U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/30/97 - 07/31/97 ** EVENT NUMBERS ** 32695 32699 32700 32701 32702 32703 32704 32705 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32695 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 02:10[CDT]| |NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 07/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO INOPERABLE PRIMARY CONTAINMENT - | | | | AT 0210 CDT, DURING THE PERFORMANCE OF A DRYWELL TO TORUS (SUPPRESSION | | CHAMBER) VACUUM BREAKER OPERATION SURVEILLANCE TEST, VACUUM BREAKER | | #PC-AO-NRV 28 FAILED TO GIVE AN INDICATED CLOSED SIGNAL AFTER BEING CYCLED. | | PER THE TEST ACCEPTANCE CRITERIA, A DRYWELL TO SUPPRESSION CHAMBER LEAKAGE | | SURVEILLANCE TEST IS REQUIRED TO BE PERFORMED IN ORDER TO DEMONSTRATE THAT | | THE VACUUM BREAKER IS CLOSED. THE VACUUM BREAKER WAS DECLARED INOPERABLE, | | AND TROUBLESHOOTING WAS PERFORMED WITHOUT A CHANGE TO THE INDICATED | | POSITION. | | | | TECH SPEC 3.7.A.4.a REQUIRES THAT ALL DRYWELL TO SUPPRESSION CHAMBER VACUUM | | BREAKERS BE POSITIONED IN THE FULLY CLOSED POSITION AS INDICATED BY THE | | POSITION INDICATING SYSTEM. IF THIS IS NOT THE CASE, THE TOTAL LEAKAGE | | BETWEEN THE DRYWELL AND SUPPRESSION CHAMBER IS REQUIRED TO BE LESS THAN | | THE EQUIVALENT LEAKAGE THROUGH A ONE-INCH DIAMETER ORIFICE. | | | | AT 0835 CDT, IT WAS DETERMINED THAT THE LEAKAGE TEST ACCEPTANCE CRITERIA | | HAD NOT BEEN MET, AND THE PRIMARY CONTAINMENT WAS DECLARED INOPERABLE. AT | | 0950 CDT, A PLANT SHUTDOWN REQUIRED BY TECH SPEC 1.0.J WAS INITIATED. THE | | PLANT IS REQUIRED TO BE IN HOT SHUTDOWN WITHIN 6 HOURS AND COLD SHUTDOWN | | WITHIN THE FOLLOWING 30 HOURS. | | | | THE LICENSEE PLANS TO PLACE THE PLANT IN COLD SHUTDOWN WITHIN 24 HOURS, | | DE-INERT THE CONTAINMENT, AND REPAIR THE VACUUM BREAKER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1633 ON 07/29/97, FROM FRED SCHIZAS ENTERED BY JOLLIFFE * * | | | | AT 1412 CDT, CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE REACTOR FROM 30% | | POWER IN ACCORDANCE WITH A NORMAL PLANT SHUTDOWN EVOLUTION. ALL CONTROL | | RODS INSERTED COMPLETELY. PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 | | (EMERGENCY CORE COOLING SYSTEMS), GROUP 3 (REACTOR WATER CLEANUP SYSTEM), | | AND GROUP 5 (STANDBY GAS TREATMENT SYSTEM) ACTUATED AS EXPECTED. | | | | AT 1419 CDT, ALL SYSTEMS WERE RESET TO NORMAL. | | | | THE PLANT IS CURRENTLY STABLE IN CONDITION 3 (HOT SHUTDOWN). DECAY HEAT | | STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A | | PRESS RELEASE. THE OPERATIONS OFFICER NOTIFIED THE R4DO (CHUCK CAIN). | | | | * * * UPDATE AT 1630 ON 07/30/97, FROM BILL GREEN ENTERED BY JOLLIFFE * * | | | | AT 0414 CDT ON 07/30/97, THE PLANT WAS PLACED IN A COLD SHUTDOWN CONDITION | | TO ALLOW FOR PRIMARY CONTAINMENT ENTRY TO VISUALLY INSPECT VACUUM BREAKER | | PC-AO-NRV 28, WHICH HAS BEEN SUBSEQUENTLY CONFIRMED TO BE NOT FULLY CLOSED. | | A VISUAL INSPECTION OF THE REMAINING 11 DRYWELL TO TORUS VACUUM BREAKERS | | DETERMINED THAT VACUUM BREAKERS PC-AO-NRV 21, 25, AND 27 MAY NOT BE FULLY | | SEATED. THIS DETERMINATION WAS MADE QUALITATIVELY BY OBSERVING AIR FLOW | | AROUND THE SEALS EVEN THOUGH THE VACUUM BREAKERS INDICATE AND APPEAR TO BE | | CLOSED. | | | | THE LICENSEE IS CURRENTLY EVALUATING THE CONDITION OF THE FOUR VACUUM | | BREAKERS AND DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED THE R4DO (LARRY YANDELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32699 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/30/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 10:15 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/31/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: RICHARD SWEENEY |LAST UPDATE DATE: 07/30/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF AN ADDITIONAL INVERTER TRIP SIGNAL FOLLOWING WHAT WAS BELIEVED | | TO BE A LIKE-FOR-LIKE CHANGEOUT | | | | THE 'A' SIDE INVERTERS WHICH SUPPLY 120-VOLT VITAL BUSES WERE REPLACED | | DURING THE LAST REFUELING OUTAGE, AND, AT THAT TIME THE CIRCUITRY FOR THE | | REPLACEMENT INVERTERS WAS BELIEVED TO BE A LIKE-FOR-LIKE CHANGEOUT. | | HOWEVER, DURING A PRECURSOR CARD REVIEW, IT WAS DETERMINED THAT THE NEW | | INVERTERS WERE NOT A LIKE-FOR-LIKE CHANGEOUT. AN ADDITIONAL TRIP CIRCUIT | | WAS DISCOVERED TO HAVE BEEN INSTALLED IN THE NEW INVERTERS, AND THIS PLACES | | THE UNIT IN AN UNANALYZED CONDITION. | | | | THE ADDITIONAL INPUT TRIP SIGNAL TO THE INVERTERS SENSES STATION BATTERY | | INPUT VOLTAGE. IF THE VOLTAGE DECREASES TO 105 VOLTS, IT OPENS THE DC | | SUPPLY BREAKER TO THE INVERTER, AND IT APPEARS THAT IT WOULD SHUT THE | | INVERTER DOWN. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32700 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/30/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:33 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/30/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:48[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/30/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |WAYNE KROPP RDO | | DOCKET: 0707002 |JOHN HICKEY, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT JERMUSYK | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CLASSIFIED VIDEO TAPE FOUND IN NON-SECURED OFFICE FILE CABINET - | | | | AT 1348 ON 07/30/97, DURING NORMAL PLANT OPERATIONS, A CLASSIFIED VIDEO | | TAPE WAS FOUND IN A NON-SECURED FILE CABINET IN THE ACR-5 OFFICE AREA OF | | THE X-326 PROCESS BUILDING. THE VIDEO WAS PROPERLY LABELED "CONFIDENTIAL." | | | | IT WAS DETERMINED THAT THE POTENTIAL FOR COMPROMISE OF CONFIDENTIAL-NSI | | MATERIAL EXISTED. UPON DISCOVERY, THE VIDEO TAPE WAS PLACED IN A SECURE | | REPOSITORY. THE CAUSE OF THIS EVENT IS BEING INVESTIGATED. | | | | THIS EVENT WAS CLASSIFIED AS A NON-CFR ONE-HOUR REPORT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32701 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/30/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/30/97 | +------------------------------------------------+EVENT TIME: 11:47[EDT]| |NRC NOTIFIED BY: A. W. HARTNER |LAST UPDATE DATE: 07/30/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NON-RESPONSIVE FEED REG