U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/18/95 - 12/19/95 ** EVENT NUMBERS ** 29560 29733 29734 29735 29736 29737 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29560 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/04/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:57 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/04/95 | +------------------------------------------------+EVENT TIME: 17:40[EST]| |NRC NOTIFIED BY: WILLIAM SPAHN |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL LAZARUS 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REMOVAL OF DRYWELL SHIELD PLUGS BEFORE ENTERING A COLD SHUTDOWN CONDITION | | IN THE LAST 14 REFUELING OUTAGES WAS NOT IN ACCORDANCE WITH NUREG-0612 | | RECOMMENDATIONS. | | | | AS A RESULT OF AN ENGINEERING REVIEW, IT WAS DETERMINED THAT PROCEDURE | | MP790, CONTROL OF HEAVY LOADS, DOES NOT EXPLICITLY STATE THAT REACTOR | | SAFETY CAVITY SHIELD BLOCK REMOVAL SHOULD NOT BE INITIATED UNTIL THE | | PRIMARY SYSTEM TEMPERATURE HAS REACHED 212øF OR LESS. AS A RESULT, THE | | POTENTIAL EXISTS THAT DURING PREVIOUS OUTAGES, THE SHIELD BLOCKS COULD HAVE | | BEEN MOVED PRIOR TO THIS TEMPERATURE. | | | | AN INITIAL REVIEW OF THE LICENSEE'S NUREG-0612 HEAVY LOADS EVALUATIONS HAS | | BEEN PERFORMED. THE REVIEW INDICATED THAT A POSTULATED DROP OF THE SHIELD | | BLOCKS ON THE REFUEL OPERATING FLOOR WAS EVALUATED AND WOULD NOT IMPACT | | SYSTEMS REQUIRED TO ACHIEVE SAFE SHUTDOWN. BASED ON THIS REVIEW, IT WAS | | NOT CLEAR WHETHER A POSTULATED DROP ON THE DRYWELL HEAD WAS EXPLICITLY | | EVALUATED. THUS, THE POTENTIAL EXISTED FOR DEGRADATION OF THE PRIMARY | | CONTAINMENT FUNCTION RESULTING FROM A SHIELD BLOCK DROP ON THE CONTAINMENT | | HEAD. THIS CONDITION IS BEING CONSERVATIVELY REPORTED. | | | | CORRECTIVE ACTION HAS BEEN TAKEN IN THAT SHIELD BLOCK REMOVAL WILL NOT BE | | INITIATED UNTIL THE PRIMARY SYSTEM TEMPERATURE IS BELOW 212øF. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS EVENT. THE NRC | | RESIDENT INSPECTOR WAS ALSO INFORMED BY THE LICENSEE. | | | | * * * 0929 DECEMBER 18, 1995, UPDATE FROM DONOVAN RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BECAUSE DESIGN ENGINEERING | | EVALUATIONS (WHICH WERE PERFORMED TO DETERMINE IF LEAKAGE WOULD OCCUR IN | | THE DRYWELL HEAD FOLLOWING AN ACCIDENTAL DROP OF A RADIATION SHIELD BLOCK | | ONTO THE HEAD) SHOWED THAT THE DRYWELL HEAD COULD WITHSTAND THE IMPACT WITH | | NO SUBSEQUENT LEAKAGE. HISTORICALLY, THE BOTTOM LAYER OF SHIELD BLOCKS IS | | NOT REMOVED UNTIL ALL CONTROL RODS ARE INSERTED AND UNTIL THE UNIT IS IN | | HOT SHUTDOWN. CONTINUATION OF THIS PROCEDURE WILL ASSURE THAT A DROP | | IMPACT WILL NOT AFFECT INSERTION OF THE RODS. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER HAS NOTIFIED THE R1DO (MODES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29733 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 05:00 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 04:40[EST]| |NRC NOTIFIED BY: GUY ERIKSEN |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE 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 STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR SCRAM APPARENTLY IN RESPONSE TO HIGH STATOR | | COOLING TEMPERATURES FOLLOWING MAINTENANCE OF A TURBINE BUILDING CLOSED | | COOLING WATER PUMP | | | | APPROXIMATELY 10 MINUTES AFTER RETURNING A TURBINE BUILDING CLOSED COOLING | | WATER PUMP TO SERVICE FOLLOWING MECHANICAL MAINTENANCE, OPERATORS NOTED | | THAT THE STATOR COOLING TEMPERATURES WERE INCREASING. HIGH TEMPERATURE | | ALARMS WERE RECEIVED AT THE SAME TIME. APPARENTLY, A TURBINE RUNBACK | | OCCURRED IN RESPONSE TO THE HIGH STATOR COOLING TEMPERATURES (89øC | | SETPOINT). THE TURBINE RUNBACK APPARENTLY RESULTED IN A TURBINE TRIP AND | | SUBSEQUENT AUTOMATIC REACTOR SCRAM FROM 100% POWER. THE BYPASS VALVES WERE | | OPENING TO ACCOMMODATE THE DECREASED TURBINE LOAD, AND THE OPERATORS WERE | | ATTEMPTING TO REDUCE RECIRCULATION FLOW TO DECREASE POWER AT THE TIME OF | | THE TURBINE TRIP/REACTOR SCRAM. AT THE TIME OF THIS NOTIFICATION, THE | | LICENSEE WAS STILL RESPONDING TO THE PLANT TRANSIENT AND DID NOT KNOW THE | | EXACT CAUSES. (APPARENTLY, WHEN THE 89øC STATOR COOLING TEMPERATURE | | SETPOINT IS REACHED, AN AUTOMATIC TURBINE TRIP OCCURS IF THE TURBINE | | GENERATOR SENSES ARMATURE CURRENT GREATER THAN APPROXIMATELY 25% OF ITS | | FULL CAPACITY, WHICH IS 4,800 AMPS, WITHIN 3 MINUTES.) ALL RODS FULLY | | INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THERE WERE NO EMERGENCY | | CORE COOLING SYSTEM INJECTIONS OR ENGINEERED SAFETY FEATURE ACTUATIONS, AND | | THE SAFETY RELIEF VALVES DID NOT LIFT. IN ADDITION, THE COOLDOWN RATE DID | | NOT EXCEED 100øF PER HOUR. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3, AND OPERATORS ARE UTILIZING NORMAL | | CONDENSATE AND FEEDWATER FOR REACTOR VESSEL LEVEL CONTROL AND THE TURBINE | | CONTROL SYSTEM WITH THE MAIN CONDENSER AS A HEAT SINK FOR REACTOR VESSEL | | PRESSURE CONTROL. ALL EMERGENCY CORE COOLING SYSTEM EQUIPMENT IS CURRENTLY | | OPERABLE AND AVAILABLE. OPERATORS ARE IN THE PROCESS OF ESTABLISHING A | | COOLDOWN RATE OF 90øF PER HOUR USING THE TURBINE CONTROLS, AND THE LICENSEE | | PLANS TO PLACE THE UNIT IN COLD SHUTDOWN (POSSIBLY TO VENT THE | | RECIRCULATION PUMPS). THE LICENSEE ALSO PLANS TO INVESTIGATE THE CAUSE OF | | THE HIGH STATOR COOLING TEMPERATURES AND SUBSEQUENT PLANT TRANSIENTS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29734 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 08:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 03:38[CST]| |NRC NOTIFIED BY: MIKE BERRENS |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |AL CHAFFEE/NRR EO | |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 STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE/REACTOR TRIP DUE TO A PARTIAL LOSS OF OFFSITE POWER | | | | AT 0338 CST, THE UNIT EXPERIENCED AN AUTOMATIC TURBINE/REACTOR TRIP DUE TO | | THE LOSS OF THE MAIN AND AUXILIARY TRANSFORMERS. THIS WAS CAUSED BY A | | PILOT WIRE RELAY LOCKOUT. ALL CONTROL RODS FULLY INSERTED, AND ALL SYSTEMS | | FUNCTIONED AS REQUIRED. (WHEN THE MAIN AND AUXILIARY TRANSFORMERS ARE | | LOST, THIS UNIT DOES NOT HAVE A FEATURE FOR THE AUTOMATIC TRANSFER TO THE | | STARTUP TRANSFORMER.) A FEEDWATER ISOLATION OCCURRED DUE TO LOW T(ave), | | AND AUXILIARY FEEDWATER ACTUATED DUE TO LOW STEAM GENERATOR LEVELS AS | | EXPECTED. THE PLANT WAS STABILIZED USING AUXILIARY FEEDWATER AND THE | | ATMOSPHERIC DUMP VALVES. THE #11 EMERGENCY DIESEL GENERATOR (EDG) STARTED | | AND LOADED ONTO THE BUS AS DESIGNED BECAUSE OFFSITE POWER TO THE 'A' TRAIN | | WAS LOST. THE 'B' AND 'C' TRAINS DID NOT LOOSE OFFSITE POWER BECAUSE THEY | | WERE POWERED FROM THE BACKUP TRANSFORMERS. (THIS IS THE NORMAL PLANT | | LINEUP.) AS A PRECAUTIONARY MEASURE, THE #12 AND #13 EDGs WERE MANUALLY | | STARTED BUT WERE NOT LOADED. THE EDGs HAVE BEEN SECURED, AND THE 'A' TRAIN | | LOADS WERE TRANSFERRED TO THE STANDBY TRANSFORMERS WITHIN ABOUT TWO HOURS. | | IN ADDITION, THE UNIT WAS ON NATURAL CIRCULATION FOR APPROXIMATELY ONE AND | | ONE HALF HOURS. | | | | AUXILIARY FEEDWATER IS CURRENTLY BEING USED TO SUPPLY WATER TO THE STEAM | | GENERATORS, AND THE ATMOSPHERIC DUMP VALVES ARE BEING USED TO DUMP | | SECONDARY STEAM. (THERE HAVE BEEN NO INDICATIONS OF STEAM GENERATOR TUBE | | LEAKAGE ABOVE TECHNICAL SPECIFICATION LIMITS.) PRESSURIZER HEATERS AND | | SPRAYS, NORMAL CHARGING AND LETDOWN, AND TWO REACTOR COOLANT PUMPS ARE | | CURRENTLY BEING USED FOR PRIMARY