U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/09/95 - 06/12/95 ** EVENT NUMBERS ** 28888 28916 28917 28918 28919 28920 28921 28922 28923 28924 28925 28926 28927 28928 28929 28930 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28888 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 06/03/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 01:57 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/02/95 | +------------------------------------------------+EVENT TIME: 23:16[EDT]| |NRC NOTIFIED BY: RUSS KEARNEY |LAST UPDATE DATE: 06/09/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR WATER CLEANUP ISOLATION / LOSS OF A 120 VAC INSTRUMENT BUS | | | | A PRIMARY SIDE FUSE TO TRANSFORMER 1R-25-SO-25 BLEW CAUSING A LOSS OF POWER | | TO 120 VAC BUS EB1A1. THE TRANSFORMER REDUCES VOLTAGE FROM 480 TO 120 | | VOLTS AND IS THE ONLY SOURCE OF POWER TO BUS EB1A1. THE BLOWN FUSE IS | | RATED AT 40 AMPS. THE ASSOCIATED BREAKER WITH AN 80 AMP SET POINT DID NOT | | TRIP. OPERATORS NOTED THAT VARIOUS RELAYS ASSOCIATED WITH THE BUS WERE | | CYCLING PRIOR TO THE FUSE BLOWING. | | | | THE LOSS OF BUS EB1A1 CAUSED THE RWCU SYSTEM TO ISOLATE. SOME OF THE MORE | | IMPORTANT LOADS ALSO LOST ARE: TRAIN A OF STANDBY LIQUID CONTROL SYSTEM, | | DIV 1 OF LEAK DETECTION SYSTEM & ALARMS & INDICATIONS ASSOCIATED WITH ECCS. | | | | THE PLANT ENTERED TECH SPEC 3.8.1.3 AT 2316 AND IS IN AN EIGHT HOUR ACTION | | STATEMENT TO RESTORE BUS EB1A1. IF THE BUS IS NOT RESTORED THE PLANT MUST | | BE SHUTDOWN WITHIN THE NEXT 12 HOURS AND PLACED IN COLD SHUTDOWN WITHIN THE | | FOLLOWING 24 HOURS. THE LICENSEE IS TROUBLESHOOTING THE PROBLEM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0935 ON 06/09/95 BY MLACHAK ENTERED BY HOO JOLLIFFE * * * | | | | LICENSEE DESIRES TO RETRACT THIS EVENT SINCE THE RWCU SYSTEM ISOLATION WAS | | INITIATED BY AN INVALID SIGNAL CAUSED BY THE LOSS OF THE 120 VAC BUS AND | | THUS DOES NOT MEET THE REPORTING CRITERIA OF 10CFR50.72 & 50.73. LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R3DO SHEAR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28916 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/09/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 03:23 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/09/95 | +------------------------------------------------+EVENT TIME: 00:07[EDT]| |NRC NOTIFIED BY: LONG |LAST UPDATE DATE: 06/09/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - HPCI SYSTEM INOP DUE TO LARGE ELECTRICAL GROUND DURING OPERABILITY TEST - | | | | DURING THE PERFORMANCE OF A HPCI SYSTEM OPERABILITY TEST, A SIGNIFICANT | | ELECTRICAL GROUND INDICATION ON THE 'A' BATTERY BUS WAS RECEIVED DUE TO | | A LARGE GROUND IN THE HPCI BAROMETRIC CONDENSER VACUUM PUMP. THIS CAUSED | | AN INCREASE IN INDICATED HPCI TURBINE SPEED AND A DECREASE IN INDICATED | | SYSTEM FLOWRATE. HOWEVER, ACTUAL HPCI TURBINE SPEED REMAINED CONSTANT. | | | | WITH THE HPCI SYSTEM INOPERABLE FOR THE TEST, TECH SPEC LCO A/S 3.5.1 | | REQUIRES LICENSEE TO RESTORE THE HPCI SYSTEM TO OPERABLE STATUS WITHIN | | 14 DAYS OR TO PLACE UNIT 1 IN AT LEAST HOT SHUTDOWN CONDITION WITHIN | | THE NEXT 12 HOURS PROVIDED THE AUTO DEPRESSURIZATION, CORE SPRAY, AND | | LPCI SYSTEMS ARE IN OPERABLE STATUS (WHICH THEY ARE). | | | | LICENSEE IS TAKING CORRECTIVE ACTIONS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28917 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: J. C. BLAIR MEMORIAL HOSPITAL |NOTIFICATION DATE: 06/09/95 | | CITY: HUNTINGDON REGION: 1 |NOTIFICATION TIME: 10:27 [ET]| | COUNTY: STATE: PA |EVENT DATE: 06/08/95 | |LICENSE#: 37-03552-02 AGREEMENT: N |EVENT TIME: 10:45[EDT]| | DOCKET: |LAST UPDATE DATE: 06/09/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WALT PASCIAK RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JUDY WELLER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PATIENT WAS INCORRECTLY GIVEN 25 millicuries of Tc-99m. | | | | J. C. BLAIR MEMORIAL HOSPITAL, HUNTINGDON, PA, REPORTED THAT ONE OF THEIR | | PATIENTS WAS INJECTED WITH 25 millicuries of Tc-99m FOR A BONE SCAN | | (OSTOSCAN HDP). IT WAS DISCOVERED LATER THAT THE PATIENT WAS NOT TO HAVE | | RECEIVED THE BONE SCAN. A NURSE MISINTERPRETED A DOCTORS ORDER. THE PATIENT | | DID NOT RECEIVE ANY ADVERSE HEALTH PROBLEMS FROM THIS ERROR. THE PATIENT'S | | PHYSICIAN WAS NOTIFIED OF THE MEDICAL MISADMINISTRATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28918 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/09/95 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/09/95 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: PETER WELLS |LAST UPDATE DATE: 06/09/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAD PREVIOUSLY REPORTED TO THE NRC RESIDENT INSPECTOR ON | | 2/2/95, THAT A NON-SUPERVISORY LICENSED REACTOR OPERATOR WAS REMOVED FROM | | DUTY AND ENTERED A PROGRAM DUE TO SUBSTANCE ABUSE. SUBSEQUENT INFORMATION | | RECEIVED BY THE LICENSEE INDICATED THAT THE INDIVIDUAL'S ABUSE PROBLEM ALSO | | INVOLVED A CONTROLLED SUBSTANCE. FOLLOW UP ACTION BY THE LICENSEE BASED ON | | THE NEW INFORMATION IS IN PROGRESS. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28919 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 06/09/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:05 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/09/95 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: JERRY RADISHOFSKI |LAST UPDATE DATE: 06/09/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ERRONEOUS RECIRC PUMP POWER INDICATION CAUSED A 1 MWt NON-CONSERVATIVE | | CALCULATION OF THE HEAT BALANCE AND CORE THERMAL POWER. | | | | THE LICENSEE DISCOVERED THAT THE POWER INDICATION FOR THE 2A RECIRC PUMP | | WAS HIGHER THAN THE ACTUAL VALUE. THIS INCREASE IN PUMP HEAT CAUSED THE | | CALCULATION OF CORE THERMAL POWER TO BE APPROXIMATELY 1 MWt LOWER THAN THE | | ACTUAL VALUE. AS A RESULT OF THIS ERROR THE LICENSEE CONSIDERS THAT IT IS | | POSSIBLE THAT UNIT 2 MAY HAVE EXCEEDED ITS STEADY STATE POWER LIMIT OVER A | | SHIFT AVERAGE. THIS IS BEING REPORTED AS A LICENSE CONDITION VIOLATION. | | | | THE LICENSEE VERIFIED THAT NO LICENSE SAFETY LIMITS WERE APPROACHED, THE | | OPERABILITY OF PLANT SYSTEMS IS NOT AFFECTED, AND CORRECTIVE ACTIONS HAVE | | BEEN TAKEN. SEE EVENTS #28371 AND #28925. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28920 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 06/10/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 02:47 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 06/09/95 | +------------------------------------------------+EVENT TIME: 23:23[CDT]| |NRC NOTIFIED BY: TOM HOUZENGA |LAST UPDATE DATE: 06/10/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -RPS ELECTRICAL PROTECTION ASSEMBLY TRIPPED DUE TO UNDERVOLTAGE CONDITION- | | | | AT 2323 (CDT) ON 06/09/95, THE #1A1 REACTOR PROTECTION SYSTEM ELECTRICAL | | PROTECTION ASSEMBLY TRIPPED DUE TO AN UNDERVOLTAGE CONDITION CAUSING A | | HALF SCRAM SIGNAL, PARTIAL PCIS GROUP 1, 2, & 3 ISOLATIONS INCLUDING A | | LOSS OF POWER TO SELECTED RADIATION MONITORS, ISOLATION