U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/10/97 - 06/11/97 ** EVENT NUMBERS ** 32320 32324 32453 32454 32455 32456 32457 32458 32459 32460 32461 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32320 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/12/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:09 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/12/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/10/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JIM MCCORMICKBARGER RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY EQUIPMENT DISABLED - (24-HOUR REPORT) | | | | AT 1530 CDT ON MAY 12, 1997, AN ENGINEERING WALKDOWN OF C-333 BUILDING | | SPRINKLER SYSTEM D-7 REVEALED THAT A SYSTEM MODIFICATION TO CORRECT A | | PREVIOUSLY IDENTIFIED DEFICIENCY HAD NOT BEEN PERFORMED. THE ENGINEERING | | DRAWING WHICH WAS PREPARED TO SHOW THE MODIFICATION REQUIRED TO CORRECT THE | | DEFICIENCY WAS INCORRECT. ONE SPRINKLER HEAD HAD BEEN IDENTIFIED ON AN | | EARLIER WALKDOWN OF THE SYSTEM AS BEING INSTALLED TOO FAR FROM THE CEILING. | | THE ENGINEERING MODIFICATION DRAWING SHOWED THE SPRINKLER HEAD TO BE IN THE | | CORRECT LOCATION. WHEN THE DRAWING WAS REVIEWED FOR WORK PACKAGE | | PREPARATION, IT WAS ASSUMED THAT THE HEAD WAS IN THE PROPER LOCATION, AND | | NO WORK WAS PERFORMED TO MOVE IT. MODIFICATIONS WERE PERFORMED TO CORRECT | | OTHER DEFICIENCIES, AND THE SYSTEM WAS RETURNED TO SERVICE. UPON | | DISCOVERY, THE SYSTEM WAS IMMEDIATELY DECLARED INOPERABLE, AND A FIRE | | PATROL WAS INITIATED AS REQUIRED BY THE TECHNICAL SPECIFICATION | | REQUIREMENTS. | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 06/10/97 @ 2329 BY CAGE TO GOULD*** THE LICENSEE IS RETRACTING | | THIS EVENT BASED ON AN ENGINEERING EVALUATION THAT CONCLUDED ONE HEAD | | OUTSIDE THE PROPER SPRINKLER TO CEILING DISTANCE WILL HAVE NO IMPACT ON THE | | ABILITY OF THE SPRINKLER SYSTEM TO PERFORM ITS SAFETY FUNCTION. THIS CAN | | BE CONCLUDED FROM THE ASSUMPTIONS THAT DUE TO A 28.5 FT. CEILING HEIGHT IN | | C-333, A RADIAL PLUME WILL FORM A 34.2 IN. CEILING JET. A FIRE DIRECTLY | | BENEATH THE SPRINKLER BEING EVALUATED WOULD ACTIVATE THE SPRINKLER WITH THE | | PROPER RESPONSE TIME BASED ON A 34.2 IN. CEILING JET AND THE SPRINKLER | | BEING 30" FROM THE CEILING. A FIRE NOT LOCATED DIRECTLY UNDER ANY OF THE | | SPRINKLERS IN THE AREA WOULD ACTUATE ADJACENT HEADS IN THE AREA WITH PROPER | | RESPONSE TIME. THE LOW SPRINKLER HEAD WOULD HAVE A DELAYED RESPONSE TIME, | | BUT IS STILL FUNCTIONAL AND WOULD AID IN CONTROLLING THE FIRE. THE | | RESIDENT INSPECTOR WAS INFORMED. NOTIFIED R3DO(CREED). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32324 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/13/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:44 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/13/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:50[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/10/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JIM MCCORMICKBARGER RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: W. F. CAGE | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY EQUIPMENT FAILURE (24-HOUR REPORT) | | | | AT 1350 ON MAY 13, 1997, FOREIGN MATERIAL WAS DISCOVERED IN A SPRINKLER | | PIPING DROP WHICH HAD BEEN REMOVED FROM SPRINKLER SYSTEM D-5 IN THE C-337 | | PROCESS BUILDING. THE REMOVED SECTION OF PIPE HAD BEEN INSTALLED IN AN | | AREA WHERE THE SPRINKLER SYSTEM DROPPED INTO A VENTILATION DUCT. SINCE | | OTHER SIMILAR DROPS EXIST ON SYSTEM D-7, THE POTENTIAL EXISTS FOR SIMILAR | | PROBLEMS