U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/17/96 - 05/20/96 ** EVENT NUMBERS ** 30290 30484 30485 30486 30487 30488 30489 30490 30491 30492 30493 30494 30495 30496 30497 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30290 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/15/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 20:06 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/15/96 | +------------------------------------------------+EVENT TIME: 19:53[EDT]| |NRC NOTIFIED BY: STEPHEN SUDIGALA |LAST UPDATE DATE: 05/17/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 CHANGE TO THE SHUTDOWN COOLING PROCEDURE RESULTED IN A CONDITION NOT IN | | ACCORDANCE WITH THE FSAR | | | | THE FSAR DESCRIBES THE SHUTDOWN COOLING SYSTEM FLOW BEING AUTOMATICALLY | | CONTROLLED BY THE HEAT EXCHANGER OUTLET VALVE AND A HEAT EXCHANGER BYPASS | | VALVE. THE TWO VALVES WORK TOGETHER TO MAINTAIN A CONSTANT FLOW THROUGH | | THE REACTOR VESSEL. | | | | THE LICENSEE BECAME CONCERNED THAT IF THE HEAT EXCHANGER BYPASS VALVE | | CONTROL AIR WERE LOST, THE VALVE WOULD FAIL OPEN. THIS COULD LEAD TO | | RUNOUT OF THE LPCI PUMP. TO PREVENT THIS FROM HAPPENING, THE LICENSEE | | CHANGED ITS SHUTDOWN COOLING PROCEDURE IN 1992. THE LICENSEE NOW PLACES | | THE HEAT EXCHANGER BYPASS VALVE IN THE FULL OPEN POSITION AND THROTTLES | | FLOW WITH THE FOUR DOWNSTREAM LOW PRESSURE COOLANT INJECTION VALVES. THIS | | CONFIGURATION IS NOT IN ACCORDANCE WITH THE FSAR. | | | | THE LICENSEE IS STILL INVESTIGATING THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL | | OFFICIALS. | | | | ***UPDATE AT 17:26 @ 5/17/96 BY BERGIN TO GOULD*** THE LICENSEE REVIEWED | | THEIR DESIGN DOCUMENTATION, AND THE METHOD FOR SHUTDOWN COOLING FLOW | | CONTROL IN THE FSAR REPRESENTS THE PREFERRED METHOD OF CONTROLLING S/D | | COOLING FLOW. THE METHOD THEY USED WOULD HAVE ENABLED THE SYSTEM TO BE | | OPERATED AS DESCRIBED IN THE FSAR EVEN THOUGH THERE WERE DIFFERENCES IN THE | | VALVES USED FOR FLOW CONTROL. THEREFORE, THE LICENSEE IS RETRACTING THIS | | EVENT SINCE IT WAS NOT A REPORTABLE CONDITION. THE RI WAS INFORMED. REG1 | | RDO DELLA GRECA WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30484 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 05/17/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 08:49 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 05/17/96 | +------------------------------------------------+EVENT TIME: 06:35[EDT]| |NRC NOTIFIED BY: JIM PROPER |LAST UPDATE DATE: 05/17/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN STEAM LINE ISOLATION VALVE (MSIV) CLOSURE DUE TO HUMAN ERROR. | | | | THE LICENSEE WAS RESTARTING THE PLANT FOLLOWING THE COMPLETION OF THEIR | | NINTH REFUELING OUTAGE. THE MSIVs AND THEIR BYPASS VALVES WERE OPEN TO | | HEAT THE STEAM LINES. AN I&C TECHNICIAN WAS PERFORMING SURVEILLANCE TESTS | | ON THE STEAM FLOW TRANSMITTERS. HE INADVERTENTLY PLACED TWO TRANSMITTERS | | INTO THE TEST MODE SIMULTANEOUSLY. THIS COMPLETED THE TWO-OUT-OF-THREE | | ACTUATION LOGIC FOR MSIV ISOLATION. THE MSIVs AND THEIR BYPASS VALVES | | CLOSED. NO OTHER ACTUATIONS OCCURRED. THE BISTABLES WERE RETURNED TO | | NORMAL AND THE VALVES REOPENED. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30485 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/17/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:24 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/17/96 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: FARSACI |LAST UPDATE DATE: 05/17/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANIELLO DELLA GRECA RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 THAT THERE IS A POSSIBILITY THAT AN INCORRECT | | EQUATION WAS USED TO CALCULATE THE REACTOR BUILDING BLOW-OUT PANEL LOADING. | | | | THIS WAS CONCLUDED DURING AN ENGINEERING OPERABILITY ANALYSIS FOR THE | | REACTOR BUILDING BLOW-OUT PANELS WHICH WAS COMPLETED 5/17/96. THEY | | DETERMINED THE INTERNAL PRESSURE FAILURE POINT IS 60 PSF FOR THE REACTOR | | BUILDING AND 59 PSF FOR THE TURBINE BUILDING BLOW-OUT PANELS USING THE | | CORRECT EQUATION. HOWEVER, THE FSAR STATES THAT THE PANELS WILL RELIEVE | | (FAIL) AT APPROXIMATELY 45 PSF INTERNAL PRESSURE, AND THAT BUILDING | | STRUCTURE FAILURE WOULD OCCUR AT AN INTERNAL PRESSURE IN EXCESS OF 80 PSF. | | THE BLOW-OUT PANELS ARE OPERABLE BECAUSE THEY WILL FAIL BEFORE EXCEEDING AN | | INTERNAL BUILDING PRESSURE OF 80 PSF. THE CALCULATION FOR COMPUTING | | BLOW-OUT PANEL LOADING INITIALLY USED AN INCORRECT SHEAR/TENSION | | INTERACTION EQUATION WHICH WAS A LINEAR EQUATION AND RESULTED IN A 45 PSF | | FAILURE FOR THE BLOW-OUT PANELS. THE CORRECT EQUATION USED DURING THIS | | ANALYSIS WAS AN ELLIPTICAL EQUATION WHICH RESULTED IN THE HIGHER FAILURE | | VALUE FOR THE BLOW-OUT PANELS. THE LICENSEE IS CURRENTLY INVESTIGATING | | THIS PROBLEM. THE NRC RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30486 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING INC |NOTIFICATION DATE: 05/17/96 | | CITY: MILLS REGION: 4 |NOTIFICATION TIME: 16:45 [ET]| | COUNTY: STATE: WY |EVENT DATE: 05/17/96 | |LICENSE#: SVA-1341 AGREEMENT: N |EVENT TIME: 00:15[MDT]| | DOCKET: |LAST UPDATE DATE: 05/17/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PHIL HARRELL RDO | | |CAMPER/BARRETT EO | +------------------------------------------------+EARL FEMA | |NRC NOTIFIED BY: VASELIN |JOHNSON DOE | |HQ OPS OFFICER: CHAUNCEY GOULD |BICKERTON USDA | +------------------------------------------------+PETIFORD EPA | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COGEMA MINING INC REPORTED THAT THEY HAD AN INJECTION SOLUTION SPILL AT THE | | CHRISTENSEN MINE FROM A 12" TRUNK LINE WHICH HAD A CRACKED PLASTIC | | CONNECTION. | | | | THE SPILL WAS APPROXIMATELY 60,000 GALS OF 0.7 PPM U3O8 SOLUTION WHICH | | FLOWED DOWN A STEEP EMBANKMENT INTO THE SMALL INTERMITTENT WILLOW CREEK | | WHICH EMPTIES INTO THE POWDER RIVER. THEY HAVE RECOVERED APPROXIMATELY | | 2,000 GALS AND THEY ARE STILL TRYING TO RECOVER MORE. THEY HAVE COLLECTED | | SOIL AND WATER SAMPLES FOR EVALUATION. EVERYTHING