OF REACTOR | | BUILDING VENTILATION SYSTEM, ISOLATION OF CONTROL ROOM VENTILATION SYSTEM, | | AUTO START OF STANDBY GAS TREATMENT SYSTEM, AND CLOSURE OF SEVERAL PRIMARY | | CONTAINMENT ISOLATION VALVES. | | | | BY 2328 (CDT), LICENSEE RESET ALL SYSTEMS TO NORMAL. HOWEVER, THE #1A MAIN | | STEAM LINE RADIATION MONITOR WOULD NOT RESET FROM ITS DOWN SCALE READING. | | LICENSEE INSERTED A HALF SCRAM SIGNAL AND A HALF PCIS GROUP 1 ISOLATION | | SIGNAL PER TECH SPEC REQUIREMENTS WHILE REPAIRS ARE BEING MADE. | | | | NO TESTING OR MAINTENANCE ACTIVITIES WERE BEING CONDUCTED AT THE TIME OF | | THE ESF ACTUATION. | | | | LICENSEE IS INVESTIGATING THE CAUSE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28921 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 06/10/95 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 03:40 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 06/10/95 | +------------------------------------------------+EVENT TIME: 01:13[EDT]| |NRC NOTIFIED BY: LEWIS / CROMWELL |LAST UPDATE DATE: 06/10/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -BREAKER TRIP DURING EDG TEST CAUSED POWER PEAK TO 103% AND ESF ACTUATION- | | | | AT 0113, DURING POST MAINTENANCE TESTING OF THE #E-2 EDG, THE OUTPUT | | CIRCUIT BREAKER FOR ELECTRICAL BUS #E-22 TRIPPED DUE TO A BACKFEED CIRCUIT | | WHICH WAS NOT IDENTIFIED IN THE DESIGN OF A RECENTLY COMPLETED PLANT | | MODIFICATION. | | | | THE DEENERGIZATION OF BUS #E-22 CAUSED A TRIP OF THE 'B' RPS M/G SET, | | A CHANNEL 'B' HALF REACTOR SCRAM SIGNAL, THE LOSS OF THE 'B' FEEDWATER | | HEATER STRING, A HALF PCIS GROUP 1 ISOLATION, AN OUTBOARD PCIS GROUPS 2 & 3 | | ISOLATION, THE AUTO START OF THE RBCCW PUMP, A RWCU SYSTEM ISOLATION, AN | | INSTRUMENT NITROGEN SYSTEM ISOLATION, A CONTAINMENT ATMOSPHERIC SAMPLING | | SYSTEM ISOLATION, AND A SBGT SYSTEM INITIATION. | | | | REACTOR POWER PEAKED AT 3552 MWT (103% POWER) DUE TO THE LOSS OF FEEDWATER | | HEATING. (100% POWER FOR UNIT 2 = 3458 MWT). | | | | LICENSEE REDUCED REACTOR POWER TO 80% (2755 MWT). | | | | LICENSEE RESET ALL SYSTEMS TO NORMAL BY 0143. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28922 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 06/10/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 09:38 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/10/95 | +------------------------------------------------+EVENT TIME: 05:51[EDT]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 06/10/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STATION SERVICE WATER PUMP AUTOMATICALLY STARTED FOR UNKNOWN REASONS - | | | | AT 0551, THE 'A' STATION SERVICE WATER PUMP AUTOMATICALLY STARTED FOR | | UNKNOWN REASONS. LICENSEE STOPPED THE PUMP AND IS INVESTIGATING THE CAUSE | | OF THE PUMP START. | | | | THIS PUMP HAS STARTED FOR UNKNOWN REASONS ON SEVERAL PREVIOUS OCCASIONS. | | NO ALARMS, TRIPS, ACTUATIONS, ISOLATIONS, OR SEQUENCER INDICATIONS OCCURRED | | WITH THIS PUMP START. | | | | LICENSEE NOTIFIED LOCAL OFFICIALS AND WILL NOTIFY THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28923 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/10/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 11:37 [ET]| |RX TYPE: [3] CE |EVENT DATE: 06/10/95 | +------------------------------------------------+EVENT TIME: 08:57[CDT]| |NRC NOTIFIED BY: WELCH |LAST UPDATE DATE: 06/10/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |HOWELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ZWOLINKSI EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BAGWELL FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |JORDAN AEOD | | |CALLEN RAIV | | |VANDENBURG RIV | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT 0857CDT, AN NOUE WAS DECLARED DUE TO A FIRE IN A TURBINE SWITCHGEAR | | CABINET WHICH RESULTED IN A REACTOR TRIP, TURBINE TRIP, AND PARTIAL LOSS OF | | OFFSITE POWER. THE FIRE IS ONGOING AND A PLANT COOLDOWN IS COMMENCING. | | | | AT 0857CDT, AN NOUE WAS DECLARED DUE TO A FIRE IN A TURBINE SWITCHGEAR | | CABINET WHICH LASTED GREATER THAN TEN MINUTES AND THE REQUEST FOR | | ASSISTANCE TO FIGHT THE FIRE FROM OFFSITE. THE FIRE RESULTED IN A LOSS OF | | POWER TO 6.9KV NON-SAFETY BUS "A1", ONE OF TWO OFFSITE POWER SOURCES. ALSO, | | 4.16KV NON-SAFETY BUS "A2" WAS DE-ENERGIZED. THE LOSS OF THESE BUSES | | RESULTED IN A LOSS OF REACTOR COOLANT PUMPS (RCPs) "1A" AND "2A" ON LOW | | VOLTAGE. COINCIDENTALLY, A HIGH-THRUST BEARING TEMPERATURE CONDITION CAUSED | | RCP "2B" TO TRIP JUST PRIOR TO THE EVENT. RCP "1B" REMAINS IN SERVICE. AN | | AUTOMATIC REACTOR TRIP ON LOSS OF RCPs (WITH TURBINE TRIP) OCCURRED AND | | EMERGENCY DIESEL GENERATOR (EDG) "A" ACTUATED ON THE UNDERVOLTAGE CONDITION | | TO THE "A" SAFEGUARDS BUS. EDG "A" LOADED ALL LOADS EXCEPT THE AUXILIARY | | COMPONENT COOLING WATER PUMP "A", WHICH WAS THEN MANUALLY ACTUATED. ALL | | RODS FULLY INSERTED ON THE REACTOR TRIP. THE EMERGENCY FEEDWATER (EFW) | | SYSTEM ACTUATED ON LOW STEAM GENERATOR (SG) LEVEL (5% NARROW RANGE) AS | | EXPECTED. EFW WAS UTILIZED TO RECOVER INVENTORY IN THE SGs AND STABILIZE | | THE HEAT SINK. NO PRIMARY OR SECONDARY SAFETY VALVES OR RELIEF VALVES | | LIFTED DURING THE TRIP. NO OTHER ESF ACTUATIONS OCCURRED. | | | | THE FIRE WAS EXTINGUISHED AT 1113CDT. THE CAUSE OF THE FIRE IS BELIEVED TO | | BE A GRID DISTURBANCE WHICH RESULTED IN A SHORT-CIRCUIT IN THE BUS "A2" | | SWITCHGEAR AND IGNITED THE ASSOCIATED INSULATION. THE FIRE BURNED FOR | | APPROXIMATELY TWO HOURS BEFORE THE FIRE BRIGADE AND OFFSITE FIRE RESOURCES | | COULD ACCESS THE SWITCHGEAR CABINET AND EXTINGUISH IT. WHILE FIRE | | DETECTION EQUIPMENT WAS AVAILABLE, NO FIRE SUPPRESSION EQUIPMENT IS LOCATED | | IN THAT PORTION OF THE TURBINE BUILDING. | | | | WHILE ATTEMPTING TO STABILIZE TEMPERATURE ON THE PRIMARY SIDE PER EMERGENCY | | OPERATIONS PROCEDURES (WITH ONE RCP IN SERVICE), GLAND SEAL STEAM SUPPLY | | WAS ISOLATED AND CONDENSER VACUUM WAS BROKEN. ATMOSPHERIC DUMP VALVES | | (ADVs) WERE THEN PLACED INTO SERVICE FOR DECAY HEAT REMOVAL. IT IS | | ANTICIPATED THAT ADVs WILL BE UTILIZED FOR COOLDOWN TO COLD SHUTDOWN (12 | | HOURS). NO SECONDARY-SIDE INVENTORY PROBLEM IS EXPECTED. | | | | CURRENTLY, THE UNIT IS STABLE IN HOT STANDBY. OFFSITE POWER IS AVAILABLE | | AND SUPPLYING "B" TRAIN EQUIPMENT AND EDG "A" IS SUPPLYING "A" TRAIN | | EQUIPMENT. EDG "B" IS OPERABLE AND AVAILABLE. ALL ECCS SYSTEMS ARE | | OPERABLE. AN ASSESSMENT OF FIRE DAMAGE IS BEING CONDUCTED AT THIS TIME. IT | | IS BELIEVED THAT IT WILL TAKE SEVERAL DAYS TO RE-ESTABLISH OFFSITE POWER TO | | "A" TRAIN EQUIPMENT. THE UNIT WILL COMMENCE A COOLDOWN SHORTLY. FIRE | | BRIGADES REMAIN POSTED IN THE TURBINE BUILDING FOR REFLASH CONCERNS. THE | | GRID IS STABLE AT THIS TIME, HOWEVER, AFTERNOON THUNDERSTORMS ARE COMMON IN | | THAT AREA OF LOUISIANA. | | | | THE LICENSEE HAS ACTIVATED THEIR TECHNICAL SUPPORT CENTER. REGION IV HAS | | ACTIVATED THE INCIDENT RESPONSE CENTER (IRC) AND ENTERED THE MONITORING | | PHASE OF NORMAL MODE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND | | HE IS IN THE CONTROL ROOM AT THIS TIME. AN AUGMENTED