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Event Notification Report for August 11, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           08/08/2003 - 08/11/2003



                              ** EVENT NUMBERS **



40048  40053  40054  



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|General Information or Other                     |Event Number:   40048       |

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| REP ORG:  SC DIV OF HEALTH & ENV CONTROL       |NOTIFICATION DATE: 08/06/2003|

|LICENSEE:  Medical University of South Carolina |NOTIFICATION TIME: 15:53[EDT]|

|    CITY:  Charleston               REGION:  2  |EVENT DATE:        07/31/2003|

|  COUNTY:                            STATE:  SC |EVENT TIME:        16:00[EDT]|

|LICENSE#:  081                   AGREEMENT:  Y  |LAST UPDATE DATE:  08/06/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |STEPHEN CAHILL       R2      |

|                                                |M. WAYNE HODGES      NMSS    |

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

| NRC NOTIFIED BY:  Melinda Bradshaw             |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT - MEDICAL EVENT                                       |

|                                                                              |

| On 7/31/03, at approximately 1600 EDT, an Iotrex I-125 sealed source was     |

| administered to a brachytherapy patient to treat a brain tumor.  The sealed  |

| source contained 325 millicuries of I-125.  On 8/5/03 at 1148 EDT, upon      |

| removal of the sealed source from the patient, the hospital staff noted that |

| the amount of I-125 withdrawn from the patient was only 31.5 millicuries.    |

|                                                                              |

| The source is a liquid that is inserted into a balloon inside the patient's  |

| skull, then removed after a designated amount of time.  On 8/6/03, a         |

| manufacturer's representative from Proxima accompanied hospital staff to     |

| inspect the catheter and balloon that were used during this administration.  |

| The catheter and balloon were visually inspected and tested with a dye for   |

| leaks.  No leaks were apparent during either test.                           |

|                                                                              |

| The licensee did not report any immediate adverse affects on the patient.    |

| The referring physician was informed of this event.                          |

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|Power Reactor                                    |Event Number:   40053       |

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| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 08/08/2003|

|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 17:10[EDT]|

|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        08/08/2003|

+------------------------------------------------+EVENT TIME:        12:54[CDT]|

| NRC NOTIFIED BY:  EURMAN HENSON                |LAST UPDATE DATE:  08/08/2003|

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

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

|EMERGENCY CLASS:          NON EMERGENCY         |JACK WHITTEN         R4      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

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

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| UNANALYZED CONTROL ROOM HABITABILITY ISSUE AT CALLAWAY                       |

|                                                                              |

| "On 7/17/03, during a plant walkdown and design review for Control Room      |

| Habitability, it was identified that the pressure boundary doors located at  |

| Health Physics Access were open. A review of the Request For Resolution that |

| approved leaving the pressure boundary doors open on a continuous basis      |

| revealed an error in the engineering evaluation. A previously unidentified   |

| air flow-path would allow unfiltered outside air to mix with areas of the    |

| Control Building that are credited in the Final Safety Analysis Record       |

| (FSAR) analysis of record for post-LOCA radiological consequences to Control |

| Room personnel. The Callaway/SNUPPS Control Room HVAC design is unique in    |

| that it credits two separate mixing volumes, the Control Building and the    |

| Control Room. The air communication pathway identified on 7/17/03 impacts    |

| the Control Building volume. Initial calculations completed on 8/8/03        |

| determined that the post LOCA thyroid dose to Control Room personnel would   |

| be approximately 31.5 REM. The FSAR reported value is 25.55 REM and the      |

| regulatory limit is 30 REM. This exceeds the current FSAR Analysis Of Record |

| and is being reported as an unanalyzed condition. Upon initial               |

| identification of the opened doors and the air communication pathway, the    |

| doors were closed and a plant bulletin was issued informing personnel to     |

| maintain these doors closed when not in use."                                |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

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|Power Reactor                                    |Event Number:   40054       |

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| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 08/11/2003|

|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 05:04[EDT]|

|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        08/10/2003|

+------------------------------------------------+EVENT TIME:        23:31[CDT]|

| NRC NOTIFIED BY:  DAVID TIDWELL                |LAST UPDATE DATE:  08/11/2003|

|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |STEPHEN CAHILL       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   |

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

|                                                   |                          |

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

|                                                   |                          |

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                                   EVENT TEXT                                   

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| AUTOMATIC START OF EMERGENCY DIESEL GENERATORS DURING BUS TRANSFER FOR       |

| MAINTENANCE                                                                  |

|                                                                              |

| "Unit 1/2 A and B Diesel Generators auto started on Undervoltage while       |

| attempting to transfer Shutdown Bus 1 to Alternate supply, the alternate     |

| supply breaker failed to close, resulting in a momentary undervoltage        |

| condition on the Shutdown Bus and 4160V Shutdown Boards A & B. Shutdown Bus  |

| 1 was reenergized by reclosure of the Normal feeder breaker. The Diesel      |

| Generators did not tie onto the board due to the voltage returned to normal  |

| prior to the DG obtaining rated speed and voltage when the operator reclosed |

| the normal supply breaker. SBGT [Standby Gas Treatment] & CREV [Control Room |

| Emergency Ventilation] auto started and Refuel Zone ventilation isolated due |

| to a failure of Unit 1 Refuel Zone Rad monitor; Unit 2 Reactor Zone          |

| ventilation isolated due to a momentary loss of I & C 'A'.                   |

|                                                                              |

| "This event is reportable as an 8 hour report per 10CFR50.72(b)(3)(iv)(A) as |

| 'Any event or condition that results in valid actuation of any of the        |

| systems listed in (b)(3)(iv)(B), specifically Emergency AC Electrical power  |

| systems, including: Emergency Diesel Generators (EDGs).'                     |

|                                                                              |

| "This is also reportable per 10CFR50.73(a)(2)(iv)(A) for the above           |

| conditions as a 60 day written report."                                      |

|                                                                              |

| The licensee reported that affected ventilation systems and electrical       |

| systems have been returned to a normal configuration with the exception of   |

| the shutdown bus "43 switch" [in normal supply]. All Emergency Diesel        |

| Generators are operable and in standby. Offsite electrical power supply to   |

| the station is in a normal configuration.                                    |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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