U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/28/96 - 03/29/96 ** EVENT NUMBERS ** 30030 30187 30188 30189 30190 30191 30192 30193 30194 30195 30196 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30030 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 02/26/96 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 18:19 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 02/26/96 | +------------------------------------------------+EVENT TIME: 14:16[EST]| |NRC NOTIFIED BY: MIKE BAILEY |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |NINF INFORMATION ONLY | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - KEOWEE STATION VOLTAGE REGULATORS LOWER LIMIT SETTINGS BEING DETERMINED - | | | | CLASS 1E EMERGENCY ELECTRICAL POWER IS SUPPLIED TO THE THREE OCONEE UNITS | | BY TWO KEOWEE HYDROELECTRIC STATIONS VIA TWO POWER PATHS: ONE ABOVE GROUND | | TRANSMISSION LINE AND ONE UNDERGROUND CABLE. | | | | THE LICENSEE COULD NOT LOCATE DOCUMENTATION ON THE CORRECT LOWER LIMIT | | SETTINGS FOR THE VOLTAGE REGULATORS ON THE KEOWEE STATIONS. THUS, | | THE LICENSEE PLANS TO PERFORM A TEST TO DETERMINE THE CORRECT SETTINGS. | | ONCE THE CORRECT SETTINGS HAVE BEEN DETERMINED, THE LICENSEE WILL EVALUATE | | THE VOLTAGE CONDITIONS ON THE EMERGENCY POWER LOADS. THE LICENSEE DECLARED | | THE UNDERGROUND CABLE INOPERABLE IN ORDER TO PERFORM THE TEST. AT 1416, | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION LCO A/S 3.7.2 WHICH REQUIRES | | THE LICENSEE TO RESTORE THE 1 INOPERABLE KEOWEE POWER PATH TO OPERABLE | | STATUS WITHIN 72 HOURS OR TO SHUT ALL 3 UNITS DOWN WITHIN THE FOLLOWING 12 | | HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. (REFER TO EVENT #30031 | | FOR A RELATED EVENT.) | | | | * * * UPDATE AT 2149 EST ON 3/28/96 FROM MIKE HILL TAKEN BY KARSCH * * * | | THE LICENSEE DETERMINED THAT THE LOWEST VOLTAGE REACHED WOULD BE 11.7-KV. | | AT THAT VOLTAGE, ALL EMERGENCY SYSTEMS WOULD RECEIVE SUFFICIENT VOLTAGE TO | | PERFORM THEIR INTENDED SAFETY FUNCTIONS. THEREFORE, THIS EVENT DID NOT | | NEED TO BE REPORTED AND IS BEING RETRACTED. THE LOWER LIMITS HAVE BEEN | | RESET TO 13.5-KV. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE | | R2DO (BELISLE) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 03/28/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 07:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 05:30[CST]| |NRC NOTIFIED BY: BROUGHTON |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THE BLACKOUT SEQUENCER STARTED ON A BLACKOUT | | SIGNAL. | | | | THIS OCCURRED WHILE THE LICENSEE WAS RESTORING THE POTENTIAL TRANSFORMER | | FUSES FOR STARTUP TRANSFORMER "XST1" ON ELECTRICAL BUS "2EA1" (TRAIN "A" | | BUS). THE LICENSEE INADVERTENTLY DISCONNECTED POTENTIAL TRANSFORMER FUSES | | FOR "XST2", AND A BLACKOUT SIGNAL WAS GENERATED. THIS RESULTED IN | | ACTUATION OF THE TRAIN "A" BLACKOUT SEQUENCER. ALL COMPONENTS FUNCTIONED | | AS DESIGNED, AND THE LICENSEE HAS RESTORED THE EQUIPMENT TO NORMAL. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30188 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/28/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:02 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 03:20[EST]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |NLTR LICENSEE 24 HR REPORT | | |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 +------------------------------------------------------------------------------+ | THE LICENSEE IS REPORTING A 24-HOUR REPORT PER TS 3.13.A.3 REGARDING | | PORTIONS OF ITS FIRE PROTECTION SYSTEM BEING INOPERABLE. | | | | THE LICENSEE APPLIED TAGOUT 96-51-85 TO THE HIGH PRESSURE FIRE PROTECTION | | SYSTEM TO ACCOMPLISH WORK ON FIRE PROTECTION VALVES "FP72" AND "FP46". THIS | | CONDITION RENDERED PORTIONS OF THE FIRE PROTECTION SYSTEM VALVES AND PIPING | | REQUIRED FOR PROTECTION OF SAFE SHUTDOWN SYSTEMS INOPERABLE. THE LCO ACTION | | STATEMENT PER TS 3.13.A.3.B WAS ENTERED AND REQUIRED THAT COMPENSATORY | | MEASURES BE PUT IN PLACE. THE COMPENSATORY ACTIONS TAKEN INCLUDED | | ADDITIONAL FIRE HOSES RUN TO THE AFFECTED AREAS AND ESTABLISHMENT OF FIRE | | WATCH TOURS EVERY 4 HRS. THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30189 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/28/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 12:04 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 11:55[EST]| |NRC NOTIFIED BY: WALT NEUMAN |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE UNIT WAS OPERATED FOR ONE FUEL CYCLE WITH THE EMERGENCY FEED INITIATION | | AND CONTROL (EFIC) SYSTEM SEISMICALLY VULNERABLE. | | | | INSTRUMENT TUBING FOR THE EFIC HIGH RANGE LEVEL CHANNELS "C" AND "D" WAS | | DISCOVERED TO BE REMOVED FROM ITS SEISMIC SUPPORTS. THIS TUBING IS THE | | HIGH SIDE OF THE LEVEL TAP AND PROVIDES THIS FUNCTION FOR THE OPERATING | | RANGE AND STARTUP RANGE FOR THE "B" ONCE THROUGH STEAM GENERATOR (OTSG). | | THE TUBING WAS REMOVED FROM THE SUPPORTS TO ALLOW INSTALLATION OF THE OTSG | | WORK PLATFORMS. THE WORK PLATFORM DESIGN DID NOT ALLOW THE TUBING SEISMIC | | SUPPORTS TO BE RE-ATTACHED. THE SUPPORTS ARE BEING REDESIGNED AT PRESENT | | AND WILL BE RE-ATTACHED BEFORE PLANT RESTART. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30190 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF MINNESOTA |NOTIFICATION DATE: 03/28/96 | | CITY: MINNEAPOLIS REGION: 3 |NOTIFICATION TIME: 12:21 [ET]| | COUNTY: HENNEFIN STATE: MN |EVENT DATE: 03/27/96 | |LICENSE#: 22-00187-46 AGREEMENT: N |EVENT TIME: 22:00[CST]| | DOCKET: |LAST UPDATE DATE: 03/28/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEWIS MILLER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JERRY STAIGER | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIVERSITY OF MINNESOTA, MINNEAPOLIS, MN - BRACHYTHERAPY UNDER DOSE | | | | DURING THE FIRST OF A TWO PART TREATMENT, A PATIENT WAS SUPPOSED TO RECEIVE | | A RADIATION DOSE FROM 5 Cs-137 SOURCES DIVIDED AMONG 2 OVOIDS AND 3 TANDEM | | APPLICATORS. THE TWO OVOID SOURCES WERE PLACED, BUT THE THREE TANDEM | | APPLICATOR SOURCES WERE NOT PLACED BECAUSE THE PHYSICIAN WAS INTERRUPTED | | DURING THE PROCEDURE AND FORGOT TO PLACE THEM. LATER, WHEN THE OVOIDS WERE | | REMOVED IT WAS DISCOVERED THAT THE THREE TANDEM SOURCES