U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/14/95 - 04/17/95 ** EVENT NUMBERS ** 28681 28682 28683 28684 28685 28686 28687 28688 28689 28690 28691 28692 28693 28694 28695 28696 28697 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28681 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 04/14/95 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 05:44 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/14/95 | +------------------------------------------------+EVENT TIME: 05:10[EDT]| |NRC NOTIFIED BY: BLESS |LAST UPDATE DATE: 04/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BRIAN SHERON EO | | |AUSTIN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED - FIRE IN THE AUX BUILDING VENTILATION SYSTEM | | | | A FIRE WAS REPORTED IN THE AUXILIARY BUILDING VENTILATION SYSTEM AT 0510. | | THE FIRE WAS ATTACKED IMMEDIATELY WITH PORTABLE CO2 EXTINGUISHERS. SEVERAL | | MINUTES LATER A FIRE HOSE WAS BROUGHT TO THE SCENE AND THE FIRE WAS | | DECLARED OUT AT 0529. THE UNUSUAL EVENT WAS DECLARED AT 0528. | | | | THE FIRE WAS CAUSED BY WELDING IN THE TURBINE BUILDING ON THE 12' LEVEL. | | THE FIRE WAS IN AN EXPANSION JOINT OF THE AUX BUILDING VENTILATION SYSTEM | | ON THE 5' LEVEL. THIS PART OF THE VENTILATION SYSTEM IS AT THE BOUNDARY OF | | THE TURBINE BUILDING AND THE AUX BUILDING. THE FIRE WAS OVERHAULED AT 0544 | | AND THE UNUSUAL EVENT WAS TERMINATED AT 0555. | | | | THE LICENSEE NOTIFIED THE THREE SURROUNDING COUNTIES AND THE MARYLAND STATE | | POLICE. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28682 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/14/95 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 08:50 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/14/95 | +------------------------------------------------+EVENT TIME: 08:20[EDT]| |NRC NOTIFIED BY: BURTON |LAST UPDATE DATE: 04/14/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 15 STARTUP | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT 0820, LICENSEE SHUT UNIT 3 DOWN FROM 15% AS A PLANNED EVOLUTION TO BEGIN | | A REFUELING OUTAGE. UNIT 3 IS STABLE IN MODE 3 (HOT SHUTDOWN). | | | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28683 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/14/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 09:58 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/14/95 | +------------------------------------------------+EVENT TIME: 08:55[EDT]| |NRC NOTIFIED BY: MIKE MCKENNEY |LAST UPDATE DATE: 04/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ISOLATION DUE TO OPERATOR ERROR | | | | GROUPS ONE THROUGH FIVE OF THE PRIMARY CONTAINMENT ISOLATION SYSTEM | | ISOLATED WHEN A POWER SUPPLY BREAKER WAS INADVERTENTLY OPENED. ALL GROUP | | 1,4 & 5 VALVES AS WELL AS SOME GROUP 2 & 3 VALVES WERE ALREADY IN THEIR | | ISOLATED CONDITION PRIOR TO THE ACTUATION. THE REMAINING GROUP 2 & 3 | | VALVES ISOLATED. DECAY HEAT WAS BEING REMOVED VIA SPENT FUEL POOL COOLING | | AND SHUTDOWN COOLING WAS NOT AFFECTED. | | | | THE POWER SUPPLY BREAKER HAS BEEN SHUT AND ALL SIGNALS HAVE BEEN RESET. THE | | APPROPRIATE VALVES HAVE BEEN REOPENED. THE LICENSEE INFORMED THE STATE AND | | THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28684 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/14/95 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 11:49 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/14/95 | +------------------------------------------------+EVENT