U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/29/98 - 09/30/98 ** EVENT NUMBERS ** 34845 34847 34848 34849 34850 34851 34852 34853 34854 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34845 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COASTAL UNILUBE COMPANY |NOTIFICATION DATE: 09/28/98 | | CITY: WEST MEMPHIS REGION: 4 |NOTIFICATION TIME: 16:58 [ET]| | COUNTY: STATE: AR |EVENT DATE: 09/23/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 09/29/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JEFF SHACKELFORD RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: B. BELL | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE FOLLOWING REPORT WAS MADE BY THE ARKANSAS DEPARTMENT OF HEALTH: | | | | COASTAL UNILUBE COMPANY (AN OIL RECYCLING FIRM) OF WEST MEMPHIS, AR, | | SUFFERED A MAJOR WAREHOUSE FIRE ON 09/23/98. ON 09/27/98, COASTAL UNILUBE | | OFFICIALS NOTIFIED THE ARKANSAS DEPARTMENT OF HEALTH THAT A FILL LEVEL/ | | DENSITY GAUGE CONTAINING A 300-mCi Am-241 SOURCE WAS LOCATED IN THE | | WAREHOUSE AT THE TIME OF THE FIRE. THE GAUGE HAD BEEN PURCHASED FROM | | INDUSTRIAL DYNAMICS COMPANY (MODEL 19567, SERIAL NO. CA378D104G) OF | | TORRANCE, CA, IN 1992. THE VENDOR HAS INFORMED COASTAL UNILUBE OFFICIALS | | THAT THE GAUGE IS TEMPERATURE RATED TO >800øC AND IS PROBABLY INTACT. THE | | ARKANSAS DEPARTMENT OF HEALTH IS DISPATCHING PERSONNEL TO THE FIRE SCENE TO | | ASSIST THE LICENSEE IN LOCATING AND INSPECTING THE GAUGE. | | | | THE ARKANSAS DEPARTMENT OF HEALTH HAS ALREADY DISCUSSED THIS MATTER WITH | | NRC REGION 4 (LINDA HOWELL). | | | | * * * UPDATE AT 1700 ON 09/29/98 FROM B. BELL TAKEN BY STRANSKY * * * | | | | A CONSULTANT HIRED BY COASTAL UNILUBE FOUND THE GAUGE UNDAMAGED AT THE FIRE | | SCENE. ARKANSAS DEPARTMENT OF HEALTH REPRESENTATIVES HAVE VISITED THE SCENE | | AND VERIFIED THE INTEGRITY OF THE SOURCE. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R4DO (SHACKELFORD). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34847 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/29/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 02:59 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/29/98 | +------------------------------------------------+EVENT TIME: 01:19[EDT]| |NRC NOTIFIED BY: CLINTON SILVERS |LAST UPDATE DATE: 09/29/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SHUTDOWN COOLING SYSTEM VALVES CLOSED DUE TO A FAILED THERMOCOUPLE - | | | | AT 0119 ON 09/29/98, WITH THE PLANT IN CONDITION 4 (COLD SHUTDOWN) IN A | | REFUELING OUTAGE, SHUTDOWN COOLING SYSTEM VALVES CLOSED DUE TO A FAILED | | 'B' RECIRC LOOP SUCTION TEMPERATURE THERMOCOUPLE. | | | | AT 0204, THE LICENSEE INSTALLED AN ELECTRICAL JUMPER AROUND THE FAILED | | THERMOCOUPLE AND RESTORED THE SHUTDOWN COOLING SYSTEM TO NORMAL OPERATION. | | REACTOR COOLANT SYSTEM TEMPERATURE INCREASED 17 DEGREES TO A MAXIMUM OF | | 131øF. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34848 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NUCLEAR FUEL SERVICES INC. |NOTIFICATION DATE: 09/29/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 08:18 [ET]| |COMMENTS: HEU CONVERSION & SCRAP RECOVERY |EVENT DATE: 09/29/98 | | NAVAL REACTOR FUEL CYCLE |EVENT TIME: 07:19[EDT]| | LEU SCRAP RECOVERY |LAST UPDATE DATE: 09/29/98 | | CITY: ERWIN REGION: 2 +-----------------------------+ | COUNTY: UNICOI STATE: TN |PERSON ORGANIZATION| |LICENSE#: SNM-124 AGREEMENT: Y |AL BELISLE RDO | | DOCKET: 07000143 |FRED COMBS, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: WAYNE PHILLIPS | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | |KBBF 70.