap media below the bottom screen' was not  |

| performed prior to the bottom flange being removed.  This requirement        |

| ensures that an unanalyzed volume of media does not spill from the trap.     |

|                                                                              |

| "The NRC Resident Inspector has been notified of the event.                  |

|                                                                              |

| "PDGP Assessment and Tracking Report No. ATR 03-1199 PGDP Event Report No.   |

| PAD-2003-008 NRC Event Worksheet [39791].                                    |

|                                                                              |

| "Responsible Division: Maintenance                                           |

|                                                                              |

| "SAFETY SIGNIFICANCE OF EVENTS:                                              |

|                                                                              |

| "Although the trap was not independently verified to be essentially empty of |

| accumulated trap mix, prior to in-place maintenance, no media was found when |

| the bottom flange was removed.                                               |

|                                                                              |

| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(s) OF HOW           |

| CRITICALITY COULD OCCUR):                                                    |

|                                                                              |

| "In order for a criticality to be possible, a critical volume of trap mix    |

| would have to be accumulated in an unsafe geometry.                          |

|                                                                              |

| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION. ETC):     |

|                                                                              |

| "Double contingency is maintained by implementing two controls on volume.    |

|                                                                              |

| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |

| LIMIT AND % WORST CASE CRITICAL MASS):                                       |

|                                                                              |

| "There was no media found when the bottom flange was removed.                |

|                                                                              |

| "NUCLEAR CRITICALITY SAFETY CONTROL (S) OR CONTROL SYSTEM(S) AND DESCRIPTION |

| OF THE FAILURES OR DEFICIENCIES:                                             |

|                                                                              |

| "The first leg of double contingency relies on controlling the volume of     |

| trap mix available to be spilled from the, trap after removal of media above |

| the bottom screen. NCSA CAS-007 requires the trap to be verified emptied of  |

| trap media prior to in-place maintenance, thus ensuring that the trap does   |

| not contain any accumulated trap mix in excess of a 5.5-gal drum.            |

| Verification of the trap mix accumulated in the trap was not done, thus,     |

| this control was violated.                                                   |

|                                                                              |

| "The second leg of double contingency relies on controlling the volume of    |

| trap mix available to be spilled from the trap after removal of media above  |

| the bottom screen. NCSA CAS-007 requires the trap to be independently        |

| verified emptied of trap media prior to in-place maintenance. Independent    |

| verification of the trap mix accumulated in the trap was not performed,      |

| therefore, this control was violated. Neither of the controls (verification  |

| and independent verification) of the single parameter (volume) were          |

| performed and double contingency was not maintained.                         |

|                                                                              |

| "No trap media was spilled from the trap, thus maintaining the volume        |

| parameter.                                                                   |

|                                                                              |

| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |

|                                                                              |

|                                                                              |

| "None."                                                                      |

|                                                                              |

| Operations notified the NRC resident inspector.                              |

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



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

|Power Reactor                                    |Event Number:   39792       |

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

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

| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 12:07[EDT]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/24/2003|

+------------------------------------------------+EVENT TIME:        11:00[EDT]|

| NRC NOTIFIED BY:  JOHN SHIPMAN                 |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

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

|EMERGENCY CLASS:          ALERT                 |MONTE PHILLIPS       R3      |

|10 CFR SECTION:                                 |MICHELE EVANS        IRO     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |TERRY REIS           NRR     |

|                                                |JIM CALDWELL         R3      |

|                                                |DENVER                       |

|                                                |JANIE EVERETTE       DOE     |

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

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

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

|1     N          N       0        Refueling        |0        Refueling        |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| ALERT AT PERRY DUE TO EVENT IN FUEL HANDLING BUILDING                        |

|                                                                              |

| "At 11:00 the control room received a High alarm on the FHB Gas and Alert on |

| FHB Iodine. ONI ZZZ-7 was entered along with ONI J11-2 and ONI D17. Fuel     |

| movement was stopped after all fuel was placed in a safe condition. The FHB, |

| Drywell, and Containment were evacuated and the Containment and FHB closure  |

| plans were carried out. At 11:30 the control room received a report that the |

| fuel bundle being inspected in the FHB had a bubble float to the top of the  |

| pool. At 11:27 the alarms in the FHB reset. The entry into an Alert was      |

| recognized at 11:50 and initial notifications were completed. The Technical  |

| Support center has been staffed to develop a recovery plan."                 |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

