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Event Notification Report for April 29, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           04/28/2003 - 04/29/2003



                              ** EVENT NUMBERS **



39659  39795  39801  39802  39803  39804  39805  39806  39807  39808  



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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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

|Power Reactor                                    |Event Number:   39659       |

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

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

| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 03/11/2003|

|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 05:23[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        03/10/2003|

+------------------------------------------------+EVENT TIME:        22:38[CST]|

| NRC NOTIFIED BY:  ANDREW OHRABLO               |LAST UPDATE DATE:  04/28/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |MARK SHAFFER         R4      |

|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          N       0        Refueling        |0        Refueling        |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| POTENTIAL RAD GROUND RELEASE PATH DISCOVERED DUE TO LOSS OF SECONDARY        |

| CONTAINMENT                                                                  |

|                                                                              |

| "This notification is being made pursuant to NRC regulation                  |

| 10CFR50.72(b)(3)(v)(D), any event or condition that at the time of discovery |

| could have prevented the fulfillment of the safety function of structures or |

| systems that are needed to mitigate the consequences of an accident.         |

|                                                                              |

| "On March 10, 2003 at 22:38, it was determined that the secondary            |

| containment was inoperable due to a leak in the Z sump manway gasket. The    |

| plant was in Mode 5, shutdown, performing fuel shuffle when secondary        |

| containment was declared inoperable. LCO 3.6.4.1 was entered. The fuel       |

| shuffle was secured at 22:40 after the completion of the fuel move that was  |

| in progress. No additional Core Alterations or OPDRVs [Operations            |

| Potentially Draining the Reactor Vessel] were in progress. Upon              |

| investigation into the secondary containment operability, it was determined  |

| that a non-Tech Spec surveillance performed on dayshift also rendered        |

| secondary containment inoperable due to additional leakage pathway via the Z |

| sump.  A principal safety function of Secondary Containment is to limit the  |

| ground level release to the environs of airborne radioactive materials       |

| resulting from a fuel handling accident.                                     |

|                                                                              |

| "As a result of the alignment of the Z sump the potential existed that if a  |

| radioactive release were to occur due to a fuel handling accident, part of   |

| the filtered release via Standby Gas Treatment System could be a ground      |

| level release vice a release through the Elevated Release Point. The         |

| surveillance has been completed and the additional leakage paths that were   |

| opened due to the surveillance have been sealed. The leaking manway gasket   |

| was determined to be due to not adequately torquing the gasket bolts. The    |

| bolts have been retorqued. Secondary containment was reestablished, and was  |

| declared OPERABLE at 02:55, 3-11-03.                                         |

|                                                                              |

| "The NRC Senior Resident has been notified."                                 |

|                                                                              |

| * * * RETRACTION TAKEN ON 04/28/03 AT 1123 EDT FROM JIM SUMPTER TO GERRY     |

| WAIG * * *                                                                   |

|                                                                              |

| "THIS IS A RETRACTION OF EVENT #39659.                                       |

|                                                                              |

| "On 3/10/2003 at 2238 CST, Cooper Nuclear Station made an 8 hour 50.72       |

| non-emergency notification to the NRC per 50.72 (b)(3)(v)(D).  It was        |

| determined that the secondary containment was inoperable due to a leak in    |

| the Z sump manway gasket.  The plant was performing fuel shuffle at the      |

| time. LCO 3.6.4.1 was entered.  The fuel shuffle was secured at 22:40 after  |

| completion of the fuel move that was in progress.   Investigation determined |

| that a non-Tech Spec surveillance performed on dayshift also rendered        |

| secondary containment inoperable due to an additional leakage pathway via    |

| the Z sump.  As a result of the alignment of the Z sump, the potential       |

| existed that if a radioactive release were to occur due to a filet handling  |

| accident, part of the filtered release via the Standby Gas Treatment System  |

| could be a ground level release.  This would potentially result in           |

| unacceptable dose levels since DBA calculations assulne an elevated release  |

| point for this accident.  Thus, the secondary containment would be unable to |

| fulfill its accident mitigation safety function to limit the release to the  |

| environs of radioactive materials from postulated design basis accidents     |

| (DBA) to control room occupants and off-site.                                |

|                                                                              |

| "Further evaluation demonstrated that if a fuel handing accident had         |

| occurred at the time of discovery of the condition, the thyroid doses to     |

| control room personnel (which are the limiting doses for this accident)      |

| would have been less than DBA values.  Other doses would remain a small      |

| fraction of 10CFR100 and General Design Criteria 19 limits.  This is because |

| the plant had been shutdown for 14 days reducing considerably the fuel       |

| handling accident source term.  In addition, the estimated ground level      |