TO THESE AREAS. SPRINKLER SYSTEM D-7 WAS IMMEDIATELY DECLARED | | INOPERABLE, AND AN HOURLY FIRE PATROL WAS INITIATED AS REQUIRED BY | | TECHNICAL SPECIFICATION REQUIREMENT 2.4.4.5.B.1. ENGINEERING PERSONNEL ARE | | EVALUATING THIS CONDITION. | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 6/10/97 @ 2329 BY CAGE TO GOULD*** THE LICENSEE IS RETRACTING | | THIS EVENT BASED ON AN ENGINEERING EVALUATION THAT CONCLUDED THAT THE | | BLOCKAGE OF ONE HEAD IN THE AFFECTED AREA WOULD HAVE NO EFFECT ON THE | | ABILITY OF THE SPRINKLER SYSTEM TO CONTROL A FIRE IN THE VENTILATION | | DUCTWORK. A SUFFICIENT NUMBER OF SPRINKLER HEADS IN CLOSE PROXIMITY TO THE | | INOPERABLE SPRINKLER HEAD WOULD CONFINE THE FIRE AND THE SPRINKLER HEADS | | ABOVE AND BELOW THE DUCTWORK WOULD ACTUATE AND LOWER THE TEMPERATURE AND | | CONTROL THE FIRE IF IT ESCAPES FROM THE DUCTWORK TO THE BUILDING. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. NOTIFIED R3DO(CREED). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32453 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NAUGATUCK VALLEY RAD. ASSOCIATES |NOTIFICATION DATE: 06/10/97 | | CITY: TORRINGTON REGION: 1 |NOTIFICATION TIME: 11:54 [ET]| | COUNTY: STATE: CT |EVENT DATE: 06/10/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 07:35[EDT]| | DOCKET: |LAST UPDATE DATE: 06/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICHARD KEIMIG RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MC CAHILL(CONN. DEP) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION REPORTED THAT A | | TRUCK HAULING WASTE TO THE TORRINGTON INCINERATOR SET OFF THE TRUCK SCALE | | RADIATION ALARM (MEASURING 100 MICRO REM). IT WAS DETERMINED FROM | | DISCARDED LAB LOGS AND X-RAYS THAT THE WASTE HAD COME FROM NAUGATUCK VALLEY | | RADIATION ASSOCIATES. THE WASTE WAS ISOLATED AND THE STATE HAS PERSONNEL | | AT THE SITE WAITING FOR NAUGATUCK VALLEY RADIATION ASSOCIATES TO RETRIEVE | | THE Tc-99m MATERIAL FROM THE INCINERATOR FACILITY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32454 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/10/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 11:55 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 06/10/97 | +------------------------------------------------+EVENT TIME: 11:01[EDT]| |NRC NOTIFIED BY: ALBERT GARROU |LAST UPDATE DATE: 06/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL THREE CHANNELS OF OVERPOWER DIFFERENTIAL TEMPERATURE (OPdT) DECLARED | | INOPERABLE. | | | | WHILE REDUCING REACTOR POWER FOR QUARTERLY TURBINE VALVE TESTING, IT WAS | | NOTED BY THE REACTOR OPERATOR THAT THE PLOT OF THE OPdT SETPOINTS WERE | | SLIGHTLY INCREASING INSTEAD OF REMAINING AT A CONSTANT VALUE. ALL THREE | | CHANNELS OF OPdT WERE DECLARED INOPERABLE DUE TO NON CONSERVATIVE SETPOINT | | RESPONSE DURING REACTOR COOLANT TEMPERATURE DECREASE [TECHNICAL | | SPECIFICATION SECTION 2.3.1.2.e REQUIRES A CONSTANT, K6 (PRESET MANUALLY | | ADJUSTABLE GAIN), TO BE ZEROED WHEN POWER IS REDUCED]. THE LICENSEE | | ENTERED 3.0 OF THEIR TECHNICAL SPECIFICATION WHICH REQUIRES THEM TO BE IN A | | HOT SHUTDOWN CONDITION WITHIN 8 HOURS (TECHNICAL SPECIFICATION 3.0 IS | | EQUIVALENT TO TECHNICAL SPECIFICATION 3.0.3 USED AT OTHER POWER PLANTS). | | | | THE LICENSEE STATED THAT THE LAST TIME THE OPdT WAS CALIBRATED WAS DURING | | THEIR LAST REFUELING OUTAGE BACK IN SEPTEMBER/OCTOBER OF 1996 AND THE | | CALIBRATION PROCEDURE USED TO CALIBRATE THE OPdT MAY HAVE AN ERROR. | | THEREFORE, THIS NON CONSERVATIVE RESPONSE OF THE OPdT SETPOINT DURING A | | DECREASE IN REACTOR POWER MAY HAVE EXISTED SINCE