U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/30/96 - 12/31/96 ** EVENT NUMBERS ** 31518 31521 31522 31523 31524 31525 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31518 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 12/28/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:27 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 12/28/96 | +------------------------------------------------+EVENT TIME: 13:14[EST]| |NRC NOTIFIED BY: TERIBERY |LAST UPDATE DATE: 12/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 18 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM FROM 18% POWER DUE TO A LOW REACTOR VESSEL | | WATER LEVEL SIGNAL AND A ALTERNATE ROD INSERTION(ARI) SIGNAL. | | | | WHILE VALVING IN THE DIVISION 1 BACKFILL SYSTEM, A SURGE IN THE SYSTEM | | CAUSED A LEVEL 8 SPIKE WHICH WAS IMMEDIATELY FOLLOWED BY A LEVEL 2 SIGNAL, | | WHICH INITIATED DIVISION 1 OF THE ARI SYSTEM, RESULTING IN THE REACTOR | | RECIRC PUMPS TRIPPING AND A REACTOR SCRAM. THE REACTOR FEED PUMP TRIPPED | | ON THE LEVEL 8 SIGNAL. THE PLANTS EOP's WERE ENTERED WHEN LEVEL 3 WAS | | REACHED. WATER WAS RESTORED USING THE STANDBY FEEDWATER SYSTEM, AND THE | | EOP's WERE EXITED AT 13:45. AT 13:49 REACTOR RECIRC PUMP "B" WAS RESTORED | | TO SERVICE. DUE TO THE RAPID INITIAL COOLDOWN, THE PLANT's ADMINISTRATIVE | | 90øF/HR LIMIT WAS EXCEEDED, BUT TS 3.4.6.1 LIMIT OF 100øF/HR, COOLDOWN RATE | | WAS NOT EXCEEDED. ALL RODS FULLY INSERTED, NO INJECTION OCCURRED AND NO | | SAFETY RELIEF VALVES OPENED. THE CONDENSER IS THE HEAT SINK. CAUSE OF THE | | SURGE IS UNKNOWN AND IS BEING INVESTIGATED. THE RESIDENT INSPECTOR WAS | | INFORMED. | | | | * * * UPDATE AT 1817 EST ON 12/30/96 FROM ARAB TAKEN BY KARSCH * * * | | THE LOWEST OBSERVED REACTOR VESSEL LEVEL WAS 164 INCHES WHICH IS WELL ABOVE | | THE LEVEL 2 ACTUATION SETPOINT OF 110 INCHES. DUE TO THE SHORT DURATION OF | | THE REFERENCE LEG LEVEL SPIKE, APPROXIMATELY 56 MILLISECONDS, NOT ALL LEVEL | | 2 EQUIPMENT ACTUATED. HPCI AND RCIC DID NOT START AND THE LPCI LOOP SELECT | | LOGIC DID NOT ACTUATE. THE PLANT STAFF CONTINUES TO INVESTIGATE THE EVENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R3DO (JACOBSON) | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31521 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TROJAN REGION: 4 |NOTIFICATION DATE: 12/30/96 | |UNIT: [1] [ ] [ ] STATE: OR |NOTIFICATION TIME: 03:36 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/29/96 | +------------------------------------------------+EVENT TIME: 20:53[PST]| |NRC NOTIFIED BY: TOM LAWSON |LAST UPDATE DATE: 12/30/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES 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 +------------------------------------------------------------------------------+ | OFFSITE FIRE DEPARTMENT CALLED TO EXTINGUISH A FIRE IN THE YARD LOOP | | CIRCUIT SWITCHER. | | | | AT 2053 PST A FIRE IN THE YARD LOOP CIRCUIT SWITCHER (LOCATED OUTSIDE MAIN | | BUILDINGS) WAS REPORTED TO THE LICENSEE. LICENSEE DEENERGIZED THE LOOP | | CIRCUIT SWITCHER AT 2059 PST BUT OIL SOAKED INSULATION IN THE SWITCHER | | CONTINUED TO BURN (INSULATION MOSTLY SMOKED). LICENSEE CALLED THE RAINIER | | FIRE DEPARTMENT AT 2103 PST TO PUT OUT THE FIRE. THE FIRE WAS EXTINGUISHED | | AT 2138 PST. THERE WERE NO INJURIES AND THE LICENSEE IS INVESTIGATING THE | | CAUSE OF THE FIRE. NO ELECTRICAL POWER WAS LOST TO THE PLANT. LICENSEE | | WILL NOTIFY THE OREGON DEPARTMENT OF ENERGY OF THIS EVENT REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31522 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 12/30/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 10:34 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/30/96 | +------------------------------------------------+EVENT TIME: 09:40[EST]| |NRC NOTIFIED BY: DAN MCDOUGOLD |LAST UPDATE DATE: 12/30/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GOING TO A COLD SHUTDOWN CONDITION AFTER IDENTIFYING FAILURE TO TEST EDG | | (EMERGENCY DIESEL GENERATOR) START LOGIC