U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/27/96 - 03/28/96 ** EVENT NUMBERS ** 30055 30095 30179 30180 30181 30182 30183 30184 30185 30186 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/01/96 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 21:24 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/01/96 | +------------------------------------------------+EVENT TIME: 18:40[MST]| |NRC NOTIFIED BY: BERT GRABO |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 | 0 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS FOUND CONDITIONS WHERE A FAILURE ON ONE TRAIN OF SAFETY | | EQUIPMENT WOULD AFFECT THE INDEPENDENT TRAIN. | | | | THE FOLLOWING NOTIFICATION WAS RECEIVED FROM THE LICENSEE: | | "CONTINUING REVIEW OF DEGRADED VOLTAGE CONDITIONS AT PALO VERDE NUCLEAR | | GENERATION STATION (PVNGS) IDENTIFIED A CONDITION THAT SHOWED PVNGS COULD | | BE OUTSIDE ITS DESIGN BASIS IN CERTAIN ACCIDENT SCENARIOS. THE POSTULATED | | ACCIDENT CONDITION IS A LIMITED RANGE OF MSLB BREAK SIZES, CONCURRENT WITH | | DEGRADED OFFSITE VOLTAGE CONDITIONS. NOTE: DEGRADED VOLTAGE CONDITIONS | | EXISTED FOR APPROXIMATELY SEVEN MINUTES DURING CALENDAR YEAR 1995. | | | | OUR DEGRADED VOLTAGE T.S. ACTION STATEMENT REQUIRES THAT A SINGLE TRAIN OF | | FBT (FAST BUS TRANSFER) BE BLOCKED WITHIN 1 HOUR WHICH RESTORES OPERABILITY | | OF THE OFFSITE POWER SOURCE TO ITS ASSOCIATED TRAIN. | | | | PVNGS HAS IDENTIFIED A SCENARIO WHEREIN IF THE A TRAIN IS BLOCKED, DEGRADED | | VOLTAGE CONDITIONS EXPERIENCED BY THE B TRAIN OF THE AFW SYSTEM MAY RESULT | | IN A COMPONENT FAILURE DURING THE DEGRADED VOLTAGE CONDITION (AFW FEED | | VALVES ARE UNABLE TO CLOSE) WHICH WILL IMPACT THE ABILITY TO ISOLATE THE | | FEEDWATER TO THE FAULTED GENERATOR. | | | | FAILURE OF THE B TRAIN OF AFW VALVES COULD RENDER THE A TRAIN AFW SYSTEM | | INOPERABLE DUE TO PREFERENTIAL FEEDING OF THE FAULTED S/G IN LIEU OF THE | | INTACT S/G. COMPENSATORY MEASURES ARE IN PLACE THAT SPECIFY BLOCKING BOTH | | TRAINS OF FBT AT THE ONSET OF DEGRADED VOLTAGE CONDITIONS. | | | | EXISTING T.S. ALLOW FOR PLACING EITHER TRAIN'S EDG ON ITS ASSOCIATED BUS | | AND DIVORCING THAT BUS FROM ITS OFFSITE SOURCE AND THEN UNBLOCKING FBT ON | | THAT SIDE. THIS ACTION ALLOWS MAINTENANCE OF FORCED CIRCULATION OF THE RCS | | POST TRIP." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1919 3/27/96 FROM ROBERSON TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE FOLLOWING IS TEXT OF A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "SINCE THE INITIAL REPORTABILITY DETERMINATION WAS MADE ON MARCH 1, 1996, | | NRA HAS REEVALUATED THE CONDITION AND DETERMINED THAT THE POTENTIAL AFW | | VALVE FAILURE IS A RESULT OF A PREVIOUSLY REPORTED DEGRADED GRID VOLTAGE | | CONDITION THAT ITSELF CONSTITUTED A CONDITION OUTSIDE OF THE DESIGN BASIS, | | AND NOT A SEPARATE REPORTABLE CONDITION. LER 528/93-011-00 AND LER | | 528/93-011-01 REPORTED POTENTIALLY SAFETY-RELATED EQUIPMENT PROBLEMS DUE TO | | DEGRADED GRID VOLTAGE. PLANS ARE IN PROGRESS TO SUBMIT AN UPDATED LET TO | | DESCRIBE ADDITIONAL INFORMATION RELATED TO DEGRADED GRID VOLTAGE ISSUES AND | | UPDATED CORRECTIVE ACTIONS. THEREFORE, THE ENS NOTIFICATION IS BEING | | RETRACTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. NOTIFIED | | R4DO (MURRRAY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30095 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: STOTTLER STARMER ASSOC. INC. |NOTIFICATION DATE: 03/11/96 | | CITY: ZEPHYR HILL REGION: 2 |NOTIFICATION TIME: 15:50 [ET]| | COUNTY: ORANGE STATE: FL |EVENT DATE: 03/04/96 | |LICENSE#: 825-02 AGREEMENT: Y |EVENT TIME: 20:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/27/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |POTTER RDO | | |JOHN GREEVES (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: PHILIP THOMA | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FLORIDA OFFICE OF RADIATION AND CONTROL FOR THE STATE OF FLORIDA WAS | | NOTIFIED BY THE STOTTLER STARMER ASSOC., INC., RADIATION SAFETY OFFICER | | THAT 4 TROXLER MOISTURE DENSITY GAUGES WERE STOLEN ON THE EVENING OF | | 03/04/96. THE FOLLOWING ADDITIONAL INFORMATION WAS REPORTED BY THE FLORIDA | | OFFICE OF RADIATION AND CONTROL: | | | | ON THE EVENING OF 03/04/96, AT ZEPHYR HILL, FLORIDA, SOMEONE CUT THROUGH A | | SECURITY FENCE, CUT A PADLOCK TO A STORAGE SHED, AND TOOK 4 TROXLER | | MOISTURE DENSITY GAUGES FROM THE SHED. THE SHED WAS LOCATED AT THE CORNER | | OF INTERSTATE 75 AND STATE HIGHWAY 54. THE MODEL NUMBERS OF THE TROXLER | | MOISTURE DENSITY GAUGES WERE ALL THE SAME (3440), AND THE SERIAL NUMBERS | | WERE 15190, 20212, 20971, AND 23039. THE GAUGES ALL CONTAINED 8 mCi OF | | Cs-137 AND 40 mCi OF Am-241. THE STATE OF FLORIDA INCIDENT NUMBER FOR THIS | | EVENT WAS FL-96-39. | | | | THE LOCAL POLICE DEPARTMENT WAS NOTIFIED OF THIS EVENT. (REFER TO THE HOO | | LOG FOR THE STOTTLER STARMER ASSOC., INC., MAILING ADDRESS IN CAPE | | CANAVERAL, FLORIDA, AND FOR A CONTACT NAME AND TELEPHONE NUMBER.) | | | | ***UPDATE ON 3/27/96 @ 07:05 FROM EAKINS TO GOULD*** THE FIVE GAUGES(FOUR | | REPORTED IN THIS EVENT AND ONE OTHER THAT WAS NOT REPORTED TO THE OPS | | CENTER) WERE FOUND INTACT ON THE SIDE OF I95 IN ST LUCIE COUNTY BY FLORIDA | | DOT ON 3/26/96. THE STATE OF FLORIDA WILL RETURN THE GAUGES TO THE OWNER. | | THE REG 2(BELISLE) AND NMSS(COOL) WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30179 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 03/27/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 02:16 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 01:35[EST]| |NRC NOTIFIED BY: PETERSON |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LEE SPESSARD EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |BAGWELL FEMA | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 81 POWER OPERATION | 81 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS SHUTTING THE PLANT DOWN DUE TO BOTH TRAINS OF THE EMERGENCY | | EQUIPMENT COOLING WATER (EECW) SYSTEM BEING INOPERABLE. | | | | A NOT-PREVIOUSLY CONSIDERED CONDITION WAS DISCOVERED, DURING A SERVICE | | WATER OPERATIONAL PERFORMANCE INSPECTION, WHICH COULD POTENTIALLY RENDER | | BOTH TRAINS OF THE EECW SYSTEM INOPERABLE. THE EECW SYSTEM HAS ONE MAKEUP | | TANK FOR EACH TRAIN TO PROVIDE MAKEUP WATER TO ACCOUNT FOR SYSTEM LEAKAGE. | | NITROGEN IS USED TO PRESSURIZE THE TANKS TO MAINTAIN SUFFICIENT SYSTEM | | PRESSURE FOR PROPER OPERATION. THE DEMINERALIZED WATER SYSTEM (WHICH | | PROVIDES MAKEUP WATER) AND THE NITROGEN SUPPLY SYSTEM ARE NOT SAFETY | | RELATED. | | | | IN THE EVENT OF