U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/16/96 - 04/17/96 ** EVENT NUMBERS ** 30194 30291 30292 30293 30294 30295 30296 30297 30298 30299 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |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: 04/16/96 | |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. | | | | THE 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. | | | | * * * UPDATE AT 1432 ON 04/16/96, BY NEFF TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. AN ENGINEERING REVIEW OF THE | | CONDITION WAS PERFORMED AND CONCLUDED THAT THE LEAKAGE RATE WAS NOT | | SIGNIFICANT ENOUGH TO CAUSE AN ADVERSE AFFECT ON THE SUPPRESSION CHAMBER. | | THE ALLOWABLE LEAK RATE FOR THE CHECK VALVES IS 30,000 SCCM, AND THE | | MEASURED LEAKAGE RATE WAS 47,300 SCCM. ADDITIONALLY, THE SUPPRESSION POOL | | SPRAY FUNCTION OF THE RHR SYSTEM COULD HAVE BEEN USED TO CONDENSE ANY STEAM | | INTRODUCED BY THE LEAKING CHECK VALVES. THEREFORE, THE HPCI SYSTEM WOULD | | NOT HAVE HAD TO BE SECURED, AND THE LICENSEE DOES NOT CONSIDER THE EVENT | | REPORTABLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 30291 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ALLIED SIGNAL CORP, METROPOLIS, IL |NOTIFICATION DATE: 04/16/96 | | CITY: SAVANNAH REGION: 2 |NOTIFICATION TIME: 07:00 [ET]| | COUNTY: STATE: GA |EVENT DATE: 04/15/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 13:30[EDT]| | DOCKET: |LAST UPDATE DATE: 04/16/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID VERRELLI RDO | | |DON COOL, NMSS EO | +------------------------------------------------+RICH BARRETT AEOD | |NRC NOTIFIED BY: JIM HARDEMAN, STATE OF GA |JIM WYATT DOE | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | |NAGR AGREEMENT STATE | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FREIGHT CONTAINERS CONTAINING DRUMS OF YELLOWCAKE SUSTAINED DAMAGE - | | | | AN ESTONIAN FLAG VESSEL TRANSPORTED 24 ISO-INTERMODAL FREIGHT CONTAINERS | | FROM ST PETERSBURG, RUSSIA, TO THE GEORGIA PORT AUTHORITY OCEAN TERMINAL | | STORAGE FIELD IN SAVANNAH, GA. THE CONTAINERS CONTAIN 55-GALLON DRUMS OF | | YELLOWCAKE AND WERE BOUND FOR ALLIED SIGNAL CORP, METROPOLIS, IL. | | | | FIFTEEN OF THESE TWENTY-FOUR CONTAINERS SUSTAINED SEVERE STRUCTURAL DAMAGE | | WITH THEIR LOADING DOORS SEVERELY BENT OUTWARDS POSSIBLY DUE TO THE | | CONTAINERS SHIFTING WHILE AT SEA. THE CONTAINERS HAVE BEEN OFFLOADED FROM | | THE SHIP. IT IS NOT KNOWN AT THIS TIME IF ANY OF THE DRUMS HAVE BEEN | | BREACHED. | | | | THE SHIPPER IS EDLOW INTERNATIONAL, WASHINGTON, DC. THE CONTAINERS HAVE | | PLACARDS AND "RADIOACTIVE" AND "CLASS 7, UN-2912" MARKINGS. | | | | THE USCG NATIONAL RESPONSE CENTER (INCIDENT REPORT #336496) NOTIFIED THE | | NRC OPERATIONS CENTER, GEORGIA DEPARTMENT OF NATURAL RESOURCES (DNS), EPA, | | DOE, AND NOAA. GEORGIA DNS NOTIFIED THE NRC OPERATIONS CENTER. | | | | (REFER TO THE HOO LOG FOR GEORGIA DNS AND SHIPPER CONTACT NAMES AND | | TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30292 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 04/16/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 12:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 10:34[EDT]| |NRC NOTIFIED BY: TOM WALLACE |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI 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 | A/R Y 84 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP - REACTOR TRIP | | | | WATTS BAR NUCLEAR PLANT WAS IN MODE 1, REACTOR POWER 84% WITH POWER | | INCREASING WHEN THE MAIN TURBINE CONTROL VALVES WENT FULLY CLOSED. CONTROL | | ROOM OPERATORS MANUALLY TRIPPED THE MAIN TURBINE RESULTING IN AN AUTOMATIC | | REACTOR TRIP. ALL SAFETY SYSTEMS FUNCTIONED AS REQUIRED. AUXILIARY | | FEEDWATER ACTUATED ON THE REACTOR TRIP WITH LOW T-AVG AS