TIME: 09:59[EDT]| |NRC NOTIFIED BY: COOK |LAST UPDATE DATE: 04/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP. | | | | THE TURBINE GENERATOR TRIPPED DUE TO LOSS OF EXCITATION, BUT ITS CAUSE IS | | UNKNOWN AND BEING INVESTIGATED. ALL RODS FULLY INSERTED AND THERE WAS NO | | ECCS INJECTION. THE MAIN STEAM RELIEF VALVES LIFTED AS EXPECTED, BUT ONE | | DID STAY OPEN AFTER THE OTHERS RESEATED. IT DID FINALLY RESEAT AFTER | | PRESSURE HAD REDUCED. THE CONDENSER IS BEING USED FOR THE HEAT SINK. THE RI | | WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28685 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CROW BUTTE RESOURCES |NOTIFICATION DATE: 04/14/95 | | CITY: CRAWFORD REGION: 4 |NOTIFICATION TIME: 13:07 [ET]| | COUNTY: STATE: NE |EVENT DATE: 04/13/95 | |LICENSE#: SUA1534 AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 04/14/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ELMO COLLINS RDO | | |BRACH EO | +------------------------------------------------+BANGART SP | |NRC NOTIFIED BY: KNODE | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT WATER SAMPLES TAKEN FROM ONE OF THEIR SHALLOW | | MONITOR WELLS(#SM4-2) AT THEIR IN-SITU MINE EXCEEDED THEIR LIMITS. | | | | THE WATER QUALITY OF THE SAMPLE TAKEN FROM THE WELL EXCEEDED THE UPPER | | CONTROL LIMITS FOR TWO OF THE FIVE PARAMETERS, HOWEVER THE WATER QUALITY | | INDICATORS ARE STILL WITHIN DRINKING WATER STANDARDS. | | | | LIMIT MEASURED | | | | 4/12/95 4/13/95 | | SODIUM 117 MG/LITER 120 MG/LITER 146 MG/LITER | | | | | | ALKALINITY 126 MG/LITER 137 MG/LITER 146 MG/LITER | | | | | | | | THE ABOVE LIMITS ARE USED WHEN TWO PARAMETERS HAVE BEEN EXCEEDED. | | | | THE LICENSEE NOTIFIED THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY AS | | PER THEIR LICENSEE CONDITION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28686 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/15/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 01:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/15/95 | +------------------------------------------------+EVENT TIME: 00:30[EDT]| |NRC NOTIFIED BY: CROKE |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WHITE 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY-RELATED 125 VOLT DC BATTERY FAILED LOAD TEST. | | | | WHILE PERFORMING A LOAD PROFILE TEST OF THE "B" 125 VDC BATTERY, A LOW CELL | | VOLTAGE ALARM WAS RECEIVED AFTER APPROXIMATELY 1 MINUTE. THE TEST WAS | | IMMEDIATELY TERMINATED. DURING VISUAL INSPECTION OF THE BATTERIES, | | TECHNICIANS DISCOVERED THAT THE INNER TIER CONNECTION PLATE FOR THE | | POSITIVE TERMINAL OF CELL #11 WAS LOOSE. (THE TWO BOLTS WHICH ATTACH THE | | PLATE TO THE BATTERY TERMINAL WERE ONLY FINGER-TIGHT.) THE LICENSEE STATED | | THAT BECAUSE OF THE LOOSE CONNECTION, THE BATTERY WOULD HAVE BEEN UNABLE TO | | PROVIDE THE REQUIRED CURRENT SPECIFIED IN THE FIRST MINUTE OF THE LOAD | | PROFILE. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE LOOSE CONNECTION. | | THE "A" BATTERY WAS TESTED SATISFACTORILY APPROXIMATELY 2 WEEKS AGO, AND | | THE "B" BATTERY TESTED SATISFACTORILY DURING THE LAST LOAD PROFILE TEST | | PERFORMED IN 1993. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28687 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/15/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 04:28 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/15/95 | +------------------------------------------------+EVENT TIME: 01:08[CDT]| |NRC NOTIFIED BY: REIS |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLAYTON 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT SYSTEM ACTUATIONS AND REACTOR BUILDING VENTILATION | | ISOLATIONS DURING TESTING. | | | | DURING THE PERFORMANCE OF LES-PC-209, "UNIT 2 PCCW & RBCCW CR 2 ISOLATION | | LOGIC SYSTEM FUNCTIONAL TEST", AN INCORRECT FUSE WAS INADVERTENTLY PULLED, | | RESULTING IN AN AUTOSTART OF THE UNIT 1 & UNIT 2 STANDBY GAS TREATMENT | | SYSTEM (SBGT) TRAINS, AND UNIT 1 AND 2 REACTOR BUILDING VENTILATION | | ISOLATIONS. IN ADDITION UNIT 2 CONTAINMENT MONITORING, REACTOR | | RECIRCULATION HPU (HYDRAULIC POWER UNIT), AND TIP PURGE ISOLATIONS WERE | | RECEIVED. | | | | THE FUSE WAS IMMEDIATELY REPLACED AND THE ISOLATIONS WERE RESET. THE UNIT | | 1 AND 2 SBGT TRAINS WERE SECURED. JUMPERS WERE INSTALLED IN THE UNIT 1 | | MSIV STEAM TUNNEL DIFFERENTIAL TEMPERATURE ISOLATION LOGIC TO PREVENT A | | MSIV ISOLATION AS THE VENTILATION SYSTEM WAS RESTORED. THE UNIT ENTERED A | | 1 HOUR TECHNICAL SPECIFICATION LCO DUE TO THE BYPASS OF THE ISOLATION | | LOGIC. THE REACTOR WATER CLEANUP (RWCU) SYSTEM ROOM DIFFERENTIAL | | TEMPERATURE ISOLATION WAS SIMILARLY BYPASSED, AND A 1 HOUR LCO WAS ENTERED. | | | | THE UNIT 1 REACTOR BUILDING VENTILATION WAS RESTARTED, AND THE MSIV AND | | RWCU DIFFERENTIAL TEMPERATURE BYPASS JUMPERS WERE REMOVED. THE UNIT 2 | | REACTOR BUILDING VENTILATION SYSTEM WAS ALSO RESTARTED. THE LICENSEE | | STATED THAT SINCE UNIT 2 IS IN REFUELING, THE OTHER AFFECTED SYSTEMS WERE | | RESTORED ONLY TO THE EXTENT DEEMED NECESSARY. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28688 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/15/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 07:11 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/15/95 | +------------------------------------------------+EVENT TIME: 02:30[CDT]| |NRC NOTIFIED BY: REIS |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLAYTON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF STANDBY LIQUID CONTROL (SBLC) SYSTEM DECLARED INOPERABLE. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 0230 ON 4/15/95 WHILE STARTING THE 2A RHR PUMP, THE "0" D/G COOLING | | WATER PUMP FAILED TO AUTO-START. THIS RENDERED THE "O" D/G INOPERABLE FOR | | BOTH UNIT 1 AND 2. AT THE TIME OF THE EVENT, THE 1B SBLC PUMP WAS | | INOPERABLE (DUE TO AN INOPERABLE RELIEF VALVE). WITH THE LOSS OF THE | | REDUNDANT EQUIPMENT'S EMERGENCY POWER SUPPLY, THE 1A SBLC PUMP WAS ALSO | | DECLARED INOPERABLE. THE LOSS OF BOTH UNIT 1 SBLC PUMPS WAS INTERPRETED AS | | A LOSS OF A SAFETY FUNCTION, RESULTING IN A 4 HOUR NOTIFICATION. | | | | AT 0450 ON 4/15/95, THE "0" D/G CWP & "0" D/G WERE BOTH DETERMINED TO BE | | OPERABLE FOR UNIT 1. ACCORDINGLY THE 1A SBLC PUMP WAS DECLARED OPERABLE. | | ALSO, THE LOSS OF THE "0" D/G CWP RESULTED IN THE LOSS OF THE UNIT 1 RCIC | | SYSTEM, ALSO A LOSS OF THE SAFE SHUTDOWN CAPABILITY." | | | | THE LICENSEE IS STILL INVESTIGATING THE REASON THAT THE "0" EMERGENCY | | DIESEL GENERATOR COOLING WATER PUMP DID NOT AUTOMATICALLY START WHEN GIVEN | | A SIGNAL FROM UNIT 2, AND THE EDG REMAINS INOPERABLE WITH RESPECT TO THAT | | UNIT. THE UNIT 1 RCIC SYSTEM AREA ROOM COOLER IS SUPPLIED BY THE "0" EDG | | COOLING WATER PUMP, HENCE THE INOPERABILITY OF THE RCIC SYSTEM DUE TO THE | | INOPERABILITY OF THE "0" EDG COOLING WATER PUMP. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28689 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/15/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 08:58 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/15/95 | +------------------------------------------------+EVENT TIME: 04:56[CDT]| |NRC NOTIFIED BY: REIS |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALTERNATE ROD INSERTION SIGNAL FOLLOWED BY SCRAM SIGNAL DURING MAINTENANCE. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON 4/15/95 AT 0455, WHILE INSTRUMENT MAINTENANCE WAS WORKING ON THE POWER | | SUPPLIES FOR THE UNIT 2 ALTERNATE ROD INSERTION (ARI) SYSTEM UNDER A WORK | | REQUEST. THE "A" AND "C" CHANNELS FOR REACTOR WATER LEVEL AND PRESSURE | | WERE INADVERTENTLY ACTUATED. THIS ARI ACTUATION RESULTED IN THE SCRAM AIR | | HEADER DEPRESSURIZING. ACCORDINGLY, THE SCRAM INLET AND OUTLET VALVES | | OPENED AND THE SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES CLOSED. | | WITH THE REPOSITIONING OF THE AFOREMENTIONED VALVES, THE SDV BEGAN FILLING | | WITH WATER. AT 0456 A FULL SCRAM SIGNAL WAS RECEIVED ON HIGH SDV LEVEL. AT | | THE TIME OF THE RPS ACTUATION, ALL CONTROL RODS WERE ALREADY FULLY | | INSERTED. | | | | INSTRUMENT MAINTENANCE WAS NOTIFIED TO RESTORE THE ARI SYSTEM BACK TO | | NORMAL. UPON RESTORATION, THE ARI SIGNAL WAS RESET, AND AT 0517 ON 4/15/95 | | THE SCRAM WAS RESET. THE CAUSE OF THE ARI ACTUATION IS PRESENTLY UNDER | | INVESTIGATION. AT THE TIME OF THE EVENT, UNIT 2 WAS IN REFUEL." | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28690 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/15/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 12:13 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/15/95 | +------------------------------------------------+EVENT TIME: 09:07[EDT]| |NRC NOTIFIED BY: ROLAND |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM FOLLOWING A TURBINE TRIP DUE TO TURBINE | | CONTROL VALVE FAST CLOSURE SIGNAL. | | | | THE TURBINE CONTROL VALVE FAST CLOSURE SIGNAL OCCURRED WHILE THEY WERE | | OPENING 1 OF 2 OUTPUT SYNC BREAKERS AND WAS CAUSED BY A LOAD REJECT. THE | | CAUSE OF THE LOAD REJECT IS UNKNOWN AT THIS TIME AND IS BEING INVESTIGATED. | | ALL RODS FULLY INSERTED AND THERE WAS NO ECCS INJECTION. THEY DID RECEIVE | | 13" LEVEL ISOLATIONS AND LEVEL WAS RETURNED AND MAINTAINED AT 35". PRESSURE | | WAS MAINTAINED WITH THE BYPASS VALVES. FOUR SRV'S LIFTED AND FULLY | | RESEATED. THE UNIT IS PROCEEDING TO COLD S/D. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28691 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF PENNSYLVANIA HOSPITAL |NOTIFICATION DATE: 04/15/95 | | CITY: PHILADELPHIA REGION: 1 |NOTIFICATION TIME: 13:20 [ET]| | COUNTY: STATE: PA |EVENT DATE: 04/14/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 16:30[EDT]| | DOCKET: |LAST UPDATE DATE: 04/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN WHITE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SELIKSON | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE UNIVERSITY OF PENNSYLVANIA HOSPITAL REPORTED THAT THEY HAD PERFORMED A | | REQUESTED I131 DIAGNOSTIC ON A PATIENT ON EITHER 4/13/95 OR 4/14/95. THE | | REFERRING PHYSICIAN CANCELED THE DIAGNOSTIC ON 4/14/95 BUT HIS NOTICE WAS | | RECEIVED AFTER THE SCAN HAD BEEN PERFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28692 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/15/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 