U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/18/96 - 10/21/96 ** EVENT NUMBERS ** 30742 31034 31176 31177 31178 31179 31180 31181 31182 31183 31184 31185 31186 31187 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30742 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/12/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 12:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/12/96 | +------------------------------------------------+EVENT TIME: 12:15[EDT]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 10/18/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |NINF INFORMATION ONLY |ROBERT DENNIG, NRR EO | | |RICHARD BARRETT AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AFTER-THE-FACT NOTIFICATION TO IDENTIFY A CONDITION WHICH PREVIOUSLY | | OCCURRED (AN EVENT THAT WAS NOT ONGOING AT THE TIME OF DISCOVERY) WHICH | | EXCEEDED AN EMERGENCY ACTION LEVEL BUT WAS NOT DECLARED AS AN EMERGENCY | | | | ON JUNE 7, 1995, SALEM UNIT 2 WAS SHUTDOWN IN COMPLIANCE WITH TECHNICAL | | SPECIFICATION 3.0.3 DUE TO THE INOPERABILITY OF BOTH TRAINS OF THE RESIDUAL | | HEAT REMOVAL SYSTEM. (REFER TO EVENT #28904 FOR ADDITIONAL INFORMATION.) | | ON JUNE 8, 1995, SALEM UNIT 2 TRANSITIONED THROUGH MODE 4 INTO MODE 5. THE | | COMBINATION OF THESE TWO CONDITIONS MEET EMERGENCY ACTION LEVEL ECG, | | SECTION 4A. AN ALERT DECLARATION SHOULD HAVE BEEN MADE AND WAS NOT. THE | | RESIDUAL HEAT REMOVAL SYSTEM WAS FUNCTIONAL AT THE TIME AND WAS UTILIZED TO | | PLACE SALEM UNIT 2 IN COLD SHUTDOWN. THE REACTOR IS CURRENTLY IN A | | DEFUELED CONDITION, AND ALL FUEL IS BEING STORED AND COOLED IN THE SPENT | | FUEL POOL. | | | | THE LICENSEE STATED THAT THIS NOTIFICATION WAS BEING MADE AS A ONE-HOUR | | REPORT PER ATTACHMENT 12 OF THE LICENSEE'S EMERGENCY ACTION LEVEL | | PROCEDURES. THIS WAS REQUIRED BECAUSE OF THE DISCOVERY OF AN EVENT OR | | CONDITION THAT HAD PREVIOUSLY OCCURRED (AND WAS NOT ONGOING AT THE TIME OF | | DISCOVERY) WHICH EXCEEDED AN EMERGENCY ACTION LEVEL BUT WAS NOT DECLARED AS | | AN EMERGENCY AND BECAUSE THERE ARE CURRENTLY NO ADVERSE CONSEQUENCES IN | | PROGRESS AS A RESULT OF THE EVENT. (AN EMERGENCY DECLARATION WILL NOT BE | | MADE FOR THIS EVENT BECAUSE THE LICENSEE DOES NOT DECLARE RETROACTIVE | | EMERGENCY CLASSIFICATIONS.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | | | ***SUPPLEMENT REPORTED BY JOHN ROBERTSON @ 1446 EDT ON 10/18/96, TAKEN BY | | MACKINNON*** | | | | DURING A REVIEW OF THE RESIDUAL HEAT REMOVAL (RHR) NORMAL OPERATING | | PROCEDURE, THE PROCEDURE WRITERS DISCOVERED THAT THE FLOW CONTROL VALVES | | (RH-18) WERE BOTH CLOSED IN MODE 4 TO OBTAIN AN RHR BORON SAMPLE. IN JULY | | 1996, THE OPERATING EXPERIENCE PROGRAM DISTRIBUTED INFORMATION ON AN RHR | | EVENT IN JUNE 1995 WHERE THE ALERT HAD NOT BEEN DECLARED WITH BOTH TRAINS | | OF RHR AVAILABLE BUT NOT OPERABLE. AS A RESULT, THESE PERSONNEL RECOGNIZED | | THAT THIS CONDITION SHOULD HAVE RESULTED IN AN "ALERT" DECLARATION DURING | | PREVIOUS PLANT OPERATIONAL SHUTDOWNS, SINCE BOTH RHR LOOPS WOULD HAVE BEEN | | BLOCKED FROM THE COLD LEG INJECTION MODE. IN ACCORDANCE WITH ECG-17D, THIS | | REPORT IS BEING SUBMITTED AS A SUPPLEMENT TO THE ABOVE EVENT REPORTED ON | | 07/12/96. CURRENTLY, BOTH SALEM UNITS ARE IN