HAD NOT BEEN PUT IN | | PLACE. THEY WERE THEN PUT INTO THE APPLICATORS TO ADMINISTER THEIR PORTION | | OF THE TREATMENT. ANY REMAINING UNDERDOSE WILL BE COMPENSATED WITH THE | | SECOND TREATMENT. THE LICENSEE WILL DISCUSS THIS EVENT WITH REGION 3 TO | | ASCERTAIN IF THIS CONSTITUTES A MEDICAL MISADMINISTRATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 30191 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 03/28/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 13:27 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 03/27/96 | | LEU FABRICATION |EVENT TIME: 22:30[EST]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 03/28/96 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |GEORGE AL BELISLE RDO | | DOCKET: 07001113 | | +------------------------------------------------+ | |NRC NOTIFIED BY: SCOTT MURRAY | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | G.E. WILMINGTON, NC - SMALL FIRE INSIDE INCINERATOR FACILITY | | | | DURING THE BOX LOAD OPERATION, THE INCINERATOR LOAD CHAMBER DOOR | | MALFUNCTIONED, AND A WASTE BOX WAS PREVENTED FROM BEING FULLY INSERTED INTO | | THE BURN CHAMBER. THE FIRE BURNING THE BOX IN THE DOOR WAS EXTINGUISHED | | QUICKLY, BUT THE DISCHARGE OF THE FIRE EXTINGUISHER SET THE LID OF THE NEXT | | BOX ON THE CONVEYOR BELT ON FIRE. THIS BURNED SEVERAL HOLES INTO ITS LID. | | THE SECOND BOX CONTAINED APPROXIMATELY 500 GRAMS OF 3.7% ENRICHED U-235. | | THERE WAS NO RELEASE OF LICENSED MATERIAL, AND THERE WERE NO PERSONNEL | | EXPOSURES. THIS EVENT HAS BEEN DISCUSSED WITH REGION 2 (G. TROUP). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30192 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 03/28/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 13:56 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 13:42[EST]| |NRC NOTIFIED BY: DAVID ESHELMAN |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEWIS MILLER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 86 POWER OPERATION | 86 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 4.0.3 ENTRY DUE TO THE DISCOVERY THAT A VENDOR'S | | PROCEDURE FOR PERFORMING CARBON FILTER SAMPLING ANALYSES UTILIZED A MORE UP | | TO DATE ANSI STANDARD TEMPERATURE (30øC VERSUS 80øC) THAN THE REGULATORY | | GUIDE AND ANSI STANDARD REQUIRED BY THE TECHNICAL SPECIFICATIONS | | | | THE LICENSEE IS REQUIRED TO SAMPLE THE UNIT'S CARBON FILTERS EVERY 18 | | MONTHS, AND ONE OF THE TESTS PERFORMED INVOLVES SHIPMENT OF A SAMPLE TO A | | VENDOR FOR THE PERFORMANCE OF VARIOUS ANALYSES. REVIEWS OF THE LICENSEE'S | | CARBON FILTER SAMPLING PROGRAM FOR THE STATION EMERGENCY VENTILATION, | | CONTROL ROOM EMERGENCY VENTILATION, AND HYDROGEN PURGE SYSTEMS HAVE SHOWN | | THAT THE LABORATORY ANALYSIS OF THE SAMPLE IS BEING PERFORMED AT 30øC IN | | LIEU OF 80øC AS DICTATED IN THE ANSI STANDARD (#N509 DATED 1976) REFERENCED | | BY REGULATORY GUIDE 1.52 WHICH IS DESCRIBED IN THE TECHNICAL SPECIFICATION | | SURVEILLANCE REQUIREMENTS. (APPARENTLY, THE 30øC CRITERIA IS MORE | | CONSERVATIVE AND IS REFERENCED IN A NEW ANSI STANDARD.) THIS, THEREFORE, | | IS A FAILURE TO PERFORM THE LITERAL REQUIREMENTS