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
Page Last Reviewed/Updated Wednesday, March 24, 2021