AN ACCIDENT OR SEISMIC EVENT, NO CREDIT IS TAKEN FOR | | OPERATION OF THE DEMINERALIZED WATER OR NITROGEN SUPPLY SYSTEMS. THE EECW | | MAKEUP TANK IS ISOLATED FROM THESE SYSTEMS, BUT NITROGEN LEAKAGE FROM THE | | TANK THROUGH THE NITROGEN SUPPLY LINE, DEMINERALIZED WATER SUPPLY LINE, OR | | MAKEUP TANK RELIEF VALVES IS EXPECTED TO CAUSE MAKEUP TANK NITROGEN | | PRESSURE TO DECAY IN A SHORT AMOUNT OF TIME. WITH THE MAKEUP TANK | | DEPRESSURIZED, PRESSURE IN THE EECW TRAIN WILL FALL TO A LEVEL THAT PUMP | | CAVITATION AND/OR AIR BINDING COULD OCCUR. THIS CONDITION COULD AFFECT BOTH | | TRAINS OF EECW. THE UFSAR FAILURE MODES AND EFFECTS ANALYSIS FOR THE EECW | | SYSTEM DESCRIBES A FAILURE OF A SINGLE ISOLATION VALVE ON THE MAKEUP TANK | | OUTLET LINE THAT WOULD BOUND THIS FAILURE, BUT IT TAKES CREDIT FOR THE | | AVAILABILITY OF THE REMAINING TRAIN. IN THIS CASE, THE LOSS OF BOTH MAKEUP | | TANKS HAS NOT BEEN PREVIOUSLY ANALYZED. WITH BOTH TRAINS OF EECW BEING | | DECLARED INOPERABLE, THE PLANT ENTERED TS 3.0.3 @ 01:35 AND PREPARED FOR | | SHUTDOWN. THE UNUSUAL EVENT WAS DECLARED AT 02:12 WITH THE COMMENCEMENT OF | | SHUTDOWN. THE RI WILL BE INFORMED ALONG WITH STATE, LOCAL & OTHER AGENCIES. | | | | * * * UPDATE 1358 3/27/96 FROM SKLARCCYK TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1350 WHEN THE UNIT ENTERED COLD | | SHUTDOWN. THE REACTOR WAS MANUALLY SCRAMMED AT 0727. ALL CONTROL RODS | | FULLY INSERTED, AND ALL SYSTEMS FUNCTIONED AS EXPECTED. REACTOR VESSEL | | WATER LEVEL IS BEING MAINTAINED USING THE STARTUP LEVEL CONTROLLER WITH | | DECAY HEAT BEING EXHAUSTED TO THE MAIN CONDENSER. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. NOTIFIED R3DO (LANKSBURY), EO | | (SPESSARD), AND FEMA (CALDWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30180 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 03/27/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 09:30 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 05:21[CST]| |NRC NOTIFIED BY: CADE |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR WATER CLEANUP(RWCU) ISOLATION ON BOTH INBOARD AND | | OUTBOARD ISOLATION VALVES. | | | | THIS OCCURRED DURING AN EVOLUTION FOR TAGGING THE "B" RWCU FILTER WHEN THE | | RWCU ISOLATION OCCURRED ON A HIGH DELTA FLOW SIGNAL. THE LICENSEE THINKS | | THE ISOLATION WAS CAUSED BY SEVERAL VALVES IN THE SYSTEM DRIFTING OPEN | | PRIOR TO HAVING GAGS INSTALLED OR POSSIBLE LEAKAGE FROM ONE OF THE INLET | | VALVES TO THE FILTER THAT WAS GAGGED. THE LICENSEE IS STILL INVESTIGATING | | THE CAUSE, BUT THE LICENSEE KNOWS THAT ONE OF THESE TWO ITEMS CREATED THE | | FLOW PATH INTO THE SHUTDOWN FILTER RESULTING IN THE ISOLATION. THE RWCU IS | | STILL ISOLATED, AND THE LICENSEE IS IN THE PROCESS OF RESTORING THE SYSTEM | | TO NORMAL. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30181 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/27/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 09:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 09:03[EST]| |NRC NOTIFIED BY: TOM WALLACE |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 Y 30 POWER OPERATION | 3 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN DUE TO FAILURE OF A REACTOR COOLANT PUMP BREAKER TO CLOSE | | DURING THE TRANSFER OF THE PUMP FROM ITS START BUT