U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/15/95 - 12/18/95 ** EVENT NUMBERS ** 29651 29703 29723 29724 29725 29726 29727 29728 29729 29730 29731 29732 29733 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29651 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 11/28/95 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 17:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/28/95 | +------------------------------------------------+EVENT TIME: 15:37[CST]| |NRC NOTIFIED BY: PAUL COX |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPARENT FAILURE TO MAINTAIN THE HEIGHT LIMIT FOR MOVING NEW FUEL OVER THE | | NEW FUEL STORAGE RACKS | | | | DURING A REVIEW OF A SIMILAR EVENT AT MILLSTONE (REFER TO EVENT NUMBER | | 29634 FOR ADDITIONAL INFORMATION.), THE LICENSEE DISCOVERED THAT THE | | 3.5-FOOT HEIGHT LIMIT FOR MOVING NEW FUEL OVER THE NEW FUEL STORAGE RACKS | | WAS APPARENTLY EXCEEDED. THE FSAR FUEL DAMAGE ESTIMATES FOR AN ASSEMBLY | | DROPPED IN THE AREA OF THE NEW FUEL STORAGE RACKS WAS BASED UPON THE | | ASSEMBLIES BEING NO HIGHER THAN 3.5 FEET ABOVE THE FUEL RACKS. HOWEVER, | | FUEL HAS ACTUALLY BEEN MOVED APPROXIMATELY 6 FEET ABOVE THE RACK. | | | | THERE IS AN INTERLOCK ON THE FUEL HANDLING BRIDGE CRANE THAT WOULD PREVENT | | THIS FROM OCCURRING. HOWEVER, THE LARGE OVERHEAD CRANE THAT IS REQUIRED TO | | TO BE USED TO MOVE THE NEW FUEL FROM THE NEW FUEL RECEIPT AREA OTHER TO THE | | RACK DOES NOT HAVE THIS LIMIT. | | | | FUEL IS NOT BEING MOVED AT THIS TIME. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 12/15/95, @ 05:50 BY BHATTY TO GOULD * * * | | AFTER A THOROUGH REVIEW, THE LICENSEE DETERMINED THAT THE NEW FUEL STORAGE | | RACKS HAVE ALWAYS BEEN IN A DRY CONDITION. AS CONFIRMED BY WESTINGHOUSE, | | UNDER DRY CONDITIONS, DEFORMATION OF THE RACKS OR ASSEMBLIES CANNOT RESULT | | IN AN UNSAFE GEOMETRIC SPACING LEADING TO ACCIDENTAL CRITICALITY OF THE | | FUEL. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R4DO (LINDA HOWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29703 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ALASKA INDUSTRIAL X-RAY COMPANY |NOTIFICATION DATE: 12/12/95 | | CITY: ANCHORAGE REGION: 4 |NOTIFICATION TIME: 13:29 [ET]| | COUNTY: STATE: AK |EVENT DATE: 12/08/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[YT ]| | DOCKET: |LAST UPDATE DATE: 12/16/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LINDA HOWELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: PETER MILLAR | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |DLOS 73.71(a) SHIPMENT LOST | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - INDUSTRIAL RADIOGRAPHY CAMERA CONTAINING IRIDIUM-192 SOURCE MISSING - | | | | ALASKA INDUSTRIAL X-RAY COMPANY, ANCHORAGE, ALASKA, WAS SHIPPING A 2-FOOT | | BY 2-FOOT BARREL CONTAINING AN INDUSTRIAL RADIOGRAPHY CAMERA WHICH CONTAINS | | A 9-CURIE IRIDIUM-192 SEALED SOURCE TO ROCKFORD CORPORATION, COLD BAY, | | ALASKA. THE SHIPPING COMPANY, NORTHERN AIR CARGO