THE DEFUELED MODE, AND THE | | RHR SYSTEM IS NOT REQUIRED TO BE OPERABLE TO MITIGATE DESIGN BASIS | | ACCIDENTS. THERE IS NO SIGNIFICANT IMPACT ON THE HEALTH AND SAFETY OF THE | | PUBLIC DUE TO THIS PROBLEM WITH THE UNIT IN THIS MODE OF OPERATION. THE | | CONDITION IN THIS REPORT WOULD HAVE BEEN REPORTED IN ACCORDANCE WITH 10 CFR | | 50.72(a)(1), AS DELINEATED IN NUREG 1022, SECTION 3.1.1. PLANT PROCEDURES | | WILL BE CHANGED TO PREVENT THIS TYPE OF INCIDENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | | THE R1DO (HERB WILLIAMS) WAS NOTIFIED OF THIS EVENT BY THE NRC OPERATIONS | | CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31034 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/20/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:41 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/20/96 | +------------------------------------------------+EVENT TIME: 14:27[EDT]| |NRC NOTIFIED BY: LANGAN |LAST UPDATE DATE: 10/18/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KEIMIG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSTULATED FAILURE OF OFFSITE DISTRIBUTION SYSTEM COULD CAUSE A LOSS OF | | OFFSITE POWER. | | | | THE LICENSEE HAS DETERMINED THAT THE FAILURE OF A PARTICULAR TOWER IN THE | | OFFSITE ELECTRICAL DISTRIBUTION SYSTEM COULD, UNDER CERTAIN CIRCUMSTANCES, | | CAUSE A LOSS OF OFFSITE POWER TO ALL UNITS. PARTICULARLY, IF ALL UNITS | | WERE OPERATING WITH ELECTRICAL GENERATION OF 2600 MWe, THE FAILURE OF THIS | | PARTICULAR TOWER COULD DISRUPT THREE SEPARATE DISTRIBUTION CIRCUITS, AND | | THE RESULTANT GRID DISTURBANCE COULD CAUSE A LOSS OF OFFSITE POWER TO THE | | UNITS. THE LICENSEE REPORTED THAT THIS NOTIFICATION IS SIMILAR TO | | MILLSTONE LER 92-20. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1009 ON 10/18/96, BY KULTERMAN ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE HAS EVALUATED THE POSSIBILITY THAT A TALL DOUBLE-CIRCUIT STEEL | | TRANSMISSION TOWER COULD FALL ONTO THE ADJACENT H-FRAME CIRCUIT THEREBY | | CAUSING THE LOSS OF 3 OF THE 4 345-KV TRANSMISSION LINES INTERCONNECTING | | THE STATION TO THE BULK POWER GRID. THE LICENSEE TRANSMISSION ENGINEERING | | DEPARTMENT HAS DETERMINED THAT EVEN IF IT IS POSTULATED THAT THE TALLER | | STEEL POLE FALLS WITHOUT BUCKLING BY PIVOTING AT ITS BASE, IT WILL NOT HIT | | THE ADJACENT CIRCUIT NOR WILL IT FALL WITHIN ARC STRIKING DISTANCE OF THE | | ADJACENT CIRCUIT. THEREFORE, IN THE WORST CASE, THE TWO CIRCUITS ON THE | | DOUBLE-CIRCUIT TOWER WOULD BE LOST. | | | | BASED ON THIS EVALUATION, THE MILLSTONE STATION HAS BOTH PHYSICAL AND | | ELECTRICAL INDEPENDENCE IN ITS TWO REQUIRED SOURCES OF OFFSITE ELECTRIC | | POWER. THIS FULLY MEETS THE REQUIREMENTS OF GENERAL DESIGN CRITERION 17, | | ELECTRIC POWER SYSTEMS. THEREFORE, THE LICENSEE DESIRES TO RETRACT THIS | | EVENT REPORT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (HERB WILLIAMS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31176 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 10/18/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 04:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/96 | +------------------------------------------------+EVENT TIME: 03:06[CDT]| |NRC NOTIFIED BY: ELIZABETH MEADERS |LAST UPDATE DATE: 