EXPECTED. ALL | | OTHER ESF EQUIPMENT AND EMERGENCY POWER SUPPLIES ARE OPERABLE AND IN | | STANDBY. ALL CONTROL RODS FULLY INSERTED INTO THE CORE. DURING THE | | TRANSIENT, THE "C1" (HIGH PRESSURE) FEEDWATER HEATER RELIEF VALVE LIFTED | | AND REMAINED OPEN. CONTROL ROOM OPERATORS MANUALLY ISOLATED THE "C1" | | HEATER. THERE WERE NO COMPLICATIONS ASSOCIATED WITH THE RELIEF VALVE | | OPENING. THE REASON FOR THE MAIN TURBINE CONTROL VALVES CLOSING IS UNDER | | INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30293 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/16/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 14:59[EDT]| |NRC NOTIFIED BY: JOHN DEDOMENICO |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 MINIMUM CRITICAL POWER RATIO (MCPR) SAFETY LIMIT WAS POTENTIALLY SET | | TOO LOW (REFER TO RELATED EVENT #30298.) | | | | GENERAL ELECTRIC INFORMED THE LICENSEE TODAY THAT THE MCPR SAFETY LIMIT | | SHOULD BE AS HIGH AS 1.094 FOR TWO LOOP OPERATION. THIS CONCLUSION WAS | | BASED ON UNVERIFIED CALCULATIONS WHICH GE IS STILL REVIEWING. THE | | LICENSEE'S TECH SPECS CURRENTLY CONTAIN MCPR SAFETY LIMITS OF 1.07 FOR TWO | | LOOP OPERATION AND 1.08 FOR SINGLE LOOP OPERATION. | | | | THE LICENSEE HAS ADMINISTRATIVELY SET THE SAFETY LIMITS AT 1.10 FOR TWO | | LOOP OPERATION AND 1.11 FOR SINGLE LOOP OPERATION. THE OPERATING MCPR | | LIMIT HAS ALSO BEEN RAISED FROM 1.26 TO 1.29. THE LOWEST STEADY STATE MCPR | | IS CURRENTLY 1.74. BASED ON CURRENT PLANT CONDITIONS, NO SAFETY LIMIT | | (USING THE NEW VALUE) WOULD HAVE BEEN EXCEEDED FOR ANY ANALYZED TRANSIENT. | | HOWEVER, HAD THE INITIAL MCPR BEEN CLOSER TO THE ALLOWABLE 1.26 VALUE, THE | | POTENTIAL TO EXCEED A SAFETY LIMIT WOULD HAVE EXISTED. | | | | USING THE HIGHER ADMINISTRATIVELY SET VALUES FOR THE MCPR SAFETY LIMIT AND | | THE MCPR OPERATING LIMIT, THE PLANT WILL NOT EXCEED A SAFETY LIMIT FOR ANY | | ANALYZED TRANSIENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30294 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 04/16/96 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: TONY COOK |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A SEWAGE SPILL | | | | THE LICENSEE NOTIFIED THE NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL, | | HEALTH AND NATURAL RESOURCES OF A 300-GALLON SEWAGE SPILL. THE SPILL HAS | | BEEN STOPPED AND DID NOT AFFECT PLANT OPERATIONS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/16/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 14:55[CDT]| |NRC NOTIFIED BY: KEITH LEECH |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNAUTHORIZED ENTRY INTO THE PROTECTED AREA BY A CONTRACT EMPLOYEE | | | | IMMEDIATE COMPENSATORY ACTION WAS TAKEN UPON DISCOVERY. THE LICENSEE | | NOTIFIED THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO LOG FOR DETAILS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30296 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/16/96 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 16:48 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 +------------------------------------------------------------------------------+ | ONLY ONE BORON DILUTION FLOW PATH AVAILABLE DURING POWER OPERATION | | | | ON MARCH 28, 1996, THE BORON DILUTION FLOW PATH VALVE (2LP-4) WAS | | DISCOVERED IN THE CLOSED POSITION. THIS VALVE IS REQUIRED TO BE OPEN IN | | ORDER FOR ONE OF THE ACTIVE POST-LOCA BORON DILUTION FLOW PATHS TO BE | | OPERATIONAL. VALVE (2LP-4) COULD NOT HAVE BEEN OPENED UNDER POST-LOCA | | CONDITIONS BECAUSE OF HIGH DOSE RATES IN THE VICINITY OF THE VALVE. | | | | THE PLANT HAS TWO ACTIVE FLOW PATHS AND ONE PASSIVE FLOW PATH. THE SECOND | | ACTIVE FLOW PATH WAS ALREADY DECLARED INOPERABLE BECAUSE OF THE | | REQUIREMENTS OF GENERIC LETTER 95-07 REGARDING PRESSURE LOCKING AND