U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/04/95 - 05/05/95 ** EVENT NUMBERS ** 28743 28757 28759 28760 28761 28762 28763 28764 28765 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28743 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/01/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 08:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/01/95 | +------------------------------------------------+EVENT TIME: 04:00[CDT]| |NRC NOTIFIED BY: C GAYHEART |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN STEAM ISOLATION VALVE (MSIV) ACCUMULATOR PRESSURES FOR STEAM GENERATOR | | "2B" & "2C" WERE BELOW MINIMUM TECHNICAL SPECIFICATION PRESSURE. | | | | DURING THE PERFORMANCE OF "2BWOS7.1.5-1" (MAIN STEAM ISOLATION VALVE FULL | | STROKE SURVEILLANCE), THE MSIV ACTIVE & STANDBY ACCUMULATOR PRESSURES FOR | | THE "2B" & "2C" VALVES WERE BELOW THE MINIMUM PRESSURE REQUIRED TO BE | | OPERABLE (4800psig). THE APPROPRIATE TECHNICAL SPECIFICATIONS ACTION | | REQUIREMENTS WERE ENTERED AND THE MSIV's WERE RECHARGED (AFTER THE VALVES | | WERE OPENED). THIS REPORT WAS MADE SINCE THE PROCEDURE, AS WRITTEN, DID NOT | | TAKE INTO ACCOUNT THE USE OF THE ACTIVE SIDE ACCUMULATOR HYDRAULICS TO | | REPOSITION THE VALVE DURING THE TEST OF THE VALVES STANDBY TRAIN | | HYDRAULICS. TECHNICAL SPECIFICATIONS ENTERED WERE TECH SPEC 3.7.1 (MSIVs | | INOPERABLE) AND TECH SPEC 3.0.3, WHICH WAS ENTERED FOR ABOUT 55 MINUTES. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1445 ON 5/4/95 BY BAL TAKEN BY WEAVER * * * | | THIS UPDATE IS TO CLARIFY THE ORIGINAL REPORT. THE PURPOSE OF THE ENS CALL | | WAS TO REPORT THE FACT THAT THE SURVEILLANCE PROCEDURE, AS WRITTEN, COULD | | HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION NECESSARY TO MITIGATE | | THE CONSEQUENCES OF AN ACCIDENT, AND WAS NOT TO REPORT THAT TWO MSIVs WERE | | BELOW THE MINIMUM PRESSURE REQUIRED TO BE OPERABLE PER TECH SPECS. THE | | INOPERABLE MSIVs WERE RECOGNIZED AT THE TIME THAT THEY WERE RENDERED | | INOPERABLE, AND TECH SPEC 3.0.3 WAS APPROPRIATELY ENTERED. THE TWO MSIVs | | WERE REOPENED, THE ACTIVE ACCUMULATOR PRESSURE INCREASED TO ABOVE THE TECH | | SPEC LIMIT, AND 3.0.3 WAS EXITED. THE UNIT WAS IN TECH SPEC 3.0.3 FOR A | | TOTAL OF 15 MINUTES FROM 0040 TO 0055. THE SYSTEM ENGINEER WAS CALLED TO | | INVESTIGATE AND AT 0400 IT WAS DETERMINED THAT THE MSIVs WERE OPERATING | | CORRECTLY AND THAT THE SURVEILLANCE PROCEDURE WAS INADEQUATE. AT 0500 THE | | LICENSEE DETERMINED THAT A FOUR HOUR REPORTABILITY REQUIREMENT EXISTED AS | | OF 0400, WHEN THE CAUSE OF THE PROBLEM WAS DISCOVERED AND THE POTENTIAL FOR | | SIMILAR FUTURE PROBLEMS EXISTED IF THE PROCEDURE WAS PERFORMED AS WRITTEN. | | HOO NOTIFIED RDO (WRIGHT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28757 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 05/03/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 05/03/95 | +------------------------------------------------+EVENT TIME: 13:47[CDT]| |NRC NOTIFIED BY: REIS |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM ACTUATION AND SEVERAL OTHER | | ENGINEERED SAFETY FEATURES ACTUATION SIGNALS WERE PRESENT DUE TO A SPURIOUS | | ELECTRICAL SPIKE IN AN INSTRUMENT RACK. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "AT 1347 (CDT) ON 5/3/95, DURING THE PERFORMANCE OF LIP-NB-618, 'UNIT 2 | | REACTOR VESSEL WATER LEVEL REFERENCE LEG CONTINUOUS BACKFILL PANEL | | 2C11-P002 OPERATION', WHILE VALVING PANEL 2C11-P002 ONTO ITS ASSOCIATED | | INSTRUMENT REFERENCE LEG, AN INSTRUMENT RACK SPIKE OCCURRED. THIS ACTION | | RESULTED IN A LOW RWL 1/2 SCRAM, A 1/2 ISOLATION SIGNAL TO PCIS GROUPS 1, | | 2, 3, 4, 5, 6, 7 & 10, A 1/2 INITIATION SIGNAL TO ARI & A HPCS DIESEL | | GENERATOR & PUMP INITIATION. THE BACKFILL RACK WAS IMMEDIATELY ISOLATED. | | THE HPCS PUMP INJECTED INTO THE RPV RAISING RWL FROM 47" TO 57" ON NARROW | | RANGE. THE HPCS INJECTION WAS SECURED IN 7 SECONDS. THE LOW LEVEL | | INITIATION SIGNAL WAS IMMEDIATELY RESET AND THE 2B D/G WAS SHUTDOWN AT | | 13:49 ON 5/3/95. THE 1/2 SCRAM WAS RESET & THE PCIS SYSTEM WAS RESET. AN | | INVESTIGATION AS TO WHY THE SPIKE OCCURRED IS IN PROGRESS. AT THE TIME OF | | THE EVENT, UNIT 2 WAS IN O.C.#4 WITH ALL RODS FULL IN." END OF TEXT. | | | | APPROXIMATELY 2000 GALLONS OF COOLANT WAS INJECTED INTO THE REACTOR COOLANT | | SYSTEM BY THE HPCS SYSTEM. OTHER THAN THE HPCS INJECTION VALVE, NO OTHER | | ESF SYSTEM VALVES CHANGED POSITION DUE TO THE ESF SIGNALS. AN | | INVESTIGATION INTO THE CAUSE OF THE ELECTRICAL SPIKE IS ONGOING. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28759 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/04/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/04/95 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: MURPHY |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTO START OF THE "21" COMPONENT COOLING WATER PUMP DUE TO | | LOW CCW SYSTEM PRESSURE. | | | | A LOW PRESSURE SIGNAL WAS CAUSED BY AN OVERRESPONSE OF THE CONTROLLER FOR | | "TCV-130" (THE LOW PRESSURE LETDOWN TEMPERATURE CONTROL VALVE), WHICH | | CAUSED THE "21" CCW PUMP TO AUTO START. THE PUMP WAS NOT SECURED UNTIL THE | | TCV CONTROLLER RETURNED TO ITS REQUIRED POSITION AND A LOCAL VERIFICATION | | OF THE PRESSURE WAS MADE TO SHOW THAT IT WAS GREATER THAN THE SETPOINT FOR | | AUTO START OF THE PUMP. THE PUMP WAS SECURED WITHIN 5-10 MINS. THE RI WAS | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28760 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/04/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/03/95 | +------------------------------------------------+EVENT TIME: 20:34[EDT]| |NRC NOTIFIED BY: SERATA |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A SPURIOUS AUTO START OF THE "A" STATION SERVICE | | WATER PUMP. | | | | THE CAUSE OF THE PUMP START IS UNKNOWN AND IS BEING INVESTIGATED. THERE WAS | | NO VALID ESF ACTUATION SIGNAL (I.E. REACTOR LEVEL 2, HIGH DRYWELL PRESSURE, | | OR HIGH REACTOR BUILDING/REFUELING FLOOR EXHAUST RADIATION). NO LOW FLOW OR | | LOW DELTA P PROCESS START SIGNALS WERE PRESENT. TROUBLESHOOTING IS | | CONTINUING, BUT A LOW STRAINER DELTA P PROCESS START IS BELIEVED TO BE THE | | INITIATING EVENT. THE "A" SSW PUMP REMAINED IN SERVICE AND THE "C" SSW PUMP | | WAS REMOVED FROM SERVICE WITHIN THE FOLLOWING 5-10 MINS. AN INCIDENT REPORT | | WAS MADE AT THE TIME OF THE EVENT TO DETERMINE THE ROOT CAUSE OF THE