U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/22/96 - 01/23/96 ** EVENT NUMBERS ** 29768 29836 29874 29875 29876 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29768 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/26/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/26/95 | +------------------------------------------------+EVENT TIME: 18:40[CST]| |NRC NOTIFIED BY: JAMES DEDIC |LAST UPDATE DATE: 01/22/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SERVICE WATER (SW) RESIDUAL HEAT REMOVAL HEAT EXCHANGER (RHR HX) "B" OUTLET | | COOLING WATER THROTTLE VALVE (SW-MO-89B) SLIDE WIRE AND GEAR ASSEMBLY, | | WHICH PROVIDES VALVE POSITION FEEDBACK TO THE CONTROLLER, WAS LISTED AS | | NON-ESSENTIAL INSTEAD OF BEING AN ESSENTIAL COMPONENT. | | | | DURING TROUBLE SHOOTING ACTIVITIES ON "SW-MO-89B" (RHR HX OUTLET COOLING | | WATER THROTTLE VALVE), IT WAS DISCOVERED THAT THE SLIDE WIRE AND GEAR | | ASSEMBLY THAT PROVIDES VALVE POSITION FEEDBACK TO THE CONTROLLER WAS | | CONSIDERED NON-ESSENTIAL. TROUBLE SHOOTING ACTIVITIES WERE BEING PERFORMED | | BECAUSE THE "SW-MO-89B" VALVE WAS NOT CONTROLLING PROPERLY DURING A | | RESIDUAL HEAT REMOVAL SERVICE WATER PUMP SURVEILLANCE TEST. THE CONTROLLER | | AND THE REST OF THE FEEDBACK LOOP ARE ESSENTIAL COMPONENTS. WITH A | | NON-ESSENTIAL COMPONENT INSTALLED IN AN ESSENTIAL APPLICATION, SHOULD A | | FAILURE OCCUR, THE POTENTIAL EXISTS TO LOSE COOLING DESPITE THE REQUIREMENT | | TO ASSURE RESIDUAL HEAT REMOVAL OPERABILITY. ALTHOUGH LOW PRESSURE COOLANT | | INJECTION MODE WOULD STILL BE AVAILABLE THERE WOULD BE NO COOLING FOR | | CONTAINMENT OR THE TORUS. THIS COULD INHIBIT THE OPERABILITY OF THE | | RESIDUAL HEAT REMOVAL SYSTEMS, CAUSED BY A HIGH ENERGY PIPE BREAK IN THE | | REACTOR BUILDING, WHICH COULD DISABLE THESE NON-ESSENTIAL COMPONENTS. THE | | LICENSEE THINKS THAT RHR LOOP "A" SW-MO-89A VALVE HAS THE SAME PROBLEM. | | BOTH LOOPS OF RHR WERE DECLARED INOPERABLE BY THE LICENSEE, BUT THEY ARE | | AVAILABLE IF NEEDED. THE PLANT IS EXITING FROM A 72-DAY REFUELING OUTAGE | | AND THE REACTOR VESSEL WATER TEMPERATURE IS 157 DEGREES F (AS MEASURED ON | | THE RHR LOOP). THE LICENSEE DOES NOT HAVE TO RUN RHR TO MAINTAIN THE | | REACTOR VESSEL WATER TEMPERATURE AT THAT TEMPERATURE. LICENSEE IS STILL | | INVESTIGATING THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * 1623 JANUARY 22, 1996, UPDATE FROM BORGAN TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. | | | | AS A RESULT OF FURTHER EVALUATION, THE LICENSEE DETERMINED THAT THE SLIDE | | WIRE AND GEAR ASSEMBLY ARE QUALIFIED BASED ON AN ANALYSIS PERFORMED AT | | HATCH NUCLEAR STATION USING IEB 79-10B PRESCRIBED METHODOLOGY FOR | | ENVIRONMENTAL QUALIFICATION. THEREFORE, THE LICENSEE BELIEVES THAT THIS | | CONDITION DID NOT AFFECT THE OPERABILITY OF VALVES SW-MO-89A AND SW-MO-89B | | AND THAT THIS OCCURRENCE IS NOT REPORTABLE. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | NOTIFIED THE R4DO (CAIN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29836 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/14/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 19:33 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/14/96 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: JIM CROSSMAN |LAST UPDATE DATE: 01/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL FOR THE UNIT 1 SAFEGUARDS FANS TO TAKE A SUCTION FROM THE UNIT 2 | | SAFEGUARDS