10/18/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN 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 Rx TRIP DUE TO LOSS OF RCP DUE TO FAILED SUPPLY BUS LOCKOUT RELAY - | | | | AT 0306 (CDT), UNIT 2 AUTOMATICALLY TRIPPED FROM 100% POWER DUE TO THE LOSS | | OF 1 OF 4 REACTOR COOLANT PUMPS (#2-03). THE RCP WAS LOST DUE TO THE LOSS | | OF ITS SUPPLY BUS (#2A3) WHICH WAS DUE TO A LOCKOUT RELAY THAT FAILED FOR | | UNKNOWN REASONS. ALL CONTROL RODS INSERTED COMPLETELY. THE AUXILIARY | | FEEDWATER SYSTEM AUTOMATICALLY STARTED ON LOW-LOW STEAM GENERATOR WATER | | LEVEL AS EXPECTED AND RESTORED STEAM GENERATOR WATER LEVELS TO NORMAL. | | STEAM IS BEING DUMPED TO THE MAIN CONDENSER. UNIT 2 IS STABLE IN MODE 3 | | (HOT STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FAILED LOCKOUT RELAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31177 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 10/18/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 10:45 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 10/18/96 | +------------------------------------------------+EVENT TIME: 07:30[CDT]| |NRC NOTIFIED BY: TIM SMITH |LAST UPDATE DATE: 10/18/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICK-BARGER 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MORE THAN 1% OF THE STEAM GENERATOR TUBES INSPECTED WERE DEFECTIVE - | | | | THE LICENSEE HAS INSPECTED 100% (915) OF THE IN-SERVICE UNSLEEVED TUBES IN | | THE 'A' STEAM GENERATOR. THE LICENSEE'S ANALYSIS OF THE 'A' STEAM | | GENERATOR EDDY CURRENT RESULTS DETERMINED THAT MORE THAN 1% (11) OF THESE | | TUBES INSPECTED (IN THE HOT LEG CREVICE) WERE DEFECTIVE. | | | | THE LICENSEE PLANS TO PLUG THE DEFECTIVE TUBES AND TO ENSURE THAT THE | | PLUGGING RATE DOES NOT RESULT IN AN UNANALYZED CONDITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31178 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ABB COMBUSTION ENGINEERING NUCLEAR |NOTIFICATION DATE: 10/18/96 | | CITY: WINDSOR REGION: 1 |NOTIFICATION TIME: 15:10 [ET]| | COUNTY: STATE: CT |EVENT DATE: 10/18/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 15:15[EDT]| | DOCKET: |LAST UPDATE DATE: 10/18/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE (NRR) PCEB | |NRC NOTIFIED BY: MOLNAR/RICKARD | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REPORTING OF DEFECTS AND NONCOMPLIANCE | | | | THE IDENTIFIED DEFECT INVOLVES THE APPLICATION OF CERTAIN ASPECTS OF THE | | ABB COMBUSTION ENGINEERING (ABB-CE) RELOAD SAFETY ANALYSIS METHODOLOGY. | | | | SPECIFICALLY, THE IDENTIFIED DEFECT CONCERNS THE SCREENING METHODOLOGY USED | | BY ABB-CE TO ASSESS THE CONTINUED CONSERVATISM AND APPLICABILITY OF THE | | DEPARTURE FROM NUCLEATE BOILING RATIO (DNBR) PROBABILITY DISTRIBUTION | | FUNCTION (PDF) FROM CYCLE-TO-CYCLE. THIS ASSESSMENT IN TURN PROVIDES | | ASSURANCE THAT THE FUEL DNBR SPECIFIC ACCEPTABLE FUEL DESIGN LIMIT (SAFDL) | | WILL NOT BE VIOLATED. IT IS IMPORTANT TO POINT OUT THAT THE CURRENT ABB-CE | | THERMAL-HYDRAULIC STATISTICAL COMBINATION OF UNCERTAINTIES (SCU) | | METHODOLOGY USED TO EXPLICITLY DETERMINE THE PDF INPUT TO THE DNBR SAFDL | | CALCULATION IS CORRECT. RATHER, THE DEFECT INVOLVES THE EVALUATION | | CRITERION USED DURING CYCLE SPECIFIC SCREENING TO DETERMINE WHETHER