The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for April 25, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/24/2000 - 04/25/2000

                              ** EVENT NUMBERS **

36922  36923  36924  36925  36926  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36922       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ILLINOIS DEPT OF NUCLEAR SAFETY      |NOTIFICATION DATE: 04/24/2000|
|LICENSEE:  ST JAMES HOSPTIAL & HEALTH CENTER    |NOTIFICATION TIME: 15:23[EDT]|
|    CITY:  CHICAGO HEIGHTS          REGION:  3  |EVENT DATE:        04/20/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:        12:00[CDT]|
|LICENSE#:  IL-01289-01           AGREEMENT:  Y  |LAST UPDATE DATE:  04/24/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SHEAR           R3      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOESPH KLINGER               |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PROJECTED DOSES TO A PATIENT MAY BE OFF BY GREATER THAN 20 PERCENT           |
|                                                                              |
| ST. JAMES HOSPITAL CALLED THE ILLINOIS DEPARTMENT OF NUCLEAR SAFETY  TO      |
| REPORT A MEDICAL THERAPY EVENT. FOUR IRIDIUM-192 SEEDS (APPROX. 5mCi each)   |
| WERE INSERTED THROUGH A PATIENTS NOSE TO TREAT THE BILE DUCT ON TUESDAY.     |
| THE PHYSICIAN HAD MARKED THE TUBE AT THE NOSE AS A REFERENCE POINT.  ON      |
| THURSDAY THE PHYSICIAN NOTICED THAT THE REFERENCE POINT HAD MOVED.  ST.      |
| JAMES HOSPITAL PERFORMED AN X-RAY AND NOTICED THAT THE SOURCES WERE NO       |
| LONGER AT THE TREATMENT SITE. THE LICENSEE BELIEVES THAT THE  DOSE TO THE    |
| INTENDED AREA WILL BE OUTSIDE THE RANGE OF THE 20% LIMIT.  THE LICENSEE      |
| BELIEVES THE TREATMENT WENT AS PLANNED FOR THE FIRST 24 HOURS AND THAT THE   |
| SEEDS MOVED SOMETIME DURING THE SECOND 24 HOURS.  TOTAL TREATMENT TIME WAS   |
| SUPPOSED TO HAVE BEEN 70 HOURS.                                              |
|                                                                              |
| THE LICENSEE IS PERFORMING A DOSE ASSESSMENT NOW AND WILL FORWARD A WRITTEN  |
| REPORT TO THE ILLINOIS DEPARTMENT OF NUCLEAR SAFETY WITHIN 15 DAYS.  THE     |
| LICENSEE PLANS TO CONTINUE THE TREATMENT ONCE THEY HAVE A BETTER ESTIMATE OF |
| DOSES TO THE TREATMENT SITE.                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36923       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SYNCOR INTERNATIONAL CORP            |NOTIFICATION DATE: 04/24/2000|
|LICENSEE:  SYNCOR INTERNATIONAL CORP            |NOTIFICATION TIME: 15:26[EDT]|
|    CITY:  STAMFORD                 REGION:  1  |EVENT DATE:        04/24/2000|
|  COUNTY:                            STATE:  CT |EVENT TIME:        05:00[EDT]|
|LICENSE#:  04-26507-01MD         AGREEMENT:  N  |LAST UPDATE DATE:  04/24/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN WHITE           R1      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+PHIL HARRELL         R4      |
| NRC NOTIFIED BY:  DAVID PELLICCIARINI          |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SURFACE CONTAMINATION FOUND ON PACKAGE DELIVERED TO SYNCOR STAMFORD, CT      |
| PHARMACY.                                                                    |
|                                                                              |
| A PACKAGE DELIVERED TO THE SYNCOR STAMFORD, CT. PHARMACY FACILITY FROM       |
| NORTHERN WESTCHESTER HOSPITAL, MOUNT KISCO, NY., WAS FOUND TO HAVE OUTSIDE   |
| SURFACE CONTAMINATION LEVEL OF 645,000 DPM/100 SQUARE CENTIMETER.  THE       |
| SURFACE CONTAMINATION OF THE PACKAGE WAS LIMITED TO THE TOP CORNER OF THE    |
| PACKAGE.  THE HIGHEST SURFACE CONTACT RADIATION LEVEL ON THE PACKAGE WAS     |
| 0.5MR/HR  (TOP CORNER OF THE PACKAGE).  THE SURFACE CONTAMINATION WAS FROM   |
| Tc-99m (145KeV GAMMA EMITTER, HALF LIFE OF ABOUT 6 HOURS).  THE PACKAGE WAS  |
| OPENED AND NO SURFACE CONTAMINATION WAS FOUND INSIDE THE PACKAGE.  THE       |
| DRIVER OF THE VEHICLE AND THE INSIDE OF THE VEHICLE THAT TRANSPORTED THE     |
| PACKAGE WERE SURVEYED AND NO CONTAMINATION WAS FOUND.  NORTHERN WESTCHESTER  |
| HOSPITAL WAS NOTIFIED BY SYNCOR OF THIS EVENT.  SYNCOR NOTIFIED NRC REGION 4 |
| (JEFF CRUZ) OF THIS EVENT.                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36924       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 04/24/2000|
