U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/08/94 - 09/09/94 ** EVENT NUMBERS ** 27701 27724 27756 27757 27758 27759 27760 27761 27762 27763 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27701 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 08/24/94 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 02:57 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/24/94 | +------------------------------------------------+EVENT TIME: 00:24[CDT]| |NRC NOTIFIED BY: EHRHARDT |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL Rx SCRAM DUE TO INCREASED MAIN T/G EXCITER BEARING VIBRATION - | | | | THE VIBRATION ON THE MAIN TURBINE GENERATOR EXCITER FRONT BEARING #11 | | INCREASED FROM 2.1 MILS TO 8.0 MILS FOR UNKNOWN REASONS. | | | | CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE REACTOR FROM 100% POWER TO | | REMOVE THE MAIN TURBINE GENERATOR FROM SERVICE. | | | | ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE INCREASED VIBRATION. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE DATE: 9/8/94 UPDATE TIME: 1427 ***FROM LICENSEE: R. RUFFIN BY | | STRANSKY *** THE REACTOR TRIP WAS PERFORMED AS PART OF A PLANNED | | EVOLUTION, AND IS THEREFORE NOT REPORTABLE UNDER 50.72. THE LICENSEE | | RETRACTED THIS EVENT AND STATED THAT NO 50.73 REPORT WOULD BE SUBMITTED. RI | | WILL BE INFORMED. R2DO (BILL CLINE) NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27724 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 08/30/94 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 08:02 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/30/94 | +------------------------------------------------+EVENT TIME: 06:35[CDT]| |NRC NOTIFIED BY: K McDONALD |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 | M/R Y 8 STARTUP | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE PERFORMED A PLANNED REACTOR SCRAM SO THEY CAN GO TO A COLD | | SHUTDOWN CONDITION TO REPAIR A MAIN GENERATOR ROTOR COOLING WATER LEAK. | | | | LICENSEE PERFORMED A PLANNED MANUAL REACTOR SCRAM FROM 8% REACTOR POWER | | AFTER THEY FOUND THAT THEIR MAIN GENERATOR ROTOR HAD A COOLING WATER LEAK. | | ALL RODS FULLY INSERTED INTO THE CORE. LICENSEE IS USING DRAIN VALVES TO | | THEIR MAIN CONDENSER TO MAINTAIN REACTOR TEMPERATURE/PRESSURE. LICENSEE | | WILL USE THEIR MAIN TURBINE BYPASS VALVES TO GO TO A COLD SHUTDOWN | | CONDITION SO THEY CAN REPAIR THE MAIN GENERATOR ROTOR COOLING WATER LEAK. | | LICENSEE SAID THAT THEY MIGHT BE SHUTDOWN 30 DAYS BEFORE RETURNING TO POWER | | OPERATION. NO ECCS ACTUATIONS OCCURRED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | *** UPDATE DATE: 9/8/94 UPDATE TIME: 1427 ***FROM LICENSEE: R. RUFFIN BY | | STRANSKY *** THE REACTOR TRIP WAS PERFORMED AS PART OF A PLANNED PLANT | | EVOLUTION, AND IS THEREFORE NOT REPORTABLE UNDER 50.72. THE LICENSEE | | RETRACTED THE EVENT AND STATED THAT NO 50.73 REPORT WOULD BE SUBMITTED. RI | | WILL BE INFORMED. R2DO (BILL CLINE) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27756 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/08/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 01:25[CDT]| |NRC NOTIFIED BY: ROBERT |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CYNTHIA PEDERSON 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 | N Y 10 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP ON HIGH SOURCE RANGE FLUX WHEN THE "N-31" SOURCE RANGE | | RE-ENERGIZED SOONER THAN EXPECTED. | | | | DURING A UNIT 1 SHUTDOWN FOR REFUELING, FOLLOWING A 508 DAY RUN, THE UNIT 1 | | REACTOR TRIPPED FROM 10% POWER ON NUCLEAR INSTRUMENTATION SOURCE RANGE HIGH | | FLUX TRIP. THE TURBINE GENERATOR WAS OFF-LINE AT THE TIME OF THE TRIP. THE | | SOURCE RANGE FLUX HIGH TRIP OCCURRED WHEN THE SOURCE RANGE "N-31" | | INADVERTENTLY RE-ENERGIZED WHEN THE "P-10" POWER RANGE PERMISSIVE RESET. | | THE SOURCE RANGE ENERGIZATION SHOULD HAVE BEEN BLOCKED BY THE SOLID STATE | | PROTECTION SYSTEM "P-6" PERMISSIVE. FOLLOWING THE REACTOR TRIP, A | | FEEDWATER ISOLATION WAS RECEIVED AS EXPECTED. ALL OTHER EQUIPMENT | | FUNCTIONED AS DESIGNED. THE MALFUNCTION OF THE "P-6" PERMISSIVE IS | | CURRENTLY BEING INVESTIGATED. | | | | ALL RODS FULLY INSERTED ON THE TRIP. THE RE-ALIGNMENT OF ELECTRICAL BUSES | | FOR THE SHUTDOWN HAD ALREADY BEEN COMPLETED, SO THERE WERE NO PROBLEMS WITH | | TRANSFERS OF ELECTRICAL BUSES. THE FEEDWATER ISOLATION WAS RESET, AND THE | | STEAM GENERATORS ARE BEING FED VIA START-UP FEEDWATER, WITH STEAM BEING | | BYPASSED TO THE MAIN CONDENSER. ALL ECCS's AND EDG's ARE CURRENTLY | | OPERABLE. | | | | THE "P-10" PERMISSIVE IS PROVIDED BY THE POWER RANGE NI's AT 10% POWER, | | ALLOWING THE SOURCE RANGE NI's TO RE-ENERGIZE (DECREASING) AND ALSO IS | | DESIGNED TO AUTOMATICALLY SECURE SOURCE RANGE NI's WHEN INCREASING ABOVE | | 10%. THE "P-6" PERMISSIVE PERFORMS THE ACTUAL AUTOMATIC RE-ENERGIZATION OF | | SOURCE RANGE NI's, WHICH IS DESIGNED TO OCCUR AT 5.0 EE-11 AMPS (LESS THAN | | 0% POWER). IN THIS INSTANCE, UPON DECREASING BELOW 10% ("P-10" | | PERMISSIVE), THE "P-6" PERMISSIVE DID NOT "WAIT" UNTIL POWER WAS FURTHER | | REDUCED PRIOR TO ACTUALLY ENERGIZING THE SOURCE RANGE NI's. THE SOURCE | | RANGE FLUX HIGH TRIP IS 1.0 EE+05 CPS. | | | | THE LICENSEE PULLED THE FUSES FOR THE "N-31" NI DRAWER WITHIN A COUPLE OF | | MINUTES OF THE EVENT. WHEN THE NORMAL "P-6" PERMISSIVE SETPOINT PERMISSIVE | | WAS REACHED, THEY RE-INSTALLED THE FUSES. THUS, THE "N-31" SOURCE RANGE NI | | WAS INOPERABLE FOR ABOUT 10 MINUTES, HOWEVER THEY ARE BOTH NOW FUNCTIONING | | PROPERLY. THE "P-6" PERMISSIVE HAS BEEN DECLARED INOPERABLE, HOWEVER THE | | TS LCO ONLY APPLIES IN MODES 1 AND 2. THE LICENSEE INFORMED THE RESIDENT | | INSPECTOR, WHO WAS ON-SITE AT THE TIME OF THE TRIP. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27757 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/08/94 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 13:31 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 12:55[EDT]| |NRC NOTIFIED BY: PATRICK WALSH |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EBE McCABE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SERVICE WATER CHECK VALVE FAILED ITS FORWARD FLOW TEST DURING PERFORMANCE | | OF QUARTERLY SURVEILLANCE TEST PROCEDURE (SERVICE WATER VALVE OPERABILITY | | TEST), PLACING LICENSEE IN TECH SPEC REQUIRED SHUTDOWN PER TECH SPEC | | 3.8.3.1. | | | | DURING PERFORMANCE OF SURVEILLANCE PROCEDURE N2-OSP-SWP-Q001, SERVICE WATER | | VALVE OPERABILITY TEST, CHECK VALVE 2SWP*V802A FAILED ITS FORWARD FLOW | | TEST. 2SWP*V802A IS THE SERVICE WATER RETURN FROM DIVISION 1 SWITCHGEAR | | UNIT COOLERS. WITH THE DIVISION 1 SWITCHGEAR UNIT COOLERS INOPERABLE THE | | ASSOCIATED DIVISION AC/DC SWITCHGEAR IS DECLARED INOPERABLE. TECH SPEC | | 3.8.3.1 REQUIRES RESTORATION OF THE DC SWITCHGEAR WITHIN 2 HOURS OR BE IN | | HOT SHUTDOWN WITHIN 12 HOURS AND COLD SHUTDOWN WITHIN THE FOLLOWING 24 | | HOURS. PLANT SHUTDOWN COMMENCED AT 1255 ON 09/08/94. CURRENT PLANS INCLUDE | | THE FOLLOWING: 1) REFINE THE TEST METHOD TO DETERMINE THE DEGRADED | | COMPONENTS, 2) EVALUATE THE TEST RESULTS BASED ON SERVICE WATER TEMPERATURE | | FOR UNIT COOLER OPERABILITY, & 3) DEVELOP A WORK PLAN TO REPAIR THE | | DEGRADED COMPONENTS. PLANT SHUTDOWN WILL PROCEED AT 5% AN HOUR FOR THE | | FIRST 2 HOURS AND 10% AN HOUR THERE AFTER. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ***UPDATE @ 1945 EDT 9/08/94 BY DEMETRIUS WILLIS TAKEN BY MACKINNON*** | | | | EXITED TECH SPEC REQUIRED SHUTDOWN AT 1945 EDT. ENGINEERING ISSUED A DESIGN | | CHANGE WHICH REMOVED THE INTERNALS OF CHECK VALVE 2SWP*V802A. THE CHECK | | VALVE WITHOUT ITS INTERNALS PASSED ITS FORWARD FLOW SURVEILLANCE TEST. | | LICENSEE HAD A SIMILAR PROBLEM WITH TRAIN "B" CHECK VALVE (2SWP*V802B) AND | | HAD ITS INTERNALS REMOVED SOMETIME LAST YEAR. LOWEST REACTOR POWER REACHED | | WAS 95% POWER. R1DO (EBE McCABE) NOTIFIED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27758 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/08/94 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 13:55[EDT]| |NRC NOTIFIED BY: TIM KULTERMAN |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EBE McCABE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUALLY TRIPPED THE REACTOR WHEN MSIV "C" CLOSED DURING MAIN STEAM LINE | | ISOLATION VALVE PARTIAL STROKE SURVEILLANCE TEST PROCEDURE (SP 3712AA). | | | | DURING MAIN STEAM LINE ISOLATION VALVE MONTHLY SURVEILLANCE TEST PROCEDURE | | (SP 3712AA), THE "C" MSIV FAILED ITS STROKE TIME TEST. PER THE STROKE TIME | | SURVEILLANCE TEST PROCEDURE, MSIV "C" WAS PARTIALLY STROKED AGAIN, AT WHICH | | TIME IT FULLY CLOSED. REACTOR WAS MANUALLY TRIPPED TO CONTROL THE PLANT | | WHEN MSIV "C" CLOSED. ALL RODS FULLY INSERTED INTO THE CORE. TURBINE DRIVEN | | & BOTH MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS STARTED ON LOW LOW STEAM | | GENERATOR WATER LEVEL (THEY ARE STILL OPERATING AND MAINTAINING STEAM | | GENERATOR WATER LEVEL). LICENSEE IS STILL INVESTIGATING WHY MSIV "C" CLOSED | | ON THEM. AS FAR AS LICENSEE KNEW NO PRIMARY OR SECONDARY CODE SAFETY VALVES | | OPENED AND NO PRIMARY PORV OR SECONDARY ATMOSPHERIC VALVES OPENED. STEAM | | DUMP BYPASS CONTROL SYSTEM OPERATED PROPERLY AND IS MAINTAINING Tave AT 557 | | DEGREES F. TENTATIVE RESTART DATE IS 09/15/94. | | | | RESIDENT INSPECTOR, STATE, & LOCAL OFFICIALS WERE INFORMED BY THE LICENSEE. | | | | ***UPDATE TAKEN BY MACKINNON AT 1518 EDT 09/08/94 FROM KULTERMAN*** | | | | LICENSEE IS GOING TO A COLD SHUTDOWN CONDITION TO REPAIR MSIV "C" (LICENSEE | | STILL DOES NOT KNOW WHAT CAUSED THE VALVE TO GO CLOSED). LICENSEE HAS | | DISCOVERED THAT THEIR TURBINE DRIVEN AUXILIARY FEEDWATER PUMP THROTTLE | | VALVE HAD TRIPPED CLOSED (LICENSEE DID NOT KNOW WHEN THE THROTTLE VALVE HAD | | CLOSED). WHEN SG "C" MSIV CLOSED ITS ASSOCIATED CODE SAFETY VALVES | | OPENED/CLOSED. RI WILL BE NOTIFIED. R1DO (EBE McCABE) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27759 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 09/08/94 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 14:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 12:25[EDT]| |NRC NOTIFIED BY: MIKE LEE |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL CLINE 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 63 POWER OPERATION | 63 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFIED DEPARTMENT OF ENVIRONMENTAL HEALTH & CONTROL OF SOUTH CAROLINA | | THAT THEY HAD DISCHARGED SOME FOAMING WATER INTO THEIR DISCHARGE AREA (LAKE | | WYLIE). THE FOAMING WATER CAME FROM THEIR LAUNDRY & HOT SHOWER TANKS. | | | | LICENSEE NOTIFIED THEIR RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27760 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/08/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 14:52[CDT]| |NRC NOTIFIED BY: KNARR |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CYNTHIA PEDERSON 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 | A N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE RECEIVED A SOURCE RANGE HIGH FLUX REACTOR TRIP SIGNAL DURING | | TROUBLESHOOTING OF TRAIN "A" SOLID STATE PROTECTION SYSTEM (SSPS) | | SUBSEQUENT TO THE REACTOR TRIP REPORTED IN EVENT # 27756. | | | | UNIT 1 RECEIVED A SOURCE RANGE HIGH FLUX REACTOR TRIP SIGNAL WHICH | | GENERATED A FEEDWATER ISOLATION. THIS OCCURRED DURING THE INVESTIGATION OF | | THE P-6 SOLID STATE PROTECTION SYSTEM MALFUNCTION WHICH CAUSED THE REACTOR | | TRIP REPORTED IN EVENT # 27756. ALL CONTROL RODS WERE FULLY INSERTED PRIOR | | TO THE SOURCE RANGE HIGH FLUX REACTOR TRIP SIGNAL. LICENSEE HAD TRAIN "A" | | SSPS IN TEST DURING TROUBLESHOOTING. REVIEWING ELECTRICAL DIAGRAMS | | FOLLOWING THE SOURCE RANGE HIGH FLUX REACTOR TRIP