THEIR LAST REFUELING | | OUTAGE IN 1996. THE LICENSEE IS INVESTIGATING THIS EVENT AT THIS TIME AND | | THEY HAVE MAINTENANCE TECHNICIANS TROUBLESHOOTING THE NON CONSERVATIVE | | SETPOINT RESPONSE OF OPdT. THE LICENSEE HOPES TO HAVE OPdT CONSTANT, K6 , | | RESET PROPERLY BEFORE THEY HAVE TO BE IN A HOT SHUTDOWN CONDITION WHICH | | OCCURS AT 1901 EDT, 06/10/97. | | | | THE ELECTRICAL GRID IS STABLE WITH ALL EMERGENCY CORE COOLING SYSTEMS AND | | EMERGENCY DIESEL GENERATORS FULLY OPERABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | ***UPDATE AT 1543 ON 6/10/97 BY KNIGHT TO GOULD*** THE PLANT EXITED THE LCO | | ACTION STATEMENT AT 1510. THEY HAVE RESTORED TWO OF THE THREE CHANNELS BY | | RESETTING THEIR SETPOINTS CORRECTLY. THE THIRD CHANNEL SHOULD BE RESTORED | | WITHIN 1 HR. PLANT IS STILL AT 100% POWER. THE RESIDENT INSPECTOR WAS | | INFORMED | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32455 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/10/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 16:20 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/05/97 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 06/10/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THEY DISCOVERED A FAILED CHECK VALVE IN THE "B" TRAIN | | CONTAINMENT BUILDING SPRAY SYSTEM CONTAINMENT ISOLATION PENETRATION. | | | | ON 6/5/97 THE LICENSEE PERFORMED AN INSPECTION ON THE "B" TRAIN CONTAINMENT | | BUILDING SPRAY(CBS) SYSTEM CONTAINMENT ISOLATION PENETRATION TO DETERMINE | | THE CAUSE OF A LOCAL LEAK RATE TEST FAILURE. THIS CONTAINMENT ISOLATION | | PENETRATION(X-15) CONSISTS OF A MOTOR OPERATED VALVE(CBS-V17) OUTSIDE | | CONTAINMENT AND A SWING CHECK VALVE (CBS-V18) INSIDE CONTAINMENT. THE | | INSPECTION REVEALED THE DISC OF THE CHECK VALVE BEING WEDGED OR STUCK IN | | THE OPEN POSITION. THE CHECK VALVE ASSOCIATED WITH PENETRATION | | "X-14"(TRAIN A) WAS FOUND IN THE CLOSED POSITION, BUT IS ALSO SUSCEPTIBLE | | TO SIMILAR STICKING. THE LOSS OF CONTAINMENT ISOLATION VALVE FUNCTION | | DURING PLANT OPERATION IS A CONDITION THAT RESULTS IN A LOSS OF CONTAINMENT | | FUNCTION OR INTEGRITY. PENETRATION X-15 IS NORMALLY ISOLATED BY A CLOSED | | MOTOR-OPERATED VALVE(CBS-V17) DURING PLANT OPERATION. IT WAS NOT | | DETERMINED UNTIL 1530 ON 06/10/97 THAT THIS WAS A REPORTABLE EVENT. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32456 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/10/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:33 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/10/97 | +------------------------------------------------+EVENT TIME: 16:15[EDT]| |NRC NOTIFIED BY: WISNIEWSKI |LAST UPDATE DATE: 06/10/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 DISCOVERED THEY HAVE NON-NUCLEAR SAFETY PRESSURE REGULATORS | | PROVIDING ALTERNATE COOLING TO THE EMERGENCY DIESEL GENERATORS(EDG's). | | | | DURING AN EQUIPMENT REVIEW BY INSTRUMENT & CONTROL PERSONNEL, IT WAS | | DISCOVERED THAT THE CONTROLLERS FOR "PCV-104-69A/B" USE NON-NUCLEAR SAFETY | | PRESSURE REGULATORS WHEN THE VALVES PERFORM A SAFETY FUNCTION (PROVIDE | | ALTERNATE COOLING TO THE EDG's). THE PRESSURE REGULATORS, HOWEVER, ARE | | CONSIDERED OPERABLE, THEREFORE ALTERNATE COOLING TO THE EDG's IS STILL | | OPERABLE. THE OPERATING PROCEDURES FOR ALTERNATE COOLING REQUIRE OPENING | | THE MANUAL ISOLATION VALVE TO THE PRESSURE CONTROL VALVE AND TO MANUALLY | | POSITIONING IT IF THE PRESSURE CONTROL VALVE IS NOT PERFORMING ITS | | FUNCTION. THEY CURRENTLY HAVE A WORK ORDER REQUEST IN TO REPLACE THESE | | REGULATORS WITH SAFETY CLASS REGULATORS. THEY ARE NOT IN