U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/20/98 - 04/21/98 ** EVENT NUMBERS ** 34022 34102 34103 34104 34105 34106 34107 34108 34109 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34022 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 04/05/98 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 15:11 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/05/98 | +------------------------------------------------+EVENT TIME: 12:18[EDT]| |NRC NOTIFIED BY: PAGE KEMP |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM PEEBLES 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN FEEDWATER CHECK VALVE TO STEAM GENERATOR 'C' MAY NOT PREVENT BACKFLOW. | | | | A SURVEILLANCE TEST ON THE 'C' STEAM GENERATOR MAIN FEEDWATER CHECK VALVE | | (2-FW-126) INDICATED THAT IT MAY NOT PREVENT BACK FLOW. THE CORRECTED LEAK | | RATE PAST THE MAIN FEEDWATER CHECK VALVE IS 40 gpm. WITH VALVE 2-FW-126 | | INOPERABLE, AUXILIARY FEEDWATER FLOW TO THE UNIT 2 'C' STEAM GENERATOR MAY | | BE REDUCED DUE TO BACK LEAKAGE INTO THE MAIN FEEDWATER SYSTEM. UNIT 2 IS | | ENTERING A REFUELING OUTAGE AND AT PRESENT, THE LICENSEE IS COOLING DOWN | | THE UNIT TO COLD SHUTDOWN. ADDITIONAL TESTING WILL BE PERFORMED ON THE | | MAIN FEEDWATER CHECK VALVE. THE STEAM GENERATOR 'A' AND 'B' MAIN FEEDWATER | | CHECK VALVES PASSED THEIR LEAK TESTS. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0925 ON 04/20/98 BY KEMP TO GOULD * * * | | | | ADDITIONAL LICENSEE TESTING WAS PERFORMED ON THE #2-FW-126 CHECK VALVE | | USING A HIGHER DIFFERENTIAL PRESSURE TO MORE APPROPRIATELY REFLECT THE | | ACTUAL OPERATING CHARACTERISTICS. THIS DEMONSTRATED THE VALVE WAS FULLY | | CAPABLE OF MEETING THE DESIGN FUNCTION OF THE AUXILIARY FEEDWATER SYSTEM. | | THE ACTUAL LEAKAGE OF 0.106 GPM WITH A 350 PSI DIFFERENTIAL PRESSURE WAS | | WELL WITHIN THE TEST ACCEPTANCE CRITERIA. WITH THE CHECK VALVE IN AN | | OPERABLE CONDITION, THE AUXILIARY FEEDWATER SYSTEM FLOW TO THE UNIT 2 "C" | | STEAM GENERATOR WOULD BE SUFFICIENT FOR ACCIDENT MITIGATION. THEREFORE, | | THIS EVENT REPORT WAS NOT REQUIRED AND IS BEING RETRACTED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R2DO KERRY LANDIS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34102 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 04/20/98 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/19/98 | +------------------------------------------------+EVENT TIME: 23:20[CDT]| |NRC NOTIFIED BY: LAMKEN |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 +------------------------------------------------------------------------------+ | UNIT 2 RECEIVED A VALID RADIATION SIGNAL WHICH GENERATED A FUEL HANDLING | | BUILDING VENTILATION SYSTEM START SIGNAL. | | | | DURING PREPARATION FOR UNIT 2 CORE OFFLOAD, A VALID ESF SIGNAL WAS | | PROCESSED BY THE FUEL HANDLING BUILDING RADIATION MONITORS. THE SIGNAL | | WAS GENERATED AFTER THE SLUICE GATE BETWEEN THE SPENT FUEL POOL AND THE | | TRANSFER CANAL WAS OPENED. THE TRANSFER CANAL LEVEL WAS 0.5 INCHES LOWER | | THAN THE SPENT FUEL POOL RESULTING IN A SMALL TRANSFER OF WATER INTO THE | | TRANSFER CANAL RESULTING IN INCREASED RADIATION LEVELS. RADIATION LEVELS | | INCREASED ABOVE THE HIGH ALARM SETPOINT OF 5mR/HR GENERATING AN ACTUATION | | SIGNAL TO START THE FUEL HANDLING BUILDING VENTILATION. THE CONDITION | | WAS EXPECTED DUE TO THE ELEVATED DOSE LEVEL IN THE TRANSFER CANAL. THE | | VENTILATION SYSTEM WAS ALREADY IN OPERATION AT THE TIME THE SIGNAL WAS | | GENERATED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34103 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/20/98 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 09:52 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | AVAILABLE NITROGEN