SIGNAL, THE LICENSEE | | DISCOVERED THAT WHEN TRAIN "A" SSPS IS IN TEST AND THEN DEENERGIZED, TRAIN | | "B" SSPS GENERATES A SOURCE RANGE HIGH FLUX REACTOR TRIP SIGNAL. THE | | LICENSEE IMMEDIATELY RESET THE FEEDWATER ISOLATION SIGNAL RESTORING NORMAL | | FEEDWATER FLOW TO ALL STEAM GENERATORS (STEAM GENERATOR WATER LEVELS DID | | NOT DECREASE DURING THE TIME THAT NORMAL FEEDWATER WAS ISOLATED). | | | | RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 09/08/94 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 18:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: GREG HOWINGTON |LAST UPDATE DATE: 09/08/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 63 POWER OPERATION | 63 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE AGENCIES NOTIFIED OF CHEMICAL RELEASE OF SODIUM NITRATE EXCEEDING | | REPORTABLE QUANTITY DURING BACK HOE OPERATIONS IN THE YARD. | | | | "WHILE DOING SOME WORK IN THE YARD OF THE PLANT, A BACK HOE OPERATOR | | ACCIDENTALLY DUG INTO ONE OF OUR CONTAINMENT CHILL WATER SYSTEMS LINES | | ASSOCIATED WITH UNIT 1." | | | | "THIS SYSTEM HAS A CHEMICAL IN IT CALLED SODIUM NITRATE. LEAKAGE OF THIS | | SYSTEM HAS CAUSED US TO EXCEED OUR REPORTABLE QUANTITY (>100 POUNDS). THIS | | REQUIRES NOTIFICATION TO DHEC, LOCAL EMERGENCY PLANNING COMMITTEE (YORK | | COUNTY) AND THE NATIONAL RESPONSE CENTER." | | | | THE LICENSEE COULD NOT ESTIMATE THE QUANTITY OF SODIUM NITRATE RELEASED BUT | | DID NOTE THAT THE SYSTEM CAPACITY IS 200 POUNDS. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/08/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 23:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 20:28[CDT]| |NRC NOTIFIED BY: CLARK |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ART HOWELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STEVEN VARGA EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BAGWELL FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |CALLAN R4 | | |BEACH R4 | | |ROE NRR | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 | 0 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM FROM 97% POWER, WITH FAILURE OF THE MAIN GENERATOR | | AND THE TURBINE TO AUTOMATICALLY TRIP. | | | | RIVER BEND HAD AN AUTOMATIC REACTOR SCRAM AT 2028 CDT FROM 97% POWER. THE | | EXACT CAUSE OF THE SCRAM IS UNKNOWN AND IS BEING INVESTIGATED. THE SCRAM | | APPEARED ROUTINE FOR APPROXIMATELY 5 MINUTES, WHEN OPERATORS NOTED THAT IT | | APPEARED THAT THE MAIN GENERATOR AND THE TURBINE HAD FAILED TO TRIP. | | OPERATORS THEN MANUALLY TRIPPED THE MAIN TURBINE AND THE MAIN GENERATOR | | OUTPUT BREAKERS. | | | | THE TRIPPING OF THE MAIN GENERATOR OUTPUT BREAKERS CAUSED AN "ELECTRICAL | | TRANSIENT", RESULTING IN A LOSS OF NORMAL CONDENSATE AND FEEDWATER AND A | | MAIN STEAM ISOLATION. OPERATORS UTILIZED MANUAL OPERATION OF THE SAFETY | | RELIEF VALVES (SRV's) TO CONTROL REACTOR PRESSURE, IN ADDITION TO MAIN | | STEAM LINE DRAIN CAPABILITY (FROM UPSTREAM OF THE INBOARD MSIV's). RCIC | | (REACTOR CORE ISOLATION COOLING) WAS INITIALLY STARTED MANUALLY, BUT | | IMMEDIATELY TRIPPED (FOR REASONS UNKNOWN AND BEING INVESTIGATED). OPERATORS | | THEN MANUALLY UTILIZED HIGH PRESSURE CORE SPRAY (HPCS) TO MAINTAIN AND | | CONTROL REACTOR VESSEL LEVEL. | | | | THE LOWEST LEVEL REACHED DURING THE EVENT WAS APPROXIMATELY +2" (NARROW | | RANGE), WHICH IS BETWEEN LEVEL 3 AND LEVEL 2. THERE WERE NO AUTOMATIC | | INITIATIONS OF ECCS EQUIPMENT (SETPOINTS ARE LEVEL 2). REACTOR PRESSURE, | | TEMPERATURE AND LEVEL ARE CURRENTLY STABLE, WITH PRESSURE BEING MAINTAINED | | BETWEEN 800-1000#, TEMPERATURE AT 500F AND LEVEL NORMAL AT +36" (NARROW | | RANGE). OPERATORS ARE IN THE PROCESS OF TRYING TO ESTABLISH ALTERNATE | | METHODS OF PRESSURE CONTROL. THERE WERE ALSO VARIOUS PRIMARY AND BALANCE OF | | PLANT (BOP) ISOLATIONS AND SYSTEM ACTUATIONS ASSOCIATED WITH THE EVENT, BUT | | A DETAILED LISTING WAS NOT AVAILABLE AT THE TIME OF THE CALL. | | | | THE UNUSUAL EVENT WAS DECLARED AT THE DISCRETION OF THE SHIFT SUPERVISOR AT | | 2209 CDT, BASED ON THE JUDGMENT THAT AUGMENTED SUPPORT WAS DESIRABLE TO AID | | IN RESTORING SYSTEMS AND TO ENSURE NO OTHER DIFFICULTIES WERE INCURRED. THE | | PLANT DID NOT MEET ANY OF THE EAL (EMERGENCY ACTION LEVEL) CRITERIA WHICH | | WOULD REQUIRE DECLARING AN UNUSUAL EVENT. | | | | WHEN THE OPERATORS MANUALLY TRIPPED THE MAIN GENERATOR OUTPUT BREAKERS, THE | | NORMAL STATION BUSES (WHICH RECEIVE POWER FROM PREFERRED BUSES) EXPERIENCED | | A VERY SLOW TRANSFER CAUSING A LOSS OF AUXILIARY SYSTEMS (MAIN FEED AND | | CONDENSATE PUMPS, RECIRCULATION PUMPS, ETC...). THE NORMAL RPS (REACTOR | | PROTECTION SYSTEM) POWER SUPPLIES (VIA THE MG SETS) WERE ALSO LOST DURING | | THE ELECTRICAL TRANSIENT, WHICH CAUSED SOME OF THE ISOLATIONS EXPERIENCED, | | AND OPERATORS QUICKLY TRANSFERRED TO THE ALTERNATE RPS POWER SUPPLY. THE | | PLANT SAFETY BUSES REMAINED ENERGIZED THROUGHOUT THE EVENT (NORMALLY | | POWERED FROM OFF-SITE POWER), AND THE EMERGENCY DIESEL GENERATORS WERE | | NEVER REQUIRED TO START. | | | | OPERATORS ARE IN THE PROCESS OF RESTORING AT LEAST ONE RECIRCULATION PUMP | | AND ONE MAIN STEAM LINE TO SERVICE. NORMAL CONDENSATE AND FEED HAS ALREADY | | BEEN RESTORED. HPCS REMAINS RUNNING, BUT IS NO LONGER INJECTING BECAUSE | | VESSEL LEVEL IS BEING ADEQUATELY MAINTAINED VIA THE CRDH (CONTROL ROD DRIVE | | HYDRAULIC) SYSTEM. THE CALLER STATED THAT THE COOLDOWN EXPERIENCED IS | | CURRENTLY BEING PLOTTED, HOWEVER, THERE WAS NO MAJOR LOWERING OF RX VESSEL | | PRESSURES OR LEVELS. THE UNIT IS NOT EXPERIENCING ANY PROBLEMS WITH | | SUPPRESSION POOL COOLING OR SRV OPERATIONS. ALL RODS FULLY INSERTED INTO | | THE CORE ON THE REACTOR SCRAM. THE LICENSEE NOTIFIED THE RESIDENT | | INSPECTOR, WHO IS IN THE CONTROL ROOM AT THIS TIME, AND STATE AND LOCAL | | AUTHORITIES. THE LICENSEE INTENDS TO TERMINATE THE UNUSUAL EVENT IN A | | FAIRLY SHORT TIME FRAME. | | | | AT 0030 EDT, THE RESIDENT INSPECTOR (WARD SMITH) BRIEFED THE FOLLOWING | | INDIVIDUALS ON THE EVENT: R4RA (CALLAN), R4 (BEACH, HARREL), R4DO (HOWELL), | | NRR EO (VARGA) AND NRR PD 3&4 (ROE). | | | | ** UPDATE DATE/TIME: 9/9/94 @ 0155 EDT *FROM LICENSEE: CLARK BY: McGINTY** | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0055 CDT. THE INITIAL LOOK AT | | THE COMPUTER PRINTOUT INDICATES THAT THE REACTOR SCRAM WAS DUE TO A LEVEL | | TRANSIENT, SPECIFICALLY A HIGH LEVEL (LEVEL 8, +51") TURBINE TRIP AND | | REACTOR SCRAM SIGNAL. THE EXACT CAUSE OF THE TRANSIENT IS STILL UNDER | | INVESTIGATION. THE ABNORMAL CONDITIONS REGARDING THE TURBINE GENERATOR | | TRIP (AS WELL AS THE RCIC TRIP) ARE STILL BEING EVALUATED. THE LICENSEE | | HAS RESTORED THE MAIN STEAM LINES TO SERVICE AND ARE CONTROLLING PRESSURE | | WITH NORMAL STEAM BYPASS. REACTOR PRESSURE VESSEL LEVEL CONTROL HAS BEEN | | RE-ESTABLISHED WITH THE NORMAL CONDENSATE AND FEEDWATER SYSTEM. THEY ARE | | STILL PURSUING THE RESTART OF A RECIRCULATION PUMP (ESTABLISHING DESIRABLE | | DELTA T AND PRESSURE CONDITIONS). THE INITIAL PLANS ARE TO PROCEED TO COLD | | SHUTDOWN. THE PLANT IS STABLE IN HOT STANDBY. | | | | HOO NOTIFIED THE R4DO (HOWELL) AND FEMA (NUSE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27763 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/09/94 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 00:20[EDT]| |NRC NOTIFIED BY: MOSHER |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM CLINE 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 8 POWER OPERATION | 8 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE AT 8% POWER DURING A SHUTDOWN TO ENTER A REFUELING OUTAGE, AN | | UNPLANNED TURBINE TRIP AND FEEDWATER TRANSIENT CAUSED A MAIN FEEDWATER PUMP | | TRIP AND AUX FEED PUMP ACTUATION. | | | | AT 0020 EDT ON 9/9/94, ALL THREE AUXILIARY FEEDWATER (AFW) PUMPS STARTED | | WHEN ALL MAIN FEEDWATER PUMPS TRIPPED DUE TO HIGH-HIGH LEVEL (75% NARROW | | RANGE) IN THE "A" STEAM GENERATOR (THE OTHER SG LEVELS WERE ALSO HIGH). THE | | HIGH-HIGH LEVEL OCCURRED DUE TO A FEEDWATER TRANSIENT WHICH STARTED WHEN | | THE UNIT WAS TAKEN OFF-LINE AND AN UNPLANNED MAIN TURBINE TRIP OCCURRED (AT | | 0017 EDT). AT THIS TIME THE CAUSE OF THE TURBINE TRIP IS UNKNOWN AND IS | | BEING INVESTIGATED. | | | | THE AFW PUMPS (TWO MOTOR DRIVEN AND ONE STEAM DRIVEN) HAVE BEEN SECURED AND | | ARE IN STANDBY, WITH MAIN FEEDWATER RESTORED TO SERVICE. THE UNIT HAS | | COMPLETED ITS SHUTDOWN AND IS IN HOT STANDBY AND BORATING, MAKING | | PREPARATIONS TO COOL DOWN. THE MAIN CONDENSER IS AVAILABLE FOR STEAMING | | VIA THE BYPASSES. ALL EDG's AND ECCS's ARE OPERABLE, AND THERE WERE NO | | PROBLEMS LINING UP THE ELECTRICAL BUSES FOR THE SHUTDOWN. WHEN THE UNIT IS | | BELOW 30% POWER, A TURBINE TRIP DOES NOT CAUSE AN AUTOMATIC REACTOR TRIP. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+