BUILDING DURING A UNIT 2 CONTAINMENT DEPRESSURIZATION ACTUATION | | AND THEN DISCHARGE TO ATMOSPHERE WITHOUT CHARCOAL FILTER FILTRATION | | | | AT APPROXIMATELY 1700, THE LICENSEE DETERMINED THAT THE UNIT 1 SAFEGUARDS | | VENTILATION DAMPERS DID NOT GO TO THE CLOSED POSITION AFTER REMOVING THE | | SYSTEM FROM THE CHARCOAL FILTERS. BECAUSE UNITS 1 AND 2 ARE TIED TOGETHER | | THROUGH COMMON DUCT WORK AND BECAUSE THEY BOTH INTERFACE AT THE IODINE | | CHARCOAL FILTERS, THE FAILURE OF THE UNIT 1 SAFEGUARDS VENTILATION DAMPERS | | TO CLOSE PROVIDED A POTENTIAL FOR THE UNIT 1 SAFEGUARDS FANS TO TAKE A | | SUCTION FROM THE UNIT 2 SAFEGUARDS BUILDING (DURING A UNIT 2 CONTAINMENT | | DEPRESSURIZATION ACTUATION) AND THEN DISCHARGE TO ATMOSPHERE WITHOUT | | CHARCOAL FILTER FILTRATION. (THE SAFEGUARDS BUILDING HOUSES THE LOW HEAD | | SAFETY INJECTION PUMPS AND THE CONTAINMENT RECIRCULATION SPRAY PUMPS.) THE | | LICENSEE SUSPECTS THAT A CONTROL AIR LEAK ON A SAFEGUARDS DAMPER WAS NOT | | ALLOWING ENOUGH AIR TO THE OTHER SAFEGUARDS DAMPERS ON UNIT 1 TO PERMIT | | PROPER OPERATION. | | | | THIS SYSTEM IS INTENDED TO AUTOMATICALLY ALIGN TO CHARCOAL FILTERS TO LIMIT | | THE RADIATION RELEASE TO THE ENVIRONMENT DURING A CONTAINMENT | | DEPRESSURIZATION ACTUATION WHEN CONTAINMENT SUMP WATER IS BEING PUMPED BY | | THE PUMPS IN THAT ROOM. ACCORDINGLY, TECHNICAL SPECIFICATION 3.7.8.1 | | REQUIRES THE LICENSEE TO HAVE AN OPERABLE CHARCOAL FILTERING SYSTEM | | AVAILABLE FOR EACH TRAIN. PER TECHNICAL SPECIFICATION 3.7.8.1, NO CHARCOAL | | FILTERS WOULD HAVE BEEN OPERABLE ON UNIT 2. THEREFORE, UNIT 2 WAS IN | | TECHNICAL SPECIFICATION 3.0.3 FOR 10 MINUTES UNTIL THE UNIT 1 SYSTEM WAS | | ALIGNED THROUGH THE CHARCOAL FILTERS. THE LICENSEE WILL NOTIFY THE NRC | | RESIDENT INSPECTOR. | | | | * * * 1512 JANUARY 22, 1996, UPDATE FROM WHALEN TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. THE LICENSEE PERFORMED | | A SUBSEQUENT ANALYSIS ON THE FLOW PATH IN THE REPORTED DAMPER CONFIGURATION | | TO DETERMINE IF UNIT 2 FLOW WOULD BYPASS THE CHARCOAL FILTERS CREATING AN | | UNFILTERED RELEASE. OF THE THREE POSSIBLE FLOW PATHS, THE UNIT 2 FILTER | | DAMPER PATH HAD THE LEAST RESISTANCE. THEREFORE, THE LICENSEE POSTULATED | | THAT IN THE CASE OF A CROSS CONNECTION BETWEEN THE TWO UNITS, FLOW WOULD BE | | TOWARD THE UNIT 2 FILTER DAMPERS AND WOULD RESULT IN A FILTERED RELEASE. | | THE LICENSEE ALSO DETERMINED THAT THE UNIT 2 SAFEGUARDS FLOW RATE (IN THE | | REPORTED DAMPER CONFIGURATION) WAS WITHIN THE TECHNICAL SPECIFICATION LIMIT | | OF 6,300 CUBIC FEET PER MINUTE PLUS OR MINUS 10 PERCENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (DECKER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29874 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 01/22/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 10:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/22/96 | +------------------------------------------------+EVENT TIME: 08:08[CST]| |NRC NOTIFIED BY: COTTON |LAST UPDATE DATE: 01/22/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAIN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER FLOW | | | | DURING TROUBLESHOOTING OF SAFETY-RELATED INVERTER 'IV1EC1', FEEDWATER FLOW | | TO ALL STEAM GENERATORS WAS LOST. OPERATORS MANUALLY TRIPPED THE UNIT IN | | RESPONSE TO THE LOSS OF FEEDWATER FLOW. ALL CONTROL RODS INSERTED FOLLOWING | | THE TRIP, AND THE AUXILIARY FEEDWATER