INSPECTION TEAM (AIT) | | WILL BE SENT TO THE SITE ON MONDAY. | | | | * * * COMMISSIONERS ASSISTANTS' BRIEFING AT 1500EDT * * * | | BRIEFER: VANDENBURG/CALLAN | | PARTICIPANTS: BROCKMAN(AEOD) HOLAHAN(AEOD) HOGAN(RCT) | | MITCHELL(EDO) CHAFFEE(NRR-EO) MADDEN(CA) | | WINSBERG(JACKSON) SORENSEN(ROGERS) MCCONNEL(SELIN) | | JENSEN(de Planque) ZIMMERMAN(RIV) ZWOLINSKI(NRR) | | GRIMES(NRR) SINGH(NRR) HANNON(NRR) | | | | * * * UPDATE 1815EDT FROM:VANDENBURG BY:SCARFO * * * | | THE NOUE WAS TERMINATED AT 1352CDT AFTER THE FIRE WAS EXTINGUISHED AND | | PLANT COOLDOWN INITIATED. REGION IV EXITED THE MONITORING PHASE OF NORMAL | | MODE AND SECURED THE IRC. R4DO(HOWELL), EO(ZWOLINSKI), FEMA(STEINEDURF) | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28924 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 06/10/95 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 12:52 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/10/95 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: MODESITT |LAST UPDATE DATE: 06/10/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE PERFORMING A STEAM JET AIR EJECTOR (SJAE) SURVEILLANCE, VALVES WERE | | MISPOSITIONED SUCH THAT THE SJAE RADIATION MONITORING SYSTEM WAS DISABLED. | | | | WHILE PREPARING FOR THE SJAE "OFFGAS SAMPLING AND OPERATION SURVEILLANCE", | | TECHNICIANS MISPOSITIONED SJAE SYSTEM VALVES SUCH THAT A STEAM TRAP WAS | | LEFT OPEN TO THE ROOM ENVIRONMENT INSTEAD OF SAMPLING THE SJAE EFFLUENT. | | THIS CAUSED BOTH CHANNELS OF THE SJAE RADIATION MONITORING SYSTEM TO BE | | INOPERABLE AS OF 0830CDT. AT 1000CDT, OPERATORS NOTICED AN ABNORMALLY LOW | | READING ON THOSE RADIATION MONITORS, PERFORMED A VALVE ALIGNMENT CHECK, AND | | DISCOVERED THE PROBLEM. AT THAT TIME, OPERATORS RE-ESTABLISHED NORMAL | | SYSTEM VALVE ALIGNMENT AND RETURNED THE RADIATION MONITORING SYSTEM TO | | SERVICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28925 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 06/11/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 03:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/10/95 | +------------------------------------------------+EVENT TIME: 19:00[EDT]| |NRC NOTIFIED BY: STEFFENAUER |LAST UPDATE DATE: 06/11/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ERROR IN A HEAT BALANCE INPUT PARAMETER RESULTED IN A NON-CONSERVATIVE | | THERMAL POWER INDICATION. | | | | THE FOLLOWING WAS REPORTED AS A 24 HOUR ENS NOTIFICATION BASED ON THE | | POTENTIAL TO HAVE EXCEEDED THE MAXIMUM LICENSE POWER FOR UNIT 2 OF 3441 | | Mw(th): | | | | DURING THE REVIEW OF THE UNIT'S HEAT BALANCE INPUT PARAMETERS, A REACTOR | | ENGINEER NOTICED REACTOR WATER CLEANUP (RWCU) INLET TEMPERATURE INDICATING | | 472 øF RATHER THAN THE EXPECTED 524 øF. A REACTOR ENGINEERING CALCULATION | | DETERMINED THE ERROR IN TEMPERATURE INDICATION RESULTED IN A | | NON-CONSERVATIVE 2.1 Mw(th) INDICATION (ACTUAL POWER GREATER THAN INDICATED | | POWER). THE UNIT WAS DERATED TO 3436 Mw(th) TO COMPENSATE FOR THIS AND | | PREVIOUSLY REPORTED PROBLEMS. PREVIOUS REPORTED PROBLEMS INCLUDED DERATES | | FOR FEEDWATER FLOW (EVENT #28731) AND REACTOR RECIRCULATION PUMP MOTOR | | POWER (EVENT #28919) INPUTS TO THE HEAT BALANCE. | | | | AN I&C INVESTIGATION DETERMINED A TRANSMITTER OUT OF CALIBRATION. THE | | INSTRUMENT WAS RECALIBRATED TO CORRECT THE TEMPERATURE INDICATION FOR THE | | PRESENT PLANT CONDITIONS. OTHER IMMEDIATE CORRECTIVE ACTIONS INCLUDED: | | | | -INCIDENT DOCUMENTED IN THE PLANT DEFICIENCY PROGRAM | | | | -REVIEW OF VALIDITY OF ALL INPUTS TO