U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/05/94 - 04/06/94 ** EVENT NUMBERS ** 27041 27042 27043 27044 27045 27046 27047 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27041 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/05/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 07:26 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/05/94 | +------------------------------------------------+EVENT TIME: 04:51[EDT]| |NRC NOTIFIED BY: FRAN LUKACZYK |LAST UPDATE DATE: 04/05/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A REACTOR SCRAM ON GENERATOR LOAD REJECT WHEN BOTH | | GENERATOR OUTPUT BREAKERS OPENED. | | | | ONE OF TWO GENERATOR OUTPUT BREAKERS (R925) WAS BEING OPENED IN PREPARATION | | FOR MAINTENANCE. WHEN THE BREAKER OPENED, THE OTHER OUTPUT BREAKER (R915) | | TRIPPED CAUSING A GENERATOR LOAD REJECT AND REACTOR SCRAM. ALL CONTROL RODS | | FULLY INSERTED WITH ALL SYSTEMS FUNCTIONING AS DESIGNED. HPCI INITIATED ON | | LOW REACTOR WATER LEVEL (+53 IN) DUE TO THE PLANT TRANSIENT. THE LOWEST | | REACTOR WATER LEVEL OBSERVED WAS +34 INCHES. THE PLANT IS CURRENTLY STABLE | | WITH DECAY HEAT BEING REJECTED VIA THE STEAM BYPASS VALVES TO THE CONDENSER | | AND THE RWCU SYSTEM. THE CAUSE OF THE GENERATOR OUTPUT BREAKER TRIP IS | | UNKNOWN AND UNDER INVESTIGATION. UNIT 1 WILL NOT RESTART FOR APPROX 5-9 | | DAYS DUE TO OTHER OUTAGE WORK. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27042 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/05/94 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 11:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/04/94 | +------------------------------------------------+EVENT TIME: 14:23[CDT]| |NRC NOTIFIED BY: NEIL HARRIS |LAST UPDATE DATE: 04/05/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 73 POWER OPERATION | 73 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTRACT SECURITY GUARD CONFIRMED POSITIVE FOR RANDOM DRUG TEST GIVEN ON | | 3/22/94. COMPENSATORY MEASURES TAKEN. SEE HOO LOG FOR DETAILS. THE LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27043 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/05/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:23 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/05/94 | +------------------------------------------------+EVENT TIME: 15:50[EDT]| |NRC NOTIFIED BY: GEORGE VOIFHNIS |LAST UPDATE DATE: 04/06/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM FOLLOWING HIGH REACTOR WATER LEVEL TRANSIENT. | | | | WHILE OPERATING AT FULL POWER, THE PLANT EXPERIENCED A REACTOR WATER LEVEL | | TRANSIENT WHICH RESULTED IN A TURBINE TRIP FOLLOWED BY A REACTOR SCRAM. ALL | | RODS FULLY INSERTED. THE REACTOR IS STABLE AT 930 PSI WITH A WATER LEVEL OF | | 150 INCHES. DECAY HEAT IS BEING DISCHARGED TO THE CONDENSER. FEED IS BEING | | SUPPLIED BY A SINGLE FEEDPUMP. NO SAFETY RELIEF VALVES LIFTED DURING THE | | TRANSIENT. ALL SYSTEMS FUNCTIONED AS REQUIRED. THE CAUSE OF THE WATER LEVEL | | TRANSIENT IS STILL UNDER INVESTIGATION. | | | | THE REACTOR WAS OPERATING IN THE NORMAL WATER LEVEL BAND OF 155 TO 165 | | INCHES WHEN WATER LEVEL STARTED TO INCREASE. WHEN LEVEL REACHED 175 INCHES | | AN AUTOMATIC TRIP OF THE TURBINE OCCURRED FOLLOWED BY AN AUTOMATIC REACTOR | | SCRAM. WATER LEVEL CONTINUED TO INCREASE TO 190 INCHES AT WHICH POINT ALL | | REACTOR FEEDPUMPS WERE PROCEDURALLY STOPPED. THE WATER LEVEL TRANSIENT WAS | | STABILIZED AND BROUGHT BACK TO THE NORMAL RANGE. | | | | THE CAUSE OF THE LEVEL TRANSIENT IS STILL NOT KNOWN. THE LICENSEE NOTES | | THAT THE RECIRCULATION PUMPS TRIPPED DURING THE TRANSIENT. THE CAUSE OF THE | | RECIRC PUMP TRIP IS SPECULATED TO BE FROM A HIGH PRESSURE