IS NOW SHUTDOWN AND THEY | | ARE IN THE PROCESS OF REPLACING THE CRACKED PLASTIC PIPE WITH STEEL PIPING. | | THEY HAVE NOTIFIED THE STATE DEPARTMENT OF ENVIRONMENTAL QUALITY. THEY | | DON'T BELIEVE IT IS A HEALTH HAZARD SINCE THE AREA IS SPARSELY POPULATED. | | HHS(RABB) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30487 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/17/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:11 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/17/96 | +------------------------------------------------+EVENT TIME: 16:25[EDT]| |NRC NOTIFIED BY: LATZ |LAST UPDATE DATE: 05/17/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANIELLO DELLA GRECA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DISCOVERED THAT PORTIONS OF THE AUTOMATIC PRESSURE RELIEF | | SYSTEM HAVE BEEN FOUND NOT TO BE SINGLE FAILURE PROOF. | | | | THIS CONDITION WAS FOUND DURING A REVIEW OF THE FSAR. THE DESIGN BASIS | | REQUIRES THAT THE AUTOMATIC PRESSURE RELIEF SYSTEM BE SINGLE FAILURE PROOF. | | SOME EXAMPLES ARE THAT CABLES DID NOT MEET SEPARATION CRITERIA, FAILURE OF | | THE BYPASS SWITCH COULD FAIL THE WHOLE SYSTEM AND CONTROL ROOM ISOLATION | | SWITCH FAILURE COULD ALSO DISABLE THE SYSTEM. ALL THE PROBLEMS WILL BE | | CORRECTED PRIOR TO STARTUP. THE NRC RI, STATE, AND LOCAL AGENCIES WERE | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30488 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/17/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/17/96 | +------------------------------------------------+EVENT TIME: 12:55[CDT]| |NRC NOTIFIED BY: CLARK |LAST UPDATE DATE: 05/17/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT THE CONTROL ROOM EMERGENCY AIR FILTRATION | | SYSTEM WAS NOT FUNCTIONING AS DESIGNED. | | | | WHILE PERFORMING A ROUTINE MONTHLY SURVEILLANCE, THE CONTROL ROOM EMERGENCY | | AIR FILTRATION SYSTEM FAILED TO MAINTAIN THE CONTROL ROOM WITHIN THE 70-80 | | DEGREE F TEMPERATURE BAND AS REQUIRED BY ACCEPTANCE CRITERIA OF THE | | PROCEDURE AND THEIR FSAR. THE EMERGENCY FILTRATION SYSTEM WAS DECLARED | | INOPERABLE AT 12:50. THE SYSTEM ENGINEER SUSPECTS A DRIFTED TEMPERATURE | | SWITCH MAY BE THE PROBLEM. BOTH UNITS ARE IN A CONDITION IN WHICH THE | | EMERGENCY FILTRATION SYSTEM IS NOT REQUIRED TO BE OPERABLE AS PER TS | | 3.8.H.1. THE NRC RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30489 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 05/17/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 22:17 [ET]| |RX TYPE: [3] CE |EVENT DATE: 05/17/96 | +------------------------------------------------+EVENT TIME: 20:07[CDT]| |NRC NOTIFIED BY: COLLINS |LAST UPDATE DATE: 05/18/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 100% POWER | | | | THEY ALSO HAD AN AUTO START OF THE EMERGENCY FEEDWATER SYSTEM DUE TO SHRINK | | OF THE S/G LEVEL FOLLOWING THE REACTOR TRIP. THE EFW WAS NOT ACTUALLY | | NEEDED TO FEED THE S/G AND WAS SECURED WITHIN APPROXIMATELY 1 HR. ALL RODS | | FULLY INSERTED AND NO RELIEF VALVES LIFTED. THEY ARE STILL