COMPANY, NOTIFIED THE | | SHIPPER THAT THE BARREL WAS MISSING. THE BARREL WAS LAST KNOWN TO BE | | LOCATED IN DUTCH HARBOR, ALASKA, AND IT WAS TO BE PICKED UP THERE BY | | ALEUTION AIR COMPANY. THE SHIPPING COMPANY IS ATTEMPTING TO LOCATE THE | | BARREL. | | | | THE LICENSEE WILL SUBMIT A WRITTEN REPORT OF THIS EVENT TO THE NRC. | | | | REFER TO THE HOO LOG FOR THE SHIPPER'S TELEPHONE NUMBER. | | | | ***UPDATE ON 12/16/95 @ 2114 ET BY PETER MILLAR TAKEN BY MACKINNON*** | | | | PETER MILLAR SAID THAT THE 9-CURIE IRIDIUM-192 SOURCE WAS FOUND AT COLD BAY | | BY THE UNITED STATES NAVY. THE INDUSTRIAL RADIOGRAPHY CAMERA WILL BE | | BARGED TO DUTCH HARBOR (UNALASKA ISLAND) AND THEN FLOWN BACK TO ANCHORAGE. | | | | THE R4DO (LINDA HOWELL) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29723 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 12/15/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 04:49 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 12/15/95 | +------------------------------------------------+EVENT TIME: 02:40[EST]| |NRC NOTIFIED BY: BRANTLEY |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC START OF THE "A" EMERGENCY FEEDWATER (EFW) PUMP DUE TO PERSONNEL | | ERROR | | | | THE AUTOMATIC START OCCURRED AFTER THE LICENSEE HAD COMPLETED TESTING OF | | THE "A" SIDE OF THE EFW SYSTEM AND WAS GOING THROUGH THE RESTORATION STEPS. | | THE TECHNICIAN PERFORMING THE TEST INADVERTENTLY PLACED THE DEFEAT SWITCH | | TO ENABLE BEFORE PLACING THE TEST SIGNAL SWITCH TO ENABLE. THIS ACTION | | CAUSED THE "A" EFW PUMP TO AUTOMATICALLY START. THE PUMP WAS SECURED | | WITHIN 3 SECONDS, AND NO WATER WAS INJECTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | * * * UPDATE AT 1106 ON 12/15/95, FROM NELSON TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS RETRACTED THIS NOTIFICATION. THE EVENT WAS NOT REPORTABLE | | BECAUSE THE ACTUATION WAS INVALID AND THE SYSTEM HAD BEEN PROPERLY REMOVED | | FROM SERVICE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (LINVILLE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29724 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 12/15/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 10:41 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 12/15/95 | +------------------------------------------------+EVENT TIME: 10:15[EST]| |NRC NOTIFIED BY: MOFFATT |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABLE BORATED WATER STORAGE TANK (BWST) VACUUM BREAKER | | | | THIS OCCURRED DURING THE PERFORMANCE OF SCHEDULED PREVENTATIVE MAINTENANCE | | ON DHV-70, BWST VACUUM BREAKER. UPON INSPECTION, AFTER REMOVING THE VALVE, | | THE LICENSEE FOUND THAT IT WAS INOPERABLE DUE TO THE SENSING LINE BEING | | BLOCKED WITH CORROSION PRODUCTS. | | | | SUBSEQUENT INVESTIGATION REVEALED THAT THE TWO EXISTING VACUUM BREAKERS | | (DHV-70 AND DHV-69 EACH CONSIDERED ALONE) DID NOT HAVE ADEQUATE RELIEF | | CAPACITY (AT THE EXISTING SETPOINT) TO SUPPORT WORST CASE BWST DRAWDOWN | | DURING LOCA CONDITIONS. THIS