OR NOT | | AN EXPLICIT SCU PDF RE-ANALYSIS IS REQUIRED TO VERIFY THE CONTINUED | | CONSERVATISM DURING THE UPCOMING CYCLE FOR THE DNBR SAFDL OF RECORD. BASED | | UPON AN EVALUATION, ABB-CE HAS CONCLUDED THAT THE ABOVE DESCRIBED SITUATION | | REPRESENTS A DEFECT AS DEFINED IN 10 CFR 21.3, "A CONDITION OR CIRCUMSTANCE | | ... THAT COULD CONTRIBUTE TO THE EXCEEDING OF A SAFETY LIMIT.." THE | | FOLLOWING POWER PLANTS ARE POTENTIALLY AFFECTED BY THIS DEFECT: ARKANSAS | | NUCLEAR ONE UNIT 2; CALVERT CLIFFS UNITS 1 AND 2; PALO VERDE UNITS 1, 2, | | AND 3; SAN ONOFRE UNITS 2 AND 3; ST. LUCIE UNIT 2; AND WATERFORD STEAM | | ELECTRIC STATION UNIT 3. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31179 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/18/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/18/96 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 10/18/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DEGRADATION OF THE STANDBY LIQUID CONTROL (SLC) SYSTEM | | | | SLC SYSTEM PERFORMANCE MAY HAVE BEEN IN A DEGRADED CONDITION DUE TO THE | | COMMON SLC STORAGE TANK BEING OPERATED AT A HIGHER THAN NORMAL OPERATING | | TEMPERATURE (ò 122øF) DURING CHEMICAL ADDITION AND SAMPLING OPERATIONS. THE | | CONCERN IS THE REQUIRED NET POSITIVE SUCTION HEAD FOR BOTH SLC PUMPS. IF | | THE TEMPERATURE OF THE SLC TANK IS ò 122øF, THE NET POSITIVE SUCTION HEAD | | WILL NOT BE SUFFICIENT TO SUPPORT A DISCHARGE FLOW RATE FROM EACH SLC PUMP | | OF ò 41.5 GPM (THE MINIMUM TECHNICAL SPECIFICATION FLOW RATE FOR EACH SLC | | PUMP). IN THE PAST, WHEN MIXING THE CHEMICAL USED IN THE SLC TANK, THE | | TEMPERATURE OF THE LIQUID INSIDE THE SLC TANK HAS BEEN AS HIGH AS 140øF. | | THE OPERATING PROCEDURE FOR THE SLC SYSTEM HAS ALWAYS HAD A MINIMUM | | TEMPERATURE AT WHICH THE SLC SYSTEM SHOULD BE MAINTAINED, BUT THE PROCEDURE | | HAS NEVER SPECIFIED A MAXIMUM TEMPERATURE LIMIT. CORRECTIVE ACTION IS TO | | ADD A MAXIMUM OPERATING TEMPERATURE LIMIT FOR THE SLC TANK. | | | | THE LICENSEE NOTIFIED LOWER ALLOWAYS CREEK TOWNSHIP OF THIS EVENT. THE NRC | | RESIDENT WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31180 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BRAIDWOOD |NOTIFICATION DATE: 10/18/96 | | CITY: BRAIDWOOD REGION: 3 |NOTIFICATION TIME: 20:33 [ET]| | COUNTY: WILL STATE: IL |EVENT DATE: 10/18/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 17:00[CDT]| | DOCKET: |LAST UPDATE DATE: 10/18/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MCCORMICK-BARGER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: RUTHERFORD/JISKRA | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE ENTERING BRAIDWOOD NUCLEAR STATION, A ROBERTS EXPRESS 22-FOOT BOX | | TRUCK WAS FOUND TO HAVE RADIOACTIVE CONTAMINATION ON ITS FLOOR IN THE CARGO | | AREA OF THE TRUCK. | | | | THE NATIONAL RESPONSE CENTER NOTIFIED THE NRC HEADQUARTERS OPERATION CENTER | | THAT THEY WERE INFORMED BY ROBERTS EXPRESS (LOCATED AT 2088 S. ARLINGTON | | ROAD, AKRON, OHIO) THAT THE CARGO AREA OF ONE ROBERTS EXPRESS TRUCK WAS | | FOUND TO HAVE RADIOACTIVE CONTAMINATION ON ITS FLOOR. ROBERTS EXPRESS WAS | | DELIVERING TWO STRONG TYPE PACKAGES (UN #2913) CONTAINING RADIOACTIVELY | | CONTAMINATED STEAM GENERATOR SLEEVING EQUIPMENT TO BRAIDWOOD