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Event Notification Report for January 8, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/07/2003 - 01/08/2003



                              ** EVENT NUMBERS **



39491  39492  39493  



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|Power Reactor                                    |Event Number:   39491       |

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| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 01/07/2003|

|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 06:05[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/07/2003|

+------------------------------------------------+EVENT TIME:        03:20[EST]|

| NRC NOTIFIED BY:  JOHN DUFF                    |LAST UPDATE DATE:  01/07/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        R2      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

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

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS)                               |

|                                                                              |

| "At 0220 hours on 01/07/03, the Safety Parameter Display System (SPDS)       |

| portion of the Emergency Response Facility Computer System (ERFCS) was noted |

| to be inoperable, due to all outputs being displayed in 'magenta' color.     |

|                                                                              |

| "Troubleshooting of the ERFCS determined that the 'B' train of the ERFCS had |

| failed and prevented the 'A' train from booting as required. This resulted   |

| in the failure of both trains of ERFCS and SPDS. Instrumentation & Controls  |

| personnel were able to restore the 'A' train ERFCS and at 0450 hours on      |

| 01/07/03 the ERFCS and SPDS were returned to service.                        |

|                                                                              |

| "SPDS was out of service for greater than 1 hour, which is considered a      |

| major loss of emergency assessment capability.                               |

|                                                                              |

| "This report is being made in accordance with 10CFR50.72(b)(3)(xiii).        |

|                                                                              |

| "NRC, Mr. Crouch notified. Faxed to NRC # 301-816-5161 at 0618 hours."       |

|                                                                              |

| The NRC Resident Inspector was notified of this event by the Licensee.       |

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|Power Reactor                                    |Event Number:   39492       |

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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/07/2003|

|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 11:00[EST]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        11/22/2002|

+------------------------------------------------+EVENT TIME:        09:43[EST]|

| NRC NOTIFIED BY:  RICHARD LOUIE                |LAST UPDATE DATE:  01/07/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |

|10 CFR SECTION:                                 |JOHN HANNON          NRR     |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|2     N          N       0        Hot Shutdown     |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| 60 - DAY OPTIONAL 10 CFR 50.73 REPORT - INVALID ACTUATION OF THE RPS SYSTEM  |

|                                                                              |

| "The following notification is provided by [Entergy Nuclear Operations] ENO  |

| regarding Indian Point Unit 2 pursuant to 10 CFR 50.73(a)(2)(iv)(A) as 'Any  |

| event or condition that resulted in manual or automatic actuation of the     |

| reactor protection system (RPS) including: reactor scram or reactor trip.'   |

| This notification is provided in lieu of submitting a written LER for a RPS  |

| actuation that was invalid and occurred while the reactor was subcritical.   |

|                                                                              |

| "On November 22, 2002, at approximately 0943 hours, a reactor trip signal    |

| occurred and the reactor trip breakers opened. The plant was in Hot Shutdown |

| Condition following the completion of 2R15 refueling activities with the     |

| reactor subcritical (100 cps), and the Reactor Coolant System (RCS)          |

| temperature and pressure at 548 F and 2195 psig, respectively. Control rod   |

| testing was in progress with Control Rod Shutdown Bank 'A' withdrawn at two  |

| steps. All other control rods were at zero steps.                            |

|                                                                              |

| "An invalid RPS actuation was initiated while in this condition due to       |

| ongoing work.  At approximately 0930 hours, in preparation for control rod   |

| drop testing the reactor trip breakers were closed. At approximately the     |

| same time, technicians were in the process of re-terminating previously      |

| de-termed RCS narrow range [Resistance Temperature Detector] RTD's.  At      |

| approximately 0940 hours, Control Rod Shutdown Bank 'A' was withdrawn at two |

| steps to support control rod drop testing.  At approximately 0943 hours,     |

| technicians landed a lead on loop 1 cold leg RTD, generating an Over         |

| Temperature Delta Temperature (OTDT) signal. This resulted in a reactor trip |

| due to a 2/4 channel OTDT trip logic.  OTDT channel 2 was previously placed  |

| in trip due to nuclear flux power range channel N-42 connected to the        |

| reactivity computer in support of low power physics testing. The reactor     |

| trip breakers opened, inserting Shutdown Bank 'A' rods.  All other rods were |

| already fully inserted. Plant response was as expected. This trip did not    |

| cause a primary or secondary transient. Plant recovery was achieved in       |

| accordance with existing operating procedures."                              |

|                                                                              |

| Licensee will notify the NRC Resident Inspector.                             |

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|Hospital                                         |Event Number:   39493       |

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| REP ORG:  MIDMICHIGAN MEDICAL CENTER           |NOTIFICATION DATE: 01/07/2003|

|LICENSEE:  MIDMICHIGAN MEDICAL CENTER           |NOTIFICATION TIME: 12:33[EST]|

|    CITY:  MIDLAND                  REGION:  3  |EVENT DATE:        01/06/2003|

|  COUNTY:  MIDLAND                   STATE:  MI |EVENT TIME:        16:45[EST]|

|LICENSE#:  21-01549-02           AGREEMENT:  N  |LAST UPDATE DATE:  01/07/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |RONALD GARDNER       R3      |

|                                                |DOUG BROADDUS        NMSS    |

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

| NRC NOTIFIED BY:  LARRY LANGRILL               |                             |

|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|LDIF 35.3045(a)(1)       DOSE <> PRESCRIBED DOSA|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| MEDICAL EVENT < 50 % OF PRESCRIBED DOSE                                      |

|                                                                              |

| At 0830 on 1/7/03, it was discovered that a patient receiving braqchytherapy |

| to the right lung using a high dose remote afterloader, received an actual   |

| dose less than the prescribed dose.  The source was a 5.2 curie Ir-192 and   |

| the prescribed dose was 2000 cGy, which was to be administered  in four 500  |

| cGy increments. The computer was programmed for the four increments, but the |

| total prescribed dose was set for 500 cGy, resulting in an actual dose       |

| delivered of 125 cGy.  The patient was informed that the dose received was   |

| lower than intended and they would be receiving the total prescribed dose in |

| the remaining three increments.  The attending Physician will be notified.   |

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