INVESTIGATING | | THE CAUSE OF THE REACTOR TRIP. THE CONDENSER IS BEING USED AS THE HEAT | | SINK VIA THE STEAM BYPASS CONTROL SYSTEM. THE NRC RI WAS INFORMED. | | | | ***UPDATE @ 0458 EDT 05/18/96 BY COLLINS TAKEN BY MACKINNON*** | | | | THE LICENSEE BELIEVES THAT ROD DRIVE MOTOR GENERATOR SET "A" VOLTAGE | | REGULATOR BEGAN TO FAIL. THIS CAUSED ROD DRIVE MOTOR GENERATOR SET "B" | | BREAKER TO OPEN. ROD DRIVE MOTOR GENERATOR SET "A" TRIED TO PICK UP ROD | | DRIVE MOTOR GENERATOR SET "B" LOAD BUT IT TRIPPED ON HIGH LOAD. THE LOSS | | OF BOTH ROD DRIVE MOTOR GENERATOR SETS CAUSED THE CONTROL RODS TO INSERT | | INTO CORE WHICH GENERATED THE REACTOR TRIP. R4DO (PHIL HARRELL) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30490 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 05/18/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 00:08 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/17/96 | +------------------------------------------------+EVENT TIME: 23:32[EDT]| |NRC NOTIFIED BY: R KASUGA |LAST UPDATE DATE: 05/18/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANIELLO DELLA GRECA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY ANALYSIS BRANCH HAS DISCOVERED A CONDITION THAT COULD HAVE RESULTED | | IN INADEQUATE CORE COOLING GIVEN A POSTULATED DESIGN LOSS OF COOLANT | | ACCIDENT (LOCA). | | | | ANALYSIS INDICATES THAT AT THE TIME OF TRANSFER TO TWO PATH RECIRCULATION | | WITH A 0.05 SQUARE FOOT BREAK IN REACTOR COOLANT SYSTEM LOOP 2 COLD LEG, | | WITH SERVICE WATER TEMPERATURE AT 95øF, AND MOV-861B (HIGH PRESSURE SAFETY | | INJECTION TO LOOP 2 COLD LEG) VALVE FAILING TO RECLOSE (SINGLE FAILURE) | | DURING THE TRANSFER TO SUMP RECIRCULATION THE REACTOR COOLANT SYSTEM (RCS) | | PRESSURE WOULD NOT HAVE DECREASED TO A VALUE SUFFICIENTLY LOW AS TO ALLOW | | LOW HEAD SAFETY INJECTION VIA THE RESIDUAL HEAT REMOVAL (RHR) PUMPS. PER | | THE RECIRCULATION PROCEDURE (ES-1.4), CHARGING FLOW WOULD HAVE BEEN | | THROTTLED, BUT ANALYSIS INDICATES THAT THE FLOW RATES WOULD HAVE BEEN | | INADEQUATE TO MAKE UP FOR FLOW OUT THE BREAK AND FOR BOIL-OFF IN THE CORE. | | COMPUTER ANALYSIS OUT THROUGH 4.4 HOURS, WHILE NOT PREDICTING CORE DAMAGE | | UP TO THAT TIME, PROVIDED NO INDICATION THAT CHARGING FLOW WOULD BE | | ADEQUATE IN THE LONG RUN. | | BASED ON A SPECTRUM OF BREAK SIZES ANALYZED IN RECENT DAYS, UNDER VARIOUS | | TEMPERATURE CONDITIONS WITH VARYING SINGLE FAILURES, IT IS JUDGED THAT THIS | | CONDITION IS LIMITED TO A VERY NARROW RANGE OF PLANT CONDITIONS AND | | POSTULATED BREAK SIZES AND LOCATIONS. | | CONTINUED PLANT OPERATION IS DEEMED ACCEPTABLE BASED ON THE FOLLOWING: | | LOWER DECAY HEAT LEVELS THAN ANALYZED PER CONSERVATIVE DESIGN BASIS | | ASSUMPTIONS, AND SERVICE WATER TEMPERATURE IS SUBSTANTIALLY BELOW 95øF | | (CURRENTLY BETWEEN 50-60øF). THE LOWER SERVICE WATER TEMPERATURE RESULTS | | IN ENHANCED CONTAINMENT HEAT REMOVAL, LOWER CONTAINMENT SUMP TEMPERATURES, | | LOWER SAFETY INJECTION TEMPERATURE DURING ES-1.3 AND ES-1.4, AND LOWER RCS | | TEMPERATURE AND