CIRCUITRY. | | AN ONGOING REVIEW OF GENERIC LETTER 96-01, FOR IDENTIFYING MISSED LOGIC | | CIRCUITRY TESTING, RESULTED IN THE IDENTIFICATION OF THE EDG START | | CIRCUITRY FOR DEGRADED GRID VOLTAGE NOT HAVING BEEN TESTED. THIS FEATURE | | PROTECTS THE EMERGENCY CORE COOLING SYSTEMS (ECCS) DURING A DEGRADED GRID | | VOLTAGE BY INITIATING EDG LOAD SHEDDING. | | | | AT 0900 ON 12/30/96, A DECISION WAS MADE TO DECLARE BOTH TRAINS OF ECCS | | INOPERABLE PER TECHNICAL SPECIFICATIONS. ONE TRAIN OF ECCS IS REQUIRED IN | | THIS CONDITION, (HOT SHUTDOWN). THE REMEDIAL ACTION TIME IS 4 HOURS. A | | PROCEDURE CAN NOT BE WRITTEN AND TEST COMPLETED WITHIN THE 4 HOURS, | | THEREFORE A PLANT SHUTDOWN TO COLD SHUTDOWN HAS COMMENCED. LICENSEE | | NOTIFIED THE STATE OF MAINE OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31523 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 12/30/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:47 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 12/30/96 | +------------------------------------------------+EVENT TIME: 11:00[CST]| |NRC NOTIFIED BY: KEVIN DORWICK |LAST UPDATE DATE: 12/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE UNITED STATES DEPARTMENT OF TRANSPORTATION | | NATIONAL RESPONSE CENTER AND THE ILLINOIS EMERGENCY MANAGEMENT AGENCY THAT | | THEY SPILLED APPROXIMATELY 25 GALLONS OF DIESEL FUEL NEAR THE SCREEN HOUSE | | INSIDE THE PROTECTED AREA. NO FUEL ENTERED THE LAKE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31524 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/30/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:26 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/30/96 | +------------------------------------------------+EVENT TIME: 14:25[EST]| |NRC NOTIFIED BY: JESSE PIKE |LAST UPDATE DATE: 12/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT AN UNSEATED CHECK VALVE IN A TWO INCH LINE FOR | | THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM VACUUM TANK CONDENSATE | | PUMP DISCHARGE IS A CONTAINMENT BOUNDARY. | | | | AFTER PERFORMANCE OF A HPCI VALVE INSERVICE TEST ON 11/30/96 THE LICENSEE | | NOTED THAT THE HPCI VACUUM TANK CONDENSATE PUMP DISCHARGE CHECK VALVE | | "1BJ-V027" FAILED TO SEAT. SUBSEQUENTLY THE LICENSEE DISCOVERED THAT THE | | CHECK VALVE IS PART OF THE EXTENDED CONTAINMENT BOUNDARY PER THEIR UFSAR. | | SINCE THIS PENETRATION WAS NOT IN CONFORMANCE TECH SPEC 3.6.1 (PRIMARY | | CONTAINMENT INTEGRITY) WAS ENTERED AND THE PENETRATION WAS ISOLATED. THIS | | ACTION RENDERED HPCI INOPERABLE. THE REACTOR CORE ISOLATION COOLING (RCIC) | | SYSTEM IS OPERABLE, AND REPAIR OF THE CHECK VALVE IS IN PROGRESS. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31525 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 12/30/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 22:11 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/30/96 | +------------------------------------------------+EVENT TIME: 21:29[EST]| |NRC NOTIFIED BY: C.W.SENN |LAST UPDATE DATE: 12/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 66 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS SHUTTING DOWN DUE TO THE EXPIRATION OF A SIX HOUR TECH SPEC | | ACTION STATEMENT. | | | | DURING QUARTERLY AUXILIARY SAFEGUARDS TESTING THE LICENSEE DETERMINED AT | | 1237 EST THAT THE RESET PUSH BUTTON FOR THE MAIN STEAM ISOLATION VALVES AND | | THE PORV VALVES FAILED. NORMALLY THE RESET PUSH BUTTON FOR THE "K616" | | RELAY MUST BE PUSHED BEFORE THE VALVES CAN BE REOPENED. THE LICENSEE | | OBSERVED THAT THE VALVES COULD BE REOPENED REGARDLESS OF WHETHER THE RESET | | BUTTON WAS PUSHED OR NOT. | | | | THE LICENSEE COMMENCED REACTOR SHUTDOWN IN ACCORDANCE WITH TECH SPEC | | 3.3.2.4.b, "STEAM LINE ISOLATION AUTOMATIC ACTUATION AND ACTUATION RELAYS", | | WHEN ACTION TO CORRECT THE PROBLEM DID NOT PROGRESS FAST ENOUGH. RESET | | CIRCUIT TROUBLE SHOOTING AND REPAIR ARE ONGOING. THE LICENSEE EXPECTS TO | | REACH HOT SHUTDOWN BY 0037 EST ON 12/31/96. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+