VALVES IN AUTO MODE DURING S/G LEVEL CHANGES - | | | | UNIT 1 IS IN MODE 3 (HOT STANDBY) IN A MAINTENANCE OUTAGE. | | | | FOLLOWING THE PERFORMANCE OF A TEST OF THE STEAM-DRIVEN AUXILIARY FEEDWATER | | PUMP, PLANT OPERATORS WERE RESTORING STEAM GENERATOR (S/G) LEVELS FROM | | APPROXIMATELY 50% NARROW RANGE TO THE NORMAL LEVEL OF 33%. THE 'A' AND 'C' | | S/G FEEDWATER REGULATING VALVES DID NOT RESPOND IN AUTOMATIC MODE AS LEVELS | | DECREASED. THE 'A' AND 'C' S/G FEEDWATER REGULATING VALVE CONTROLS WERE | | PLACED IN MANUAL CONTROL TO RESTORE S/G LEVELS TO NORMAL. | | | | THE MANUAL ADDITION OF FEEDWATER RESULTED IN A REACTOR COOLANT SYSTEM (RCS) | | COOLDOWN WHICH CAUSED THE ACTUATION OF THE P-12 SETPOINT (LOW-LOW Tave = | | 541øF). THIS ACTUATION CAUSED AN AUTOMATIC CLOSURE OF THE MAIN CONDENSER | | STEAM DUMP VALVES IN ORDER TO STOP THE RCS COOLDOWN. AT THE TIME OF THE | | ACTUATION, THE MAIN CONDENSER STEAM DUMP SYSTEM WAS NOT IN SERVICE, AND THE | | MAIN STEAM ISOLATION VALVES WERE SHUT. RCS TEMPERATURE WAS BEING | | CONTROLLED BY THE OPERATION OF THE RESIDUAL HEAT RELEASE VALVE TO | | ATMOSPHERE. PLANT OPERATORS TOOK MANUAL CONTROL TO CLOSE THE RESIDUAL HEAT | | RELEASE VALVE, SHUT THE S/G FEEDWATER REGULATING VALVES, ISOLATE THE S/G | | BLOWDOWN VALVES, AND MANUALLY ISOLATE RCS LETDOWN. RCS TEMPERATURE | | DECREASED TO APPROXIMATELY 538øF BEFORE BEING RESTORED TO NORMAL | | TEMPERATURE AT 547øF. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32702 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/30/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 00:44[EDT]| |NRC NOTIFIED BY: DICK BONNER |LAST UPDATE DATE: 07/30/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 OFFSITE POWER TO 4160VAC POWER SUPPLY TRAIN DUE TO A BLOWN FUSE- | | | | UNIT 2 IS DEFUELED IN MODE 6 IN A REFUELING OUTAGE. | | | | AT 0044 ON 07/29/97, WHILE SHIFTING THE 4160VAC BUS POWER SUPPLY FROM THE | | NORMAL STATION SERVICE TRANSFORMER TO THE RESERVE STATION SERVICE | | TRANSFORMER, A LOSS OF OFFSITE POWER TO ONE TRAIN OF THE 4160VAC POWER | | SUPPLY OCCURRED. THE CAUSE IS BELIEVED TO BE A BLOWN FUSE IN AN ENGINEERED | | SAFEGUARDS SYSTEM POWER SUPPLY. THE PLANT EMERGENCY DIESEL GENERATORS DID | | NOT START AS IS EXPECTED DURING THE PRESENT PLANT CONDITIONS. | | | | AT 0416 ON 07/29/97, OFFSITE POWER WAS RESTORED TO THE 4160VAC BUSES. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THIS EVENT AND | | DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32703 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 07/30/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:21 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 07/30/97 | +------------------------------------------------+EVENT TIME: 15:06[EDT]| |NRC NOTIFIED BY: DAVE SPENCE |LAST UPDATE DATE: 07/30/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILT SHYMLOCK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -AUTO Rx TRIP FROM 100% DUE TO MSIV CLOSURE; AFW PUMP TRIPPED ON OVERSPEED- | | | | AT 1506, THE 3B MAIN STEAM ISOLATION VALVE (MSIV) WENT CLOSED FOR UNKNOWN | | REASONS. THERE