14:15 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/14/95 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTO START OF TWO SERVICE WATER PUMPS DURING A TEST. | | | | DURING THE PERFORMANCE OF THEIR RECIRCULATION SWITCH TEST(PTR-13A), THEY | | HAD AN AUTO START OF TWO SERVICE WATER PUMPS THAT WAS NOT ANTICIPATED. AN | | INVESTIGATION OF WHY THESE PUMPS STARTED WHILE THEY WERE TESTING SWITCHES | | #2 AND #5 IS BEING MADE SINCE THESE PUMPS(#26 & #24) SHOULD NOT HAVE | | STARTED DURING THE TEST. THEY ARE REPORTING THIS EVENT LATE DUE TO THE TIME | | IT TOOK TO EVALUATE THE TEST. THE RI WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28693 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/15/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 22:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/15/95 | +------------------------------------------------+EVENT TIME: 21:37[EDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 04/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED ESF ACTUATIONS WHICH OCCURRED FOLLOWING MAINTENANCE | | ON THE "B" ECCS BATTERY. | | | | THIS OCCURRED WHILE THEY WERE REPLACING FUSES IN THE ECCS CABINET FOLLOWING | | MAINTENANCE ON THE "B" ECCS BATTERY. (SEE RELATED EVENT #28686.) THEY | | RECEIVED A "D" RHR PUMP START AND RHR-27-A & B VALVES FULLY OPENED. THEY | | ALSO HAD LOAD SHED OF BUS "5" AND PUMP DISCHARGE RECIRC VALVES RECEIVED A | | SIGNAL TO CLOSE. AT THIS TIME THE "A" LOOP OF THE RHR AND THE RHR SERVICE | | WATER PUMPS WERE TAGGED OUT OF SERVICE. THE "B" LOOP(WHICH HAD THE "B" & | | "D" PUMPS) HAD THE "B" PUMP ALREADY RUNNING IN SHUTDOWN COOLING MODE. THE | | "A" CORE SPRAY, THE "A" DIESEL, AND THE "B" RECIRC LOOP WERE TAGGED OUT OF | | SERVICE AND THE VESSEL WAS FLOODED UP PRIOR TO THIS EVENT. THEY ARE | | INVESTIGATING WHY THEY RECEIVED ESF ACTUATIONS WHEN THE FUSES WERE | | REPLACED. ALL SYSTEMS WERE RETURNED TO THEIR ORIGINAL CONDITIONS. THE FUSES | | HAVE BEEN REPLACED AND THE BATTERY IS BACK IN SERVICE. THE RI WAS INFORMED. | | THE STATE WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28694 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/16/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 02:39 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/16/95 | +------------------------------------------------+EVENT TIME: 00:16[CDT]| |NRC NOTIFIED BY: SOKOL |LAST UPDATE DATE: 04/16/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |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 | M/R Y 0 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DURING LOW-POWER PHYSICS TESTING. | | | | DURING LOW-POWER PHYSICS TESTING WITH THE REACTOR CRITICAL AT ZERO POWER, | | CONTROL ROD F-12, WHICH IS IN SHUTDOWN BANK "A", DROPPED INTO THE CORE. IN | | ORDER TO INVESTIGATE THE CAUSE OF THE DROPPED ROD, FUSES FOR THE STATIONARY | | GRIPPER, MOVABLE GRIPPER AND LIFT COILS WERE REMOVED TO PROVIDE ELECTRICAL | | ISOLATION. ONE OF THE FUSES WAS COMMON TO THE MOVABLE GRIPPER COIL FOR ROD | | E-11. WHEN OPERATORS ATTEMPTED TO STEP THE CONTROL RODS, ROD E-11 ALSO | | DROPPED PART WAY INTO THE CORE, CAUSING THE REACTOR TO BECOME SUBCRITICAL. | | | | OPERATORS MANUALLY TRIPPED THE REACTOR IN ACCORDANCE WITH THE LOW-POWER | | PHYSICS TEST PROCEDURE AND NORMAL STARTUP PROCEDURE, WHICH DO NOT ALLOW FOR | | RESTART OF THE REACTOR FROM THIS CONFIGURATION. ALL CONTROL RODS INSERTED | | INTO THE REACTOR FOLLOWING