|    UNIT:  [1] [] []                 STATE:  AL |NOTIFICATION TIME: 16:26[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/24/2000|
+------------------------------------------------+EVENT TIME:        12:53[CDT]|
| NRC NOTIFIED BY:  WES CUMBEE                   |LAST UPDATE DATE:  04/24/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC START OF THE PENETRATION ROOM FILTRATION SYSTEM DURING MAINTENANCE |
| ACTIVITIES.                                                                  |
|                                                                              |
| Maintenance investigation of a  high vibration on "1B" Spent Fuel Pool       |
| Exhaust fan resulted in the trip of the Spent Fuel Pool ventilation and      |
| subsequent autostart of the Penetration Room Filtration System.  All systems |
| operated as required.                                                        |
|                                                                              |
| Operations restarted the Spent Fuel Pool ventilation and secured the         |
| Penetration Room Filtration System.                                          |
|                                                                              |
| An investigation into this event is in progress.                             |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36925       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 04/24/2000|
|    UNIT:  [] [2] [3]                STATE:  AL |NOTIFICATION TIME: 17:01[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        04/23/2000|
+------------------------------------------------+EVENT TIME:        22:08[CDT]|
| NRC NOTIFIED BY:  JOE BENNETT                  |LAST UPDATE DATE:  04/24/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          N       0        Refueling        |0        Refueling        |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY DIESEL GENERATOR "3ED" RECEIVED AND AUTOMATIC START SIGNAL.        |
|                                                                              |
| On 04/21/00 at 2208, the "3ED" Emergency Diesel Generator received an        |
| automatic start signal due to degraded voltage as a result of testing        |
| activities associated with the "3ED" 4 kv Shutdown Board.  At the time the   |
| start was received, the Diesel Generator and the 4 kv Shutdown Board were    |
| considered inoperable for their Technical Specification functions, therefore |
| the event was not deemed reportable as an Engineered Safety Feature (ESF)    |
| actuation.  Further review of the event by the plant staff along with the    |
| Senior Resident Inspector concluded that this event should have been         |
| considered an ESF actuation, since the automatic start was not preplanned,   |
| and the Diesel Generator started as the result of a valid initiation         |
| signal.                                                                      |
|                                                                              |
| The NRC Resident will be notified of this event notification by the          |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36926       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 04/24/2000|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 17:06[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/24/2000|
+------------------------------------------------+EVENT TIME:        14:03[EDT]|
| NRC NOTIFIED BY:  ARDIE KISSINGER              |LAST UPDATE DATE:  04/24/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INVALID ISOLATED SIGNAL WAS GENERATED                                        |
|                                                                              |
| During operation of Unit 2 at 100% power, it has been determined that the    |
| inboard Primary Containment Isolation Valves associated with the Containment |
| Radiation Monitors (CRMs) received an invalid isolation signal.  During      |
| maintenance activities in the panel to change out a previously failed relay  |
| for the "A" CRM, the relay for automatic isolation was disturbed and an      |
| invalid signal was generated.  The relay inputs a close signal to the        |
| inboard valves of both CRM's, and the invalid signal caused the "B" CRM to   |
| isolate.  The licensee is investigating this event.                          |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Wednesday, March 24, 2021