NUCLEAR POWER | | STATION FROM KEWAUNEE NUCLEAR POWER STATION. THE MANIFEST STATED THAT THE | | CONTENTS IN THE TWO RADIOACTIVE STRONG TYPE PACKAGES WAS STEAM GENERATOR | | SLEEVING EQUIPMENT TO BE USED FOR UNIT 1 STEAM GENERATOR WORK. A BRAIDWOOD | | RADIATION TECHNICIAN SAID THAT THE ACTIVITY OF THE FIRST STRONG TYPE | | PACKAGE WAS 1.13E-03 CURIES, AND THE ACTIVITY OF THE OTHER STRONG TYPE | | PACKAGE WAS 1.36E-03 CURIES. WHEN ROBERTS EXPRESS ENTERED BRAIDWOOD | | NUCLEAR POWER STATION, THE BACK OF THE TRUCK WAS OPENED TO BE SEARCHED. IT | | WAS FOUND THAT THE BOLTS ON ONE OF THE TWO STRONG TYPE PACKAGES WAS LOOSE. | | THE RADIATION TECHNICIAN PERFORMED A RADIATION SURVEY (A LARGE AREA SWIPE) | | OF THE BACK OF THE TRUCK AND FOUND LOOSE SURFACE CONTAMINATION OF 3,000 | | DPM. WHEN THE RADIATION TECHNICIAN EXITED THE BACK OF THE TRUCK, HE WAS | | FOUND TO HAVE 80 CPM CONTAMINATION READINGS ON HIS FOOT. THE RADIATION | | TECHNICIAN'S FOOT WAS DECONTAMINATED. THE BACK DOORS OF THE TRUCK WERE | | CLOSED AND LOCKED. THE BRAIDWOOD RADIATION TECHNICIANS ARE PRESENTLY | | WAITING FOR INSTRUCTIONS ON HOW TO DECONTAMINATE THE BACK OF THE TRUCK. | | | | THE NRC SENIOR RESIDENT INSPECTOR CALLED THE NRC HEADQUARTERS OPERATION | | CENTER AS WELL AS THE BRAIDWOOD UNIT 1 SUPERVISOR (BOB YURKOVAICH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31181 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/18/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 23:03 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/18/96 | +------------------------------------------------+EVENT TIME: 19:18[CDT]| |NRC NOTIFIED BY: SCOTT BENHAM |LAST UPDATE DATE: 10/18/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CAIN RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT CLOSURE WAS BREACHED WHEN REFUELING OPERATIONS WERE IN | | PROGRESS. | | | | REFUELING OPERATIONS WERE IN PROGRESS FOR OFF LOADING THE CORE WHEN THE | | CONTROL ROOM WAS NOTIFIED THAT CONTAINMENT CLOSURE WAS BREACHED. ALL | | REFUELING OPERATIONS WERE IMMEDIATELY STOPPED. CRAFT PERSONNEL WERE | | IMMEDIATELY DISPATCHED TO RE-INSTALL THE BONNET ON THE INBOARD CONTAINMENT | | ISOLATION VALVE FOR "A" STEAM GENERATOR BLOWDOWN (HCV-1388A), AND | | CONTAINMENT CLOSURE WAS RE-ESTABLISHED AT 1956 CDT. TECHNICAL | | SPECIFICATION 2.8.1 REQUIRES THAT CONTAINMENT CLOSURE BE MAINTAINED DURING | | REFUELING OPERATIONS. THIS PREVENTS THE CONTAINMENT CLOSURE ENGINEERING | | SAFETY FEATURE FROM PERFORMING ITS INTENDED FUNCTION. OPERATIONS | | IMMEDIATELY INITIATED A WALKDOWN OF ALL REQUIRED PENETRATIONS TO ENSURE | | THAT ALL WERE INTACT. REFUELING OPERATIONS WILL NOT RESTART UNTIL THE | | WALKDOWN IS COMPLETED. | | | | PRIOR TO THE COMMENCEMENT OF REFUELING OPERATIONS, THE "A" STEAM GENERATOR | | MAIN STEAM ISOLATION VALVE, HCV-1041A, WAS REMOVED FOR OUTAGE MAINTENANCE | | ACTIVITIES. CONTAINMENT CLOSURE WAS BEING MAINTAINED BY ENSURING THAT ALL | | STEAM GENERATOR SECONDARY OPENINGS IN CONTAINMENT WERE CLOSED. THE OUTAGE | | CONTROL CENTER RELEASED A MAINTENANCE WORK ORDER ON HCV-1388A ON 10/17/96, | | AT 0154 CDT WITH AN ESTIMATED DURATION OF 10 HOURS. HOWEVER, THE | | MAINTENANCE ACTIVITIES WERE NOT STARTED UNTIL APPROXIMATELY 0000 CDT ON | | 10/18/96. REFUELING