| release flow rate was a small percentage of the elevated release point flow  |

| rate.  Finally, most of the radiation dose from this accident occurs in the  |

| first 90 seconds of the event via the unfiltered Reactor Building exhaust.   |

| Therefore, the secondary containment, which includes the Standby Gas         |

| Treatment system and the elevated release point, would have performed its    |

| accident mitigation safety function and was operable."                       |

|                                                                              |

| The licensee will notifiy the NRC Resident Inspector                         |

|                                                                              |

| NRC R4DO (Greg Pick) was notified.                                           |

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



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

|General Information or Other                     |Event Number:   39795       |

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

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

| REP ORG:  OHIO BUREAU OF RADIATION PROTECTION  |NOTIFICATION DATE: 04/24/2003|

|LICENSEE:  REPUBLIC ENGINEERED PRODUCTS LLC     |NOTIFICATION TIME: 15:59[EDT]|

|    CITY:  LORAIN                   REGION:  3  |EVENT DATE:        04/03/2003|

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

|LICENSE#:  OH31201480007         AGREEMENT:  Y  |LAST UPDATE DATE:  04/24/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |MONTE PHILLIPS       R3      |

|                                                |TOM ESSIG            NMSS    |

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

| NRC NOTIFIED BY:  SNEE                         |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| REPORT OF EXPOSURE OF LICENSEE EMPLOYEES WAS MADE TO THE STATE               |

|                                                                              |

| The licensee reported the exposure of licensee employees to radiation from a |

| TN Technologies model 5174 (serial # B103) fixed gauge containing a 2 curie  |

| Cs-137 sealed source.  The gauge fell approximately 6 feet from its location |

| on a coke hopper on approximately 04/03/03.  The welds which attached the    |

| gauge anchoring bolts appear to have failed.  The gauge had been in place    |

| since 1992.  The gauge fell with the shutter open onto the first landing of  |

| the skip pit area.  The gauge went un-noticed for a week until April 11 @    |

| 1300 when maintenance workers were called to move what was thought to be a   |

| motor (all labels and markings on the gauge were unreadable).  The workers   |

| spent approximately 1.5 hours rigging and moving the gauge before an         |

| individual recognized the gauge and secured the area.   A contractor,        |

| Radiometrics, was then called in to secure the gauge.  The Ohio department   |

| of Health was called concerning the incident on April 17 @1400.  An on-site  |

| investigation was done and a dose assessment of affected personnel is in     |

| progress.                                                                    |

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



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

|Hospital                                         |Event Number:   39801       |

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

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

| REP ORG:  HOSPITAL OF ST. RAPHAEL              |NOTIFICATION DATE: 04/28/2003|

|LICENSEE:  HOSPITAL OF ST. RAPHAEL              |NOTIFICATION TIME: 11:37[EDT]|

|    CITY:  NEW HAVEN                REGION:  1  |EVENT DATE:        04/28/2003|

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

|LICENSE#:  0600200-03            AGREEMENT:  N  |LAST UPDATE DATE:  04/28/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |TODD JACKSON         R1      |

|                                                |FRED BROWN           NMSS    |

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

| NRC NOTIFIED BY:  CHARLES GIGNAC               |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NINF                     INFORMATION ONLY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| PROVISIONAL REPORT OF MEDICAL MISADMINISTRATION                              |

|                                                                              |

| On 4/22/03, Nuclear Medical Technicians at St. Raphael Hospital received 2   |

| vials ( 75 millicurie each) of I-131 that was to be administered to a        |

| patient later that afternoon.  The vials were placed in their normal storage |

| location.  When the patient arrived,  a nuclear technician administered only |

| one vial of the I-131 which only gave the patient half of the prescribed     |

| dose.  On 4/23/03, while preparing nuclear medicine for a different patient, |

| a technician discovered the second vial of I-131 that was to be administered |

| to the patient from the previous day.  Upon discovery, the patient and the   |

| prescribing physician was notified of the error.  The physician determined   |

| that the 27 hour span between doses would have no deleterious effects on the |

| patient so the second dose was administered in the afternoon of 4/23/03.     |

| The intended dosage was 150 millicuries and the received dose was 142.4      |

| millicuries.  The RSO was notified at 0800 hrs. EDT on 4/24/03 and contacted |

| NRC Inspector Richard McKinley who advised the licensee to make this         |

| notification.                                                                |

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



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

|Other Nuclear Material                           |Event Number:   39802       |

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

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

| REP ORG:  DELTA CONSULTING ENGINEER            |NOTIFICATION DATE: 04/28/2003|

|LICENSEE:  DELTA CONSULTING ENGINEER            |NOTIFICATION TIME: 12:03[EDT]|

|    CITY:  GUAYNABO                 REGION:  2  |EVENT DATE:        04/28/2003|

|  COUNTY:                            STATE:  PR |EVENT TIME:        10:00[EDT]|

|LICENSE#:  522541501             AGREEMENT:  N  |LAST UPDATE DATE:  04/28/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |MIKE ERNSTES         R2      |