PRESSURE. | | PREVIOUS SENSITIVITY RESULTS INDICATE RCS PRESSURE WOULD BE SUFFICIENTLY | | BELOW THE SHUTOFF HEAD OF THE RHR PUMPS TO ALLOW ADEQUATE SAFETY INJECTION | | DURING TRANSFER TO TWO PATH RECIRCULATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE OF THIS | | EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30491 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/18/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 12:48 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/18/96 | +------------------------------------------------+EVENT TIME: 10:50[EDT]| |NRC NOTIFIED BY: KAMINSKI |LAST UPDATE DATE: 05/18/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 LAKE COUNTY COMMISSIONER OF THE RELEASE OF | | FIFTEEN 8-10LB BAGS OF TRASH, SOME OF WHICH EXCEEDED THEIR ADMINISTRATIVE | | LIMITS FOR FREE RELEASE OUTSIDE. | | | | THESE BAGS OF TRASH CAME FROM THE LICENSEE'S RADIOLOGICAL RESTRICTED AREA | | AND WERE TAKEN TO THE LAKE COUNTY LANDFILL FOR DISPOSAL. THERE WILL BE NO | | ATTEMPT TO RETRIEVE THESE BAGS UNLESS THE COUNTY COMMISSIONER HAS SOME | | CONCERNS. THE ADMINISTRATIVE LIMIT IS 10-20 NANOCURIES PER BAG AND THE | | HIGHEST BAG CALCULATED WAS 32 NANOCURIES. THE NRC RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30492 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 05/18/96 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 13:14 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/18/96 | +------------------------------------------------+EVENT TIME: 11:30[CDT]| |NRC NOTIFIED BY: SCHROEDER |LAST UPDATE DATE: 05/18/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 90 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 90% DUE TO A TURBINE TRIP. | | | | THE TURBINE TRIP'S FIRST OUT ANNUNCIATOR WAS TURBINE STOP VALVES TO CLOSE. | | THEY ARE INVESTIGATING THE CAUSE OF THE TURBINE TRIP SIGNAL. ALL RODS | | FULLY INSERTED AND NO SAFETY VALVES LIFTED OR ECCSs ACTUATED. THE AUX | | FEEDWATER SYSTEM DID AUTO START AND THEY ARE CURRENTLY USING THE STEAM | | GENERATORS FOR THE HEAT SINK. THE NRC RI WAS INFORMED AND THERE MAY BE A | | PRESS RELEASE. | | | | ***UPDATE 0437 EDT 05/19/95 BY KEN SOKOL TAKEN BY MACKINNON*** | | | | THE LICENSEE REPLACED THE MAIN TURBINE EMERGENCY TRIP ELECTROHYDRAULIC | | FLUID SOLENOID VALVE (20ET). THE SOLENOID VALVE HAD FAILED OPEN WHICH | | DUMPED THE MAIN TURBINE STOP VALVES ELECTROHYDRAULIC FLUID CAUSING THEN TO | | CLOSE. THE LICENSEE SAID THAT THEY HAVE A 14 GALLON PER DAY PRIMARY TO | | SECONDARY LEAK. R3DO (ROY CANIANO) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30493 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CALPINE CORP |NOTIFICATION DATE: 05/18/96 | | CITY: SANTA ROSA REGION: 4 |NOTIFICATION TIME: 14:54 [ET]| | COUNTY: STATE: CA |EVENT DATE: 05/16/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:14[PDT]| | DOCKET: |LAST UPDATE DATE: 05/18/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PHIL HARRELL RDO | | |LARRY CAMPER EO | +------------------------------------------------+CONGEL IRD | |NRC