ANY TYPE OF LCO | | ACTION STATEMENT. THE RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | HOO NOTE: SEE SIMILAR EVENT #32370 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32457 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 06/10/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 19:18 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/10/97 | +------------------------------------------------+EVENT TIME: 18:31[EDT]| |NRC NOTIFIED BY: DAVIS |LAST UPDATE DATE: 06/10/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AUTO START OF THE HIGH PRESSURE CORE SPRAY(HPCS) SYSTEM. | | | | THIS OCCURRED WHILE AN I&C TECH WAS MANIPULATING VALVES ASSOCIATED WITH A | | REFERENCE LEG PURGE PANEL FOR CONDENSING CHAMBER "1B21D004D". WHILE | | PERFORMING THIS EVOLUTION, A LEVEL SPIKE CAUSED HPCS TO INITIATE ON A | | REACTOR LEVEL 2 SIGNAL, STARTING THE HPCS PUMP AND DIESEL GENERATOR. THE | | DIESEL DID NOT LOAD. THE PLANT ALSO RECEIVED A HALF SCRAM AND HALF BOP | | ISOLATION AND THERE WAS NO INJECTION TO THE REACTOR PRESSURE VESSEL. THE | | HPCS PUMP WAS SECURED AND THE SIGNAL CLEARED. THE DIESEL WAS LOADED TO 50% | | AND WILL RUN FOR ONE HOUR BEFORE IT CAN BE SHUT DOWN. THE ROOT CAUSE OF | | THE EVENT IS STILL BEING INVESTIGATED. THE RESIDENT INSPECTOR HAS BEEN | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32458 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/10/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:39 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/10/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:15[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/10/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 | | +------------------------------------------------+ | |NRC NOTIFIED BY: SPAETH | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE FEEDING A 48" UF6 CYLINDER IN AUTOCLAVE #2, THE OPERATOR AT X-343 | | RECEIVED AN AUDIBLE AND VISUAL ALARM INDICATING STEAM SHUTDOWN OF THE | | AUTOCLAVE. AN INVESTIGATION REVEALED THAT BOTH HIGH LEVEL CONDENSATE | | ALARMS WERE ACTIVATED CAUSING THE STEAM TO SHUTDOWN. | | | | AUTOCLAVE #2 WAS IMMEDIATELY SHUTDOWN AND DECLARED INOPERABLE BY THE PLANT | | SHIFT SUPERVISOR AT 1930. THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR | | RADIOLOGICAL CONTAMINATION EXPOSURE ASSOCIATED WITH THIS ACTIVATION. A | | LARGE AMOUNT OF CONDENSATE WAS REMOVED FROM THE DRAIN LINE INDICATING THAT | | A VALID SAFETY SYSTEM ACTUATION HAD OCCURRED DUE TO A POTENTIAL DRAIN LINE | | PLUG OR RESTRICTION. THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32459 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/11/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/10/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:09[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/11/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN JORDAN | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFICATION OF STATE AGENCY DUE TO EXCEEDING LIMITS OF AIR POLLUTION | | PERMIT. | | | | "ON TUESDAY, JUNE 10, 1997, AT 2209 HOURS EDT, THE X-600 STEAM PLANT #1 | | BOILER AND ELECTROSTATIC PRECIPITATOR (ESP) EXPERIENCED AN OPACITY | | EXCEEDANCE. | | | | THE OHIO ENVIRONMENTAL PROTECTION AGENCY (OHIO EPA) AIR PERMIT ISSUED TO | | PORTS DEFINES AN OPACITY EXCEEDANCE AS OCCURRING WHEN OPACITY (SOOT AND | | FLYASH CONCENTRATION) EXCEED 20% FOR MORE THAN SIX (6) MINUTES. SINCE 2209 | | HOURS, FOUR (4) EXCEEDANCES HAVE BEEN RECORDED: 2209-2215 @ 21%, 2232-2238 | | @ 21%, 2305-2311 @ 21% AND 2333-2339 @ 22%. | | | | SINCE RECORDING THE EXCEEDANCES, THE OPACITY HAS STABILIZED