OPERATIONS COMMENCED AT 2158 CDT ON 10/17/96. WHEN | | THIS VALVE BONNET WAS REMOVED, THIS PROVIDED A DIRECT VENT PATH FROM THE | | CONTAINMENT THROUGH THE "A" STEAM GENERATOR TO ATMOSPHERE THROUGH THE MAIN | | STEAM LINE. THE NRC RESIDENT WAS INFORMED OF THIS BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31182 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/19/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 12:57 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/19/96 | +------------------------------------------------+EVENT TIME: 12:50[EDT]| |NRC NOTIFIED BY: EMPREY |LAST UPDATE DATE: 10/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS 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 +------------------------------------------------------------------------------+ | NON-SAFETY CLASS THERMOCOUPLE FOUND IN HIGH PRESSURE COOLANT INJECTION | | (HPCI) TURBINE CASING | | | | ON MARCH 21, 1995 A NON-NUCLEAR SAFETY THERMOCOUPLE WAS INSTALLED IN THE | | HPCI TURBINE CASING. THE THERMOCOUPLE, WHICH MONITORS THE HPCI TURBINE | | TEMPERATURE, WAS SUPPOSED TO BE SAFETY CLASS 2. THE THERMOCOUPLE ON THE | | HPCI TURBINE WAS IDENTIFIED AS THERMOCOUPLE #6, (TE-23-TC6). THIS PROBLEM | | IS CURRENTLY BEING EVALUATED BY THE LICENSEE. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS BY THE LICENSEE. | | | | * * RETRACTION BY HENRIQUEZ @ 1559 EDT ON 10/19/96, TAKEN BY MACKINNON * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE BELIEVES THAT THE | | THERMOCOUPLE DOES NOT IN ITSELF RESULT IN THE PLANT BEING IN A SERIOUSLY | | DEGRADED CONDITION. THE THERMOCOUPLE IS RATED FOR MUCH HIGHER PRESSURE | | THAN WILL BE EXPERIENCED WHILE IN SERVICE. THIS CONDITION DOES NOT RESULT | | IN ANY SAFETY BARRIER BEING SERIOUSLY DEGRADED OR SIGNIFICANTLY COMPROMISE | | PLANT SAFETY. EVEN A COMPLETE FAILURE OF THE THERMOCOUPLE WHICH RESULTED | | IN IT BEING TOTALLY EJECTED WOULD NOT HAVE PREVENTED THE HPCI SYSTEM FROM | | BEING FULLY OPERABLE AND CAPABLE OF PERFORMING ITS SAFETY FUNCTION. | | | | THE THERMOCOUPLE IS PRESENTLY BEING REMOVED SO THAT IT CAN BE UPGRADED TO | | SAFETY CLASS. THE LICENSEE EXPECTS THAT THIS UPGRADE WILL BE ACCOMPLISHED, | | AND THE EXISTING THERMOCOUPLE WILL BE REINSTALLED. THIS AGAIN DEMONSTRATES | | THAT THERE WAS NO SERIOUS DEGRADATION FROM THE INSTALLED CONFIGURATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | | THE R1DO (WILLIAMS) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31183 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DELTA INSPECTION & TESTING |NOTIFICATION DATE: 10/19/96 | | CITY: NEW ORLEANS REGION: 4 |NOTIFICATION TIME: 19:36 [ET]| | COUNTY: STATE: LA |EVENT DATE: 10/19/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 06:30[CDT]| | DOCKET: |LAST UPDATE DATE: 10/20/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES CAIN RDO | | |JOHN LINEHAN (NMSS) EO | +------------------------------------------------+BILL BEECHER (HQ) OPA | |NRC NOTIFIED BY: TOM PATTERSON | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |NAGR AGREEMENT STATE | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STOLEN TROXLER MOISTURE DENSITY GAUGE | | | | THE LOUISIANA RADIATION PROTECTION DIVISION NOTIFIED THE NRC OPERATIONS | | CENTER THAT A TROXLER