PRESSURE, INVENTORY, AND TRANSPORT | | CONTROL. THE LICENSEE IS CONTINUING TO INVESTIGATE THE CAUSE OF THE | | LOCKOUT ISOLATION, AND THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29735 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:23 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 08:57[EST]| |NRC NOTIFIED BY: MOHNEY |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES 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 +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATOR (EDG) AUTOMATICALLY STARTED DURING MAINTENANCE | | ON VITAL BUS. | | | | DURING THE DE-ENERGIZATION AND TAGGING OF THE 'B' VITAL BUS (10A-402) FOR A | | NORMAL SYSTEM OUTAGE, THE 'B' EDG WAS INADVERTENTLY STARTED. THE | | INADVERTENT START OCCURRED WHILE TAGGING THE NORMAL AND ALTERNATE FEEDER | | BREAKERS FOR THE 'B' VITAL BUS. DURING THE TAGGING OF THESE BREAKERS, | | KNIFE SWITCHES WERE OPENED. THIS PROVIDED A LOSS OF OFFSITE POWER SIGNAL | | FOR EACH FEEDER. WITH THE KNIFE SWITCHES FOR BOTH BREAKERS OPEN, THE LOSS | | OF OFFSITE POWER LOGIC WAS MADE UP. THIS PROVIDED THE EDG WITH A LOSS OF | | OFFSITE POWER START SIGNAL. | | | | THE EDG WAS SECURED AFTER LOADING TO THE VITAL BUS FOR APPROXIMATELY TWO | | MINUTES, AND IT HAS BEEN TAGGED OUT OF SERVICE TO SUPPORT MAINTENANCE ON | | THE 'B' VITAL BUS. THE UNIT IS CURRENTLY IN A REFUELING OUTAGE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29736 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 12:40 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 09:21[EST]| |NRC NOTIFIED BY: REED |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CASTO 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NON-LICENSED SUPERVISOR TESTED POSITIVE FOR ALCOHOL DURING A RANDOM TEST. | | THE INDIVIDUAL WAS ALREADY ENROLLED IN THE EMPLOYEE ASSISTANCE PROGRAM AND | | WAS SUBJECT TO INCREASED TESTING. THE INDIVIDUAL WAS ESCORTED OFFSITE. THE | | LICENSEE WILL REVIEW THE INDIVIDUAL'S WORK TO ENSURE ITS QUALITY. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29737 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:43 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 16:11[EST]| |NRC NOTIFIED BY: HARTNER |LAST UPDATE DATE: 12/18/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 94 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN TO REPLACE EXPANSION JOINTS IN RIVER WATER COOLING SYSTEM | | | | AT 1611 ON 12/18/95, THE LICENSEE COMMENCED A UNIT SHUTDOWN IN ACCORDANCE | | WITH TECHNICAL SPECIFICATIONS IN ORDER TO INSPECT AND REPLACE EXPANSION | | JOINTS IN THE RIVER WATER AND COMPONENT COOLING WATER SYSTEMS. THE | | LICENSEE STATED THAT THIS SHUTDOWN IS BEING PERFORMED BECAUSE OF A | | CONSERVATIVE MANAGEMENT DECISION. | | | | ON 12/15/95, AN EXPANSION JOINT ON THE 'A' RIVER COOLING WATER HEADER | | RUPTURED. THE LICENSEE RETRIEVED INSPECTION DATA FOR THIS EXPANSION JOINT | | FROM THE ARCHIVES AND NOTED THAT THE RUPTURE OCCURRED AT A LOCATION WHICH | | HAD SHOWN SOME INDICATION ON AN INSPECTION VIDEOTAPE. AT THE TIME OF THE | | INSPECTION, THE LICENSEE HAD DETERMINED THAT THE INDICATION WAS NOT | | INDICATIVE OF ANY PROBLEM. SUBSEQUENTLY, THE LICENSEE REVIEWED THE | | INSPECTION TAPE FROM THE 'B' HEADER AND NOTICED INDICATIONS SIMILAR TO | | THOSE SEEN ON THE 'A' HEADER. THE LICENSEE REPORTED THAT A NUMBER OF OTHER | | EXPANSION JOINTS THROUGHOUT THE PLANT (APPROXIMATELY EIGHT JOINTS TOTAL) | | ARE OF THE SAME VINTAGE AS THE ONES IN THE RIVER COOLING WATER SYSTEM. | | ADDITIONALLY, REVIEW OF VENDOR INFORMATION INDICATES THAT THESE EXPANSION | | JOINTS MAY BE BEYOND THEIR RECOMMENDED SERVICE LIFE. | | | | THE LICENSEE PLANS TO PLACE THE UNIT IN COLD SHUTDOWN AND REPLACE THE | | EXPANSION JOINTS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+