AT 19.8%. THE | | EXCEEDANCES RESULTED FROM AN ELECTRICAL MALFUNCTION INSIDE THE ESP WHICH | | CAUSED LOSS OF PRIMARY AND SECONDARY POWER TO THE SOOT AND FLYASH COLLECTOR | | PLATES, AND AN INABILITY TO CONTROL EMISSIONS WITHIN LIMITS WITHOUT THE | | NECESSARY POWER. | | | | THE CURRENT PLANT STEAM LOAD REQUIRES TWO (2) OF THE THREE (3) BOILERS AT | | X-600 TO BE OPERATING. BOILER #3 IS BEING PREPARED FOR START-UP AFTER | | BEING OUT OF SERVICE FOR REPAIR. DURING BOILER START-UP, THE PORTS AIR | | PERMITS ALLOWS FOR AN EXTENDED OPACITY EXCEEDANCE OF UP TO SIX (6) HOURS. | | AFTER BOILER #3 IS PLACED ON-LINE, UTILITIES OPERATIONS WILL SHUTDOWN | | BOILER #1 FOR ELECTRICAL REPAIRS. | | | | NO ADVERSE ENVIRONMENTAL EFFECTS ARE ANTICIPATED AS A RESULTS OF THIS | | EVENT. THE OHIO ENVIRONMENTAL PROTECTION AGENCY ASSIGNED REPORT #2331 TO | | THIS EVENT, AND THE PIKE COUNTY SHERIFF'S OFFICE WAS NOTIFIED AS POINT OF | | CONTACT FOR THE PIKE COUNTY EMERGENCY PLANNING COMMITTEE. THE NRC SENIOR | | RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS EVENT." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32460 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 06/11/97 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 02:22 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 06/10/97 | +------------------------------------------------+EVENT TIME: 23:50[CDT]| |NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 06/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INVALID ESF SIGNAL DURING SURVEILLANCE TESTING. | | | | "WHILE LIFTING LEADS TO DEFEAT AN ISOLATION SIGNAL TO THE HIGH PRESSURE | | COOLANT INJECTION (HPCI) SYSTEM TO FACILITATE VALVE CYCLING FOR OPERATING | | SURVEILLANCES, A HPCI SUCTION AUTO-TRANSFER OCCURRED. THE APPARENT CAUSE | | OF THE EVENT WAS THAT A DAISY CHAIN IN THE HPCI CONTROL LOGIC WAS BROKEN | | RESULTING IN AN INVALID CST LO-LO LEVEL SIGNAL. UNIT 3 IS IN MODE 4 AND | | HPCI WAS NOT REQUIRED TO BE OPERABLE." | | | | THE LICENSEE IS BACKING OUT OF THE SURVEILLANCE. CORRECTIVE ACTIONS | | INCLUDE REVISING THE PROCEDURE TO BE MORE SPECIFIC IN IDENTIFYING THAT THE | | "FIELD" SIDE OF THE TERMINAL BOARD LEADS SHOULD BE LIFTED ("IN-COMING" SIDE | | LEADS WERE LIFTED IN THIS INSTANCE). UPON COMPLETION OF THE INVESTIGATION | | AND CORRECTIVE ACTIONS, THE LICENSEE WILL REPEAT THIS SURVEILLANCE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32461 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/11/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 03:44 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/11/97 | +------------------------------------------------+EVENT TIME: 02:10[EDT]| |NRC NOTIFIED BY: GARY SCHIENDELMAN |LAST UPDATE DATE: 06/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 92 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN UNPLANNED ISOLATION OF THE STEAM SUPPLY LINE TO THE | | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM DUE TO OPERATOR ERROR. | | | | "WHILE PERFORMING RESTORATION OF THE UNIT 2 RCIC SYSTEM, THE MAIN CONTROL | | ROOM OPERATOR MISTAKENLY OPENED THE OUTBOARD STEAM LINE ISOLATION VALVE | | PRIOR TO ENSURING THE STEAM PIPING WAS FILLED/WARMED. AS A RESULT, A HIGH | | STEAM FLOW ISOLATION SIGNAL WAS GENERATED AND THE INBOARD AND OUTBOARD | | STEAM LINE ISOLATION VALVES CLOSED. THE STEAM LINE WARMING WAS REINITIATED | | TO PLACE RCIC INTO A STANDBY CONDITION. ALL SYSTEMS RESPONDED AS DESIGNED | | DURING THIS EVENT. THIS EVENT IS BEING REPORTED PURSUANT TO | | 10CFR50.72(b)(2)(ii) FOR AN ESF ACTUATION." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+