THE TRIP. THE LICENSEE WILL CONTINUE TO | | TROUBLESHOOT THE PROBLEM WITH CONTROL ROD F-12, AND ANTICIPATES RESTARTING | | THE UNIT LATER TODAY. THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR | | OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28695 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/16/95 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:00 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/16/95 | +------------------------------------------------+EVENT TIME: 13:33[EDT]| |NRC NOTIFIED BY: PINKOWITZ |LAST UPDATE DATE: 04/16/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTO START OF THE "A" D/G DURING A VALVE TEST. | | | | WHILE THE LICENSEE WAS PERFORMING A VOTES VALVE TEST ON THEIR RECIRC SPRAY | | SYSTEM, AN INADVERTENT CONTAINMENT DEPRESSURIZATION ACTUATION SIGNAL WAS | | RECEIVED BY THE "A" TRAIN EMERGENCY SEQUENCER. THE SEQUENCER RESPONDED BY | | STARTING THE "A" TRAIN D/G AND TRIPPING THE "A" TRAIN REACTOR PLANT | | COMPONENT COOLING WATER SYSTEM. THEY RESPONDED BY CLEARING THE INADVERTENT | | SIGNAL AND RESTARTING THE COOLING WATER SYSTEM SINCE IT WAS PROVIDING | | COOLING WATER TO THEIR SHUTDOWN COOLING. NO INCREASE IN PRIMARY TEMPERATURE | | WAS NOTICED. THE D/G WAS BEING RESTORED TO NORMAL MODE. THEY ARE | | INVESTIGATING THE CAUSE. THE RI WILL BE INFORMED AND STATE AND LOCAL | | AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28696 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/16/95 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/16/95 | +------------------------------------------------+EVENT TIME: 13:58[CDT]| |NRC NOTIFIED BY: VERCELLI |LAST UPDATE DATE: 04/16/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED THEIR HPCI SYSTEM TO BE INOPERABLE, PUTTING THEM IN A | | 7 DAY LCO ACTION STATEMENT. | | | | THE LICENSEE NOTICED DURING PANEL WALKDOWNS THAT THE HPCI SYSTEM ROOM | | COOLER WAS RUNNING, BUT THERE WAS NO CHANGE IN ROOM TEMPERATURE. AN | | OPERATOR WAS DISPATCHED TO THE ROOM AND FOUND THAT THE BELT ON THE COOLER | | WAS BROKEN. HPCI WAS IMMEDIATELY DECLARED INOPERABLE AND THEY ENTERED AN | | LCO ACTION STATEMENT. MAINTENANCE PERSONNEL ARE ON THEIR WAY IN TO REPLACE | | THE BELT. THE RI WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28697 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/17/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 00:02 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/16/95 | +------------------------------------------------+EVENT TIME: 20:20[CDT]| |NRC NOTIFIED BY: POHL |LAST UPDATE DATE: 04/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |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 Y 30 POWER OPERATION | 30 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED LOCAL SHERIFF OF GUNSHOTS COMING FROM BOAT ON MISSOURI | | RIVER. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 2018 ON 4/16/95, THE CONTROL ROOM WAS NOTIFIED THAT A BOAT ON THE | | MISSOURI RIVER WAS FIRING GUN SHOTS. SECURITY WAS IMMEDIATELY NOTIFIED AND | | THE BOAT WAS PLACED UNDER SURVEILLANCE WITH TELEPHOTO CAMERAS. THE | | WASHINGTON COUNTY SHERIFF'S OFFICE WAS NOTIFIED AT 2020 AND A DESCRIPTION | | OF THE BOAT AND ITS OCCUPANTS WAS GIVEN. IT COULD NOT BE DETERMINED IF THE | | GUNFIRE WAS DIRECTED AT THE FACILITY OR THE OPPOSITE RIVER BANK. NO DAMAGE | | TO SITE PERSONNEL OR PROPERTY HAS BEEN DISCOVERED." | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+