IS THE CONDITION THAT IS OUTSIDE THE DESIGN | | BASIS. | | | | TO CORRECT THE PROBLEM, BOTH VALVES WILL BE REPLACED WITH UPGRADED VALVES | | WHICH ARE NOT SUSCEPTIBLE TO THE FAILURE MECHANISM NOTED ON DHV-70. IN | | ADDITION, EACH VALVE WILL BE SIZED TO HANDLE FULL VACUUM RELIEF | | REQUIREMENTS THUS ELIMINATING THE POTENTIAL DESIGN BASIS ISSUE. | | CALCULATIONS WILL BE FINALIZED TO DETERMINE WHETHER CRYSTAL RIVER UNIT 3 | | WAS IN FACT OUTSIDE THE DESIGN BASIS OF THE PLANT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29725 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 12/15/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:51 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 12/15/95 | +------------------------------------------------+EVENT TIME: 08:51[CST]| |NRC NOTIFIED BY: BENGTSON |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 83 POWER OPERATION | 83 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INACCURACIES IDENTIFIED IN THE CORE THERMAL POWER CALCULATION. | | | | IT WAS RECENTLY DISCOVERED THAT THE REACTOR RECIRCULATION SEAL PURGE FLOW | | IS TAPPED OFF THE CONTROL ROD DRIVE (CRD) SYSTEM PRIOR TO THE FLOW | | MEASUREMENT SENSOR WHICH IS USED AS INPUT FOR THE CORE THERMAL POWER | | CALCULATION. AS A RESULT, FLOW IS NOT ACCOUNTED FOR IN THE HEAT BALANCE | | CALCULATION. WITH A BOUNDING CASE SCENARIO OF 12 GPM (6 GPM PER CRD PUMP) | | AND NO CREDIT TAKEN FOR SEAL STAGING FLOW, THE INACCURACY IN THE CORE | | THERMAL POWER CALCULATION CAN BE AS HIGH AS 2 MWt. | | | | REACTOR BUILDING CLOSED COOLING WATER REMOVES HEAT FROM THE REACTOR | | RECIRCULATION SYSTEM VIA A HEAT EXCHANGER. THIS FLOW, APPROXIMATELY 40 | | GPM, CAN PROVIDE SLIGHTLY LESS THAN 0.3 MWt OF COOLING. THE AFFECTS OF | | THIS COOLING ARE NOT PRESENTLY ACCOUNTED FOR IN THE HEAT BALANCE | | CALCULATIONS. | | | | THE LICENSEE'S REACTOR ENGINEERS IN CONJUNCTION WITH GE HAVE COMPLETED A | | REVIEW OF THE IMPACT OF THESE UNCERTAINTIES ON THE CORE THERMAL POWER | | CALCULATION. IT HAS BEEN DETERMINED THAT THESE UNCERTAINTIES ARE BOUNDED | | BY THE ASSUMPTIONS OF THE CORE THERMAL POWER CALCULATION. AS A RESULT OF | | THIS INVESTIGATION, THE LICENSEE HAS CONCLUDED THAT NEITHER UNIT HAS | | OPERATED ABOVE THE LICENSED RATED THERMAL POWER LIMIT (3,323 MWt) SPECIFIED | | IN THE TECHNICAL SPECIFICATIONS. | | | | FOR ADDITIONAL CONSERVATISM AND UNTIL UNCERTAINTIES CAN BE SPECIFICALLY | | ACCOUNTED FOR WITHIN THE CORE THERMAL POWER CALCULATION, THE LICENSEE HAS | | LIMITED REACTOR POWER TO A MAXIMUM OF 3,320 MWt. (THE LICENSE LIMIT IS | | 3,323 MWt.) | | | | THE FINAL SOLUTION WILL BE TO INCLUDE A 2.3 MWt BIAS TO THE "RADIANT HEAT | | LOSS" TERM OF THE CORE THERMAL POWER CALCULATION, THE PROCESS COMPUTER HEAT | | BALANCE PROGRAM, AND THE MANUAL HEAT BALANCE PROCEDURE. THESE ACTIONS | | SHOULD BE ACCOMPLISHED BY 12/22/95. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | | | | (REFER TO EVENT NUMBER 29716 FOR A SIMILAR EVENT.