MOISTURE DENSITY GAUGE HAD BEEN STOLEN. THE TROXLER | | MOISTURE DENSITY GAUGE WAS IN ITS SHIELDED POSITION, LOCKED IN ITS CASE, | | AND CHAINED AND LOCKED INSIDE A 1984 CHEVY BLAZER. THE VEHICLE WAS STOLEN | | IN EAST NEW ORLEANS BETWEEN 0630 AND 0930 CDT ON OCTOBER 19, 1996. STATE | | POLICE THINK THAT THE VEHICLE WAS STOLEN FOR ITS MAG WHEELS AND BIG TIRES | | AND NOT FOR THE TROXLER MOISTURE GAUGE. THE COLOR OF THE CHEVY BLAZER WAS | | BLUE OVER DARK GRAY. THE MODEL NUMBER OF THE TROXLER MOISTURE DENSITY | | GAUGE WAS 3411, AND IT CONTAINED 8.3 MILLICURIES OF CESIUM AND 40 | | MILLICURIES OF AMERICIUM-BERYLLIUM. THE TROXLER MOISTURE DENSITY GAUGE WAS | | LICENSED TO DELTA INSPECTION & TESTING WHICH WAS LOCATED IN NEW ORLEANS. | | | | THE STATE POLICE INFORMED LOCAL TELEVISION STATIONS THAT A NUCLEAR DEVICE | | HAD BEEN STOLEN AND THAT THIS WAS A DEADLY SERIOUS EVENT. THREE TELEVISION | | STATIONS MADE AN ANNOUNCEMENT ABOUT THE STOLEN TROXLER MOISTURE DENSITY | | GAUGE. | | | | *** 1000 OCTOBER, 20, 1996, UPDATE FROM PATTERSON RECEIVED BY TROCINE *** | | | | THE LOUISIANA RADIATION PROTECTION DIVISION NOTIFIED THE NRC OPERATIONS | | CENTER THAT THE VEHICLE CONTAINING THE MISSING MOISTURE DENSITY GAUGE HAD | | BEEN FOUND BY THE POLICE AND THAT THE GAUGE WAS CURRENTLY IN THE LICENSEE'S | | POSSESSION. APPARENTLY, THE STOLEN VEHICLE WAS LOCATED AT 0230 CDT ON | | OCTOBER 20, 1996, IN NEW ORLEANS NEAR THE LOCATION THAT IT HAD BEEN STOLEN | | FROM. THE VEHICLE HAD BEEN STRIPPED AND DUMPED, BUT THE GAUGE WAS STILL | | LOCATED IN THE BACK. THE SOURCE WAS ALSO STILL LOCKED IN ITS SHIELDED | | POSITION. AT 0855 CDT, THE LOUISIANA RADIATION PROTECTION DIVISION | | (LOCATED IN BATON ROUGE) WAS NOTIFIED THAT THE GAUGE HAD BEEN RECOVERED. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R4DO (CAIN), NMSS EO (LINEHAN), AND | | HQ OPA (BEECHER). (REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 10/19/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 23:07 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/19/96 | +------------------------------------------------+EVENT TIME: 23:05[EDT]| |NRC NOTIFIED BY: DAN BOYLE |LAST UPDATE DATE: 10/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 2 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL SHUTDOWN FROM 2% REACTOR POWER IN ORDER TO REPAIR 1 OF 16 SAFETY | | RELIEF VALVE (SRV) ACOUSTIC MONITORS | | | | SRV 1F-013L ACOUSTIC MONITOR FAILED (WENT INTO ITS ALARM STATE). THE | | LICENSEE'S TECHNICAL SPECIFICATIONS REQUIRE THAT ALL SRV ACOUSTIC MONITORS | | BE OPERABLE WHEN THE REACTOR IS CRITICAL. SRV 1F-013L DID NOT OPEN, BUT | | ITS ACOUSTIC MONITOR FAILED. THE LICENSEE WILL INSERT ALL CONTROL RODS | | FULLY INTO THE CORE BEFORE PLACING THE REACTOR MODE SWITCH IN THE SHUTDOWN | | POSITION. THE REACTOR WILL BE SHUT DOWN WITHIN THE NEXT 6 HOURS. THE | | REACTOR HAD STARTED UP EARLIER TODAY. THE RESTART DATE WILL BE EITHER | | OCTOBER 20 OR 21, 1996. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31185 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/20/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 06:36 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/20/96 | +------------------------------------------------+EVENT TIME: 06:30[EDT]| |NRC NOTIFIED BY: STEVE FULLER |LAST UPDATE DATE: 10/20/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS 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 N 0 STARTUP | 0 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANNED PRESS RELEASE TO ANNOUNCE A UNIT STARTUP AFTER THE PERFORMANCE OF A | | REFUELING OUTAGE | | | | THE LICENSEE IS CURRENTLY IN THE PROCESS OF COMMENCING A UNIT STARTUP AFTER | | THE PERFORMANCE OF A REFUELING OUTAGE WHICH BEGAN ON SEPTEMBER 4, 1996. AS | | A RESULT, THE LICENSEE PLANS TO ISSUE A PRESS RELEASE LATER TODAY. THE | | LICENSEE ALSO PLANS TO PLACE THE UNIT ON LINE TOMORROW. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31186 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 10/20/96 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 14:27 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 10/20/96 | +------------------------------------------------+EVENT TIME: 13:37[EDT]| |NRC NOTIFIED BY: STEEL |LAST UPDATE DATE: 10/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 20 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 20% POWER DUE TO A TURBINE TRIP WHILE AT GREATER THAN 10% | | POWER | | | | THIS EVENT OCCURRED WHILE THE UNIT WAS COMING BACK ON LINE FROM A REFUELING | | OUTAGE. WITH ALL FEEDWATER REGULATING VALVES IN AUTOMATIC, THE "B" | | FEEDWATER REGULATING VALVE FAILED OPEN. AN OPERATOR THEN TOOK MANUAL | | CONTROL TO CLOSE THE "B" FEEDWATER REGULATING VALVE BUT WAS UNABLE TO CLOSE | | IT BEFORE THE HIGH LEVEL TRIP SETPOINT WAS REACHED IN THE "B" STEAM | | GENERATOR. THIS SIGNAL RESULTED IN A TURBINE TRIP AND MAIN FEEDWATER PUMP | | TRIP. THE TURBINE TRIP WHILE AT GREATER THAN 10% POWER CAUSED THE REACTOR | | TRIP. BOTH REACTOR TRIP BREAKERS OPENED. ALL RODS FULLY INSERTED, NO | | SAFETY INJECTION OCCURRED, AND NO POWER OPERATED RELIEF VALVES LIFTED. THE | | AUXILIARY FEEDWATER PUMPS STARTED AS EXPECTED WHEN THE MAIN FEEDWATER PUMPS | | TRIPPED. THE CAUSE OF THE "B" FEEDWATER REGULATING VALVE FAILURE IS | | UNKNOWN AND IS BEING INVESTIGATED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 10/20/96 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 16:28 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/20/96 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: ZIMMERMAN |LAST UPDATE DATE: 10/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENGINEERED SAFETY FEATURE (ESF) ACTUATION DUE TO AN UNDERVOLTAGE TRANSIENT | | ON BUS "1Y21" WHICH IS THE DIVISION 2 INSTRUMENTATION AC BUS | | | | THIS BUS UNDERVOLTAGE TRANSIENT (3 SECONDS) CAUSED COMPLETE CONTAINMENT | | ISOLATION (GROUP 3) AND A REACTOR WATER CLEANUP ISOLATION SIGNAL (GROUP 5). | | THE UNIT IS IN A TEMPORARY POWER LINEUP ON THE DIVISION 2 SIDE OF THE | | INSTRUMENT AC BUS DUE TO THE OUTAGE. A POWER CART WHICH HAD OTHER LOADS | | CONNECTED WAS ALSO POWERED OFF THIS SAME SOURCE. IT APPEARS THAT AS LOADS | | WERE BEING ADDED AND REMOVED FROM THIS POWER CART, IT CAUSED A FLUCTUATION | | OF POWER TO THE REG TRANSFORMER WHICH RESULTED IN THE LOADS BEING STRIPPED | | OFF. THIS CONDITION CAUSED THE ESF ACTUATION. THE LICENSEE HAS NOT RESET | | THE SIGNALS AND IS REMOVING THE POWER CART FROM THAT POWER SOURCE. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+