U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/28/97 - 12/01/97 ** EVENT NUMBERS ** 33323 33324 33325 33326 33327 33328 33329 33330 33331 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33323 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 11/28/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:40 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 11/28/97 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: LINGL |LAST UPDATE DATE: 11/28/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE N.Y. DEPARTMENT OF ENVIRONMENTAL CONSERVATION AND | | THE U.S. COAST GUARD OF A 300 GALLON OIL SPILL INTO THE DISCHARGE CANAL. | | | | THE ESTIMATED 300 GALLONS OF OIL CAME FROM A LEAK IN A HEAT EXCHANGER AND | | HAS SINCE BEEN ISOLATED. A SPILL TEAM ON SITE IS PUTTING OUT BOOMS TO | | CONTAIN THE SPILL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33324 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/28/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 23:29 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/28/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/28/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CRABTREE | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL LOSS OF ONE CONTROL IN THE DOUBLE CONTINGENCY MATRIX. | | | | THIS EVENT WAS REPORTED UNDER NRC BULLETIN 91-01, AS A 24 HOUR CALL. | | | | AT 1130 HOURS, 11/28/97, OPERATIONS PERSONNEL DISCOVERED A POTENTIAL | | VIOLATION OF A NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA). NCSA-330 | | 004.A01, PART C, CONTINGENCY EVENT A/B.6.a.1, HAS TWO NUCLEAR CRITICALITY | | SAFETY (NCS) CONTROLS WHICH ARE CONTAINED IN THE DOUBLE CONTINGENCY MATRIX | | (CONTROL "A" AND CONTROL "B"). NINE CASCADE CELLS, WHICH ARE CURRENTLY | | SHUTDOWN (OFF STREAM) AND AT A URANIUM HEXAFLUORIDE NEGATIVE (< 10 ppm | | URANIUM-235 AT 10 psia), DO NOT HAVE COOLANT (FREON R-114) AND | | RECIRCULATING COOLING WATER (RCW) DRAINED. CONTROL "A" OF THE DOUBLE | | CONTINGENCY MATRIX REQUIRES THAT COOLANT (FREON, R-114) PRESSURE BE | | MAINTAINED ABOVE BOTH URANIUM HEXAFLUORIDE AND RCW PRESSURES TO PROVIDE | | PROTECTION FROM RCW INLEAKAGE INTO THE CASCADE. THE COOLANT PRESSURE IN THE | | NINE AFFECTED CELLS WAS NOT WITHIN THE RANGE OF THE AVAILABLE PRESSURE | | GAUGE, THUS CREATING A POTENTIAL VIOLATION OF CONTROL "A", SINCE IT CANNOT | | BE SHOWN THAT THE COOLANT PRESSURE REMAINED ABOVE THE URANIUM HEXAFLUORIDE | | AND RCW PRESSURE. ENGINEERING WILL EVALUATE SYSTEM INFORMATION ASSOCIATED | | WITH THIS INCIDENT. ALL RCW SUPPLY AND CONTROL VALVES WERE CLOSED AND ALL | | RCW RETURN VALVES WERE VERIFIED OPEN TO ASSURE COOLANT PRESSURE (R-114) | | REMAINED ABOVE RCW PRESSURE. ALL OTHER CASCADE CELLS IN ALL PROCESS | | BUILDINGS WERE VERIFIED TO BE IN COMPLIANCE. THERE WAS NO RELEASE OF | | HAZARDOUS MATERIALS OF RADIOLOGICAL CONTAMINATION EXPOSURES ASSOCIATED WITH | | THIS EVENT. THIS EVENT IS BEING REPORTED PER REPORTING PROCEDURE | | UE2-RA-RE-1030, APPENDIX D, CRITERIA A, PARAGRAPH 4.6. | | | | IT WAS FOUND THAT RCW PRESSURE WAS AT 65 psia AND THE CALCULATED COOLANT | | (R-114) PRESSURES FOR THE NINE CELLS MENTIONED ABOVE RANGED FROM 49 psia TO | | 55 psia. | | | | SAFETY SIGNIFICANCE OF EVENT: | | | | POTENTIAL LOSS OF ONE CONTROL IN THE DOUBLE CONTINGENCY MATRIX. | | | | POTENTIAL CRITICALITY PATHWAY INVOLVED: | | | | RCW PRESSURE MUST REMAIN BELOW THE COOLANT (R-114) PRESSURE TO ASSURE RCW | | CANNOT ENTER THE COOLANT AND URANIUM HEXAFLUORIDE SYSTEM. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | | | CONTROL "A": COOLANT (R-114) PRESSURE MAINTAINED ABOVE RCW & URANIUM | | HEXAFLUORIDE SYSTEM PRESSURES. | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE CRITICAL MASS): | | | | LESS THAN OR EQUAL TO 10% ENRICHMENT. | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | | | POTENTIAL LOSS OF ONE CONTROL IN THE DOUBLE CONTINGENCY MATRIX. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: | | | | OTHER X-330 CELLS IN COMPLIANCE. AFFECTED CELLS IN THE X-330 WERE | | IMMEDIATELY BROUGHT INTO COMPLIANCE. ASSURED THAT CELLS IN THE X-326 AND | | X-333 PROCESS AREAS WERE IN COMPLIANCE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33325 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 11/29/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 17:33 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/29/97 | +------------------------------------------------+EVENT TIME: 14:35[CST]| |NRC NOTIFIED BY: KURAS |LAST UPDATE DATE: 11/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 7 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 7% POWER ON A HIGH INTERMEDIATE RANGE FLUX SIGNAL. | | | | WHILE AT 7% POWER ONE OF THE INTERMEDIATE RANGE CHANNELS SPIKED HIGH (>25% | | POWER) RESULTING IN A REACTOR TRIP. THE CAUSE OF THE SPIKE IS UNKNOWN AND | | IS BEING INVESTIGATED. ALL RODS FULLY INSERTED AND NO SAFETY RELIEF VALVES | | LIFTED. THE MOTOR DRIVEN AUX FEEDWATER PUMP AUTO STARTED ON A LOW STEAM | | GENERATOR WATER LEVEL SIGNAL. THE PLANT WAS STABILIZED IN MODE 3 WITH THE | | CONDENSER AS THE ULTIMATE HEAT SINK. THE NRC RESIDENT INSPECTOR WAS | | NOTIFIED. | | | | *** UPDATE ON 11/30/97 AT 0214 EST BY RICK HUBBART TAKEN BY MACKINNON *** | | | | THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS STARTED ON A LOSS OF FEEDWATER | | SIGNAL WHICH WAS GENERATED WHEN MAIN FEEDWATER PUMP "A" TRIPPED ON HIGH | | DISCHARGE PRESSURE. REACTOR TRIP COINCIDENT WITH LOW Tave CAUSED AN | | EXPECTED FEEDWATER ISOLATION WHICH CAUSED THE OPERATING MAIN FEEDWATER PUMP | | TO TRIP ON HIGH DISCHARGE PRESSURE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE. | | | | THE OPERATIONS OFFICER NOTIFIED THE R4DO CHUCK CAIN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33326 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/29/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:42 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/29/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:55[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/29/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y | | | DOCKET: 0707001 |FRED COMBS, NMSS EO | +------------------------------------------------+JIM CREED, R3 IAT | |NRC NOTIFIED BY: UNDERWOOD | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |PAAA 95.57(b) LOSS OF CLASSIFIED INFO | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A COMPROMISE OF CLASSIFIED DOCUMENTS/SAFEGUARDS | | INFORMATION. COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. REFER TO | | THE HOO LOG FOR ADDITIONAL DETAILS. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33327 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 11/30/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/30/97 | +------------------------------------------------+EVENT TIME: 03:27[CST]| |NRC NOTIFIED BY: TOM PETELLE |LAST UPDATE DATE: 11/30/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT VENTILATION ISOLATION ACTUATION SIGNAL AND ALARM RECEIVED. | | | | THE LICENSEE RECEIVED A CONTAINMENT VENTILATION ISOLATION ACTUATION SIGNAL | | AND ALARM. IT WAS DETERMINED THAT THE 2AR012 "CONTAINMENT BUILDING FUEL | | HANDLING INCIDENT" AREA RADIATION MONITOR HAD FAILED ITS DAILY AUTO | | CHECKOUT TEST, CAUSING AN RM-11 OPERATE FAILURE WHICH GENERATED A TRAIN "B" | | CONTAINMENT ISOLATION SIGNAL. THERE WAS NO RELEASE IN PROGRESS AND ALL | | REQUIRED CONTAINMENT ISOLATION VALVES WERE CLOSED PRIOR TO THE EVENT. | | SUBSEQUENTLY, A MANUAL CHECK SOURCE WAS SUCCESSFULLY PERFORMED AND THE | | CONTAINMENT VENTILATION ISOLATION SIGNAL WAS RESET WITHOUT INCIDENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33328 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/30/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/29/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:48[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/30/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS RDO | | DOCKET: 0707001 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAURER | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HIGH PRESSURE FIRE WATER SYSTEM ADT COMPANY ALARM COMPUTER IN THE | | "C-300" BUILDING LOCKED UP. | | | | ON 11/29/97 AT 1845, THE "C-300" BUILDING ALARM COMPUTER FOR THE PLANT'S | | HIGH PRESSURE FIRE WATER SYSTEM (HPFWS) LOCKED UP. UPON DISCOVERY OF THE | | "C-300" COMPUTER MALFUNCTION, AN OPERATOR WAS DISPATCHED TO MONITOR THE | | REDUNDANT ADT COMPANY ALARM COMPUTER IN THE "C-200" BUILDING. THE SYSTEM | | ENGINEER WAS NOTIFIED AND THE "C-300" BUILDING ADT COMPANY COMPUTER WAS | | RESTORED TO OPERABLE STATUS AT 2025 ON 11/29/97. IT WAS THEN DETERMINED | | THAT FOR A PORTION OF THE ADT COMPANY