AUTOMATICALLY STARTED AND INJECTED TO | | RECOVER STEAM GENERATOR WATER LEVELS. THE LICENSEE REPORTED THAT POWER | | RANGE NUCLEAR INSTRUMENTATION CHANNEL N42 FAILED TO GENERATE A NEGATIVE | | RATE TRIP SIGNAL FOLLOWING THE MANUAL REACTOR TRIP. THE UNIT IS CURRENTLY | | STABLE IN MODE 3, WITH THE STEAM DUMPS BEING USED TO EXHAUST DECAY HEAT TO | | THE MAIN CONDENSER. | | | | ON 1/21/96, A FUSE IN THE INVERTER WAS BLOWN DUE TO UNKNOWN REASONS. AT THE | | TIME OF THE EVENT, TECHNICIANS WERE INVESTIGATING THE CAUSE OF THE BLOWN | | FUSE, AND HAD JUST REINSTALLED A REPLACEMENT FUSE. THE LICENSEE IS STILL | | REVIEWING POST-TRIP INFORMATION, BUT BELIEVES THAT A FEEDWATER ISOLATION | | SIGNAL WAS GENERATED WHEN THE FUSE WAS REINSTALLED (SEVERAL RELAYS IN THE | | FEEDWATER ISOLATION LOGIC ARE POWERED BY THIS INVERTER). THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: STINE-HASKELL RESEARCH CENTER |NOTIFICATION DATE: 01/22/96 | | CITY: NEWARK REGION: 1 |NOTIFICATION TIME: 13:32 [ET]| | COUNTY: NEW CASTLE STATE: DE |EVENT DATE: 12/22/95 | |LICENSE#: 07-13441-02 AGREEMENT: N |EVENT TIME: 17:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/22/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICHARD KEIMIG RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: NORMAN W. HENRY III | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE LOSS OR THEFT OF A GAS CHROMATOGRAPH (ELECTRON CAPTURE DETECTOR) | | CONTAINING A 15-MILLICURIE, NICKEL-63, PLATED, SEALED SOURCE | | | | ON DECEMBER 22, 1995, AFTER EXTENSIVE ON-SITE SEARCHING FOLLOWING A | | SEMI-ANNUAL AUDIT, THE LICENSEE DETERMINED THAT A GAS CHROMATOGRAPH | | CONTAINING A 15-MILLICURIE, NICKEL-63, PLATED, SEAL SOURCE WAS MISSING. THE | | SOURCE WAS CONFIGURED AS AN ELEMENTAL FOIL. THE GAS CHROMATOGRAPH HAD BEEN | | STORED IN A SECURE STORAGE AREA FOR APPROXIMATELY 3 YEARS, AND APPARENTLY, | | THE ROOM HAD BEEN CLEANED OUT SOME TIME BETWEEN THE JUNE 1995 AND DECEMBER | | 1995 SEMI-ANNUAL AUDITS. THE GAS CHROMATOGRAPH MAY HAVE BEEN MOVED TO | | ANOTHER STORAGE AREA, MISPLACED, OR POSSIBLY DISPOSED OF. THE LICENSEE IS | | CONTINUING ITS SEARCH AND BELIEVES THAT THERE IS MINIMAL RISK TO | | INDIVIDUALS IN UNRESTRICTED AREAS BECAUSE THE SOURCE WAS SMALL AND BECAUSE | | IT WAS LOCATED INSIDE THE GAS CHROMATOGRAPH. | | | | THE LICENSEE PLANS TO SEND A WRITTEN REPORT TO THE REGIONAL OFFICE WITHIN | | 30 DAYS. (REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29876 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/22/96 | |UNIT: [1] [2] [3] STATE: IL |NOTIFICATION TIME: 14:29 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/22/96 | +------------------------------------------------+EVENT TIME: 08:25[CST]| |NRC NOTIFIED BY: ROBERT BROWN |LAST UPDATE DATE: 01/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSITIVE RANDOM TEST FOR A CONTROLLED SUBSTANCE (OTHER THAN ALCOHOL) | | | | A LICENSED SUPERVISOR TESTED POSITIVE FOR A CONTROLLED SUBSTANCE (OTHER | | THAN ALCOHOL) DURING A RANDOM TEST ON JANUARY 19, 1996. THE INDIVIDUAL'S | | ACCESS WAS IMMEDIATELY DENIED, AND THE LICENSEE IS CURRENTLY PERFORMING A | | WORK PERFORMANCE INVESTIGATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE NRC REGION 3 | | OFFICE (JIM BELANGER). (REFER TO THE HOO LOG FOR A CONTACT TELEPHONE | | NUMBER AND FOR ADDITIONAL INFORMATION.) | +------------------------------------------------------------------------------+