THE HEAT BALANCE PERFORMED USING | | REDUNDANT INSTRUMENTATION WHERE POSSIBLE TO CONFIRM HEAT BALANCE INPUT | | VALUES | | | | -ADMINISTRATIVE LIMIT OF 3436 Mw(th) PLACED ON UNIT 2 (2Mw(th) DERATE FOR | | THIS INCIDENT AND 1 Mw(th) FOR EACH OF TWO PREVIOUSLY REPORTED INCIDENTS | | | | -REACTOR ENGINEERING CONFIRMED NO LICENSE SAFETY LIMITS WERE APPROACHED | | | | THIS INCIDENT DOES NOT AFFECT THE OPERABILITY OF ANY PLANT SYSTEM. THE | | LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28926 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 06/11/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 10:23 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 06/11/95 | +------------------------------------------------+EVENT TIME: 05:10[CDT]| |NRC NOTIFIED BY: DANIELS |LAST UPDATE DATE: 06/11/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 74 POWER OPERATION | 74 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VOLUNTARY SHUTDOWN TO BE PERFORMED DUE TO AN MSIV PROBLEM. | | | | THE LICENSEE MADE A COURTESY NOTIFICATION BASED ON INITIATING A VOLUNTARY | | UNIT 1 SHUTDOWN. DURING MSIV FULL STROKE TESTING, THE "1B21-F028A" | | (OUTBOARD) MSIV DID NOT REMAIN CLOSED WITH THE CONTROL SWITCH IN THE CLOSED | | POSITION. THE LICENSEE "SLOW" CLOSED THE MSIV BY DEPRESSING THE | | PUSHBUTTON, AND WHEN THE VALVE CLOSED, POSITIONED THE CONTROL SWITCH TO THE | | CLOSED POSITION. THE VALVE THEN STROKED FULL OPEN AND THEN BACK CLOSED. | | THE VALVE HAS REMAINED CLOSED. | | | | THE "1B21-F022A" (INBOARD) MSIV IS OUT OF SERVICE AND CLOSED TO ENSURE THE | | PRIMARY CONTAINMENT PENETRATION IS ISOLATED. UNIT 1 HAS BEEN OPERATING | | UNDER AN OPERABILITY EVALUATION GENERATED DUE TO A SIMILAR PROBLEM ON UNIT | | 2 IN FEBRUARY, 1995. UNIT 2 EXPERIENCED A STICKING PROBLEM WITH SOME | | "ASCO" BRAND SOLENOIDS. SINCE THAT TIME, UNIT 1 HAS BEEN TESTING THE | | MSIV's MONTHLY VICE QUARTERLY. TODAY'S UNIT 1 PROBLEM MAY BE FROM A | | SIMILAR CAUSE. | | | | THE FOURTH MSIV TESTED EXPERIENCED THE PROBLEM. THE FIRST THREE OPERATED | | AS EXPECTED. THE REMAINING 4 MSIV's ("C" & "D" LINES) WILL NOT BE TESTED | | AT POWER. ADDITIONAL TESTING AND ROOT CAUSE DETERMINATION WILL BE DONE | | FOLLOWING SHUTDOWN. THE FORCED OUTAGE DURATION IS EXPECTED TO BE | | APPROXIMATELY SEVEN DAYS. THE LICENSEE WILL BE CONDUCTING AN ORDERLY | | SHUTDOWN OF UNIT 1 TODAY, EXPECTING TO REACH MODE 3 THIS EVENING. THE | | LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28927 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 06/11/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 14:12 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/11/95 | +------------------------------------------------+EVENT TIME: 12:02[CDT]| |NRC NOTIFIED BY: DAVE GOODWIN/TIM CLOWSER |LAST UPDATE DATE: 06/11/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO THE LOSS OF BOTH MAIN FEEDWATER PUMPS. | | | | DURING TESTING OF THE SLAVE RELAY FOR THE 'A' TRAIN SAFETY INJECTION SYSTEM | | THE NON-SAFETY 118 VOLT INVERTER FAILED. THIS INVERTER PROVIDES CONTROL | | POWER TO BOTH OF THE TURBINE DRIVEN MAIN FEEDWATER PUMPS, AND AN INTERLOCK | | FUNCTION TO BOTH OF THE CONDENSATE PUMPS. AS RESULT OF THE LOSS OF THE | | INVERTER BOTH MAIN FEEDWATER PUMPS AS WELL AS THE CONDENSATE PUMPS TRIPPED. | | OPERATORS NOTED THE LOSS OF THE FEEDWATER PUMPS/ CONDENSATE PUMPS AND THEN | | MANUALLY TRIPPED THE REACTOR. | | | | STEAM GENERATOR WATER LEVEL WAS RESTORED BY THE MOTOR DRIVEN AUXILIARY | | FEEDWATER (AFW) PUMPS. ALL THREE AFW PUMPS RECEIVED AN AUTOMATIC