U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/17/98 - 09/18/98 ** EVENT NUMBERS ** 34789 34790 34791 34792 34793 34794 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34789 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/17/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 15:13 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/17/98 | +------------------------------------------------+EVENT TIME: 14:52[EDT]| |NRC NOTIFIED BY: ROGER VARNADORE |LAST UPDATE DATE: 09/17/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ED GOODWIN, NRR EO | | |JOSEPH GIITTER IRD | | |BERNICE CARR FEMA | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UE DUE TO 2 POTENTIALLY CONTAMINATED CONTRACTORS TRANSPORTED TO HOSPITAL- | | | | THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO TRANSPORTING TWO POTENTIALLY | | CONTAMINATED, INJURED CONTRACTORS BY AMBULANCE TO A LOCAL HOSPITAL. THE | | CONTRACTORS WERE ACCOMPANIED BY LICENSEE HEALTH PHYSICS TECHNICIANS. | | | | A TUBE BUNDLE WAS BEING REMOVED FROM A MOISTURE SEPARATOR REHEATER WHEN | | A CHAIN FALL BROKE AND THE TUBE BUNDLE DROPPED APPROXIMATELY THREE FEET. | | THE CHAIN FALL STRUCK ONE INDIVIDUAL AND THE OTHER FELL APPROXIMATELY | | THREE FEET FROM FROM A PLATFORM. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 1646 ON 09/17/98 BY BARRY COLEMAN TO JOLLIFFE * * * | | | | AT 1645 ON 09/17/98, THE LICENSEE TERMINATED THE UNUSUAL EVENT WHEN THEY | | DETERMINED THAT THE TWO INJURED CONTRACTORS BEING TREATED IN THE LOCAL | | HOSPITAL WERE NOT CONTAMINATED. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND PLANS TO NOTIFY THE | | NRC RESIDENT INSPECTOR OF THE TERMINATION OF THE UNUSUAL EVENT. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO AL BELISLE, NRR EO | | BILL BECKNER, IRD JOE GIITTER, AND FEMA CHUCK BAGWELL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34790 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/17/98 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 16:18 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/17/98 | +------------------------------------------------+EVENT TIME: 13:20[CDT]| |NRC NOTIFIED BY: DAVE THRONE |LAST UPDATE DATE: 09/17/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STATE NOTIFIED OF GASOLINE FROM A TANK COMING IN CONTACT WITH ADJACENT SOIL | | | | WHILE THE LICENSEE WAS REMOVING A RETIRED GASOLINE TANK FROM THE GROUND, | | GASOLINE FROM THE TANK CAME IN CONTACT WITH SOIL ADJACENT TO THE TANK. | | THE LICENSEE DETERMINED THAT THERE WAS NO RISK OF FIRE OR EXPLOSION, OR | | THREAT TO THE HEALTH AND SAFETY OF THE PUBLIC. THE LICENSEE IS CLEANING | | UP THE SOIL CONTAINING THE GASOLINE AND PLANS TO DISPOSE OF IT PROPERLY. | | | | THE LICENSEE NOTIFIED THE ILLINOIS EMERGENCY MANAGEMENT AGENCY AND THE | | NATIONAL RESPONSE CENTER AND PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34791 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 09/17/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 18:31 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 09/17/98 | | FABRICATION & SCRAP RECOVERY |EVENT TIME: 12:00[PDT]| | COMMERICAL LWR FUEL |LAST UPDATE DATE: 09/17/98 | | CITY: RICHLAND REGION: 4 +-----------------------------+ | COUNTY: BENTON STATE: WA |PERSON ORGANIZATION| |LICENSE#: SNM-1227 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 07001257 | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: HARVEY CURAT | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 10CFR PART 21 REPORT - DEFECT RELATED TO MCPR OPERATING LIMITS - | | | | FOR BWR REACTORS WHERE SIEMENS POWER CORPORATION (SPC) PROVIDES RELOAD | | FUEL, POSTULATED TRANSIENT EVENTS ARE ANALYZED EACH FUEL CYCLE TO ESTABLISH | | MINIMUM CRITICAL POWER RATIO (MCPR) OPERATING LIMITS. DURING TRANSITION | | CYCLES, SPC ESTABLISHES LIMITS FOR SPC FUEL AND ALSO FOR CO-RESIDENT FUEL | | MANUFACTURED BY OTHER FUEL VENDORS. TRANSIENT ANALYSES ARE REQUIRED TO | | ADDRESS CO-RESIDENT FUEL AS WELL AS SPC FUEL BECAUSE PREVIOUS CO-RESIDENT | | FUEL TRANSIENT ANALYSES AND LIMITS MAY NO LONGER BE VALID DUE TO CHANGES IN | | CORE NEUTRONIC CHARACTERISTICS. INPUTS TO THE TRANSIENT ANALYSES INCLUDE | | THE FUEL PELLET TO CLADDING GAP HEAT TRANSFER COEFFICIENT FOR BOTH SPC FUEL | | AND CO-RESIDENT FUEL. THE GAP HEAT TRANSFER COEFFICIENT IS CALCULATED | | USING THE RODEX2 COMPUTER CODE. | | | | AN SPC INTERNAL LICENSING METHODOLOGY REVIEW WAS PERFORMED AND CONCERNS | | WERE IDENTIFIED RELATIVE TO THE VALUES FOR SEVERAL FUEL ROD CHARACTERISTICS | | USED IN THE RODEX2 ANALYSES TO CALCULATE GAP CONDUCTANCE VALUES FOR INPUT | | TO THE TRANSIENT ANALYSES FOR CO-RESIDENT FUEL. AN EVALUATION OF THESE | | CONCERNS DETERMINED THAT REPORTABLE DEFECTS EXIST. THE DEFECTS WERE A | | CONSEQUENCE OF MODELING THE CO-RESIDENT FUEL WITH COLD-WORKED CLADDING, | | TYPICAL OF SPC CLADDING, INSTEAD OF ANNEALED CLADDING, AS IT SHOULD HAVE | | BEEN. THE GAP CONDUCTANCE BEHAVIOR OF THE CO-RESIDENT FUEL AFFECTED THE | | CORE WIDE NEUTRONIC BEHAVIOR THROUGH VOID REACTIVITY FEEDBACK DURING | | CERTAIN TRANSIENTS AND, CONSEQUENTLY, THE CALCULATION OF THE TRANSIENT | | DIFFERENTIAL CRITICAL POWER RATIO FOR THE LIMITING SPC FUEL. | | | | THE DEFECTS ARE NON-CONSERVATIVE MCPR OPERATING LIMITS PREVIOUSLY PROVIDED | | TO COMMONWEALTH EDISON FOR LASALLE UNIT 2 CYCLE 8 AND QUAD CITIES UNIT 2 | | CYCLE 15. THE PREVIOUSLY CALCULATED AND REPORTED OPERATING LIMIT FOR | | LASALLE WILL BE REVISED BEFORE THE REACTOR STARTS UP (ANTICIPATED STARTUP | | IN MARCH, 1999). THE PREVIOUSLY CALCULATED AND REPORTED OPERATING LIMITS | | FOR QUAD CITIES UNIT 2 CYCLE 15 WERE DETERMINED AT THE LIMITING | | END-OF-CYCLE EXPOSURE CONDITIONS. CORRECTIVE ANALYSES HAVE BEEN PERFORMED | | WHICH DEMONSTRATE THAT THE CURRENT OPERATING LIMITS ARE BOUNDING FROM | | BEGINNING-OF-CYCLE TO A CYCLE EXPOSURE OF 8 GWd/MTU. THE QUAD CITIES | | UNIT 2 OPERATING LIMITS WILL BE REVISED BEFORE THE CYCLE REACHES 8 GWd/MTU. | | | | SPC EVALUATED THIS ISSUE UNDER SPC CONDITION REPORT #6565, DATED 03/02/98, | | AND PREVIOUSLY INFORMED THE NRC OF THIS ISSUE VIA SPC INTERIM REPORT | | #98-004, DATED 07/22/98. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34792 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/17/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:09 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/17/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:40[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/17/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MONTE PHILLIPS RDO | | DOCKET: 0707002 |JOSE PICCONE, NMSS EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NRC BULLETIN 91-01, 24 HOUR REPORT - | | | | NUCLEAR CRITICALITY SAFETY APPROVAL NCSA-PLANT025, PART B, REQUIREMENT 11, | | STATES