SPIKE WHEN THE | | TURBINE TRIPPED. NOTHING ELSE UNUSUAL OR NOT UNDERSTOOD OCCURRED DURING THE | | TRANSIENT. THE LICENSEE IS PROCEEDING TO COLD SHUTDOWN PRIOR TO RESTARTING | | THE RECIRCULATION PUMPS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | *** UPDATE DATE/TIME:4/6/94 @ 0400 EDT BY:McGINTY *** | | DURING THE MORNING STATUS CALL, THE LICENSEE SAID THAT THE CAUSE OF THE | | WATER LEVEL TRANSIENT WAS THE DENSITY COMPENSATION TO THE STEAM FLOW | | ELEMENTS, WHICH FAILED UPSCALE. THIS CAUSED THE REACTOR WATER PUMPS TO GO | | INTO FULL RUNOUT, AND THE SUBSEQUENT LEVEL INCREASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT SAINT VRAIN REGION: 4 |NOTIFICATION DATE: 04/05/94 | |UNIT: [1] [ ] [ ] STATE: CO |NOTIFICATION TIME: 16:36 [ET]| |RX TYPE: [1] GA (GENERAL ATOMIC) |EVENT DATE: 04/04/94 | +------------------------------------------------+EVENT TIME: 14:00[MDT]| |NRC NOTIFIED BY: JOHN HACK |LAST UPDATE DATE: 04/05/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FOUR HOUR NON-EMERGENCY REPORT BECAUSE OF OFFSITE NOTIFICATION OF HIGH PH | | IN A WASTE WATER DITCH. | | | | THE FACILITY REPORTED A HIGH PH IN A WASTE WATER DITCH. THE LICENSEE | | NOTIFIED THE COLORADO DEPARTMENT OF HEALTH. THE HIGH PH WAS FIRST NOTED ON | | 4/4/94 AT APPROXIMATELY 1400 MDT. REGION IV WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27045 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/05/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/05/94 | +------------------------------------------------+EVENT TIME: 16:16[EDT]| |NRC NOTIFIED BY: JESSIE PIKE |LAST UPDATE DATE: 04/05/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ISOLATED PRESSURE TRANSMITTER CAUSED A LOSS OF THE "A" RHR SHUTDOWN | | COOLING LOOP. | | | | THE RHR "A" SHUTDOWN COOLING LOOP RECEIVED AN ISOLATION SIGNAL FROM THE | | NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM (NSSSS). THE SIGNAL WAS GENERATED BY | | AN ISOLATED PRESSURE DETECTOR. RHR LOOP "A" WAS RESTORED AT 1701, HAVING | | BEEN ISOLATED FOR APPROXIMATELY 45 MINUTES. REACTOR COOLANT SYSTEM | | TEMPERATURE ROSE FROM 95F TO 97F DURING THIS TIME. | | | | THE LICENSEE IS SPECULATING THAT AN ISOLATED PRESSURE DETECTOR SENSED AN | | INCREASED PRESSURE WHEN AMBIENT TEMPERATURE INCREASED, AND WHEN PRESSURE | | REACHED THE ISOLATION SET POINT, THE RHR SYSTEM ISOLATED. THE PRESSURE | | DETECTOR WAS ISOLATED FOR MAINTENANCE AT THE BEGINNING OF THIS EVENT. | | | | THE LICENSEE VENTED OFF THE PRESSURE DETECTOR, CLEARING THE HIGH PRESSURE | | SIGNAL. SHUTDOWN COOLING WAS THEN RESTORED. | | | | THE RESIDENT INSPECTOR AND LOWER ALLOWAYS CREEK TOWNSHIP WERE INFORMED. | | | | ***UPDATE FROM RIDDLE TO WEAVER AT 2134EDT ON 4/5/94*** | | | | LICENSEE STATED THAT A SECOND ISOLATION WAS RECEIVED WHILE THE ORIGINAL | | REPORT WAS BEING MADE. AFTER VENTING OFF THE PRESSURE DETECTOR, THE | | LICENSEE FAILED TO RESET THE NSSSS SIGNAL. WHEN THE ISOLATION BYPASS | | SWITCHES WERE TAKEN OUT OF BYPASS, A SECOND ISOLATION WAS RECEIVED. | | SHUTDOWN COOLING WAS RESTORED IN APPROXIMATELY FOUR MINUTES, WITH NO | | APPRECIABLE CHANGE IN REACTOR COOLANT SYSTEM TEMPERATURE. | | | | THE RESIDENT INSPECTOR AND THE REGION I DUTY OFFICER WERE INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27046 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/05/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/05/94 | +------------------------------------------------+EVENT TIME: 15:39[CDT]| |NRC NOTIFIED BY: RALPH RICHARD |LAST UPDATE DATE: 04/06/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |ROBERT CAPRA EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP WITH STUCK ROD FOLLOWING A MAIN