SUPPLY IS INSUFFICIENT TO MEET OVERPRESSURE PROTECTION | | SYSTEM DESIGN BASIS. | | | | DURING TRANSIENT TESTING OF THE NITROGEN SUPPLY TO PRESSURIZER POWER | | OPERATED RELIEF VALVES FOR LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM | | (OPS), THE LICENSEE DETERMINED THAT THE AVAILABLE SUPPLY OF NITROGEN MAY | | NOT MEET THE OPS SYSTEM DESIGN BASIS OF 200 OPERATING CYCLES IN 10 MINUTES. | | THE OPS IS CURRENTLY NOT REQUIRED TO BE OPERABLE. IMMEDIATE LICENSEE | | ACTION IS TO PROVIDE FOR ADDITIONAL NITROGEN SUPPLY TO ASSURE THAT THE | | DESIGN BASIS IS MET TO SUPPORT OPS OPERABILITY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34104 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/20/98 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 11:28 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 07:30[CDT]| |NRC NOTIFIED BY: J CLARK |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PARISH & STATE OFFICIALS NOTIFIED OF INADVERTENT EMERGENCY SIREN ACTIVATION | | | | AT 0740 CDT, A MEMBER OF THE PUBLIC NOTIFIED RIVER BEND OF AN EMERGENCY | | SIREN ACTUATION FOR APPROXIMATELY TWO MINUTES. THE LICENSEE DETERMINED | | THAT THE SIREN ACTUATION WAS INADVERTENT AND NOTIFIED LOUISIANA OFFICE OF | | EMERGENCY PREPAREDNESS AND EAST FELICIANA PARISH OFFICIALS. THE LICENSEE | | IS INVESTIGATING THE CAUSE OF THE SIREN ACTIVATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34105 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/20/98 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 08:58[CDT]| |NRC NOTIFIED BY: KLIMEK |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM GAVULA 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 | A/R Y 60 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 AUTO REACTOR SCRAM FROM 60% POWER DUE TO A MAIN TURBINE TRIP. | | | | THE UNIT 2 REACTOR AUTOMATICALLY SCRAMMED FROM 60% POWER. THIS APPEARS | | TO HAVE BEEN CAUSED BY A MAIN TURBINE TRIP BASED ON THE FIRST HIT ON | | ANNUNCIATOR #A-13 (CHANNEL A/B GENERATOR-TURBINE LOAD MISMATCH). THE | | EXACT CAUSE OF THE MAIN TURBINE TRIP IS UNKNOWN AND BEING INVESTIGATED BY | | THE LICENSEE. ALL CONTROL RODS FULLY INSERTED INTO THE CORE, NO SAFETY | | INJECTION OCCURRED AND NO SAFETY/RELIEF VALVES LIFTED. ALL PLANT SYSTEMS | | RESPONDED TO THE SCRAM, AS EXPECTED. SINCE THERE IS VERY LITTLE DECAY HEAT | | IN THE CORE DUE TO A RECENT PLANT STARTUP, THE HEAT SINK IS BEING PROVIDED | | VIA FEED AND BLEED (CONTROL ROD DRIVES AND REACTOR WATER CLEANUP). THE MAIN | | CONDENSER IS OPERABLE IF NEEDED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34106 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/20/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 10:17[EDT]| |NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 80 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - RCIC SYSTEM INOPERABLE DUE TO FAILURE OF RCIC SYSTEM BATTERY CHARGER - | | | | AT 1017 ON 04/20/98, THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM | | BATTERY CHARGER UNEXPECTEDLY SHUT DOWN. THE LICENSEE DECLARED THE RCIC | | SYSTEM INOPERABLE WHICH PLACES THE PLANT IN A 14 DAY SHUTDOWN LCO. LICENSEE | | ATTEMPTS TO RESET THE CHARGER HAVE, AS YET, PROVEN UNSUCCESSFUL. LICENSEE | | TROUBLESHOOTING IS CONTINUING. THE RCIC SYSTEM IS LINED UP FOR OPERATION | | AND ITS BATTERIES ARE STILL CAPABLE OF SUPPLYING ELECTRICAL ENERGY TO THE | | REQUIRED SYSTEM COMPONENTS NECESSARY TO SUPPORT OPERATION. | | | | THE PLANT REMAINS AT 80% POWER IN SUPPORT OF ONLINE HYDRAULIC CONTROL UNIT | | MAINTENANCE ACTIVITIES. CURRENTLY, SEVEN CONTROL RODS ARE INOPERABLE. | | PLANT TECHNICAL SPECIFICATIONS PERMIT A MAXIMUM OF EIGHT CONTROL RODS TO | | BE INOPERABLE AT ANY ONE TIME. | | | | ADDITIONALLY, THE FOLLOWING