THAT A MINIMUM SPACING OF 23 INCHES CENTER-TO-CENTER SHALL BE | | MAINTAINED BETWEEN SMALL DIAMETER CONTAINERS WITHIN A STORAGE AREA. | | | | AT 0940 ON 09/17/98, THE LICENSEE DISCOVERED THAT THE ABOVE NCSA | | REQUIREMENT WAS NOT BEING MAINTAINED IN THE X-330 PROCESS BUILDING AREA | | CONTROL ROOM #2 SEAL EXHAUST STATION. TWO SMALL DIAMETER CONTAINERS | | (POLY BOTTLES) WERE DISCOVERED NOT MEETING THE MINIMUM SPACING REQUIREMENT | | OF 23 INCHES CENTER-TO-CENTER. | | | | THE LOSS OF SPACING CONSTITUTES A LOSS OF ONE CONTROL (CONTROL 'A') IN | | THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY EVENT A/B.7.2. CONTROL 'B' | | (GEOMETRY AND ENRICHMENT) WAS MAINTAINED THROUGHOUT THIS EVENT. | | | | AT 1048 ON 09/17/98, THE LICENSEE INSERTED SLEEVES AROUND THE BOTTLES TO | | CORRECT THE DEFICIENCY AND MAINTAIN THE CORRECT SPACING. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL NOR RADIOACTIVE OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34793 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 09/17/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 23:00 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 09/17/98 | +------------------------------------------------+EVENT TIME: 20:45[CDT]| |NRC NOTIFIED BY: RON RUSTICK |LAST UPDATE DATE: 09/17/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -S/D COOLING VALVES COULD NOT BE OPENED ELECTRICALLY DUE TO FAILED SWITCH- | | | | DURING THE PERFORMANCE OF A REACTOR HIGH PRESSURE SHUTDOWN COOLING | | PERMISSIVE/ISOLATION CALIBRATION AND FUNCTIONAL TEST, SWITCH #1-261-23B-SW1 | | FAILED TO CLOSE WHEN REQUIRED (118 PSIG AND INCREASING). WITH THE | | FAILURE OF THIS SWITCH, THE SHUTDOWN COOLING SUCTION VALVES COULD NOT BE | | ELECTRICALLY OPENED FROM THE CONTROL ROOM IF REQUIRED FOR SHUTDOWN COOLING | | BUT COULD BE OPENED MANUALLY. PLANT OPERATORS ELECTRICALLY DISARMED THE | | SWITCH AND DECLARED IT INOPERABLE. SHUTDOWN COOLING IS NOT REQUIRED IN | | MODES 1 AND 2. THE LICENSEE PLANS TO REPAIR/REPLACE THE SWITCH. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34794 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/17/98 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 23:05 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/17/98 | +------------------------------------------------+EVENT TIME: 20:32[EDT]| |NRC NOTIFIED BY: MARK SCHRY |LAST UPDATE DATE: 09/17/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF 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 +------------------------------------------------------------------------------+ | - AUTO REACTOR TRIP FROM 100% POWER DUE TO LIGHTNING STRIKING UNIT 2 - | | | | AT 2032 ON 09/17/98, LIGHTING STRUCK UNIT 2 DURING A LIGHTNING STORM | | CAUSING THE REACTOR TO AUTOMATICALLY TRIP FROM 100% POWER DUE TO AN OTdT | | SIGNAL. ALL CONTROL RODS INSERTED COMPLETELY. NO SAFETY OR RELIEF VALVES | | LIFTED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. THE AUXILIARY | | FEEDWATER SYSTEM AUTOMATICALLY STARTED DUE TO LO/LO STEAM GENERATOR LEVELS, | | AS EXPECTED. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). PLANT PERSONNEL ARE INSPECTING | | THE PLANT FOR POSSIBLE DAMAGE. THERE WERE NO PERSONNEL INJURIES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | UNIT 1 WAS UNAFFECTED BY THE STORM. | +------------------------------------------------------------------------------+