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF POWER DURING TEST CAUSES SECURITY AND CRITICALITY MONITORING SYSTEM | | FAILURES | | | | A SAFEGUARDS SYSTEM DEGRADATION RELATED TO POWER SUPPLY FUNCTION OCCURRED. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. REFER TO THE HOO | | LOG FOR ADDITIONAL DETAILS. | | | | * * * UPDATE AT 1536 ON 09/29/98 FROM ROSENBERGER TAKEN BY STRANSKY * * * | | | | THIS EVENT IS ALSO REPORTABLE UNDER THE REQUIREMENTS OF 10CFR70.50(b)(ii) | | BECAUSE THE CRITICALITY MONITORING INSTRUMENTS BECAME INOPERABLE FOR | | APPROXIMATELY 4 MINUTES DURING THE EVENT. DUE TO SECURITY/SAFEGUARDS | | CONCERNS, NO ADDITIONAL DETAILS ARE PROVIDED IN THIS REPORT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS UPDATE BY THE | | LICENSEE. THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (BOLAND) AND NMSS EO | | (COMBS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34849 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/29/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 11:14 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/29/98 | +------------------------------------------------+EVENT TIME: 10:30[EDT]| |NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 09/29/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HYDROSTATIC TEST OF THE 'B' ISOLATION CONDENSER TUBE SHEET SHOWED A | | LACK OF TUBE INTEGRITY. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING OUR CURRENT REFUELING OUTAGE, OYSTER CREEK DISCOVERED MINOR LEAKAGE | | FROM THE TUBE SHEET ON [THE] 'B' ISOLATION CONDENSER WHILE PERFORMING A | | HYDROSTATIC TEST. THE PLANT'S DESIGN BASES ASSUMES ZERO LEAKAGE." | | | | "OYSTER CREEK IS CURRENTLY SHUTDOWN, AND THE NECESSARY REPAIRS WILL BE | | COMPLETED PRIOR TO RESTART. THIS CONDITION IS REPORTABLE UNDER | | 10CFR50.72(b)(2)(i) FOR (PREVIOUS) OPERATION OF THE PLANT OUTSIDE [THE] | | DESIGN BASIS." | | | | THERE ARE TWO ISOLATION CONDENSERS EACH CONTAINING TWO TUBE BUNDLES | | CONNECTED TO THE REACTOR COOLANT SYSTEM (RCS). DURING NORMAL OPERATION THE | | ISOLATION CONDENSER'S TUBE BUNDLES ARE PRESSURIZED FROM THE RCS AND | | ISOLATED ON THE OUTLET OF TUBE SIDE. THE LICENSEE PERFORMS PERIODIC | | SAMPLING DURING POWER OPERATION TO ASCERTAIN TUBE INTEGRITY. THERE WAS NO | | INDICATION OF ANY TUBE TO SHELL LEAKAGE. ELEVATED SHELL TEMPERATURES WERE | | ATTRIBUTED TO KNOWN LEAKBY ON THE RETURN ISOLATION VALVES. DURING THE 'B' | | ISOLATION CONDENSER HYDROSTATIC TEST ONE TUBE BUNDLE WAS WETTED WHILE THE | | OTHER SPRAYED. THE 'A' ISOLATION CONDENSER HAS NOT BEEN TESTED. THE | | ISOLATION CONDENSERS ARE NOT REQUIRED BY TECHNICAL SPECIFICATIONS FOR | | CURRENT PLANT CONDITIONS. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34850 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/29/98 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:16 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 09/29/98 | +------------------------------------------------+EVENT TIME: 13:15[EDT]| |NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 09/29/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN UNAUTHORIZED ENTRY INTO THE PROTECTED AREA OCCURRED BY A CONTRACT | | EMPLOYEE. IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE | | LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR | | ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34851 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/29/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:33 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/29/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:20[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/29/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |GARY SHEAR RDO | | DOCKET: 0707001 |ROBERT PIERSON, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEVIN BEASLEY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT DUE TO INOPERABLE CRITICALITY ACCIDENT ALARM CLUSTER | | | | AT 0120 CDT, THE C-300 CENTRAL CONTROL FACILITY RECEIVED A TROUBLE ALARM ON | | THE "K" CRITICALITY ACCIDENT ALARM SYSTEM (CAAS) CLUSTER LOCATED IN THE | | C-331 CASCADE BUILDING. AN OPERATOR WAS DISPATCHED TO INVESTIGATE THE | | ALARM. THE OPERATOR REPORTED THAT THE LEFT MODULE WAS IN FAULT AND THE | | CENTER MODULE WAS READING ZERO. (A READING OF ZERO INDICATES THAT THE | | MODULE WAS NOT OPERATING PROPERLY.) WITH THE TWO MODULES NOT WORKING | | PROPERLY, THE "K" CAAS CLUSTER COULD NOT HAVE PERFORMED ITS INTENDED SAFETY | | FUNCTION. OTHER CAAS CLUSTERS LOCATED IN THE C-331 BUILDING DO NOT PROVIDE | | OVERLAPPING COVERAGE OF THE AREA COVERED BY THE "K" CAAS CLUSTER. | | APPROPRIATE ACTIONS WERE TAKEN IN ACCORDANCE WITH THE TECHNICAL SAFETY | | REQUIREMENTS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY PADUCAH PERSONNEL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34852 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/29/98 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/29/98 | +------------------------------------------------+EVENT TIME: 14:00[CDT]| |NRC NOTIFIED BY: S. BRILEY |LAST UPDATE DATE: 09/29/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ROD BLOCK MONITORS DECLARED INOPERABLE ON BOTH UNITS | | | | THE ROD BLOCK MONITORS ON BOTH UNITS 2 AND 3 WERE DISCOVERED TO HAVE | | INOPERABLE LPRM COUNT CIRCUITS. DEPENDING ON THE PREVIOUSLY SELECTED | | CONTROL ROD, THE POTENTIAL EXISTS FOR THE ROD BLOCK MONITOR TO DETECT MORE | | LPRM INPUTS THAN ARE ACTUALLY PRESENT (50% OF LPRMS ARE REQUIRED). WHEN | | THIS OCCURS, THE ROD BLOCK MONITOR WILL NOT PROVIDE THE REQUIRED "INOP" | | TRIP AND ROD BLOCK. THE UPSCALE AND DOWNSCALE TRIPS REMAIN UNAFFECTED. THE | | LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THIS CONDITION. ALL ROD | | BLOCK MONITORS ARE CURRENTLY TRIPPED IN ACCORDANCE WITH PLANT TECHNICAL | | SPECIFICATIONS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34853 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 09/29/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:50 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 09/29/98 | +------------------------------------------------+EVENT TIME: 16:20[EDT]| |NRC NOTIFIED BY: JOHN SCHORK |LAST UPDATE DATE: 09/29/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | MISSING THERMOLAG FIRE BARRIER | | | | DURING THE REMOVAL OF THERMOLAG MATERIAL, A FIRE RESISTANT MATERIAL THAT | | WAS INSTALLED IN 1987 TO MEET THE REQUIREMENTS OF 10 CFR PART 50, APPENDIX | | R, WORKERS OBSERVED THAT IT APPEARED, BUT COULD NOT BE