TO ITS NORMAL POWER | | SUPPLY | | | | WITH UNIT 1 AT 30% REACTOR POWER, THE LICENSEE TRANSFERRED THE #3 REACTOR | | COOLANT PUMP FROM ITS START BUS TO THE UNIT STATION SERVICE TRANSFORMERS | | (THE NORMAL POWER SUPPLY) TO SUPPORT POWER ASCENSION TESTING. AT 0903, THE | | REACTOR COOLANT PUMP #3 BREAKER FAILED TO CLOSE, AND THE REACTOR COOLANT | | PUMP TRIPPED. AN ORDERLY PLANT SHUTDOWN WAS COMMENCED IN ACCORDANCE WITH | | ABNORMAL OPERATING INSTRUCTION #39. THE TURBINE WAS MANUALLY TRIPPED AT | | 0928, AND THE UNIT WAS STABILIZED AT 3% POWER (MODE 2) AT 0930. DURING THE | | UNIT SHUTDOWN, CONTROL ROOM OPERATORS MANUALLY INITIATED MOTOR-DRIVEN | | AUXILIARY FEEDWATER FLOW TO INCREASE STEAM GENERATOR WATER LEVELS. THERE | | WAS NO LOSS OF FEEDWATER FLOW. ALL EMERGENCY DIESEL GENERATORS AND | | ENGINEERED SAFEGUARDS FEATURE EQUIPMENT IS AVAILABLE IF REQUIRED. | | | | THE LICENSEE CURRENTLY PLANS TO MAINTAIN THE UNIT IN MODE 2 AND ATTEMPT TO | | RESTORE THE REACTOR COOLANT PUMP TO SERVICE. IF THE REACTOR COOLANT PUMP | | IS NOT RESTORED TO SERVICE BY 1503, THE LICENSEE PLANS TO PLACE THE UNIT IN | | MODE 3. ACTIONS ARE UNDERWAY TO INVESTIGATE THE REACTOR COOLANT PUMP | | BREAKER FAILURE TO CLOSE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30182 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/27/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:28 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 14:25[EST]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGGE 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 +------------------------------------------------------------------------------+ | 4160-VOLT BUS UNDERVOLTAGE REACTOR PROTECTION SYSTEM TRIP LOGIC DOES NOT | | MEET CHANNEL SEPARATION REQUIREMENTS | | | | DURING A DESIGN REVIEW, THE LICENSEE DETERMINED THAT A PLANT MODIFICATION | | TO INSTALL AN RPS TRIP ON 4160-VOLT UNDERVOLTAGE DOES NOT MEET PLANT DESIGN | | REQUIREMENTS; SPECIFICALLY, THE MODIFICATION DOES NOT MEET IEEE-279 | | SEPARATION CRITERIA. THE LICENSEE DISCOVERED THAT BOTH 'S1' AND 'S2' | | COMPONENTS WERE NOT ADEQUATELY SEPARATED IN ACCORDANCE WITH THE DESIGN | | CRITERIA. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30183 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 03/27/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:23 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 13:53[CST]| |NRC NOTIFIED BY: WASHKO |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANKSBURY 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS FULL SCRAM SIGNAL DURING CONTROL ROD DRIVE TESTING | | | | WHILE PERFORMING CONTROL ROD DRIVE TESTING, A FULL SCRAM SIGNAL WAS | | RECEIVED DUE TO A SPIKE ON THE 'H' INTERMEDIATE RANGE NEUTRON MONITOR | | CHANNEL. (RPS SHORTING LINKS WERE REMOVED, SO A TRIP OF ANY ONE OF THE | | EIGHT IRM CHANNELS WOULD CAUSE A FULL SCRAM SIGNAL.) ONE CONTROL ROD, | | WHICH WAS WITHDRAWN AT THE TIME OF THE SCRAM, INSERTED COMPLETELY. | | | | THE LICENSEE STATED THAT THE IRM SPIKE WAS SPURIOUS BECAUSE THE 'H' IRM | | MONITORS NEUTRON FLUX IN THE SOUTHEAST QUADRANT OF THE CORE, AND THE | | WITHDRAWN CONTROL ROD WAS LOCATED IN THE NORTHWEST QUADRANT. THE LICENSEE | | HAS BYPASSED THE 'H' IRM CHANNEL PENDING FURTHER INVESTIGATION OF THE | | SPURIOUS SIGNAL. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/27/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:05 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 14:46[CST]| |NRC NOTIFIED BY: KLIMEK |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANKSBURY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL SCRAM WITH ALL CONTROL RODS INSERTED INTO CORE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "WHILE PERFORMING AN IM SURVEILLANCE, DIS 1600-02, 'DRYWELL HIGH PRESSURE | | SCRAM AND CONTAINMENT ISOLATION SWITCHES,' THE NUCLEAR STATION OPERATOR | | DEPRESSED BOTH MANUAL SCRAM BUTTONS WHEN THE FIRST ALARMS WERE RECEIVED. | | ALL CONTROL RODS WERE FULLY INSERTED AND THE MODE SWITCH WAS IN REFUEL | | PRIOR TO THE EVENT. THE EVENT IS CONSIDERED TO BE A RESULT OF OPERATOR | | ERROR." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30185 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 03/27/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:16 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: ADAMSON |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELISLE 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER PUMP | | | | DURING PROTECTIVE RELAY TESTING ON THE ALTERNATE FEEDER BREAKER FOR | | 4160-VAC BUS '3C', A BUS LOCKOUT OCCURRED RESULTING IN THE TRIP OF THE '3B' | | STEAM GENERATOR FEEDWATER PUMP. AN AUTOMATIC MAIN TURBINE RUNBACK OCCURRED | | IN RESPONSE TO THE LOSS OF THE FEEDWATER PUMP. OPERATORS MANUALLY TRIPPED | | THE REACTOR DUE TO DECREASING STEAM GENERATOR WATER LEVELS AT APPROXIMATELY | | 25% NARROW RANGE LEVEL. ALL CONTROL RODS INSERTED FOLLOWING THE REACTOR | | TRIP, AND ALL SYSTEMS FUNCTIONED AS EXPECTED. THE AUXILIARY FEEDWATER | | SYSTEM AUTOMATICALLY ACTUATED DUE TO LOW STEAM GENERATOR WATER LEVELS. NO | | PRIMARY OR SECONDARY RELIEF VALVES LIFTED DURING THE EVENT. | | | | THE PLANT IS STABLE IN MODE 3 WITH DECAY HEAT BEING EXHAUSTED TO THE MAIN | | CONDENSER. THE LICENSEE INTENDS TO RESTART THE UNIT TOMORROW. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30186 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 03/27/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 21:58 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 03/27/96 | +------------------------------------------------+EVENT TIME: 20:00[CST]| |NRC NOTIFIED BY: BAILEY |LAST UPDATE DATE: 03/27/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANKSBURY RDO | |AFIR 50.72(b)(1)(vi) FIRE (ONSITE) | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE IN HEATER BAY | | | | THE ONSITE FIRE BRIGADE RESPONDED TO A FIRE IN THE UNIT 1 HEATER BAY. THE | | FIRE WAS LOCATED ON AN ACETYLENE LINE AND WAS EXTINGUISHED AFTER THE | | ACETYLENE BOTTLE WAS LOCATED AND ISOLATED. NO PERSONNEL WERE INJURED, AND | | NO SAFETY-RELATED EQUIPMENT WAS AFFECTED. THE LICENSEE REPORTED THAT THE | | FIRE WAS EXTINGUISHED WITHIN 14 MINUTES. (THE PLANT EMERGENCY PLAN | | REQUIRES A NOTIFICATION OF UNUSUAL EVENT FOR AN ONSITE FIRE LASTING GREATER | | THAN 15 MINUTES.) | | | | THE LICENSEE STATED THAT OFFSITE FIRE ASSISTANCE WAS CALLED BUT WAS NOT | | USED TO HELP EXTINGUISH THE FIRE. THE LICENSEE IS CURRENTLY INVESTIGATING | | THE CAUSE OF THE FIRE. NO PRESS RELEASE IS PLANNED AT THIS TIME. THE NRC | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+