|                                                |FRED BROWN           NMSS    |

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

| NRC NOTIFIED BY:  SOUSA                        |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BLO2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| STOLEN TROXLER GAUGE                                                         |

|                                                                              |

| Licensee reported that a Troxler Gauge Model 3430 serial number #029673      |

| containing approximately 90 millicuries of Cs-137 and 44 millicuries of      |

| Am-241 was stolen from a construction site trailer in Guaynabo, PR. sometime |

| between the evening of 4/25/03 and 10:00 on 4/28/03.   The licensee has      |

| notified the local law enforcement.                                          |

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



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

|Power Reactor                                    |Event Number:   39803       |

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

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

| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 04/28/2003|

|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 14:25[EDT]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        04/28/2003|

+------------------------------------------------+EVENT TIME:        09:00[EDT]|

| NRC NOTIFIED BY:  MARCUSSEN                    |LAST UPDATE DATE:  04/28/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |TODD JACKSON         R1      |

|10 CFR SECTION:                                 |                             |

|HFIT 26.73               FITNESS FOR DUTY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

|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                                   

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

| FAILURE TO TAKE FITNESS FOR DUTY TEST                                        |

|                                                                              |

| A contract supervisor refused to take a required fitness for duty test this  |

| morning.  This action resulted in him being permanently denied access.   His |

| work history was reviewed and no discrepancy was found.   The individual has |

| turned in his resignation.                                                   |

|                                                                              |

| The NRC Resident inspector will be informed.                                 |

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



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

|Power Reactor                                    |Event Number:   39804       |

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

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

| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 04/28/2003|

|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 19:27[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        04/28/2003|

+------------------------------------------------+EVENT TIME:        16:45[EDT]|

| NRC NOTIFIED BY:  GRIFFITH                     |LAST UPDATE DATE:  04/28/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |TODD JACKSON         R1      |

|10 CFR SECTION:                                 |JAMES LYONS          NRR     |

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

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

|                                                |                             |

|                                                |                             |

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

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

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

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

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP                           |

|                                                                              |

| The licensee reported they had a turbine trip possibly due to the loss of    |

| output breakers which resulted in turbine overspeed causing the trip.  The   |

| reactor trip from 100% was caused by the turbine trip.  All rods fully       |

| inserted and there was no ECCS actuation, however one PORV lifted and        |

| reseated.  All three emergency diesel generators auto started and loaded.    |

| The 4 reactor coolant pumps lost power, so the reactor was in natural        |

| circulation from 1645 to 1823 when they restored one coolant pump.  The      |

| plant had lost power restored at 1904.  They also had their aux. feedwater   |

| to auto start as expected due to a low steam generator level.  The plant is  |

| currently stable and they are investigating the cause of the turbine trip.   |

|                                                                              |

| The NRC Resident Inspector was notified along with the New York Public       |

| Service Commission                                                           |

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



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

|Power Reactor                                    |Event Number:   39805       |

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

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

| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 04/28/2003|

|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 19:57[EDT]|

|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        04/28/2003|

+------------------------------------------------+EVENT TIME:        18:35[EDT]|

| NRC NOTIFIED BY:  EDDINGER                     |LAST UPDATE DATE:  04/28/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |MIKE ERNSTES         R2      |

|10 CFR SECTION:                                 |                             |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|3     N          Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| REDUCED REACTOR POWER FROM 100% TO HOT STANDBY DUE TO INOPERABLE ISOLATION   |

| VALVE                                                                        |

|                                                                              |

| Unit 3 commenced a load reduction at 1835 to comply with T.S. 3.6.4,         |

| Containment Isolation Valve.  The letdown isolation valve CV-3-200B was      |

| declared inoperable at 1600 due to indications there may be through valve    |

| leakage.  Letdown is still currently in service.  The intent is to isolate   |

| the letdown penetration once the unit is in mode 3, and affect               |

| troubleshooting and repairs.                                                 |

|                                                                              |

| The NRC Resident Inspector will be notified.                                 |

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



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

|General Information or Other                     |Event Number:   39806       |

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

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

| REP ORG:  GE NUCLEAR ENERGY                    |NOTIFICATION DATE: 04/28/2003|

|LICENSEE:  GE NUCLEAR ENERGY                    |NOTIFICATION TIME: 21:37[EDT]|

|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        04/28/2003|

|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/28/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |GREG PICK            R4      |

|                                                |RONALD GARDNER       R3      |

+------------------------------------------------+TODD JACKSON         R1      |

| NRC NOTIFIED BY:  JASON POST                   |JACK FOSTER          NRR     |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| INTERIM SURVEILLANCE PROGRAM FOR FUEL CHANNEL BOW MONITORING (PART 21)       |