THERMAL | | BINDING. | | | | THEREFORE, ONLY THE PASSIVE BORON DILUTION FLOW PATH THROUGH THE REACTOR | | VESSEL INTERNALS WAS AVAILABLE IN THE EVENT OF A LOCA DURING THE PERIOD IN | | WHICH 2LP-4 WAS CLOSED. THIS CONDITION IS CONSIDERED OUTSIDE THE DESIGN | | BASIS OF THE PLANT SINCE THE FSAR REQUIRES AT LEAST TWO FLOW PATHS BE | | AVAILABLE IN THE EVENT OF A LOCA. | | | | THE VALVE OUT OF POSITION WAS DISCOVERED BY AN OPERATOR WHO MANIPULATED THE | | VALVE AND QUESTIONED THE INITIAL POSITION OF THE VALVE. THIS LED TO A | | REVIEW WHICH GENERATED THIS EVENT REPORT TODAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30297 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/16/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:26 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 16:46[EDT]| |NRC NOTIFIED BY: JOHN MANSELL |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A FREON RELEASE | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONTROL THAT 65 POUNDS OF FREON-22 WAS RELEASED TO THE ENVIRONMENT. THE | | FREON CAME FROM A CONTROL ROOM AIR CONDITIONING UNIT'S COOLING COILS. THE | | LEAK WAS FROM A FITTING ON A ROOF AND DID NOT REPRESENT A PERSONNEL HAZARD | | OR IMPACT SITE OPERATIONS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/16/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/16/96 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: JAMES BOYLE |LAST UPDATE DATE: 04/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (MCPR) MAY BECOME | | NON-CONSERVATIVE (REFER TO RELATED EVENT #30293.) | | | | GENERAL ELECTRIC INFORMED THE LICENSEE OF A NON-CONSERVATISM IN THE SAFETY | | LIMIT MCPR ANALYSIS. THE SAFETY LIMIT MCPR IS NOW CALCULATED TO BE 1.099 | | AT THE POINT IN THIS FUEL CYCLE OF PEAK HOT EXCESS REACTIVITY (7000 MWD/ST | | OR ABOUT 7 MONTHS INTO CYCLE 7). THE TECH SPEC SAFETY LIMIT FOR TWO LOOP | | OPERATION IS 1.07. THEREFORE, THE EXISTING TECH SPEC MAY BE | | NON-CONSERVATIVE BY 0.O3 AT HIGHER BURNUPS. | | | | THE LICENSEE HAS IMPLEMENTED, IN THE SHORT TERM, A PENALTY ON THE OPERATING | | LIMIT CRITICAL POWER RATIO IN ORDER TO BOUND NON-CONSERVATISMS IN THE | | GENERIC SAFETY LIMIT MCPR CALCULATION. RIVER BEND HAS CURRENTLY | | IMPLEMENTED AN ADMINISTRATIVE MARGIN UNTIL A CHANGE IN THE CORE MONITORING | | COMPUTER CAN BE IMPLEMENTED. THIS CORE MONITORING MARGIN WILL BE INCREASED | | BY 0.03 TO BOUND THE CYCLE 7 ANALYSIS SUPPLIED BY GENERAL ELECTRIC. THIS | | ADDITIONAL MARGIN WILL BOUND ALL KNOWN POINTS IN THE CURRENT FUEL CYCLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30299 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 04/17/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 03:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/17/96 | +------------------------------------------------+EVENT TIME: 02:07[CDT]| |NRC NOTIFIED BY: DAVE SCHUELLER |LAST UPDATE DATE: 04/17/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 +------------------------------------------------------------------------------+ | REACTOR TRIP, CAUSE UNKNOWN | | | | THE REACTOR TRIPPED WITH A FIRST OUT ANNUNCIATOR INDICATION OF LOW FLOW IN | | ONE LOOP/COOLANT PUMP BREAKER OPEN; HOWEVER, NO LOW FLOW EXISTED. ALL | | REACTOR COOLANT PUMPS WERE RUNNING AFTER THE TRIP. ALL CONTROL RODS | | INSERTED FULLY AFTER THE TRIP, AND PLANT RESPONSE WAS NORMAL. THE LICENSEE | | IS INVESTIGATING THE CAUSE OF THE REACTOR TRIP. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0525 EDT FROM SCHUELLER TAKEN BY KARSCH * * * | | | | EXAMINATION OF COMPUTER RECORDS DETERMINED THAT THE REACTOR TRIP OCCURRED | | AT 0206 CDT CAUSED BY LOW FLOW IN LOOP "C" ON TWO OF THREE LOOP FLOW | | INSTRUMENTS (CHANNELS 424 AND 425). | +------------------------------------------------------------------------------+