U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/03/98 - 09/04/98 ** EVENT NUMBERS ** 34668 34729 34730 34731 34732 34733 34734 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34668 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: XRI TESTING |NOTIFICATION DATE: 08/21/98 | | CITY: MISHAWAKA REGION: 3 |NOTIFICATION TIME: 18:17 [ET]| | COUNTY: STATE: IN |EVENT DATE: 08/21/98 | |LICENSE#: 21-05472-01 AGREEMENT: N |EVENT TIME: 16:00[EDT]| | DOCKET: |LAST UPDATE DATE: 09/03/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | |JOHN GREEVES, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: SHUE |FRED COMBS NMSS | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL PERSONNEL OVEREXPOSURE | | | | XRI TESTING OF OAK LAWN, IL, REPORTED THAT ONE OF THE THEIR RADIOGRAPHY | | TECHNICIANS MAY HAVE RECEIVED AN OVEREXPOSURE WHEN HE WALKED IN FRONT OF | | THE CAMERA WHILE THE SOURCE WAS NOT FULLY WITHDRAWN INTO THE CAMERA. THIS | | INCIDENT OCCURRED AT A WESTINGHOUSE PLANT IN MISHAWAKA, IN, WHERE THEY WERE | | PERFORMING RADIOGRAPHS OF PIPE WELDS. THE INDIVIDUAL'S DOSIMETER WENT OFF | | SCALE. THEY ARE RETURNING TO THEIR ILLINOIS FACILITY SO THAT THE FILM | | BADGE AND WALLET CARD CAN BE PROCESSED. | | | | * * * UPDATE 1330EDT ON 8/26/98 FROM TIM RANDLE TO S.SANDIN * * * | | | | LICENSEE IS UPDATING THIS REPORT TO INCLUDE THE RESULTS OF THE FILM BADGE | | PROCESSING. THE WHOLE BODY DOSE WAS 1.7 REM AND THE EXTREMITY DOSE TO THE | | RIGHT HAND WAS 95 REM WHICH EXCEEDS THE 10 CFR PART 20 LIMIT OF 50 REM. THE | | LICENSEE DISCUSSED THESE RESULTS WITH REGION 3(CAMERON). NOTIFIED | | R3DO(HILAND), EO(CAMPER) AND IRD(CONGEL). | | | | * * * RETRACTION 1617 9/3/98 FROM TIM RANDLE TAKEN BY STRANSKY * * * | | | | AFTER PERFORMING DOSE CALCULATIONS WITH THE ASSISTANCE OF NRC REGION 3, THE | | LICENSEE HAS DETERMINED THAT THE INDIVIDUAL RECEIVED A DOSE OF | | APPROXIMATELY 25 REM TO THE OUTER EXTREMITIES, WHICH IS NOT AN | | OVEREXPOSURE, AND IS THEREFORE NOT REPORTABLE. NOTIFIED R3DO (LANKSBURY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34729 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MARYLAND QC LABORATORY, INC. |NOTIFICATION DATE: 09/03/98 | | CITY: REGION: 1 |NOTIFICATION TIME: 08:05 [ET]| | COUNTY: HARFORD STATE: MD |EVENT DATE: 08/31/98 | |LICENSE#: MD-2502201 AGREEMENT: Y |EVENT TIME: 14:18[EDT]| | DOCKET: |LAST UPDATE DATE: 09/03/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID LEW RDO | | |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RAY MANLEY | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Agreement State report from the State of Maryland concerning a vehicular | | accident while transporting an Amersham Model 660B camera. | | | | "On August 31, 1998 at approximately 2:10 p.m. a truck returning from a | | radiographic field job experienced a left rear tire blowout on north bound | | I-95 at approximate mile marker 74-2. The driver lost control of the truck, | | it rolled onto the passenger side, the camper shell/darkroom was ripped off | | the bed of the truck, and the exposure device (Amersham 660B) was thrown | | from the hold box The radiographer in charge, (Mr. Donald Wilson) | | immediately located, surveyed, and secured a restricted area around the | | exposure device. He then notified the RSO, Bruce E. Dewey by cell phone. | | The RSO and support personnel arrived at the scene at approximately 2:45 | | p.m. and proceeded to survey and inspect the exposure device. The exposure | | device was intact with minor scraping of the outer casing. The exposure | | device was secured in a lock box and was transported to MQC Labs, Aberdeen. | | Further inspection of the exposure device revealed two loose screws on the | | handle and stiffness of the nut connected to the shipping plug. A swipe | | test was performed and is en-route to the manufacturer. Upon receipt of a | | satisfactory leak test the exposure device will be returned to the | | manufacturer for evaluation. All other radiographic equipment onboard | | (guide tubes and crank assembly) will receive a thorough inspection for | | damage and operability prior to being returned to service." | | | | The camera (serial number 2849) contains a 46 Ci Iridium-192 source (model | | number 424-9, serial number C6448). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34730 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING, INC. |NOTIFICATION DATE: 09/03/98 | | CITY: 15 MILES NE OF REGION: 4 |NOTIFICATION TIME: 11:10 [ET]| | COUNTY: JOHNSON STATE: WY |EVENT DATE: 09/02/98 | |LICENSE#: SUA-1341 AGREEMENT: N |EVENT TIME: 00:00[MDT]| | DOCKET: |LAST UPDATE DATE: 09/03/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |IAN BARNES RDO | | |DON COOL, NMSS EO | +------------------------------------------------+JOE HOLONICH NMSS | |NRC NOTIFIED BY: JOHN VASELIN | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Licensee determined that a shallow monitor well is in an excursion status. | | | | A routine bi-weekly sample collected on September 1 from monitor well | | MW46S, exceeded two of its three upper control limits (UCLs). A | | confirmation sample was then collected on September 2, which also exceeded | | two UCLs. MW46S was then placed on excursion status as per license Section | | 11.2 and its sampling frequency increased to weekly. MW46S is a shallow | | monitor well (100 feet deep) located within Mine Unit 3 at the Christensen | | Mine, in Johnson County Wyoming. The nearest community is Linch, Wyoming. | | approximately 15 miles to the southwest. | | | | Analysis data | | Conductivity Uranium | | Date Chloride mg/l æmhos/cmý Alkalinity mg/l mg/l U308 | | Sampled UCL 13.5 UCL 1087 UCL 184.4 no UCL | | 9-1-98 13.6 1940 132.4 <.4 | | 9-2-98 13.7 1849 145.3 <.4 | | | | Health and Environmental Hazards | | None. | | | | Corrective Action | | Corrective pumping of a nearby production well began on this date. | | | | Written Notification | | A written notification will be submitted to NRC Uranium Recovery Branch | | Chief within 7 days. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34731 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/03/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:25 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/02/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/03/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |SCOTT MOORE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: K. SISLER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-Hour NRC Bulletin 91-01 Report | | | | Facility personnel discovered that a nuclear criticality safety approval | | (NCSA) requirement was not being maintained in a laboratory storage area | | (Room 232) of the X-710 Laboratory. One poly bottle containing 8 grams of | | U-235 was found in this storage area in an array stored less than 12 inches | | from an inside room corner, thus violating Requirement #6 of | | NCSA_PLANT006.A04. This constitutes a loss of control "A" (reflection) in | | the double contingency matrix for contingency event A.8.2 (reflection). | | Control "B" (spacing) was maintained throughout this event. Control "A" was | | established at 2030 under the direction of a nuclear criticality safety | | (NCS) personnel. | | | | The NRC resident inspector has been informed of this event. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34732 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 09/03/98 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 16:10 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 09/03/98 | +------------------------------------------------+EVENT TIME: 13:30[EDT]| |NRC NOTIFIED BY: ALAN HALL |LAST UPDATE DATE: 09/03/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Offsite notification due to sea turtle in intake canal. | | | | The licensee notified the Florida State Department of Environmental | | Protection regarding the sighting of a small sea turtle in the plant intake | | canal. Plant employees were redeploying nets to trap jellyfish at the time | | of the sighting. The licensee plans to attempt to remove the turtle from | | the intake canal. The NRC resident inspector will be informed by the | | licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34733 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/03/98 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/03/98 | +------------------------------------------------+EVENT TIME: 17:05[EDT]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 09/03/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RHR heat exchanger outlet throttle valve positions were discovered to have | | been set nonconservatively. | | | | While performing test PTV-24D to set the positions of RHR heat exchanger | | outlet throttle valves HCV-638 and HCV-640, the licensee discovered that | | the valves had been adjusted nonconservatively. Upon investigation, the | | licensee determined that the position of these valves had been changed | | during the 1995 refueling outage without a safety evaluation. In the | | as-found condition, actual system flow may have challenged minimum flow | | assumptions used in the Emergency Core Cooling System (ECCS) analyses, as | | well as the flow assumptions for the recirculation phase analysis of a Loss | | of Coolant Accident (LOCA). The licensee has reviewed the current LOCA | | analysis of record, and is reviewing the impact of this condition on | | previous LOCA analyses. The licensee has also revised numerous analyses and | | procedures to reflect the revised flow rates. | | | | The NRC resident inspector will be informed of this event by the licensee. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34734 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/04/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 02:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/04/98 | +------------------------------------------------+EVENT TIME: 00:24[EDT]| |NRC NOTIFIED BY: DAVID McCARY |LAST UPDATE DATE: 09/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN AUTOMATIC TURBINE TRIP/REACTOR TRIP FROM 100% POWER | | DURING SURVEILLANCE TESTING. | | | | "AT APPROXIMATELY 0024EDT UNIT 2 AUTOMATICALLY TRIPPED DUE TO A TURBINE | | TRIP/REACTOR TRIP 125VDC TRIP SIGNAL. ALL SYSTEMS FUNCTIONED AS REQUIRED, | | INCLUDING AN AUX FEEDWATER ACTUATION, AND THE PLANT IS STABLE IN MODE 3 AT | | THIS TIME. AN ESFAS SLAVE RELAY BLOCK TEST FOR TRIP OF BOTH MAIN FEED | | PUMPS AND TURBINE TRIP WAS IN PROGRESS AT THE TIME OF THE TRIP. | | INVESTIGATION AS TO THE ACTUAL CAUSE OF THE TRIP IS IN PROGRESS." | | | | ALL CONTROL RODS FULLY INSERTED WITH NO PRIMARY/SECONDARY SAFETIES OR | | RELIEFS LIFTING DURING THE TRANSIENT. BOTH MOTOR-DRIVEN AND THE | | STEAM-DRIVEN AUXILIARY FEEDWATER PUMPS AUTOSTARTED AS EXPECTED. DECAY HEAT | | IS BEING REMOVED VIA THE STEAM DUMPS TO THE MAIN CONDENSER WITH MAKEUP FEED | | SUPPLIED BY THE AFW SYSTEM. ALL ECCS EQUIPMENT IS AVAILABLE. | | | | THE LICENSEE HAS NO ESTIMATE FOR RESTART AND HAS INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+