U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/11/96 - 10/15/96 ** EVENT NUMBERS ** 31018 31137 31138 31139 31140 31141 31142 31143 31144 31145 31146 31147 31148 31149 31150 31151 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31018 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/17/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/17/96 | +------------------------------------------------+EVENT TIME: 20:35[CDT]| |NRC NOTIFIED BY: PEASE |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 7 DAY LCO ACTION STATEMENT WHEN THE CONTROL ROOM | | EMERGENCY FILTER SYSTEM(CREFS) WAS DECLARED INOPERABLE DUE TO ITS | | ASSOCIATED RADIATION MONITOR(RMV-RM-1) NOT BEING PROPERLY TESTED. | | | | THE OPERABILITY OF THE SINGLE TRAIN CREFS REQUIRES THE FUNCTIONALITY OF THE | | RMV-RM-1 RAD MONITOR, WHICH INITIATES THE SYSTEM'S ALIGNMENT WITH ITS | | SAFETY MODE OF OPERATION UPON EXCEEDING THE SETPOINT OF ANY OF ITS THREE | | PARAMETERS. TS 4.2.D.4 REQUIRES THE RAD MONITOR TO BE CALIBRATED ONCE EVERY | | 3 MONTHS, ENCOMPASSING THE ENTIRE INSTRUMENT, INCLUDING THE SENSOR AND | | ALARM/OR TRIP FUNCTIONS. IT WAS DISCOVERED THAT THE CALIBRATION PROCEDURE | | VERIFIES THE TRIP FUNCTION OCCURS, BUT DOES NOT VALIDATE THE REQUIRED | | SETPOINT, WHICH IS PERFORMED DURING A SEPARATE ANNUAL TEST. ACCORDINGLY, | | THE QUARTERLY CALIBRATIONS HAVE THEREFORE BEEN JUDGED TO BE DEGRADED | | SURVEILLANCES, RESULTING IN THE RAD MONITOR BEING DECLARED INOPERABLE. | | FURTHER INVESTIGATIONS ARE BEING MADE TO DETERMINE IF THE RAD MONITOR COULD | | STILL BE CONSIDERED FUNCTIONAL. THE CREFS HAS BEEN PLACED IN ITS BYPASS | | CONFIGURATION, WHICH RESTORED ITS ABILITY TO PERFORM ITS SAFETY FUNCTION OF | | MITIGATING THE CONSEQUENCES OF AN ACCIDENT. THE RI WAS INFORMED. | | | | * * * UPDATE AT 1402 ON 10/11/96 BY BILL GREEN ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE HAS DETERMINED THAT THE CONTROL ROOM VENTILATION RADIATION | | MONITOR SETPOINT WAS BEING "CHECKED" DURING A YEARLY NON-TECH SPEC | | ELECTRONIC CALIBRATION PROCEDURE WHICH HAS BEEN MOST RECENTLY PERFORMED | | DURING THE CURRENT QUARTERLY SURVEILLANCE INTERVAL. | | | | THE LICENSEE THEREFORE CONCLUDES THAT WHILE THERE IS A SURVEILLANCE | | IMPLEMENTATION ISSUE THAT REQUIRES RESOLUTION, THE CONTROL ROOM VENTILATION | | RADIATION MONITOR HAS BEEN ABLE TO ADEQUATELY SUPPORT THE CREFS ACCIDENT | | MITIGATION FUNCTION AND THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT | | NOTIFICATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R4DO LINDA HOWELL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31137 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/11/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 02:01 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 00:45[EDT]| |NRC NOTIFIED BY: DAVE PIETRUSKI |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION AND | | THE OCEAN COUNTY HEALTH DEPARTMENT THAT THEY SPILLED APPROXIMATELY ONE | | GALLON OF OIL ONTO THE GROUND. | | | | AN OIL LINE RUPTURE OCCURRED ON A TEMPORARY AIR COMPRESSOR LOCATED OUTSIDE | | THE MONITORING AND CHANGE BUILDING. APPROXIMATELY ONE GALLON OF COMPRESSOR | | OIL SPILLED ONTO THE GROUND. THE OIL SPILL IS