EVENT. | | NO CAUSE HAS BEEN CONFIRMED, SO THE EVENT IS BEING CONSIDERED AN INVALID | | ESF START. THIS APPEARS TO BE A REPEAT OF A SIMILAR EVENT(#28709) WHICH | | OCCURRED ON 4/21/95 AND ITS CAUSE IS STILL UNKNOWN. THE RI AND LOCAL | | AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT SAINT VRAIN REGION: 4 |NOTIFICATION DATE: 05/04/95 | |UNIT: [1] [ ] [ ] STATE: CO |NOTIFICATION TIME: 11:24 [ET]| |RX TYPE: [1] GA (GENERAL ATOMIC) |EVENT DATE: 05/04/95 | +------------------------------------------------+EVENT TIME: 08:31[MDT]| |NRC NOTIFIED BY: HAK |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ALLEN JOHNSON 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 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE COLORADO DEPARTMENT OF HEALTH THAT IT EXCEEDED | | ITS BIO-CHEMICAL LIMITATION OUT OF THEIR SEWAGE LAGOON. | | | | THE LICENSEE EXCEEDED THE LIMITATION(30PPM) ON THE EFFLUENT OUT OF THEIR | | SEWAGE LAGOON FOR THE MONTH OF APRIL. THE AVERAGE AMOUNT RELEASED FOR APRIL | | WAS 37.2PPM. THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/04/95 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 11:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/04/95 | +------------------------------------------------+EVENT TIME: 08:48[CDT]| |NRC NOTIFIED BY: JAY PHELPS |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ALLEN JOHNSON 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 | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - ESF DIESEL #21 AUTOMATICALLY STARTED | | | | THE TRAIN "A" ESF DIESEL GENERATOR #21 AUTOMATICALLY STARTED IN THE NORMAL | | (NON EMERGENCY MODE). THE DIESEL DID NOT LOAD ONTO THE BUS AS NO SIGNAL WAS | | PRESENT TO DIRECT CLOSING OF THE DIESEL'S OUTPUT BREAKER. ALL DIESEL | | GENERATOR SUPPORT SYSTEMS FUNCTIONED AS DESIGNED IN RESPONSE TO THE START | | SIGNAL. THE START IS CLASSIFIED AS NORMAL BASED ON AN INDICATION AVAILABLE | | ON THE DIESEL LOCAL CONTROL PANEL. | | | | THE EDG WAS MANUALLY SECURED IN ACCORDANCE WITH APPROVED PROCEDURES AT 0932 | | ON 5/4/95 AND RESTORED TO STANDBY STATUS. AN INVESTIGATION IS IN PROGRESS | | TO DETERMINE THE CAUSE OF THE SPURIOUS START OF THE DIESEL GENERATOR. THE | | EDG REMAINS OPERABLE AND CAPABLE OF PERFORMING ITS INTENDED FUNCTION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28763 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 05/04/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 12:00 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/04/95 | +------------------------------------------------+EVENT TIME: 08:00[CDT]| |NRC NOTIFIED BY: KELLY MACDONALD |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ALLEN JOHNSON 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO LUBRICATING OIL SPILL ONSITE | | | | AN OIL SPILL OCCURRED AT 0300 WHILE TRANSFERRING LUBE OIL FROM THE SUMP OF | | THE #11 EDG TO A STORAGE TANK. THE SPILL WAS CAUSED WHEN THE TRANSFER LINE | | DISCONNECTED. APPROXIMATELY 120 GALLONS OF LUBE OIL WERE SPILLED. ALL BUT | | 10 GALLONS WERE RECOVERED. THE REMAINING TEN GALLONS WERE FLUSHED INTO THE | | SEDIMENT BASIN BY A RAIN STORM. THE LICENSEE IS CURRENTLY RECOVERING THE | | REMAINING OIL FROM THE SEDIMENT BASIN AND DOES NOT EXPECT ANY OIL TO GET | | OFFSITE. | | | | THE LICENSEE CALLED THE STATE DEPARTMENT OF ENVIRONMENTAL QUALITY. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28764 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/04/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 12:52 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/30/95 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 05/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT 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 33 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR RADIATION RELEASE DUE TO INBOARD AND OUTBOARD MSIV LEAKAGE | | CONTROL SYSTEMS INOPERABLE | | | | DURING THE 4TH REFUELING OUTAGE THE OUTBOARD MSIVs BEFORE SEAT DRAIN LINES | | WERE SEALED OFF TO ELIMINATE A PREVIOUSLY UNIDENTIFIED AND UNANALYZED PATH | | FOR SECONDARY CONTAINMENT BYPASS LEAKAGE. THIS MODIFICATION INTRODUCED A | | SITUATION WHEREIN THE INBOARD MSIV LEAKAGE CONTROL SYSTEM (MSIV-LCS) IS | | CONSIDERED INOPERABLE IN OPERATIONAL CONDITIONS 1,2 & 3 BELOW 50% OF RATED | | THERMAL POWER (RTP). THE INOPERABILITY IS DUE TO ACCUMULATED WATER IN THE | | BOTTOM OF THE STEAM LINE BETWEEN THE MSIVs FROM CONDENSATION AT LOW STEAM | | FLOWS. THIS MODIFICATION HAS, IN EFFECT, MADE THE MSIV-LCS A SINGLE TRAIN | | SAFETY SYSTEM BELOW 50% RTP. DURING POWER ESCALATION ABOVE 50% RTP, | | OPERABILITY OF THE INBOARD MSIV-LCS IS RESTORED BECAUSE THE CONDENSATE | | COLLECTED BETWEEN THE MSIVs IS SWEPT DOWNSTREAM BY THE STEAM VELOCITY AND | | DRAINED OUT THROUGH DOWNSTREAM DRAINS. | | | | ON APRIL 30, 1995, AT 1130, (WITH THE PLANT AT 33% RTP) TECHNICAL | | SPECIFICATION SURVEILLANCE TESTING RESULTED IN THE DISCOVERY THAT THE | | OUTBOARD MSIV-LCS WAS INOPERABLE DUE TO A BLOWER NOT STARTING AS REQUIRED. | | THE INOPERABILITY OF BOTH THE INBOARD AND OUTBOARD MSIV-LCS RESULTED IN | | ENTRY INTO TECHNICAL SPECIFICATION 3.0.3 AND ALSO AN EVENT OR CONDITION | | THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF A | | SYSTEM NEEDED TO CONTROL THE RELEASE OF RADIOACTIVE MATERIAL. THIS IS THE | | BASIS OF THE NOTIFICATION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28765 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/05/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:35 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/05/95 | +------------------------------------------------+EVENT TIME: 03:24[CDT]| |NRC NOTIFIED BY: DAVIS |LAST UPDATE DATE: 05/05/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE UNIT 2 DIESEL GENERATOR AUTO START DUE TO LOSS OF A 4 KV BUS. | | | | DURING AN OUT OF SERVICE EVOLUTION, AN EQUIPMENT OPERATOR INADVERTENTLY | | OPENED THE WRONG POTENTIAL FUSE DRAWER ON A 4KV BUS, CAUSING THE 4KV BUS | | AND ALL OF ITS SUB-BUSES TO BECOME DEENERGIZED. THE UNIT 2 D/G AUTO | | STARTED AND CLOSED IN TO THE ECCS BUS. DUE TO THE PLANT'S ELECTRICAL BUS | | LINEUP, BOTH RPS BUSES WERE LOST. THE REACTOR BUILDING VENTILATION ISOLATED | | AND THE STANDBY GAS TREATMENT SYSTEM AUTO STARTED. THE POTENTIAL FUSES WERE | | RECLOSED AND THE ELECTRICAL SYSTEMS REALIGNED TO THEIR PREVIOUS POSITIONS | | WITHIN 50 MINUTES. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+