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



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

|Power Reactor                                    |Event Number:   39793       |

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

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

| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 15:33[EDT]|

|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/24/2003|

+------------------------------------------------+EVENT TIME:        09:47[CDT]|

| NRC NOTIFIED BY:  ROBERT BRINKMAN              |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |CHUCK CAIN           R4      |

|10 CFR SECTION:                                 |MICHELE EVANS        IRO     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|TERRY REIS           NRR     |

|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

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

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

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

|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| GRAND GULF AUTOMATIC SCRAM AND ECCS INJECTION DUE TO PARTIAL LOOP            |

|                                                                              |

| "At 09:47 (CDT), Grand Gulf Nuclear Station (GGNS) auto scrammed due to      |

| complications following a partial loss of offsite power. At the time of the  |

| scram there was a severe thunderstorm in the vicinity of GGNS. It is         |

| believed that high winds caused damage in the GGNS switchyard which in turn  |

| led to the partial LOOP. The following items actuated/initiated during this  |

| event:                                                                       |

|                                                                              |

| "1. RPS automatic actuation, exact cause unknown.                            |

| "2. HPCS and RCIC initiated on reactor water level 2 and injected into the   |

| vessel to restore water level.                                               |

| "3. Division 2 and 3 EDGs started on a loss of power to the 16 and 17 buses. |

| Division 2 and 3 EDG energized the 16 and 17 buses respectively.             |

| "4. Some time after the initial event the 15 bus lost power and was          |

| re-energized by the Division 1 EDG.                                          |

| "5. All MSIVs isolated on loss of power.                                     |

| "6. Containment isolation occurred on power loss and on reactor water level  |

| 2.                                                                           |

|                                                                              |

| "At present reactor water level is being maintained with RCIC and reactor    |

| pressure is being maintained with SRVs. A review of plant data is underway   |

| to confirm proper response of plant equipment."                              |

|                                                                              |

| The NRC Resident Inspector was notified by the licensee.                     |

|                                                                              |

| *****UPDATE ON 4/24/03 AT 19:20 FROM BRINMAN TO LAURA*****                   |

|                                                                              |

| "It should be noted that offsite power was always available to the GGNS from |

| the ESF transformer #12 during/following the scram at 09:47 hours (CDT) on   |

| 4/24/03. Also, there was no structural damage to the GGNS switchyard. There  |

| was only minor damage to a locking collar on a disconnect in the GGNS        |

| switchyard. The wind blew the disconnect closed breaking it's locking collar |

| and grounding the switchyard through a grounding strap. The grounding strap  |

| disintegrated and a lockout occurred on service transformer #21 and the west |

| bus of the GGNS switchyard. Power has been restored to all busses and all    |

| diesel generators have been secured."                                        |

|                                                                              |

| Notified R4DO (C. Cain)                                                      |

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



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

|Power Reactor                                    |Event Number:   39794       |

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

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

| FACILITY: HADDAM NECK              REGION:  1  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 15:01[EDT]|

|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        04/24/2003|

+------------------------------------------------+EVENT TIME:        14:06[EDT]|

| NRC NOTIFIED BY:  REID                         |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |HAROLD GRAY          R1      |

|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        Decommissioned   |0        Decommissioned   |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| OFFSITE NOTIFICATION DUE TO HYDRAULIC OIL SPILL                              |

|                                                                              |

| The licensee notified the state that they had approximately one tablespoon   |

| of hydraulic oil spill from a manlift to the soil in the south RCA yard near |

| the rad waste reduction facility.                                            |

|                                                                              |

| The NRC RDO(Gray) was notified.                                              |

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