NOTIFIED BY: CHEN | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER REPORTED THAT THE CAPLINE CORP CALLED ABOUT A | | RELEASE WHICH OCCURRED IN MIDDLETOWN, CA. | | | | THE RELEASE OCCURRED AT THEIR FACILITY WHEN A GEOTHERMAL STEAM WELL | | RELEASED MATERIAL DUE TO A POWER PLANT SHUTDOWN. THE MATERIALS RELEASED | | WERE; 1329LBS OF HYDROGEN SULFIDE, 786LBS OF AMMONIA ANHYDROUS, 1.5LBS OF | | ARSENIC & 107 CURIES OF RADON. THERE WERE NO REPORTED INJURIES OR | | FATALITIES AND THE RELEASE HAS BEEN SECURED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30494 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/19/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 02:57 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/18/96 | +------------------------------------------------+EVENT TIME: 23:18[CDT]| |NRC NOTIFIED BY: P KARABA |LAST UPDATE DATE: 05/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 3 EMERGENCY DIESEL GENERATOR INADVERTENTLY STARTED BY AN INVALID | | SIGNAL WHILE CLEARING AN OUT OF SERVICE. | | | | ELECTRICAL CHECKS WERE IN PROGRESS PRIOR TO CLEARING AN OUT OF SERVICE WHEN | | AN INVALID ACTUATION SIGNAL WAS GENERATED CAUSING THE UNIT 3 EMERGENCY | | DIESEL GENERATOR TO AUTOSTART. THE UNIT 3 EMERGENCY DIESEL GENERATOR THE | | WAS SECURED. UNIT 3 EMERGENCY DIESEL GENERATOR IS OPERABLE. APPARENT | | CAUSE OF THE EVENT WAS THE PERFORMANCE OF A CONTINUITY CHECK ACROSS | | CONTACTS WHICH SUBSEQUENTLY ENERGIZED THE UNIT 3 EMERGENCY DIESEL GENERATOR | | AUTOSTART RELAY. THE LICENSEE IS INVESTIGATING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THE EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30495 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/19/96 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 05:02 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 05/19/96 | +------------------------------------------------+EVENT TIME: 03:30[CDT]| |NRC NOTIFIED BY: L MCCARTY |LAST UPDATE DATE: 05/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |GARY HOLAHAN EO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION |DAN RISHE FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |FRANK CONGEL (IRD) AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REACTOR TRIP AFTER LOSS OF BOTH MAIN FEEDWATER PUMPS. THE "B" ONCE | | THROUGH STEAM GENERATOR (OTSG) RELIEF STUCK OPEN AND CAUSED AN UNCONTROLLED | | DEPRESSURIZATION OF THE OTSG. | | | | THE LICENSEE MANUALLY TRIPPED THE REACTOR AFTER THE LOSS OF BOTH MAIN | | FEEDWATER PUMPS. ALL RODS FULLY INSERTED INTO THE CORE. THE MOTOR DRIVEN | | AND THE TURBINE DRIVEN EMERGENCY FEEDWATER PUMPS AUTOSTARTED ON LOW OTSG | | WATER LEVEL. THE "B" OTSG HAD TO BE MANUALLY ISOLATED AFTER ONE OF ITS | | RELIEF VALVES STUCK OPEN WHICH CAUSED AN UNCONTROLLED DEPRESSURIZATION OF | | THE OTSG. THE RELIEF VALVE APPEARS TO HAVE CLOSED AFTER "B" OTSG PRESSURE | | WAS REDUCED. THE "B" OTSG WAS BLOWN DOWN AND IS NOW CONSIDERED DRY. THE | | LICENSEE PLANS TO GAG THE RELIEF VALVE (PSV-2685) AND THEN INCREASE "B" | | OTSG