START | | SIGNAL ON LOW-LOW STEAM GENERATOR WATER LEVEL, HOWEVER THE TURBINE DRIVEN | | AFW PUMP TRIPPED ALMOST IMMEDIATELY ON AN OVERSPEED CONDITION. IN | | ADDITION, BECAUSE OF THE SLAVE RELAY TESTING ON THE 'A' TRAIN, THE 'A' AFW | | PUMP WAS ALIGNED TO ITS TEST LOOP AND NOT TO THE STEAM GENERATORS. | | OPERATORS IMMEDIATELY REALIGNED THE 'A' AFW PUMP TO SUPPLY THE #1 AND #2 | | STEAM GENERATOR WHICH IS THE NORMAL ALIGNMENT. THIS PROCESS TOOK | | APPROXIMATELY 5 MINUTES AND THE LOWEST LEVELS REACHED IN THESE STEAM | | GENERATORS WAS APPROXIMATELY 22-25% OF WIDE RANGE INDICATION. THE 'B' | | MOTOR DRIVEN AFW PUMP STARTED AND SUPPLIED THE #3 AND #4 STEAM GENERATORS. | | THE LOWEST LEVEL REACHED IN THESE STEAM GENERATORS WAS APPROXIMATELY 40% OF | | WIDE RANGE INDICATION. | | | | ALL RODS INSERTED AND NO PRIMARY OR SECONDARY SAFETY RELIEF VALVES LIFTED. | | THE MAIN CONDENSER REMAINS AVAILABLE AS A HEAT SINK. ALL ELECTRICAL BUSSES | | TRANSFERRED PROPERLY. ALL EMERGENCY DIESEL GENERATORS AND EMERGENCY CORE | | COOLING SYSTEMS ARE OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THE LOSS OF THE 118 VOLT NON-VITAL BUS AS | | WELL AS THE OVERSPEED TRIP OF THE TURBINE DRIVEN AFW PUMP. AS PART OF THE | | SLAVE RELAY TEST THE ALTERNATE POWER SUPPLY FOR THE 118 NON-VITAL INVERTER | | IS DEENERGIZED. NORMALLY IF THERE IS A PROBLEM WITH THE PREFERRED POWER | | SUPPLY THE INVERTER AUTOMATICALLY SWITCHES TO THE ALTERNATE POWER SUPPLY. | | THE SLAVE RELAY TEST THAT WAS DONE SHOULD HAVE HAD NO EFFECT ON THE | | PREFERRED POWER SUPPLY FOR THIS INVERTER. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28928 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/11/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:28 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/11/95 | +------------------------------------------------+EVENT TIME: 14:45[EDT]| |NRC NOTIFIED BY: MAGNATTA |LAST UPDATE DATE: 06/11/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 Y 73 POWER OPERATION | 73 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) INOPERABLE FOR APPROXIMATELY 10 | | SECONDS. | | | | AT 11:00 EDT THE LICENSEE RECEIVED AN INDICATION OF A GROUND ON THE 125 | | VOLT DC BUS. AS PART OF THE GROUND ISOLATION PROCEDURE THE POWER FOR THE | | RCIC TURBINE INVERTER WAS DEENERGIZED. THE LICENSEE DETERMINED THAT THE | | GROUND WAS NOT DUE TO THE RCIC SYSTEM AND REENERGIZED THE SYSTEM. RCIC WAS | | CONSIDERED INOPERABLE DURING THE TIME THE POWER FOR THE INVERTER WAS | | DEENERGIZED. THE LICENSEE IS CONTINUING TO INVESTIGATE THE SOURCE OF THE | | GROUND INDICATION. ALL OTHER EMERGENCY CORE COOLING SYSTEMS ARE OPERABLE. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | ***UPDATE @ 16:55 6/11/95 FROM MAGNATTA TAKEN BY SEBROSKY**** | | | | THE LICENSEE IS CONTINUING TO TRY TO LOCATE THE SOURCE OF THE GROUND. AS | | AN ADDITIONAL PART OF THE GROUND ISOLATION PROCEDURE THE LICENSEE HAD TO | | DEENERGIZE POWER TO SEVERAL RCIC VALVES. THE VALVES WERE DEENERGIZED FOR | | APPROXIMATELY 1 MINUTE. DURING THE TIME THE RCIC VALVES WERE DEENERGIZED | | THE LICENSEE CONSIDERED THE RCIC SYSTEM INOPERABLE. THE LICENSEE CONTINUES | | TO SEARCH FOR THE SOURCE OF THE GROUND. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. HOO NOTIFIED | | R1DO(PASCIAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28929 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/11/95 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:19 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/11/95 | +------------------------------------------------+EVENT TIME: 15:40[EDT]| |NRC NOTIFIED BY: SNYDER |LAST UPDATE DATE: 06/11/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 100 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A LOW BATTERY VOLTAGE. | | | | UNIT 1 HAD BEEN OBSERVING A 7 DAY LIMITING CONDITION FOR OPERATION (LCO) | | SINCE 6/5/95 FOR 1 CELL OF A 60 CELL SAFETY RELATED BATTERY BANK BEING | | BELOW THE TECH SPEC REQUIRED VALUE OF 2.14 VOLTS. CELL 43 OF THE '1B' | | BATTERY HAD EXPERIENCED DEGRADED VOLTAGE AND ATTEMPTS TO RESTORE AND | | MAINTAIN FULL VOLTAGE BY SINGLE CELL CHARGING AND BATTERY EQUALIZING HAVE | | NOT BEEN SUCCESSFUL. | | | | AT 15:40 CELL 43's VOLTAGE FELL BELOW THE MINIMUM TECHNICAL SPECIFICATION | | ALLOWED VALUE OF 2.07 VOLTS. THIS REQUIRED THE UNIT TO ENTER A 2 HOUR LCO | | AND A UNIT 1 DOWN POWER WAS COMMENCED. THE '1B' BATTERY BUS IS STILL | | AVAILABLE BUT NOT OPERABLE. THE UNIT IS CURRENTLY AT 97% POWER AND IS | | REDUCING POWER AT ONE MEGAWATT PER MINUTE. THE LCO REQUIRES THE UNIT TO | | FIX THE PROBLEM WITHIN 2 HOURS OR BE IN HOT STANDBY CONDITION WITHIN THE | | FOLLOWING 6 HOURS. | | | | REPAIR OPTIONS FOR CELL 43 ARE BEING EVALUATED. AT THIS TIME, THE LICENSEE | | DOES NOT BELIEVE THAT THE CELL CAN BE RESTORED BY CHARGING. THE LICENSEE | | IS EVALUATING IF THE CELL CAN BE JUMPERED OUT. AN ENGINEERING SAFETY | | EVALUATION WHICH WAS DONE WOULD ALLOW OPERATION OF THE UNIT WITH UP TO TWO | | CELLS OF A 60 CELL BANK JUMPERED OUT. THE LICENSEE IS EVALUATING, AMONG | | OTHER OPTIONS, IF THE CELL CAN BE JUMPERED OUT AT POWER. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | ***UPDATE @ 22:08 6/11/95 FROM SNYDER TAKEN BY SEBROSKY *** | | | | THE UNIT EXITED THE TECHNICAL SPECIFICATION REQUIRED SHUTDOWN AT 21:51 WHEN | | THE '1B' BATTERY BUS WAS DECLARED OPERABLE. THE LICENSEE SUCCESSFULLY | | JUMPERED OUT CELL 43. WITH THIS CELL JUMPERED OUT THE BATTERY MEETS ITS | | TECHNICAL SPECIFICATIONS. THE LOWEST POWER REACHED WAS 40%. THE LICENSEE | | PLANS TO INCREASE POWER. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED | | R2DO(SHYMLOCK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28930 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/11/95 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 23:04 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/11/95 | +------------------------------------------------+EVENT TIME: 21:39[CDT]| |NRC NOTIFIED BY: WES CUMBEE |LAST UPDATE DATE: 06/11/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |ARPS 50.72(b)(2)(ii) RPS 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 STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP DUE TO THE 'C' MAIN STEAM ISOLATION VALVE (MSIV) | | CLOSING. | | | | WITH THE UNIT AT 100% POWER THE 'C' DOWNSTREAM MSIV CLOSED FOR UNKNOWN | | REASONS. ANY MSIV NOT BEING OPENED IN ANY OF THE THREE MAIN STEAM LINES | | CAUSES A TURBINE TRIP SIGNAL TO BE GENERATED. THE TURBINE TRIP THEN CAUSED | | A REACTOR TRIP. THE LICENSEE IS INVESTIGATING WHAT CAUSED THE 'C' | | DOWNSTREAM MSIV TO CLOSE. | | | | THE POST TRIP RESPONSE WAS NORMAL. ALL RODS INSERTED AND NO PRIMARY OR | | SECONDARY SAFETY RELIEF VALVES LIFTED. IN ADDITION, NO PRIMARY PORVs OR | | SECONDARY ATMOSPHERIC DUMP VALVES LIFTED. ALL EMERGENCY CORE COOLING | | SYSTEMS AND ALL EMERGENCY DIESEL GENERATORS ARE OPERABLE. THE MAIN | | CONDENSER IS AVAILABLE AS A HEAT SINK. STEAM GENERATOR WATER LEVEL WAS | | RESTORED, AND IS BEING MAINTAINED, BY THE AUXILIARY FEEDWATER SYSTEM. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+