CONFIRMED, THAT A | | PORTION OF FIRE BARRIER "1 FHC-FB-20" (APPROXIMATELY ONE FOOT IN LENGTH) | | LOCATED IN FIRE ZONE FH-FZ-1 IN THE 281' ELEVATION OF THE TMI-1 FUEL | | HANDLING BUILDING DID NOT HAVE A REQUIRED FILLET OF TROWEL GRADE MATERIAL | | 330-1 WHERE THE THERMOLAG PANEL ABUTTED AGAINST THE REACTOR BUILDING WALL. | | THE THERMOLAG WAS BEING REMOVED IN PREPARATION FOR ITS REPLACEMENT WITH | | MECATISS. LATER IN THE DAY, THE FIRE BARRIER WAS DISASSEMBLED TO ENABLE A | | DETAILED VISUAL INSPECTION OF THE POTENTIAL NONCONFORMING SECTION OF THE | | FIRE BARRIER. THAT VISUAL INSPECTION CONFIRMED THAT A FILLET OF TROWEL | | GRADE MATERIAL HAD NOT BEEN APPLIED AT THE TIME OF INSTALLATION OF THE FIRE | | BARRIER AS REQUIRED IN THE FIRE BARRIER DESIGN DOCUMENTATION. | | | | THE CONTROL ROOM WAS NOTIFIED, AND A FIRE WATCH WAS POSTED IN ACCORDANCE | | WITH THE SITE FIRE PROTECTION PROGRAM PROCEDURE. AT 1620, THE TMI PLANT | | REVIEW GROUP CONCLUDED A REVIEW OF THE NONCONFORMING CONDITION AND | | DETERMINED THAT THE CONDITION WAS IMMEDIATELY REPORTABLE TO THE NRC IN | | ACCORDANCE WITH 10CFR50.72(b)(1)(ii) AS A CONDITION OUTSIDE OF THE DESIGN | | BASIS OF THE PLANT AND AS A SUPPLEMENT TO EARLIER SIMILAR NOTIFICATIONS | | MADE ON 08/25/98 (#34682) AND 09/14/98 (#34769). THE CONDITION WAS | | DETERMINED TO BE REPORTABLE BECAUSE THE FIRE BARRIER DID NOT CONFORM TO ITS | | DESIGN BASIS AND THERE WAS REASONABLE JUSTIFICATION THAT THE NONCONFORMING | | CONDITION WAS NOT THE RESULT OF AGE-RELATED DEGRADATION BUT RATHER AN | | INCORRECT INSTALLATION. THERE IS SOME POSSIBILITY THAT ADDITIONAL SIMILAR | | CONDITIONS MAY BE DISCOVERED DURING THE COMPLETION OF THE PROJECT IN WHICH | | THERMOLAG IS BEING REPLACED WITH MECATISS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34854 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 09/30/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:07 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 09/30/98 | +------------------------------------------------+EVENT TIME: 02:06[CDT]| |NRC NOTIFIED BY: REED |LAST UPDATE DATE: 09/30/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM FROM 100% POWER ON A LOW REACTOR WATER LEVEL | | SIGNAL. | | | | THE PLANT HAD GROUP 2 AND GROUP 3 ISOLATIONS ALONG WITH THE LOW REACTOR | | LEVEL SCRAM. ALL RODS FULLY INSERTED WITH THE EXCEPTION OF ONE WHICH | | BOUNCED TO THE 02 POSITION. IT HAS BEEN FULLY INSERTED. NO SAFETY VALVES | | LIFTED, AND NO ECCS INITIATIONS OCCURRED. THE REACTOR WATER LEVEL | | INITIALLY DROPPED TO -20" AND SUBSEQUENTLY INCREASED TO +60.5". THE | | REACTOR FEED PUMPS TRIPPED ON REACTOR HIGH LEVEL, BUT LEVEL WAS RESTORED TO | | 30" WITH ONE REACTOR FEED PUMP RUNNING. REACTOR PRESSURE IS STABLE AT 920 | | LBS. THE GROUP 2 AND 3 ISOLATIONS HAVE BEEN RESET, AND THE UNIT IS IN A | | STABLE HOT SHUTDOWN CONDITION. | | | | A PRELIMINARY INVESTIGATION HAS THE CAUSE OF THIS EVENT DUE TO AN OUT OF | | SERVICE WHICH WAS IN PROGRESS FOR THE "1A" REACTOR FEED PUMP. THIS OUT OF | | SERVICE REQUIRED ISOLATING THE FLOW INDICATOR FOR THE "1A" REACTOR FEED | | PUMP. AS IT WAS TAKEN OUT OF SERVICE, THE INDICATOR FAILED HIGH. THIS MAY | | HAVE AFFECTED THE FEED FLOW PORTION OF THE 3 ELEMENT LEVEL CONTROL, | | RESULTING IN THE LOW LEVEL CONDITION. THE LICENSEE IS CONTINUING ITS | | INVESTIGATION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+