|                                                                              |

| The control rod-fuel channel interference evaluation has been completed. It  |

| determined that BWR/6 and BWR/4 & 5 C-lattice plants with GNF thick/thin     |

| channels potentially have increased channel bow that can impact fuel bundle  |

| lift, loads on reactor internals, and control rod operability. An interim    |

| surveillance program has been developed to augment the surveillance          |

| requirements in the plant Technical Specifications until other actions,      |

| which mitigate or limit the potential for control rod-channel interference   |

| due to channel bow can be identified and implemented. The recommendations    |

| address the extent and frequency of surveillance actions, and the plants to  |

| which they should be applied. This surveillance program provides early       |

| indication of potentially degraded operational performance and assurance     |

| that action is taken before reaching excessive levels of control rod         |

| friction.  This surveillance plan is limited to BWR/6 and BWR/4 &5 C-lattice |

| plants with GNF thick/thin channels and GE control rods.  There have been no |

| indications of operational or scram problems on BWR/2, 3 and 4 D-lattice     |

| plants, and as a result, they are excluded from the interim surveillance     |

| program.                                                                     |

|                                                                              |

| Plants Recommended for Surveillance Program                                  |

|                                                                              |

| Clinton                                            Hope Creek                |

| Nine Mile Point 2                                                            |

| Fermi 2                                                                      |

| Grand Gulf                                                                   |

| River Bend                                                                   |

| LaSalle 1                                                                    |

| LaSalle 2                                                                    |

| Limerick 1                                                                   |

| Limerick 2                                                                   |

| Perry 1                                                                      |

| Susquehanna 1                                                                |

| Susquehanna 2                                                                |

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



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

|Power Reactor                                    |Event Number:   39807       |

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

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

| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 04/29/2003|

|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 04:52[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        04/29/2003|

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

| NRC NOTIFIED BY:  CARL SMYERS /JOHN BRAKHIA    |LAST UPDATE DATE:  04/29/2003|

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

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

|EMERGENCY CLASS:          UNUSUAL EVENT         |TODD JACKSON         R1      |

|10 CFR SECTION:                                 |JAMES LYONS          NRR     |

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

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|                                                   |                          |

|3     M/R        Y       60       Power Operation  |0        Hot Standby      |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| UNUSUAL EVENT DECLARED DUE TO FIRE IN THE TURBINE                            |

|                                                                              |

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

|                                                                              |

| "Class B fire south end of Main High Pressure Turbine located 53 foot        |

| elevation of turbine building.  Reactor and turbine were manually tripped.   |

| Fire brigade was dispatched.  Fire was out in 47 minutes.  There were no ESF |

| actuations or other anomalies during trip with one exception - letdown       |

| isolated on low pressurizer [level] and was subsequently restore[d].  No     |

| injuries."                                                                   |

|                                                                              |

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

|                                                                              |

| * * * UPDATE ON 4/29/03 @ 0527 EDT FROM MIKE DONEGAN TO HOWIE CROUCH * * *   |

|                                                                              |

| The licensee has terminated the NOUE on the basis that the fire is out and   |

| the plant is stable.                                                         |

|                                                                              |

| Notified R1DO (Jackson), NRR EO (Lyons), DIRO (Evans), DENVER and FEMA       |

| (Sullivan).                                                                  |

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



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

|Power Reactor                                    |Event Number:   39808       |

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

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

| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 04/29/2003|

|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 06:01[EDT]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        04/29/2003|

+------------------------------------------------+EVENT TIME:        03:13[EDT]|

| NRC NOTIFIED BY:  MIKE DONEGAN                 |LAST UPDATE DATE:  04/29/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |TODD JACKSON         R1      |

|10 CFR SECTION:                                 |JAMES LYONS          NRR     |

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

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|                                                   |                          |

|3     M          Y       60       Power Operation  |0        Hot Standby      |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| MANUAL REACTOR TRIP DUE TO FIRE IN THE HIGH PRESSURE TURBINE                 |

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

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| "Class B fire south end of turbine resulted in manual trip of the Rx and     |

| Turbine.  The fire was out in 47 minutes.  There were no ESF actuations -    |

| all systems responded as expected except let down isolated on a low          |

| pressurizer level.  Due to the fire being greater than 15 minutes a [Notice  |

| of Unusual Event] was entered at 0313 [EDT] and exited at 0520 [see event    |

| notification 39807].  The plant is currently in Mode 3 Hot Standby."         |

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| During the reactor trip, all rods inserted.  The electrical bus is stable    |

| and supplying required plant loads.  The other unit on the site was already  |

| shutdown and unaffected by the fire or reactor trip.  Core decay heat is     |

| being removed using the steam dump to condenser system and the auxiliary     |

| feedwater system. The extent of damage to the turbine is under investigation |

| by the licensee.                                                             |

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| The NRC Resident Inspector has been notified by the licensee.                |

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