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29726 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 12/15/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 12:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/15/95 | +------------------------------------------------+EVENT TIME: 09:33[CST]| |NRC NOTIFIED BY: DUDEK |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM KOZAK 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATOR (EDG) "2B" INADVERTENTLY STARTED. | | | | WHILE ATTEMPTING TO PLACE THE "2B" EDG CONTROL SWITCH IN THE PULL-TO-LOCK | | POSITION, THE EDG INADVERTENTLY STARTED. THE OPERATOR HAD SOME DIFFICULTY | | OPERATING THE SWITCH (IT DID NOT TURN IT FAR ENOUGH TO THE LEFT WHEN HE | | PULLED IT OUT.) AND INADVERTENTLY PLACED THE SWITCH IN THE START POSITION. | | THE EDG AND ITS AUXILIARY EQUIPMENT ALL FUNCTIONED AS REQUIRED. THE EDG | | HAS SINCE BEEN SHUTDOWN AND PLACED IN AN OUT-OF-SERVICE CONDITION AS WAS | | THE ORIGINAL INTENTION. EDG "2A" IS FULLY OPERABLE IF NEEDED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29727 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNITED STATES ARMY |NOTIFICATION DATE: 12/15/95 | | CITY: COLORADO SPRING REGION: 4 |NOTIFICATION TIME: 16:23 [ET]| | COUNTY: STATE: CO |EVENT DATE: 12/15/95 | |LICENSE#: BML1200722-07 AGREEMENT: Y |EVENT TIME: 15:23[MST]| | DOCKET: |LAST UPDATE DATE: 12/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM KOZAK RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: G. BUCKROP | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPROXIMATELY 0.016 CURIES OF PROMETHIUM-241 WAS BURIED AT FORT CARSON | | LOCATED NEAR COLORADO SPRINGS, COLORADO. | | | | OFFICER G. BUCKROP (ALTERNATE RADIATION PROTECTION OFFICER) OF THE UNITED | | STATES ARMY CALLING FROM THE INDUSTRIAL OPERATION CENTER LOCATED AT ROCK | | ISLAND, ILLINOIS, REPORTED THE FOLLOWING EVENT. | | | | BETWEEN AUGUST OF 1994 AND NOVEMBER 1995, 378 FRONT AIMING SIGHTS FROM | | LIGHT ANTI-TANK WEAPON SYSTEMS EACH CONTAINING A SMALL QUANTITY OF | | PROMETHIUM-241 WERE ACCIDENTALLY BURIED AT FORT CARSON. THE FRONT AIMING | | SIGHTS WERE MANUFACTURED DURING THE MID 1970s. EACH FRONT AIMING SIGHT | | ORIGINALLY CONTAINED 3 MILLICURIES OF PROMETHIUM-241. THE PROMETHIUM-241 | | IS ENCAPSULATED INSIDE A CERAMIC MICROSPHERE, AND THE MICROSPHERE IS | | LAMINATED BETWEEN TWO PIECES OF PLASTIC. | | | | THE LICENSEE MADE A CONSERVATIVE ESTIMATION THAT 0.016 CURIES OF | | PROMETHIUM-241 WAS BURIED AT FORT CARSON. THE LICENSEE ASSUMED THAT THE | | HALF LIFE OF PROMETHIUM-241 WAS 2.62 YEARS, THAT EACH SIGHT CONTAINED 3 | | MILLICURIES, AND THAT THEY WERE ALL MANUFACTURED IN 1979. THE LICENSEE IS | | INVESTIGATING THIS INCIDENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29728 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 12/15/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 16:24 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/15/95 | +------------------------------------------------+EVENT TIME: 12:27[CST]| |NRC