ALARM OUTAGE, THE "C-300" BUILDING | | FIRE ALARM ANNUNCIATOR AND ALARM LIGHT PLATE WERE ALSO EFFECTIVELY | | DISABLED. THIS CONDITION DOES NOT MEET TSR 2.3.4.8 AND 2.4.4.5 | | REQUIREMENTS. HOWEVER, THE LICENSEE STILL HAD THE CAPABILITY TO DETERMINE | | IF HPFWS SPRINKLER SYSTEM ACTUATION OCCURRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33329 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 11/30/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 17:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/30/97 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: PTACEK |LAST UPDATE DATE: 11/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION WHICH WOULD HAVE RESULTED IN THE PLANT | | BEING IN AN UNANALYZED CONDITION IF IT HAD BEEN OPERATING. | | | | DURING MAINTENANCE ACTIVITIES ON 11/26/97, THE LICENSEE DISCOVERED THAT ONE | | OF TWO TRAIN "B" INLET LINES FOR HYDROGEN REMOVAL AND AIR RECIRCULATION | | FROM THE #22/23 STEAM GENERATOR ENCLOSURE HAD BEEN INADVERTENTLY SEALED | | OVER SOMETIME IN THE PAST (POSSIBLY BACK TO 1985). THIS CONDITION DEGRADES | | THE ABILITY OF THE CONTAINMENT AIR RECIRCULATION SYSTEM FROM PERFORMING ITS | | DESIGN FUNCTION OF PREVENTING HYDROGEN ACCUMULATION AND CIRCULATION OF AIR | | IN THE SUBJECT ENCLOSURE FOLLOWING A LOCA. THE UPDATED FINAL SAFETY | | ANALYSIS REPORT (UFSAR) STATES THAT 455 SCFM FROM THE ENCLOSURE ENSURES THE | | HYDROGEN CONCENTRATION WOULD NOT EXCEED 4% BY VOLUME. NOMINALLY, ONE INLET | | OPENING WOULD PROVIDE APPROXIMATELY 250 SCFM, WHICH IS SLIGHTLY >50% OF THE | | FLOW STATED IN THE UFSAR. TRAIN "A" INLET LINES WERE OPEN AND WOULD HAVE | | PROVIDED THE REQUIRED FLOW. HOWEVER, ASSUMING A LOSS OF TRAIN "A" DURING A | | LOCA RESULTS IN THE DEGRADED TRAIN "B" HAVING TO MEET THE REQUIRED FLOW, | | WHICH IT COULD NOT. | | | | ACTIVITIES HAVE BEEN INITIATED TO REMOVE THE SEAL FROM THE OPENING. OTHER | | SIMILAR OPENINGS WERE CHECKED AND FOUND TO BE CLEAR OF OBSTRUCTION. THE | | LICENSEE IS INVESTIGATING THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33330 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/30/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 22:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/30/97 | +------------------------------------------------+EVENT TIME: 20:50[EST]| |NRC NOTIFIED BY: MILLER |LAST UPDATE DATE: 11/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KATHLEEN MODES 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 1 STARTUP | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC STEAM SUPPLY ISOLATION VALVES CLOSED ON A HIGH RCIC STEAM FLOW SIGNAL. | | | | WHILE PERFORMING A STEAM LINE WARM UP OF THE RCIC SYSTEM, AN AUTOMATIC | | ISOLATION SIGNAL WAS RECEIVED ON A HIGH STEAM LINE FLOW SIGNAL AND ALL | | PLANT COMPONENTS RESPONDED PROPERLY. THE ISOLATION SIGNAL APPEARS TO HAVE | | BEEN GENERATED THROUGH STEAM FLASHING IN THE INSTRUMENT SENSING LINES, BUT | | THE LICENSEE IS STILL INVESTIGATING. THIS HAS BEEN A PRIOR PROBLEM AND, AT | | THE TIME OF THE EVENT, RECORDERS WERE INSTALLED TO OBTAIN DATA TO ASSIST IN | | CORRECTING ANY OBSERVED DEFICIENCIES. THE LICENSEE HAS NOT YET RESET THE | | ISOLATION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR AND LOWER ALLOWAYS | | CREEK OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33331 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/01/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 00:09 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/30/97 | +------------------------------------------------+EVENT TIME: 21:53[CST]| |NRC NOTIFIED BY: D. NOHR |LAST UPDATE DATE: 12/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DURING | | SURVEILLANCE TESTING. | | | | DURING THE QUARTERLY HIGH PRESSURE COOLANT INJECTION VALVE TIMING | | SURVEILLANCE, THE 1-2301-29 (HPCI STEAM SUPPLY DRAIN LINE ISOLATION VALVE | | TO THE MAIN CONDENSER) VALVE WAS TIMED IN THE CLOSED DIRECTION AT 5.6 | | SECONDS. THE IN-SERVICE TESTING TIME REQUIRED FOR THIS VALVE IS 5.4 | | SECONDS. THE HPCI SYSTEM WAS DECLARED INOPERABLE AND A 14 DAY LIMITING | | CONDITION OF OPERATION WAS ENTERED PER TECHNICAL SPECIFICATION 3.5.A, | | ACTION 3. REACTOR CORE ISOLATION COOLING AND ALL OTHER EMERGENCY CORE | | COOLING SYSTEMS ARE FULLY OPERABLE, IF NEEDED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+