CONTAINED AND IS BEING | | CLEANED UP. LICENSEE NOTIFIED THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL | | PROTECTION AND THE OCEAN COUNTY HEALTH DEPARTMENT THAT ONE GALLON OF | | COMPRESSOR OIL HAD BEEN SPILLED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31138 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 10/11/96 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 11:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 08:27[EDT]| |NRC NOTIFIED BY: DAVE PORTER |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BOB DENNIG EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |HENRY BAILEY AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 47 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL Rx TRIP FROM 47% POWER DUE TO UNCONTROLLED MAIN TURBINE RUNBACK - | | | | AT 0827, WHILE SHUTTING UNIT 2 DOWN FROM 50% POWER DUE TO HIGH #2 SEAL | | LEAKOFF ON THE #4 REACTOR COOLANT PUMP (APPROXIMATELY 1.5 GPM; NORMAL IS | | APPROXIMATELY 3 GPH), CONTROL ROOM OPERATORS MANUALLY TRIPPED THE #2B MAIN | | FEEDWATER PUMP. | | | | A FAILED MAIN TURBINE IMPULSE PRESSURE SWITCH INITIATED A MAIN TURBINE | | RUNBACK AND AN INITIATION OF THE AUXILIARY FEEDWATER SYSTEM ON THE LOSS OF | | ONE MAIN FEEDWATER PUMP ABOVE 80% MAIN TURBINE LOAD SIGNAL. | | | | WHEN REACTOR COOLANT SYSTEM TEMPERATURE DROPPED FROM THE NORMAL OPERATING | | TEMPERATURE OF 578øF TO 550øF, THE MAIN FEEDWATER SYSTEM AUTOMATICALLY | | ISOLATED, AS EXPECTED. HOWEVER, THE #4 STEAM GENERATOR MOTOR OPERATED MAIN | | FEEDWATER ISOLATION VALVE #2-FCV-3-100 FAILED TO CLOSE DUE TO A LOSS OF | | ELECTRICAL POWER. ALSO, THE #2 STEAM GENERATOR AIR OPERATED MAIN FEEDWATER | | REGULATING VALVE #2-FCV-3-048 FAILED TO CLOSE FOR UNKNOWN REASONS. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR FROM 47% POWER AS A | | CONSERVATIVE ACTION BASED ON THE UNCONTROLLED MAIN TURBINE LOAD REDUCTION. | | ALL CONTROL RODS INSERTED COMPLETELY. | | | | FOLLOWING THE REACTOR TRIP, CONTROL ROOM OPERATORS WERE UNABLE TO | | MANUALLY CONTROL AUXILIARY FEEDWATER FLOW TO REDUCE PLANT COOLDOWN DUE | | TO THE AUXILIARY FEEDWATER START SIGNAL FROM THE FAILED PRESSURE SWITCH. | | WHEN THE REACTOR COOLANT SYSTEM COOLED DOWN TO 538øF, CONTROL ROOM | | OPERATORS MANUALLY INITIATED EMERGENCY BORATION. A TOTAL OF 4500 GALLONS | | OF BORATED WATER WAS INJECTED INTO THE REACTOR COOLANT SYSTEM. | | | | AFTER ADEQUATE STEAM GENERATOR LEVELS WERE ESTABLISHED, BOTH MOTOR DRIVEN | | AUXILIARY FEEDWATER PUMPS WERE STOPPED AND THEIR CONTROL SWITCHES PLACED | | IN THE PULL-TO-LOCK POSITION TO CONTROL PLANT COOLDOWN. | | | | AT 1031, CONTROL ROOM OPERATORS REESTABLISHED MANUAL CONTROL OF AUXILIARY | | FEEDWATER FLOW USING THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS. DECAY | | HEAT STEAM IS BEING DUMPED TO THE MAIN CONDENSER. A HEAT SINK USING THE | | STEAM GENERATORS WAS MAINTAINED AT ALL TIMES THROUGHOUT THIS EVENT. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). | | | | LICENSEE IS INVESTIGATING THE CAUSE(S) OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31139 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/11/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 13:41[CDT]| |NRC NOTIFIED BY: TOM COOK |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DEGRADATION INDICATIONS IN >1% OF THE TUBES IN ALL 4 STEAM GENERATORS - | | | | WITH UNIT 2 DEFUELED IN MODE 6 IN A REFUELING OUTAGE, THE LICENSEE IS | | PERFORMING AN EDDY CURRENT INSPECTION OF 100% OF THE TUBES IN ALL 4 | | STEAM GENERATORS. | | | | THE LATEST INSPECTION REVEALED TUBE DEGRADATION INDICATIONS IN EACH | | STEAM GENERATOR IN EXCESS OF THE MAXIMUM NUMBER OF TUBES (1%) SPECIFIED | | IN UNIT 2 TECH SPEC 4.3.1.B.2, CATEGORY C-3. | | | | THE LICENSEE PLANS TO REPAIR THE DEGRADED TUBES. | | | | THIS REPORT IS BEING MADE IN COMPLIANCE WITH THE REQUIREMENTS OF UNIT 2 | | TECH SPEC 4.3.1.B.5.C, TABLE 4.3.B-2. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31140 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNITED TECHNOLOGIES-PRATT & WHITNEY |NOTIFICATION DATE: 10/11/96 | | CITY: NORTH HAVEN REGION: 1 |NOTIFICATION TIME: 16:23 [ET]| | COUNTY: STATE: CT |EVENT DATE: 10/11/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 13:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PETER ESELGROTH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: STEVE JUERS | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TRUCK CARRYING LOW LEVEL RADIOACTIVE SCRAP METAL SET OFF SCRAP YARD ALARM- | | | | A TRUCK TRANSPORTED A SCRAP 4 FEET DIAMETER FURNACE COVER WITH A | | RADIOACTIVE SOURCE INSIDE IT FROM UNITED TECHNOLOGIES-PRATT & WHITNEY, | | AN AIRCRAFT ENGINE MANUFACTURER IN NORTH HAVEN, CT, TO AN AEROSPACE METALS, | | INC, SCRAP RECYCLE YARD IN HARTFORD, CT. UPON ENTERING THE SCRAP RECYCLE | | YARD, THE TRUCK SET OFF THE GATE RADIATION ALARM. | | | | THE CONNECTICUT STATE DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) | | WAS NOTIFIED AND A DEP RADIATION UNIT REPRESENTATIVE CAME TO THE YARD. | | HE MEASURED 50 MICROREMS AT THE OUTSIDE SURFACE OF THE COVER. THE SOURCE | | HAD NOT BEEN PUNCTURED AND NO PERSONS WERE CONTAMINATED. | | | | THE TRUCK HAS RETURNED THE COVER TO THE UNITED TECHNOLOGIES-PRATT & WHITNEY | | SITE IN NORTH HAVEN, CT. | | | | UNITED TECHNOLOGIES-PRATT & WHITNEY REPRESENTATIVES ARE DETERMINING | | CORRECTIVE ACTIONS. | | | | SEE HOO LOG FOR CALLER'S TELEPHONE NUMBER. | | | | MR JUERS HAS REPORTED THIS EVENT TO REGION 1 DUNCAN WHITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31141 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/11/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:12 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 17:50[EDT]| |NRC NOTIFIED BY: RICH SWEENEY |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - REMOVAL OF PUMP AUTO START SIGNAL DURING PLANT MOD OUTSIDE DESIGN BASIS - | | | | DURING A REVIEW OF A DIESEL LOADING CALCULATION, THE LICENSEE DETERMINED | | THAT THE CALCULATION ASSUMED THAT THE STEAM DRIVEN EMERGENCY FEEDWATER PUMP | | (SDEFP) WAS RUNNING WHEN THE MOTOR DRIVEN EMERGENCY FEEDWATER PUMP RECEIVED | | AN AUTOMATIC TRIP SIGNAL AT REACTOR COOLANT SYSTEM PRESSURE OF 500 PSIG. | | THIS INFORMATION IS NOT INCLUDED IN PLANT TECHNICAL SPECIFICATIONS. | | | | A PLANT MODIFICATION HAD REMOVED ONE OF THE AUTO START SIGNALS FROM THE | | SDEFP TO PREVENT PUMP RUNOUT DURING CERTAIN SCENARIO CONDITIONS WHEN ITS | | FLOW CONTROL VALVE FAILED WIDE OPEN. | | | | THUS, A CONDITION OUTSIDE OF THE PLANT DESIGN BASIS COULD HAVE OCCURRED | | WHILE THE PLANT WAS OPERATING AT POWER. | | | | THIS CONDITION IS NOT IN EFFECT WHILE THE PLANT IS IN ITS PRESENT COLD | | SHUTDOWN MODE. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTION(S) AND WILL RESOLVE THIS | | ISSUE PRIOR TO PLANT RESTART. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31142 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/11/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:27 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 17:20[CDT]| |NRC NOTIFIED BY: MIKE GRAHAM |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TRAIN 'B' CR HVAC REFRIG UNIT CRANKCASE HEATER FED FROM NON-Q POWER SUPPLY | | | | QUAD CITIES UNITS 1 AND 2 HAVE A COMMON CONTROL ROOM. THE TRAIN 'A' | | CONTROL ROOM HVAC SYSTEM IS A NON-SAFETY RELATED SYSTEM NOT CONTROLLED BY | | THE REQUIREMENTS OF PLANT TECHNICAL SPECIFICATIONS. THE TRAIN 'B' CONTROL | | ROOM HVAC SYSTEM IS A SAFETY RELATED SYSTEM CONTROLLED BY THE REQUIREMENTS | | OF PLANT TECHNICAL SPECIFICATIONS. | | | | DURING AN ENGINEERING REVIEW, THE LICENSEE DETERMINED THAT THE TRAIN 'B' | | CONTROL ROOM HVAC REFRIGERATION UNIT CRANKCASE HEATER IS FED FROM A | | NON-SAFETY RELATED (NON-Q) POWER SUPPLY. THE CRANKCASE HEATER IS REQUIRED | | TO MAINTAIN AN OIL TEMPERATURE OF AT LEAST 99øF IN THE CRANKCASE WHEN THE | | COMPRESSOR IS NOT RUNNING. | | | | IN THIS CONDITION, IT IS NOT ASSURED THAT THE COMPRESSOR WILL BE ABLE TO | | PERFORM ITS DESIGN FUNCTION UNDER ALL CONDITIONS. | | | | THE LICENSEE DECLARED THE TRAIN 'B' CONTROL ROOM HVAC SYSTEM INOPERABLE. | | TECH SPEC LCO A/S 3.8.D.1.B REQUIRES THE LICENSEE TO RESTORE THE TRAIN 'B' | | CONTROL ROOM HVAC SYSTEM TO OPERABLE STATUS WITHIN 30 DAYS WITH EITHER UNIT | | IN CONDITION 1, 2, OR 3, OR TO PLACE BOTH UNITS IN AT LEAST HOT SHUTDOWN | | CONDITION WITHIN THE NEXT 12 HOURS AND COLD SHUTDOWN CONDITION WITHIN THE | | FOLLOWING 24 HOURS. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS WHICH WILL PROBABLY INCLUDE | | RECONNECTING THE TRAIN 'B' HEATER TO A SAFETY RELATED POWER SUPPLY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31143 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/11/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 21:29 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 17:45[EDT]| |NRC NOTIFIED BY: JOHN REINSBURROW |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LESS THAN 1øF TEMPERATURE RISE DURING LOSS OF S/D COOLING FOR 7 MINUTES - | | | | UNIT 1 IS IN CONDITION 5 IN A REFUELING OUTAGE WHICH BEGAN ON 10/05/96 WITH | | RHR LOOP 'B' SHUTDOWN COOLING IN OPERATION. | | | | AT 1745, UNIT 1 RECEIVED A PARTIAL PCIS GROUP 8 ISOLATION FROM AN INVALID | | SIGNAL FOR UNKNOWN REASONS. THIS SIGNAL CAUSED THE RHR SHUTDOWN COOLING | | OUTBOARD SUCTION ISOLATION VALVE #1-E11-F008 TO CLOSE. | | | | AT 1752, CONTROL ROOM OPERATORS RESET THE ISOLATION SIGNAL, OPENED THE F008 | | VALVE, AND REESTABLISHED SHUTDOWN COOLING. | | | | THE REACTOR COOLANT SYSTEM INCREASED LESS THAN 1øF IN THE 7 MINUTES THAT | | SHUTDOWN COOLING HAD BEEN LOST. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE INVALID ISOLATION SIGNAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31144 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/11/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 22:00 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: MATT MORGAN |LAST UPDATE DATE: 10/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - APPROXIMATELY 213 ITE/GOULD J-12 RELAYS TO BE REPLACED IN UNIT 2 - | | | | UNIT 2 IS IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE. | | | | DURING REASSESSMENT OF NRC INFORMATION NOTICE 92-27, "THERMALLY INDUCED | | ACCELERATED AGING AND FAILURE OF ITE/GOULD AC RELAYS USED IN SAFETY RELATED | | APPLICATIONS", THE LICENSEE DISCOVERED THAT THE SAME FAILURE MECHANISM | | STATED IN IN 92-27 POTENTIALLY EXISTS IN UNIT 2 FOR ITE/GOULD J-12 RELAYS. | | SPECIFICALLY, DURING THE CURRENT REFUELING OUTAGE, LICENSEE INSPECTION OF | | THESE RELAYS IDENTIFIED THAT THESE J-12 RELAYS HAVE THE POTENTIAL TO BIND. | | SUBSEQUENT BENCH TESTING OF A REMOVED SUSPECT J-12 RELAY REVEALED THAT THIS | | RELAY WILL OVERHEAT AND POTENTIALLY CAUSE A SHORT CIRCUIT. SUCH A SHORT | | CIRCUIT COULD RESULT IN THE FAILURE OF THE CONTROL POWER CIRCUIT FUSE FOR | | THE COMPONENT, RENDERING THE COMPONENT INOPERABLE SUCH THAT THIS CONDITION | | COULD HAVE PREVENTED THE FULFILLMENT OF THE RESPECTIVE SAFETY FUNCTION. | | THESE J-12 RELAYS ARE USED IN MULTIPLE SAFETY RELATED CIRCUITS IN UNIT 2 | | AND THERE ARE APPROXIMATELY 213 J-12 RELAYS PRESENTLY INSTALLED IN UNIT 2. | | THESE RELAYS PROVIDE ALARMS, BYPASS INOPERABLE STATUS INDICATION, AND | | THERMAL OVERLOAD PROTECTION FOR VARIOUS MOVs, FANS, AND PUMPS. | | | | THE LICENSEE IS EVALUATING THE REPLACEMENT OF THESE J-12 RELAYS ON UNIT 2 | | AT THE PRESENT TIME. THE LICENSEE WILL KEEP UNIT 2 IN MODE 5 UNTIL | | RESOLUTION OF THIS ISSUE IS COMPLETED. | | | | THERE ARE NO J-12 RELAYS INSTALLED IN UNIT 1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31145 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/12/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 02:51 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/11/96 | +------------------------------------------------+EVENT TIME: 22:55[CDT]| |NRC NOTIFIED BY: PALLAS |LAST UPDATE DATE: 10/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 +------------------------------------------------------------------------------+ | CONTAINMENT PURGE ISOLATION WHILE OPENING STEAM GENERATOR MANWAY COVER | | | | AFTER REMOVING THE STEAM GENERATOR PRIMARY SIDE MANWAY, RADIATION LEVELS IN | | THE CONTAINMENT INCREASED ABOVE THE HIGH CONTAINMENT RADIATION SETPOINT. | | THIS RESULTED IN A CONTAINMENT VENTILATION ISOLATION ACTUATION SIGNAL | | (VIAS). THE VIAS AUTOMATICALLY SECURED THE CONTAINMENT PURGE WHICH WAS IN | | PROGRESS. BASED UPON PRELIMINARY CALCULATIONS, THE LICENSEE DOES NOT | | BELIEVE THAT THIS EVENT RESULTED IN A RADIOACTIVE RELEASE IN EXCESS OF 10 | | CFR PART 20 LIMITS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31146 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 10/12/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 05:21 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/12/96 | +------------------------------------------------+EVENT TIME: 03:19[CDT]| |NRC NOTIFIED BY: CUNNINGHAM |LAST UPDATE DATE: 10/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 | M/R N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AFW AUTOSTART FOLLOWING MANUAL REACTOR TRIP TO ENTER REFUELING OUTAGE. | | | | THE LICENSEE HAD INITIATED A MANUAL REACTOR TRIP IN ORDER TO VERIFY CONTROL | | ROD DROP TIMES. THE MAIN TURBINE HAD BEEN TAKEN OFFLINE SEVERAL HOURS | | BEFORE, AND THE LICENSEE BELIEVES THAT LATENT HEAT FROM THE MAIN STEAM | | SYSTEM WAS TRANSMITTED TO THE STEAM SIDE OF THE FEEDWATER HEATERS AND | | CAUSED FEEDWATER SYSTEM PRESSURE TO SLOWLY INCREASE. THE LICENSEE WAS | | SECURING FROM THE TEST PROCEDURE WHEN FEEDWATER SYSTEM PRESSURE REACHED | | 1900 PSIG AND BOTH MAIN FEEDWATER PUMPS AUTOMATICALLY TRIPPED, CAUSING AN | | AUTOMATIC START OF THE AUXILIARY FEEDWATER PUMPS. THE LICENSEE REPORTED | | THAT ALL SYSTEMS FUNCTIONED AS EXPECTED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31147 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BP OIL CORPORATION |NOTIFICATION DATE: 10/14/96 | | CITY: OREGON REGION: 3 |NOTIFICATION TIME: 10:13 [ET]| | COUNTY: LUCAS STATE: OH |EVENT DATE: 10/13/96 | |LICENSE#: 34-07269-02 AGREEMENT: N |EVENT TIME: 16:30[EDT]| | DOCKET: |LAST UPDATE DATE: 10/14/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEACH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: M. SULLIVAN | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE AT BP OIL REFINERY NEAR TOLEDO, OH. | | | | LATE ON 10/12/96, A FIRE OCCURRED AT THE BP OIL REFINERY NEAR TOLEDO, OH. | | AS PART OF FIREFIGHTING EFFORTS, A NUCLEAR SOURCE WAS REMOVED FROM ITS | | HOLDER BY TEXAS NUCLEAR, INC. AT 1630 ON 10/13/96, OMART, INC. TOOK | | POSSESSION OF THE SOURCE AND ITS HOLDER. THE SOURCE WAS UNDAMAGED. THE | | LICENSEE PLANS TO CONTACT NRC REGION 3 REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31148 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/14/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 21:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/14/96 | +------------------------------------------------+EVENT TIME: 19:28[EDT]| |NRC NOTIFIED BY: JAMES ROBINSON |LAST UPDATE DATE: 10/14/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 50 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP - LOSS OF FEED TO ONE STEAM GENERATOR | | | | "ON OCTOBER 14, 1996, AT 1928, A MANUAL REACTOR TRIP WAS INITIATED ON UNIT | | TWO WHEN THE LOOP 3 MAIN FEEDWATER REGULATING VALVE STARTED DRIFTING SHUT. | | THE PLANT WAS OPERATING AT APPROXIMATELY 50% REACTOR POWER PRIOR TO THE | | TRANSIENT AND WAS STABILIZED IN MODE 3 AT NORMAL OPERATING TEMPERATURE AND | | PRESSURE FOLLOWING THE TRIP." | | | | ALL CONTROL RODS FULLY INSERTED. AUXILIARY FEEDWATER IS SUPPLYING THE | | STEAM GENERATORS. STEAM IS BEING DUMPED TO THE MAIN CONDENSER AS NECESSARY | | TO REMOVE DECAY HEAT. THE EMERGENCY DIESEL GENERATORS AND OFFSITE POWER | | ARE OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31149 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 10/14/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 22:44 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/14/96 | +------------------------------------------------+EVENT TIME: 20:10[EDT]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 10/14/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - ACTIVITY RELEASE GREATER THAN STATED IN THE PUBLIC | | INFORMATION MESSAGE | | | | THE LICENSEE NOTIFIED THE STATE OF MAINE THAT MORE ACTIVITY WAS RELEASED IN | | A DAY THAN STATED IN THEIR PUBLIC INFORMATION MESSAGE. THE LICENSEE HAS AN | | AGREEMENT WITH THE STATE TO MAKE A NOTIFICATION TO THE STATE WHEN THIS | | QUANTITY OF ACTIVITY IS EXCEEDED. THE MESSAGE FOR TODAY STATES THAT 0.01 Ci | | WOULD BE RELEASED. THE ACTUAL AMOUNT OF ACTIVITY RELEASED WAS 0.103 Ci. | | THE INCREASED ACTIVITY WAS DUE TO Xe-131 ACTIVITY MEASURED IN THE PLANT | | STACK. THE CONCENTRATION WAS ON THE ORDER OF 1E-8 æCi/ml. | | | | THE EXACT SOURCE OF THE ACTIVITY WAS NOT IDENTIFIED. PRIMARY COOLANT | | ACTIVITY IS SLIGHTLY HIGHER THAN NORMAL, AND THIS MAY HAVE BEEN ENOUGH TO | | CAUSE THE ACTIVITY IN THE STACK TO REACH DETECTABLE LEVELS. ACTIVITY | | LEVELS IN THE STACK HAVE SINCE RETURNED TO NORMAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31150 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 10/15/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 02:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 01:36[EDT]| |NRC NOTIFIED BY: McGUINESS |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |POTTER RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED OFFSITE TO HOSPITAL | | | | WHILE PERFORMING A CONTAINMENT INSPECTION, AN INDIVIDUAL FELL DOWN AN | | INSTALLED PLANT LADDER IN THE LOWER CONTAINMENT. THE INDIVIDUAL WAS | | IMMOBILIZED AND TRANSPORTED TO THE LOCAL HOSPITAL. HOWEVER, DUE TO THE NEED | | FOR IMMOBILIZATION, A PORTION OF THE INDIVIDUAL'S BODY COULD NOT BE CHECKED | | DURING THE PRE-TRANSPORT WHOLE BODY SURVEY. THOSE PORTIONS OF THE | | INDIVIDUAL'S BODY WHICH WERE SURVEYED SHOWED NO SIGNS OF CONTAMINATION, AND | | THE LICENSEE DOES NOT EXPECT TO FIND CONTAMINATION ON OTHER PARTS OF THE | | INDIVIDUAL. THE SURVEY WILL BE COMPLETED UPON ARRIVAL AT THE HOSPITAL. THE | | NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE 0346 FROM McGUINESS TAKEN BY STRANSKY * * * | | | | THE SURVEY OF THE INDIVIDUAL WAS COMPLETED, AND NO CONTAMINATION WAS FOUND. | | NOTIFIED R2DO (POTTER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/15/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 00:20[CDT]| |NRC NOTIFIED BY: HALVERSON |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEACH RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FEEDWATER ISOLATION VALVES FAIL LOCAL LEAK RATE TEST | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "THE CONTAINMENT ISOLATION VALVES ON THE 'B' FEEDWATER LINE DID NOT MEET | | LOCAL LEAK RATE TESTING REQUIREMENTS FROM 10 CFR 50, APPENDIX J, AND | | TECHNICAL SPECIFICATION 3.6.1.3, 'PRIMARY CONTAINMENT ISOLATION VALVES'. | | THE LEAK RATE OF EACH VALVE WAS BEYOND THE LIMITS OF THE LLRT TEST | | EQUIPMENT. THE VALVES AFFECTED ARE THE 1B21F010B (REACTOR FEEDWATER HEADER | | CHECK VALVE) AND 1B21F032B (FEEDWATER CONTAINMENT ISOLATION CHECK VALVE)." | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+