NOTIFIED BY: CLARK |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 87 POWER OPERATION | 87 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DIVISION 1 PRIMARY CONTAINMENT ISOLATION INSTRUMENT FOR THE REACTOR CORE | | ISOLATION COOLING (RCIC) SYSTEM STEAM FLOW-HIGH ISOLATION FUNCTION FAILED | | DOWNSCALE. | | | | THE DIVISION 1 PRIMARY CONTAINMENT ISOLATION INSTRUMENT (E311-N683A) FOR | | THE RCIC SYSTEM STEAM FLOW-HIGH ISOLATION FUNCTION FAILED DOWNSCALE. | | FAILURE OF THE INSTRUMENT CAUSED A DIVISIONAL ISOLATION OF THE RCIC STEAM | | SUPPLY OUTBOARD ISOLATION VALVE (ESI-F064). THE ISOLATION OF THE SYSTEM | | CAUSED AUTOMATIC CLOSURE OF THE RCIC TURBINE TRIP/THROTTLE VALVE (WHICH WAS | | IN STANDBY). ALARM RESPONSE PROCEDURES WERE UTILIZED TO VERIFY THAT | | REQUIRED SYSTEM RESPONSE HAD OCCURRED. ALL SYSTEMS AND COMPONENTS | | RESPONDED AS REQUIRED. TECHNICAL SPECIFICATION 3.3.6.1, TABLE 3.3.6.1-1, | | FUNCTION 3A, STATES THAT DIVISION 1 PRIMARY CONTAINMENT ISOLATION | | INSTRUMENT (E311-N683A) HAS TO BE REPAIRED WITHIN 24 HOURS. ALL OTHER | | EMERGENCY CORE COOLING SYSTEMS ARE FULLY OPERABLE IF NEEDED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29729 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 12/15/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:05 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/15/95 | +------------------------------------------------+EVENT TIME: 17:02[EST]| |NRC NOTIFIED BY: PIERRE L'HEUREUX |LAST UPDATE DATE: 12/15/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM LINVILLE 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 +------------------------------------------------------------------------------+ | LOW PRESSURE SAFETY INJECTION (LPSI) FLOW RATE MAY BE REDUCED AS MUCH AS | | 10%. | | | | A REVIEW OF PAST LPSI FLOW TESTS HAS RAISED QUESTIONS AS TO THE ABILITY OF | | THE LPSI SYSTEM TO DELIVER THE FLOW AS ASSUMED IN THE EMERGENCY CORE | | COOLING SYSTEM ANALYSIS. AS MUCH AS 10% REDUCTION MAY BE POSSIBLE. NO | | DEGRADATION OF THE PUMPS OR SYSTEM COMPONENTS IS SUSPECTED. A REANALYSIS | | OF THE APPENDIX K LOSS OF COOLANT ACCIDENT SCENARIO WITH THE 10% REDUCTION | | AT THIS CURRENT TIME IN CORE LIFE HAS RESULTED IN AN OPERABLE CONCLUSION. | | LOOKING BACK TO THE BEGINNING OF CORE LIFE, HOWEVER, THE PEAK CLADDING | | TEMPERATURE LIMIT OF 2,200øF MAY BE EXCEEDED FOR THE POSTULATED LOSS OF | | COOLANT ACCIDENT. NEXT REFUELING OUTAGE (SEPT 1996), THE LICENSEE WILL | | CHECK THE LPSI FLOW RATE AND MAKE ADJUSTMENTS IF THEY ARE NEEDED. | | | | JOHN ROGGE OF NRC REGION 1 HAS ALREADY BEEN BRIEFED ABOUT THIS EVENT BY THE | | LICENSEE. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29730 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 12/16/95 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 06:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/16/95 | +------------------------------------------------+EVENT TIME: 04:30[EST]| |NRC NOTIFIED BY: JOEL HOWELL |LAST UPDATE DATE: 12/16/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL INITIATION OF AUXILIARY FEEDWATER DUE TO A LOSS OF AUXILIARY STEAM | | TO THE MAIN FEEDWATER PUMP TURBINES | | | | WHILE BOTH UNITS WERE SHUT DOWN, A STEP IN A UNIT 1 SHUTDOWN PROCEDURE | | TEMPORARILY ISOLATED THE AUXILIARY STEAM HEADER WHICH SUPPLIES STEAM TO THE | | UNIT 2 MAIN FEEDWATER PUMP TURBINES. AS A RESULT, THE DISCHARGE PRESSURE | | OF THE UNIT 2 MAIN FEEDWATER PUMPS STARTED TO DECREASE, AND THE AMOUNT OF | | FLOW TO THE STEAM GENERATORS WAS REDUCED. IN ORDER TO ENSURE AN ADEQUATE | | SUPPLY OF WATER TO THE STEAM GENERATORS, THE LICENSEE MANUALLY INITIATED | | AUXILIARY FEEDWATER. AUXILIARY STEAM WAS SUBSEQUENTLY REALIGNED. UNIT 1 | | WAS NOT AFFECTED. | | | | PRESSURIZER HEATERS AND SPRAYS, NORMAL CHARGING AND LETDOWN, AND THE | | REACTOR COOLANT PUMPS ARE CURRENTLY BEING USED FOR PRIMARY PRESSURE, | | INVENTORY, AND TRANSPORT CONTROL. IN ADDITION, SECONDARY STEAM IS BEING | | DUMPED TO THE CONDENSER, AND THE UNIT 2 MAIN FEEDWATER PUMPS ARE SUPPLYING | | WATER TO THE STEAM GENERATORS. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29731 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 12/16/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 09:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/16/95 | +------------------------------------------------+EVENT TIME: 07:00[CST]| |NRC NOTIFIED BY: GARY DUBECK |LAST UPDATE DATE: 12/16/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK 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 50 POWER OPERATION | 50 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF AN INTOXICATED INDIVIDUAL HITTING THE OWNER | | CONTROLLED FENCE WITH AN AUTOMOBILE | | | | AT 0700 CST, AN INDIVIDUAL IN A VEHICLE WAS NOTICED TO BE ACTING STRANGELY | | IN THE PLANT PARKING LOT AND WAS OBSERVED TO BE DRIVING THE VEHICLE AROUND | | AIMLESSLY. WHEN THE INDIVIDUAL ATTEMPTED TO LEAVE THE PROPERTY, HE DROVE | | THE VEHICLE INTO THE OWNER CONTROLLED FENCE, AND THE VEHICLE BECAME STUCK | | IN THE FENCE. SITE SECURITY PERSONNEL SURROUNDED THE VEHICLE AND CONTACTED | | THE WILL COUNTY SHERIFF. DUE TO THE FACT THAT THE SHERIFF COULD NOT | | RESPOND FOR 30 MINUTES, THE CITY OF BRAIDWOOD POLICE DEPARTMENT WAS ALSO | | CONTACTED. AT 0735 CST, THE BRAIDWOOD POLICE ARRIVED ON SITE AND ARRESTED | | THE DRIVER OF THE VEHICLE. (REFER TO THE HOO LOG FOR THE DRIVER'S NAME AND | | FOR A SITE CONTACT TELEPHONE NUMBER.) THE DRIVER APPEARED TO BE UNDER THE | | INFLUENCE OF ALCOHOL. THERE WAS DAMAGE TO THE OWNER CONTROLLED FENCE AND | | TO THE VEHICLE. (THE INDIVIDUAL WAS NOT A LICENSEE EMPLOYEE.