TRANSFORMER FAULT. | | | | THE FACSIMILE OF THE EVENT REPORT READS AS FOLLOWS: | | "UNIT 2 RECEIVED A MAIN TRANSFORMER DIFFERENTIAL CURRENT GENERATOR TRIP | | CAUSING A TURBINE TRIP/REACTOR TRIP ABOVE P-8. ALL SYSTEMS RESPONDED AS | | EXPECTED EXCEPT WE HAVE INDICATION OF ONE ROD STUCK OUT AT 210 STEPS(K2). | | ALL ACTIONS AS REQUIRED PER EMERGENCY PROCEDURES ARE COMPLETE. | | INVESTIGATION OF MAIN TRANSFORMER "2E" SHOWS MINIMAL OIL LEAKAGE. ACTIONS | | PER BWRP 750-8 (OIL SPILL PREVENTION AND CONTROL COUNTERMEASURE PLANS) ARE | | IN PROGRESS." | | | | THE REACTOR IS STABLE AT 557 DEGREES AND 2235 PSI. DECAY HEAT IS BEING | | DISCHARGED TO THE MAIN CONDENSER. FEEDWATER IS BEING SUPPLIED WITH A | | STARTUP FEEDWATER PUMP. NO PRIMARY OR SECONDARY SAFETIES LIFTED DURING THE | | TRANSIENT. THE MAIN TRANSFORMER FAULT CAUSED AN ACTUATION OF THE FIRE | | PROTECTION WATER SYSTEM. NO ACTUAL FIRE WAS OBSERVED ON THE TRANSFORMER BUT | | SOME SMOKE AND STEAM WAS SEEN. A LIGHT OIL SHEEN ON THE OUTSIDE OF THE | | TRANSFORMER CASING INDICATES THE THE TRANSFORMER RELIEF VALVE MAY HAVE | | LIFTED. OTHER THAN ALREADY DESCRIBED, NOTHING UNUSUAL OR NOT UNDERSTOOD | | OCCURRED DURING THE TRANSIENT. | | | | THE APPARENT STUCK ROD WAS AT 231 STEPS BEFORE THE TRIP. AFTER THE TRIP IT | | WAS INDICATING 210 STEPS ON THE DIGITAL ROD POSITION INDICATION (DRPI) | | SYSTEM. THE LICENSEE HAS NOT YET INDEPENDENTLY CONFIRMED THAT THE ROD IS | | ACTUALLY STUCK. | | | | THE LICENSEE IS REMAINING IN MODE 3 WHILE THEY ASSESS THE SITUATION AND | | DETERMINE A COURSE OF ACTION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | *** UPDATE DATE/TIME:04/06/94 @ 1630 EDT BY:McGINTY *** | | ROD "K2" HAS BEEN CONFIRMED TO BE STUCK AT 210 STEPS. THE LICENSEE | | PERFORMED A SPECIAL TEST TONIGHT WHERE THEY DRIVE THE ROD IN 5 STEPS, FOR | | WHICH THE ROD INDICATION DID NOT MOVE. THEN, THE OPERATORS PULLED THE ROD | | OUT FOR 5 STEPS, AND IT DID MOVE OUT. UPON TRIPPING THE RX TRIP BREAKERS, | | THE ROD ENDED UP AT THE SAME 210 STEP POSITION. THERE APPEARS TO BE SOME | | KIND OF MECHANICAL BINDING, AND THE LICENSEE SAID ANYTHING BEYOND THAT | | WOULD BE SPECULATION AT THIS TIME. THE EXACT COURSE OF ACTION IS YET TO BE | | DETERMINED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27047 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/06/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 05:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/06/94 | +------------------------------------------------+EVENT TIME: 01:54[CDT]| |NRC NOTIFIED BY: BOYLE |LAST UPDATE DATE: 04/06/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF 230 KV LINE TO EXXON STATION CAUSED SEVERAL ESF ACTUATIONS | | (POSSIBLY WILL BE CONSIDERED INVALID) | | | | THIS NOTIFICATION IS BEING MADE AS A CONSERVATIVE MEASURE, PENDING RESULTS | | OF AN ENGINEERING INVESTIGATION. | | | | AT 0154 CDT, A VOLTAGE TRANSIENT OCCURRED DUE TO THE LOSS OF A 230 KV | | OFF-SITE LINE (TO EXXON STATION). PLANT RESPONSE RESULTED IN: | | - A HALF MSIV ISOLATION | | - BOTH STANDBY GAS TREATMENT SYSTEMS STARTED | | - ANNULUS MIXING SYSTEM STARTED | | - FUEL BUILDING FILTER TRAIN "B" STARTED ("A" WAS OUT OF SERVICE) | | - DIV. 2 CONTROL BUILDING VENTILATION AUTO-STARTED | | - BOTH RWCU PUMPS TRIPPED, WITH NO ISOLATIONS ON ANY RWCU VALVE | | - FUEL BUILDING AND AUXILIARY BUILDING DIV. 2 DAMPERS ISOLATED | | | | ENGINEERING IS INVESTIGATING WHAT HAPPENED. THE LICENSEE DID NOT LOSE | | POWER TO ANYTHING THAT STAYED OUT. THE PLANT IS OPERATING SMOOTHLY AT THIS | | TIME WITH NOTHING ABNORMAL. ALL OF THE ABOVE EQUIPMENT HAS BEEN RETURNED | | TO A STANDBY STATUS. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+