U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/21/1999 - 12/22/1999
** EVENT NUMBERS **
36530 36531 36532
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36530 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LONGVIEW INSPECTIONS |NOTIFICATION DATE: 12/21/1999|
|LICENSEE: LONGVIEW INSPECTIONS |NOTIFICATION TIME: 10:36[EST]|
| CITY: BROOMFIELD REGION: 3 |EVENT DATE: 12/20/1999|
| COUNTY: STATE: WI |EVENT TIME: 17:00[CST]|
|LICENSE#: 4227593-01 AGREEMENT: N |LAST UPDATE DATE: 12/21/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |THOMAS KOZAK R3 |
| |BRIAN SMITH EO NMSS |
+------------------------------------------------+JOHN DAVIDSON IAT NMSS |
| NRC NOTIFIED BY: WALLANDER |RON ALBERT IAT NRR |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAD1 20.2202(a)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POSSIBLE INTENTIONAL OVEREXPOSURE OF AN EMPLOYEE'S TLD BADGE |
| |
| THE LICENSEE REPORTED THAT A RADIOGRAPHER'S TLD BADGE WAS OVEREXPOSED FOR |
| THE MONTH OF OCTOBER. THE READING FROM THE TLD WAS 77 REM. (NORMAL |
| READINGS RANGE FROM 100 mREM-300 mREM.) THEY HAVE STARTED AN INVESTIGATION |
| AND HAVE COMMENCED INTERVIEWS WITH INDIVIDUALS THAT WORKED WITH THIS PERSON. |
| SINCE THE WORK HAS BEEN COMPLETED, ALL OF THE WORKERS WERE LAID OFF, AND |
| THEY STILL HAVE ADDITIONAL PERSONS TO LOCATE AND INTERVIEW. |
| |
| (CALL THE NRC OPERATIONS OFFICER FOR PRELIMINARY CONCLUSIONS AND A LICENSEE |
| CONTACT TELEPHONE NUMBER.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36531 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 12/21/1999|
|LICENSEE: UNIVERSITY OF TEXAS |NOTIFICATION TIME: 16:30[EST]|
| CITY: GALVESTON REGION: 4 |EVENT DATE: 12/16/1999|
| COUNTY: STATE: TX |EVENT TIME: 12:00[CST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 12/21/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |SUSAN SHANKMAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION |
| |
| The University of Texas Medical Branch at Galveston reported a |
| misadministration to the State of Texas on 12/20/99. The misadministration |
| involved the first patient for an I-131 anti B1 research protocol, sponsored |
| by Coulter. The prescribed therapeutic dose was 55.4 mCi I-131 anti B1. |
| It was discovered on the morning of 12/20/99 that the infusion bag contained |
| a significant residual activity due to the bag apparently not being flushed |
| into the patient. As a result the patient only received 46.7 mCi I-131; 84% |
| of the intended dose. |
| |
| The sponsor of the research project and the patients referring physician |
| have been notified. Since this is a research protocol, it is not known what |
| the significance of this under dosing will be to the patient's treatment. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36532 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/21/1999|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 19:34[EST]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 12/21/1999|
+------------------------------------------------+EVENT TIME: 18:52[EST]|
| NRC NOTIFIED BY: NEIL CONSTANCE |LAST UPDATE DATE: 12/21/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES OGLE R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM ON HIGH REACTOR SYSTEM PRESSURE |
| |
| "Unit 2 tripped on RCS high pressure at 1852. The Reactor Protection System |
| (RPS) setpoint of 2345 psig was exceeded, resulting in an RPS actuation and |
| tripping [of] all CRD breakers. RCS pressure peaked at 2378 psig. The |
| initiating event was a transient on the secondary plant that affected heat |
| removal capabilities. Post-trip response was normal. The plant is |
| presently in mode 3 with a trip investigation in progress." |
| |
| No primary Power-Operated Relief valves or code safety valves lifted. |
| Secondary side code safeties lifted as expected on a trip. All valves shut, |
| but two have minor leakage. The plant is stable in mode 3 with RCPs running |
| and decay heat being removed via the Steam Generators to the main |
| condenser. |
| |
| The NRC resident inspector was notified. |
+------------------------------------------------------------------------------+