EQUIPMENT IS INOPERABLE FOR SCHEDULED | | MAINTENANCE ACTIVITIES AND IS EXPECTED TO BE RESTORED TO OPERABLE STATUS | | THIS AFTERNOON: 'B' STANDBY LIQUID CONTROL PUMP, 'B' MAIN GENERATOR | | STATOR WATER COOLING PUMP, AND THE 'B' HYDROGEN/OXYGEN ANALYZER (ONE OF | | ITS CONTAINMENT ISOLATION VALVES). | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34107 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 04/20/98 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 14:43 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 09:45[EDT]| |NRC NOTIFIED BY: OSBORNE / HOLLEMAN |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FITNESS FOR DUTY REPORT - | | | | AT 0945 ON 04/20/98, A NON-LICENSED SUPERVISOR TESTED POSITIVE FOR ALCOHOL | | DURING A RANDOM TEST. THE EMPLOYEE'S PLANT ACCESS AUTHORIZATION HAS BEEN | | TERMINATED AND HE HAS BEEN RELIEVED OF HIS NUCLEAR RELATED DUTIES. REFER | | TO THE HOO LOG FOR ADDITIONAL DETAILS. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34108 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/20/98 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 15:35[CDT]| |NRC NOTIFIED BY: TODD MIELKE |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM GAVULA 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT ACCIDENT FAN COOLERS DECLARED INOPERABLE DUE TO CALCULATION | | UNCERTAINTIES. | | | | DURING A REVIEW OF FAN COOLER FOULING FACTORS, THE LICENSEE IDENTIFIED A | | POTENTIAL PROBLEM WITH INSTRUMENTATION AND ANALYSIS TECHNIQUE UNCERTAINTIES | | USED IN A CALCULATION THAT EVALUATED THE PERFORMANCE OF THE UNIT 1 | | CONTAINMENT ACCIDENT FAN COOLERS. WHEN THESE UNCERTAINTIES ARE APPLIED | | CONSERVATIVELY (ADDITIVELY), THE CALCULATION RESULTS NO LONGER MEET THE | | ESTABLISHED HEAT TRANSFER ACCEPTANCE CRITERIA. THEREFORE, THE LICENSEE | | DECLARED THE UNIT 1 CONTAINMENT ACCIDENT FAN COOLERS INOPERABLE. THE | | LICENSEE PLANS TO CLEAN THE COILS OF THE FAN COOLERS AND RETEST THEM. | | THE LICENSEE WILL RESOLVE THIS CONDITION PRIOR TO THE RESTART OF UNIT 1. | | | | THE LICENSEE DETERMINED THAT THIS CONDITION DOES NOT APPLY TO UNIT 2. | | WHEN THESE UNCERTAINTIES ARE APPLIED TO THE UNIT 2 CALCULATIONS, THE | | RESULTS STILL MEET THE HEAT TRANSFER ACCEPTANCE CRITERIA. THE UNIT 2 | | CONTAINMENT ACCIDENT FAN COOLERS REMAIN OPERABLE. UNIT 2 IS CURRENTLY | | AT 100% POWER. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34109 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 04/20/98 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 18:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 17:45[EDT]| |NRC NOTIFIED BY: JAMES ROBINSON |LAST UPDATE DATE: 04/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER RODGERS RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 30 POWER OPERATION | 30 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ACCUMULATOR LEVEL INSTRUMENTATION CALIBRATION PROCEDURE CONTAINS ERROR - | | | | AT 1745 ON 04/20/98, I&C TECHNICIANS DISCOVERED ERRORS IN A TEST PROCEDURE | | THAT COULD HAVE RESULTED IN THE CALIBRATION FOR THE LEVEL INSTRUMENTATION | | FOR ALL FOUR ACCUMULATORS ON UNITS 1 AND 2 BEING IN ERROR. THIS COULD HAVE | | ALLOWED A SITUATION TO EXIST WHEREBY ACCUMULATOR LEVELS WERE NOT WITHIN | | REQUIRED TECHNICAL SPECIFICATION LIMITS. THE LICENSEE HAS DETERMINED | | THAT ALL CURRENT ACCUMULATOR LEVELS ARE WITHIN THE REQUIRED TECHNICAL | | SPECIFICATION VOLUME WHILE TAKING INTO ACCOUNT THE ERROR ASSOCIATED WITH | | EACH LEVEL INSTRUMENT. THE LICENSEE WILL RECALIBRATE EACH LEVEL INSTRUMENT | | TO INDICATE THE PROPER LEVEL. THE LICENSEE IS INVESTIGATING THIS SITUATION | | AND PLANS TO REVISE THE CALIBRATION TEST PROCEDURE, AS NECESSARY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+