WERE NO TESTING OR MAINTENANCE ACTIVITIES OCCURRING AT THE | | TIME. THIS CAUSED THE REACTOR TO AUTOMATICALLY TRIP FROM 100% POWER DUE | | TO LEVEL IN THE 3B STEAM GENERATOR (S/G) REACHING THE LOW LEVEL SETPOINT OF | | 10% NARROW RANGE. ALL CONTROL RODS INSERTED COMPLETELY. THE AUXILIARY | | FEEDWATER (AFW) SYSTEM AUTOMATICALLY ACTUATED AS EXPECTED DUE TO THE LOW 3B | | S/G LEVEL SIGNAL. HOWEVER, FOLLOWING THE REACTOR TRIP, THE 'A' AFW PUMP | | TRIPPED DUE TO MECHANICAL OVERSPEED. | | | | ALL MSIVs ARE CURRENTLY CLOSED, AND SECONDARY STEAM IS BEING DUMPED TO THE | | ATMOSPHERE. NONE OF THE SAFETY OR RELIEF VALVES LIFTED, AND THERE IS NO | | RADIOACTIVITY BEING RELEASED TO THE ATMOSPHERE. WARM-UP STEAM IS BEING | | SUPPLIED FROM UNIT 4. UNIT 3 IS STABLE IN MODE 3 (HOT STANDBY) AT NORMAL | | TEMPERATURE AND PRESSURE. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSES OF THE 3B MSIV CLOSURE | | AND THE 'A' AFW PUMP OVERSPEED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32704 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/31/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:38 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 00:52[EDT]| |NRC NOTIFIED BY: MICHELLE SAVINO |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 Y 91 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR BLOWDOWN RADIATION MONITOR ACTUATION AND STEAM GENERATOR | | BLOWDOWN ISOLATION DUE TO HIGH ACTIVITY (COBALT) DURING POWER ASCENSION | | | | DURING A POWER ASCENSION, A STEAM GENERATOR BLOWDOWN RADIATION MONITOR | | TRIPPED ON HIGH ACTIVITY AND CAUSED STEAM GENERATOR BLOWDOWN VALVES TO | | ISOLATE. THE ALARM AND SETPOINT WERE RESET PER PLANT PROCEDURES, AND A | | MANUAL CHEMISTRY SAMPLE WAS TAKEN. THIS SAMPLE INDICATED AN INCREASE IN | | ACTIVITY, AND THE ISOTOPE CAUSING THE INCREASE WAS COBALT. THE LICENSEE | | STATED THAT SMALL AMOUNTS OF COBALT ARE EXPECTED WITH AN INCREASE IN | | REACTOR POWER AND THAT THIS WAS NOT AN INDICATION OF STEAM GENERATOR TUBE | | LEAKAGE. STEAM GENERATOR BLOWDOWN HAS BEEN RE-ESTABLISHED. ALL SYSTEMS | | FUNCTIONED AS REQUIRED, AND THERE WAS NOTHING THAT WAS UNUSUAL OR NOT | | UNDERSTOOD. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32705 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 07/31/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 05:56 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 03:55[CDT]| |NRC NOTIFIED BY: E. ROAN |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF SPDS AND OTHER COMPUTER FUNCTIONS | | | | DURING MAINTENANCE TO THE ALTERNATE POWER SUPPLY TO THE INVERTER FOR THE | | PLANT VAX COMPUTER, THE INVERTER TRIPPED, CAUSING A LOSS OF THE PLANT | | COMPUTER. THIS RESULTED IN THE LOSS OF SPDS (SAFETY PARAMETER DISPLAY | | SYSTEM), ERDS (EMERGENCY RESPONSE DISPLAY SYSTEM), ERIS (EMERGENCY RESPONSE | | INFORMATION SYSTEM), AND DRMS (DIGITAL RADIATION MONITOR SYSTEM). THE | | INVERTER HAS BEEN REENERGIZED, AND DRMS HAS BEEN RESTORED. THE LICENSEE IS | | WORKING TO RESTORE THE ERDS, SPDS AND ERIS FUNCTIONS. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+