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 |
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| NRC NOTIFIED BY: Melinda Bradshaw | |
| HQ OPS OFFICER: ERIC THOMAS | |
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|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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| | |
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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| the amount of I-125 withdrawn from the patient was only 31.5 millicuries.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 | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|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| |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021