WATER LEVEL USING AN EMERGENCY FEEDWATER PUMP. LOWEST PRESSURIZER | | LEVEL WAS 32". A HIGH PRESSURE INJECTION PUMP WAS MANUALLY STARTED PER | | THEIR EMERGENCY OPERATING PROCEDURE DUE TO OVER COOLING CONDITION TO | | SUPPORT THE NORMALLY OPERATING MAKE UP PUMP TO MAINTAIN PROPER PRESSURIZER | | WATER LEVEL (LETDOWN WAS MANUALLY ISOLATED). LOWEST REACTOR COOLANT | | TEMPERATURE WAS 535øF. HOT STANDBY REACTOR COOLANT TEMPERATURE IS 552øF. | | THE HIGH PRESSURE INJECTION PUMP THAT WAS MANUALLY STARTED HAS BE SECURED. | | THE "A" OTSG ATMOSPHERIC VALVE IS BEING USED TO CONTROL REACTOR COOLANT | | SYSTEM TEMPERATURE BECAUSE OF LOW CONDENSER VACUUM DUE TO THE LOSS OF GLAND | | SEAL STEAM TO THE CONDENSER WHICH COMES FROM THE "B" OTSG. THE "A" OTSG | | DOES NOT HAVE ANY LEAKING TUBES. | | ALL EMERGENCY CORE COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE | | FULLY OPERABLE IF NEEDED. THE ELECTRICAL GRID IS ALSO STABLE. | | THE LICENSEE IS BRINGING IN ENGINEERS TO EVALUATE USING EMERGENCY FEEDWATER | | TO RECOVER "B" OTSG WATER LEVEL. THE LICENSEE WILL THEN USE EMERGENCY | | FEEDWATER TO RECOVERY OTSG "B" WATER LEVEL AFTER DISCUSSIONS WITH B&W. | | | | THE LICENSEE MADE A MISTAKE WHEN THEY INFORMED THE STATE THAT THEY WERE IN | | AN ALERT EMERGENCY CLASSIFICATION INSTEAD OF BEING IN UNUSUAL EVENT | | EMERGENCY CLASSIFICATION. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | | | | ***UPDATE @ 0700 EDT 05/19/96 BY STEVE STUMBAUGH TAKEN BY MACKINNON*** | | | | MAIN CONDENSER VACUUM HAS BEEN RESTORED AND "A" OTSG IS NOW DUMPING STEAM | | TO THE MAIN CONDENSER. THE LICENSEE IS PREPARING TO GAG THE RELIEF VALVE. | | | | ***CONFERENCE CALL SET UP @ 715 EDT 05/19/96*** | | | | A CONFERENCE CALL WAS SET UP BETWEEN REGION 4 AND HEADQUARTERS CONCERNING | | THE ABOVE EVENT. THE PARTICIPANTS WERE: REGION 4 ADMINISTRATOR (JOE | | CALLAN), DIVISION OF REACTOR PROJECTS DIRECTOR (JIM DYER), REGION 4 (TERRY | | REIS), R4DO (PHIL HARRELL), ANO SENIOR RESIDENT INSPECTOR (KRISS KENNEDY), | | NRR EO (GARY HOLAHAN), AND AEOD IRD (FRANK CONGEL). | | | | ****COMMISSIONERS ASSISTANTS BRIEFING @ 13:00 05/19/96**** | | THE COMMISSIONERS ASSISTANTS BRIEFING INCLUDED: BAILEY/BARRETT(ERB), | | LANDAU/HENDERSON(PAO), BANGART(SP), MITCHELL(EDO), HOLAHAN(NRR EO), | | HART(SECY), CALLAHAN(CA), MCOSKER(CHAIRMAN), SORENSEN(ROGERS), | | LUBENAU/CHAN(DICUS), KENNEDY(SRI), BECKNER(NRR), KALMAN(PM), CALLAN(RA), | | DYER/REIS(REG 4), AND HARRELL(RDO). | | | | ***UPDATE AT 14:24 FROM PRUITT TO GOULD*** THE NOUE WAS TERMINATED AT | | 13:04CDT. NORMAL FEEDWATER HAS BEEN RESTORED TO THE "B" OTSG AND EMERGENCY | | FEEDWATER HAS BEEN SECURED. THE RI WILL BE NOTIFIED. R4DO (HARRELL), EO | | (HOLAHAN), FEMA (CALDWELL), & IRD (CONGEL) NOTIFIED. | | | | ***UPDATE 2254 EDT 05/19/96 BY MARK GOHMAN TAKEN BY MACKINNON*** | | | | FROM SEQUENCE OF EVENTS: 1. "A" MAIN FEEDWATER PUMP TRIPPED, 2. THE | | LICENSEE THINKS THAT THE REACTOR AUTOMATICALLY TRIPPED ON HIGH REACTOR | | COOLANT SYSTEM PRESSURE JUST WHEN THE REACTOR WAS MANUALLY TRIPPED, AND | | THEN 3. "B" MAIN FEEDWATER PUMP TRIPPED (LICENSEE THINKS THE "B" MAIN | | FEEDWATER PUMP TRIPPED ON HIGH DISCHARGE PRESSURE). THE INTEGRATED CONTROL | | SYSTEM (ICS) SHOULD HAVE PREVENTED THE REACTOR FROM TRIPPING ON HIGH | | REACTOR COOLANT SYSTEM PRESSURE AFTER THE "A" MAIN FEEDWATER PUMP TRIPPED. | | THE LICENSEE IS INVESTIGATING THIS PROBLEM. | | | | IT APPEARS THAT THE COTTER PIN HOLDING THE NUT IN PLACE ON THE STEM OF THE | | RELIEF VALVE WAS NOT CRIMPED PROPERLY OR IT BROKE OFF. THE NUT SITS ON TOP | | OF THE RELIEF VALVE MANUAL LIFT LEVER. WHEN THE RELIEF VALVE OPENED THE NUT | | ON TOP OF THE MANUAL LIFT LEVER VIBRATED DOWN THE SHAFT. WHEN "B" OTSG | | PRESSURE GOT LOW ENOUGH FOR THE RELIEF VALVE TO RESEAT THE NUT JAMED ON THE | | VALVE BODY WHICH PREVENT THE RELIEF VALVE FROM PROPERLY RESEATING. R4DO | | (PHIL HARRELL) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30496 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 05/19/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/19/96 | +------------------------------------------------+EVENT TIME: 15:18[CDT]| |NRC NOTIFIED BY: BASNER |LAST UPDATE DATE: 05/19/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED BOTH EMERGENCY DIESEL GENERATORS INOPERABLE AND IS | | SHUTTING THE PLANT DOWN PER TS 3.0.3. THE LICENSEE USES NEI (NUMARC) BASED | | CLASSIFICATION FOR EMERGENCIES. | | | | ON 5/19/96 @ 00:46 THE "2B" D/G WAS DECLARED INOPERABLE DUE TO ELEVATED | | LUBE OIL AND JACKET WATER TEMPERATURES. AT 15:18 THE "2A" D/G WAS STARTED | | FOR TS REQUIRED SURVEILLANCE. THE "2A" D/G OUTPUT BREAKER TRIPPED WITH | | REVERSE POWER INDICATION, BUT THE D/G CONTINUED TO RUN. WITH BOTH D/G's | | DECLARED INOPERABLE, THE PLANT ENTERED LCO 3.0.3 WHICH REQUIRES THE PLANT | | TO BE IN HOT S/D IN 5 HRS. THEY ARE NOW RAMPING POWER DOWN AT THE RATE OF | | .5%/MIN. THE CAUSE OF THE "2A" D/G BEING INOPERABLE IS BEING INVESTIGATED. | | THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30497 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/20/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 04:00 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/20/96 | +------------------------------------------------+EVENT TIME: 01:06[CDT]| |NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 05/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFF GAS RADIATION MONITOR TRIPPED AFTER REACTOR PROTECTION SYSTEM (RPS) | | MOTOR GENERATOR (MG) SET TRIPPED CAUSING A FULL SCRAM SIGNAL. | | | | WITH UNIT 3 IN THE REFUEL MODE A TRIP OF THE "B" RPS MG SET RESULTED IN A | | FULL REACTOR SCRAM (NO ROD MOVEMENT) AND THE COMPLETION OF THE OFF GAS | | RADIATION MONITOR TRIP LOGIC (ONE MONITOR DOWNSCALE AND ONE MONITOR | | UPSCALE). THIS RESULTED IN OFF GAS SYSTEM VALVES REPOSITIONING TO THEIR | | ISOLATION POSITION. ADDITIONALLY, THE SCRAM DISCHARGE VOLUME VENTS AND | | DRAINS REPOSITIONED AS EXPECTED. THE "3A" RPS BUS WAS ALIGNED TO ITS | | RESERVE FEED AND THE SCRAMS AND ISOLATIONS WERE RESET. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+