OF THE SURVEILLANCE WITHIN | | THE ALLOWED TIME INTERVAL, AND THIS CONDITION HAS EXISTED SINCE | | APPROXIMATELY 1991. THIS REPRESENTS AN EVENT OR CONDITION THAT ALONE COULD | | HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF STRUCTURES OR | | SYSTEMS THAT ARE NEEDED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT OR | | CONTROL THE RELEASE OF RADIOACTIVE MATERIAL. | | | | BASED ON THE FACT THAT THIS AFFECTS BOTH TRAINS OF THE UNIT'S STATION | | EMERGENCY VENTILATION, CONTROL ROOM EMERGENCY VENTILATION, AND CONTAINMENT | | HYDROGEN PURGE SYSTEMS PER TECHNICAL SPECIFICATIONS 3.6.5.1, 3.7.6.1, AND | | 3.6.4.4, RESPECTIVELY; THE LICENSEE ENTERED THE ACTION STATEMENTS OF | | TECHNICAL SPECIFICATION 3.0.3 AT 1342. BECAUSE OF THE FACT THAT THE | | REQUIRED TECHNICAL SPECIFICATION 3.0.3 ACTION IS TO BE COMPLETED IN LESS | | THAN 24 HOURS, THE LICENSEE HAS INVOKED TECHNICAL SPECIFICATION 4.0.3 WHICH | | ALLOWS FOR THE DELAY OF THE TECHNICAL SPECIFICATION 3.0.3 ACTIONS FOR 24 | | HOURS IN ORDER TO FACILITATE THE PERFORMANCE OF THE APPROPRIATE | | SURVEILLANCE REQUIREMENTS. | | | | THIS WAS DISCOVERED AS A RESULT OF A SIMILAR ISSUE AT THE SUMMER FACILITY. | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30193 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/28/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 14:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 10:45[EST]| |NRC NOTIFIED BY: THAD REAMES |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOTH TRAINS OF COMPONENT COOLING WATER (CCW) WERE INOPERABLE FOR 37 | | MINUTES. | | | | TRAIN "1A" OF CCW (DESIGNATION KC) WAS INOPERABLE FOR REPAIR OF MOTOR | | OPERATED VALVE "1KC-1A". DURING THE PROCESS OF RESTORING "1KC-1A" TO | | OPERABLE STATUS, THE LICENSEE DISCOVERED THAT "1KC-2B" WOULD NOT OPERATE | | EITHER FROM THE CONTROL ROOM OR LOCALLY. WITH BOTH TRAINS OF CCW | | INOPERABLE TECH SPEC 3.0.3 WAS ENTERED FOR 37 MINUTES UNTIL "1KC-2B" WAS | | CLOSED MANUALLY RESTORING OPERABILITY OF THE "B" TRAIN OF CCW. THE CAUSE | | OF THE MALFUNCTION OF "1KC-2B" IS UNDER INVESTIGATION. THE CAUSE MIGHT BE | | A MALADJUSTMENT OF THE CAM MECHANISM FOR THE REMOTE/LOCAL OPERATION HANDLE. | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30194 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 03/28/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 15:15 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 11:17[EST]| |NRC NOTIFIED BY: JEFFREY TUCKER |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 +------------------------------------------------------------------------------+ | THE HPCI (HIGH PRESSURE COOLANT INJECTION) DECLARED INOPERABLE BECAUSE | | TURBINE EXHAUST CHECK VALVES EXCEEDED THE ALLOWED LEAKAGE RATE. | | | | HPCI SYSTEM WAS DECLARED INOPERABLE FOLLOWING THE UNSATISFACTORY | | PERFORMANCE OF THE HPCI TURBINE EXHAUST VACUUM BREAKER SURVEILLANCE TEST | | (ST-4-055-953-2). THE FAILURE OF THE TWO SETS OF PARALLEL CHECK VALVES (4 | | TOTAL) IN THE EXHAUST LINE COULD RESULT IN SUPPRESSION POOL/CONTAINMENT | | PRESSURIZATION DURING HPCI OPERATION. UNIT 2 IS IN A 14-DAY TECH SPEC LCO | | WHICH STARTED AT 0204 EST ON 03/27/96, DUE TO HPCI INOPERABILITY. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30195 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/28/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 12:05[CST]| |NRC NOTIFIED BY: MIKE MORROW |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF NORMAL OFFSITE POWER TO A 4-KV SHUTDOWN BOARD RESULTING IN | | MOMENTARY DE-ENERGIZATION OF A SHUTDOWN BOARD, LOSS OF A REACTOR PROTECTION | | SYSTEM (RPS) BUS, ACTUATION OF THE PRIMARY CONTAINMENT ISOLATION SYSTEM | | (PCIS), AND AUTOMATIC STARTING AND LOADING OF AN EMERGENCY DIESEL GENERATOR | | (EDG) DUE TO PERSONNEL ERROR DURING A SHUTDOWN BUS FUNCTIONAL CHECK | | | | DURING A FUNCTIONAL CHECK OF BREAKERS ASSOCIATED WITH 4-KV SHUTDOWN BUS #1, | | THE ALTERNATE FEEDER BREAKER TO 4-KV SHUTDOWN BOARD 'D' WAS RACKED OUT OF | | ITS COMPARTMENT, AND INSTALLATION OF A CELL SWITCH BLOCK HAD BEEN PERFORMED | | PER THE APPLICABLE PROCEDURE. AT 1205 CST, THE INDIVIDUAL PERFORMING THE | | PROCEDURE INADVERTENTLY ACTUATED SWITCH 52STA IN THE BREAKER COMPARTMENT. | | THIS ACTION GAVE AN ERRONEOUS INDICATION TO THE TRIP CIRCUIT OF THE NORMAL | | 4-KV SHUTDOWN BOARD 'D' FEEDER BREAKER THAT THE ALTERNATE FEEDER BREAKER | | HAD CLOSED. THIS IN TURN RESULTED IN A TRIP OF THE NORMAL FEEDER BREAKER | | AS DESIGNED. SHUTDOWN BOARD 'D' DE-ENERGIZED RESULTING IN A LOSS OF RPS | | BUS '2B', AN RPS HALF SCRAM, AND ACTUATION OF THE PCIS LOGIC CHANNELS | | POWERED FROM RPS BUS '2B'. THE AFFECTED PCIS LOGIC CHANNELS WERE | | VENTILATION RELATED (GROUP 6). OTHER GROUPS WERE ALREADY ISOLATED OR | | BYPASSED FOR OUTAGE WORK. IN ADDITION TO THESE OCCURRENCES, EDG 'D' | | AUTOMATICALLY STARTED ON UNDERVOLTAGE AND TIED TO THE BOARD AS EXPECTED. | | | | THE FUNCTIONAL CHECK WAS HALTED, THE CAUSE OF THE POWER LOSS WAS | | DETERMINED, AND ALL EXPECTED AUTOMATIC ACTIONS TOOK PLACE. NORMAL POWER | | WAS RETURNED TO THE BOARD WITHIN APPROXIMATELY 20 MINUTES, AND THE 'D' EDG | | WAS SECURED. RPS '2B' POWER WAS RESTORED, AND THE HALF SCRAM AND | | ISOLATIONS WERE RESET. SHUTDOWN COOLING WAS NOT LOST, AND NO TECHNICAL | | SPECIFICATION ACTIONS STATEMENTS WERE ENTERED BECAUSE THE UNIT WAS IN A | | REFUELING OUTAGE. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30196 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 03/28/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:43 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 03/28/96 | +------------------------------------------------+EVENT TIME: 14:08[EST]| |NRC NOTIFIED BY: TERRY WHITE |LAST UPDATE DATE: 03/28/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAINTENANCE ON PRESSURIZER PORVs RENDERED BOTH INOPERABLE SIMULTANEOUSLY. | | | | THE PORVs WERE INOPERABLE ON MARCH 8, 1996, FOR 1 HOUR AND 37 MINUTES. I&C | | TECHS CONNECTED AIR SETS TO THE VALVES DURING MAINTENANCE. THE VALVES | | WOULD NOT HAVE RESPONDED EITHER AUTOMATICALLY OR MANUALLY FROM THE CONTROL | | ROOM TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT (eg. A STEAM GENERATOR | | TUBE RUPTURE). THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+