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29732 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/17/95 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 06:55 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/17/95 | +------------------------------------------------+EVENT TIME: 05:15[CST]| |NRC NOTIFIED BY: DAVID THRONE |LAST UPDATE DATE: 12/17/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK/R3 RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JACK STROSNIDER/NRR EO | | |E. CAUPP FEMA | | |C. HAUGHNEY/NMSS EO | | |HENRY BAILEY ERB | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N Y 98 POWER OPERATION | 98 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DECLARATION OF AN UNUSUAL EVENT DUE TO THE DETECTION OF POTENTIALLY | | FLAMMABLE GASES ACCUMULATING IN THE AREAS OF THE RAD WASTE BUILDING | | | | AT 0515 CST, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO THE PRESENCE OF | | POTENTIALLY FLAMMABLE GASES ACCUMULATING IN THE AREAS OF THE RAD WASTE | | BUILDING. IT IS BELIEVED THAT THE GASES ARE EMANATING FROM AN UNDERGROUND | | HYDROGEN SUPPLY LINE THAT FEEDS THE UNIT 2 MAIN GENERATOR FROM THE HYDROGEN | | TANK FARM. THE POTENTIAL SOURCE HAS BEEN ISOLATED AND WILL BE REMOVED FROM | | SERVICE. PRELIMINARY INDICATIONS SHOW THAT THE GASES ARE DISPERSING, BUT | | THE GASES ARE STILL BEING DETECTED IN VARIOUS AREAS (PRIMARILY AT HIGHER | | ELEVATIONS). ADDITIONAL MONITORING EQUIPMENT IS BEING BROUGHT TO THE SITE | | TO FURTHER EVALUATE THE IDENTIFICATION OF THE GASES, AND IT IS EXPECTED TO | | ARRIVE ON SITE BY 0700 CST. THE AFFECTED BUILDING'S ACCESS ROLL-UP DOORS | | HAVE BEEN OPENED TO AID IN THE DISPERSION OF THE GASES, AND PERSONNEL | | ACCESS HAS BEEN RESTRICTED. THERE HAVE BEEN NO PERSONNEL INJURIES AS A | | RESULT OF THIS EVENT. THE APPLICABLE RADIATION MONITORS DID NOT ALARM AND | | WERE UNAFFECTED BY THE GASES, AND NO TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION WERE ENTERED. | | | | THE EMERGENCY ACTION LEVEL FOR DECLARATION OF THE UNUSUAL EVENT WAS H.U.6 | | (TOXIC OR FLAMMABLE GAS RELEASE AFFECTING PLANT OPERATIONS), AND THE | | INITIATING CONDITION WAS THE DETECTION OF TOXIC (COULD PRODUCE WORKER | | INCAPACITATION) OR FLAMMABLE GASES THAT MAY BE DETRIMENTAL TO SAFE | | OPERATION OF THE PLANT. THE LICENSEE PLANS TO TERMINATE THE UNUSUAL EVENT | | WHEN THE ATMOSPHERE IS NO LONGER ALARMING THE DETECTION INSTRUMENTS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE OF THIS | | EVENT. | | | | ***UPDATE 12/17/95, @ 1251 EST BY BOB SCOTT TAKEN BY MACKINNON*** | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1115 CST WHEN ALL HYDROGEN | | CONCENTRATION READINGS IN THE RAD WASTE BUILDING INDICATED HYDROGEN LEVELS | | TO BE AT 0% LOWER EXPLOSIVE LIMIT. THE LICENSEE FOUND THAT THE HYDROGEN | | SUPPLY TO THE UNIT 2 MAIN GENERATOR HAD A LEAK. THE LEAK WAS ISOLATED, AND | | THE RAD WASTE BUILDING WAS VENTILATED TO REMOVE HYDROGEN FROM THE BUILDING. | | | | THE HIGHEST HYDROGEN LEVEL IN THE RAD WASTE BUILDING WAS APPROXIMATELY | | 1.4%. THE LICENSEE ORIGINALLY THOUGHT THERE WERE HIGHER HYDROGEN | | CONCENTRATION LEVELS IN THE RAD WASTE BUILDING BECAUSE THE INDICATION OF | | THE DETECTION INSTRUMENT (HAND HELD EXPLOSIVE METER) WAS PEGGED HIGH | | OFFSCALE. THE HAND HELD EXPLOSIVE METER WAS CALIBRATED FOR READING | | HYDROGEN SULFIDE. A CORRECTION TO THE HAND HELD EXPLOSIVE METER HAD TO BE | | MADE PER A GRAPH TO GET THE REAL HYDROGEN CONCENTRATION LEVELS IN THE RAD | | WASTE BUILDING. AFTER MAKING THE CORRECTION, THE HYDROGEN CONCENTRATION | | LEVELS WERE FOUND TO BE APPROXIMATELY 1.4%. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR AND THE STATE THAT THE UNUSUAL | | EVENT HAD BEEN TERMINATED. THE R3DO (TOM KOZAK), NRR EO (JACK STROSNIDER), | | FEMA (WITSBERGER), AND ERB (HENRY BAILEY) WERE NOTIFIED BY THE NRC | | OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29733 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 05:00 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 04:40[EST]| |NRC NOTIFIED BY: GUY ERIKSEN |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR SCRAM APPARENTLY IN RESPONSE TO HIGH STATOR | | COOLING TEMPERATURES FOLLOWING MAINTENANCE OF A TURBINE BUILDING CLOSED | | COOLING WATER PUMP | | | | APPROXIMATELY 10 MINUTES AFTER RESTORING OF A TURBINE BUILDING CLOSED | | COOLING WATER PUMP TO SERVICE FOLLOWING MECHANICAL MAINTENANCE, OPERATORS | | NOTED THAT THE STATOR COOLING TEMPERATURES WERE INCREASING. HIGH | | TEMPERATURE ALARMS WERE RECEIVED AT THE SAME TIME. APPARENTLY, A TURBINE | | RUNBACK OCCURRED IN RESPONSE TO THE STATOR COOLING HIGH TEMPERATURES (89øC | | SETPOINT). THE TURBINE RUNBACK APPARENTLY RESULTED IN A TURBINE TRIP AND | | SUBSEQUENT AUTOMATIC REACTOR SCRAM FROM 100% POWER. THE BYPASS VALVES WERE | | OPENING TO ACCOMMODATE THE DECREASED TURBINE LOAD, AND THE OPERATORS WERE | | ATTEMPTING TO REDUCE RECIRCULATION FLOW TO DECREASE POWER AT THE TIME OF | | THE TURBINE TRIP/REACTOR SCRAM. THE LICENSEE WAS STILL RESPONDING TO THE | | EVENT AND DID NOT KNOW THE EXACT CAUSES AT THE TIME OF THE NOTIFICATION. | | (APPARENTLY, WHEN THE 89øC STATOR COOLING TEMPERATURE SETPOINT IS REACHED, | | AN AUTOMATIC TURBINE TRIP OCCURS IF THE TURBINE GENERATOR SENSES ARMATURE | | CURRENT GREATER THAN APPROXIMATELY 25% OF ITS FULL CAPACITY, WHICH IS 4,800 | | AMPS, WITHIN 3 MINUTES.) ALL RODS FULLY INSERTED, AND ALL SYSTEMS | | FUNCTIONED AS REQUIRED. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. NORMAL CONDENSATE AND FEEDWATER IS | | BEING UTILIZED FOR REACTOR VESSEL LEVEL CONTROL, AND TURBINE CONTROL SYSTEM | | WITH THE MAIN CONDENSER AS A HEAT SINK FOR REACTOR PRESSURE CONTROL. SAFETY | | RELIEF VALVES DID NOT LIFT. ALL EMERGENCY CORE COOLING EQUIPMENT IS | | CURRENTLY OPERABLE AND AVAILABLE, AND THERE WERE NO EMERGENCY CORE COOLING | | SYSTEMS INJECTIONS. THERE WERE NO ENGINEERED SAFETY FEATURE ACTUATIONS, | | AND THE COOLDOWN RATE DID NOT EXCEED 100øF PER HOUR. | | | | OPERATORS ARE CURRENTLY ESTABLISHING A COOLDOWN RATE OF 90øF PER HOUR USING | | THE TURBINE CONTROLS, AND PLANS ARE TO PROCEED TO COLD SHUT DOWN (POSSIBLY | | TO VENT THE RECIRCULATION PUMPS). THE LICENSEE IS CURRENTLY INVESTIGATING | | THE CAUSE OF THE HIGH STATOR COOLING TEMPERATURES AND SUBSEQUENT PLANT | | TRANSIENTS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+