U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/02/96 - 12/03/96 ** EVENT NUMBERS ** 31392 31393 31394 31395 31396 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31392 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 12/02/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/02/96 | +------------------------------------------------+EVENT TIME: 14:50[EST]| |NRC NOTIFIED BY: JOHN MANSELL |LAST UPDATE DATE: 12/02/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED OTHER FEDERAL/STATE AGENCIES OF AN ASBESTOS RELEASE | | ONSITE. | | | | APPROXIMATELY 3 POUNDS OF ASBESTOS INSULATION ON A RETIRED UNIT 1 STEAM | | LINE CAME LOOSE DURING HIGH WINDS AND FELL THROUGH THE 105-FOOT ELEVATION | | GRATING TO THE 88-FOOT ELEVATION FLOOR IN THE UNIT 1 NUCLEAR SERVICE | | BUILDING. THE AREA HAS BEEN ROPED OFF, AND POLY MATERIAL HAS BEEN WRAPPED | | AROUND THE PIPE. | | | | THE LICENSEE NOTIFIED THE DEPARTMENT OF ENVIRONMENTAL CONTROL FEDERAL/STATE | | AGENCIES AND THE WESTCHESTER COUNTY DEPARTMENT OF PUBLIC HEALTH AND SAFETY. | | THE LICENSEE ALSO PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31393 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DUPONT-MERCK PHARMACEUTICAL CO. |NOTIFICATION DATE: 12/02/96 | | CITY: NORTH BILLERICA REGION: 1 |NOTIFICATION TIME: 16:26 [ET]| | COUNTY: MIDDLESEX STATE: MA |EVENT DATE: 12/01/96 | |LICENSE#: 20-28598-01 AGREEMENT: N |EVENT TIME: 14:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/02/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GLENN MEYER RDO | | |FREDERICK COMBS EO | +------------------------------------------------+STUART RUBIN, IRD AEOD | |NRC NOTIFIED BY: SKIP ROY | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED CONTAMINATION RESTRICTING PERSONNEL ACCESS > 24 HOURS | | | | AT 1400 EST ON 12/01/96, APPROXIMATELY 6 GALLONS OF EFFLUENT CONTAINING | | MOLYBDENUM-99 (2.2 ęCi/ml) AND TECHNETIUM-99m (4.3 ęCi/ml) OVERFLOWED A | | 300-GALLON HOLDING TANK. THE EFFLUENT SPILLED ONTO AN ASPHALT AND GRASSY | | AREA AT THE DUPONT-MERCK PHARMACEUTICAL COMPANY FACILITY LOCATED AT 331 | | TREBLE COVE ROAD, NORTH BILLERICA, MASSACHUSETTS. THE LICENSEE ATTRIBUTES | | THE ERROR TO AN OPERATOR BELIEVING THAT THE TANK WAS EMPTY PRIOR TO | | DIRECTING THE EFFLUENT TO THE TANK. THE TOTAL ACTIVITY RELEASED IS | | ESTIMATED AT 50 mCi OF MOLYBDENUM-99 AND 97 mCi OF TECHNETIUM-99m OVER AN | | AREA OF APPROXIMATELY 20 FEET BY 20 FEET. THE AREA HAS BEEN ROPED OFF. THE | | LICENSEE IS EVALUATING CORRECTIVE ACTIONS. BOTH ISOTOPES HAVE RELATIVELY | | SHORT HALF-LIVES, i.e., 66 HOURS FOR MOLYBDENUM-99 AND 6 HOURS FOR | | TECHNETIUM-99m. THERE WAS NO PERSONNEL EXPOSURE INVOLVED. | | | | THE LICENSEE WILL INFORM THE NRC REGION I OFFICE AND THE MASSACHUSETTS | | RADIATION CONTROL PROGRAM OFFICE. (REFER TO THE HOO LOG FOR CONTACT | | TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31394 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/02/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 16:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/02/96 | +------------------------------------------------+EVENT TIME: 14:00[EST]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 12/02/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING CHANGEOUT OF THE UNIT 2 CONTROL RODS, THE LICENSEE DISCOVERED A | | BROKEN BULLET NOSE ON ONE OF THE RODLETS. | | | | "DURING THE CONTROL ROD CHANGEOUT ON SALEM UNIT 2, THE ENGINEERS FOUND THAT | | ONE OF THE BULLET NOSES ON THE RODLET WAS BROKEN OFF. THIS CONDITION WAS | | DISCOVERED ON 1 DECEMBER 1996, WHEN THE CONTROL ROD FAILED TO INSERT INTO A | | SPENT FUEL ASSEMBLY IN THE SPENT FUEL POOL. THE REASON FOR CHANGING THE | | CONTROL ROD WAS PART OF A COMPLETE CHANGEOUT OF ALL THE CONTROL RODS. THESE | | WESTINGHOUSE CONTROL RODS HAD BEEN USED IN THE CORE SINCE INITIAL STARTUP | | OF SALEM UNIT 2 IN 1981. A SECOND RODLET WAS FOUND WITH THE SAME CONDITION | | ON 2 DECEMBER 1996, WHEN THE CONTROL ROD WOULD NOT INSERT INTO THE | | ASSEMBLY. APPROXIMATELY HALF OF THE CONTROL RODS HAVE BEEN REPLACED AT | | THIS TIME, AND THE CURRENT PLANS ARE TO EXAMINE ALL FIFTY-THREE (53) OLD | | CONTROL RODS FOR THIS PROBLEM. PRELIMINARY DISCUSSION WITH THE VENDOR | | INDICATES THAT SIMILAR PROBLEMS HAVE OCCURRED WITH HAFNIUM CONTROL RODS AND | | THAT ONE CONTROL ROD HAD BEEN REPORTED WITH THIS CONDITION AT INDIAN POINT. | | THE VENDOR HAS INDICATED THAT THE CONTROL ROD WOULD STILL BE EXPECTED TO | | FULLY INSERT WITH NO MECHANICAL INTERFERENCE, SINCE THE RODLETS ARE | | PARTIALLY INSERTED IN THE ASSEMBLY DURING POWER OPERATION, AND THE BULLET | | NOSE WOULD NOT WEDGE ITSELF IN THE GUIDE TUBE. THIS CONDITION WOULD NOT | | AFFECT THE SHUTDOWN MARGIN DUE TO ITS LOCATION IN AN INACTIVE REGION OF THE | | FUEL ASSEMBLY. ENGINEERING IS CONTINUING THE INVESTIGATION OF THIS PROBLEM | | WITH THE VENDOR. CURRENTLY, BOTH SALEM UNITS ARE IN THE DEFUELED MODE, AND | | THE ROD CONTROL SYSTEM IS NOT REQUIRED TO BE OPERABLE TO MITIGATE DESIGN | | BASIS ACCIDENTS. THERE IS NO SIGNIFICANT IMPACT DUE TO THIS PROBLEM ON THE | | HEALTH AND SAFETY OF THE PUBLIC IN THIS MODE OF OPERATION. THIS CONDITION | | IS BEING REPORTED VOLUNTARILY AS DELINEATED IN NUREG-1022, SECTION 2.9" | | | | THE LICENSEE INFORMED THE LOWER ALLOWAYS CREEK TOWNSHIP AND WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31395 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/02/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:26 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/02/96 | +------------------------------------------------+EVENT TIME: 15:10[EST]| |NRC NOTIFIED BY: GLENN PATON |LAST UPDATE DATE: 12/02/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN INADVERTENT DIVISION 1 LOCA SIGNAL WAS RECEIVED DURING A SURVEILLANCE | | TEST OF THE UNIT 2 'A' LOOP OF CORE SPRAY. | | | | DURING PERFORMANCE OF UNIT 2 'A' LOOP CORE SPRAY RESPONSE TIME TEST | | (ST-2-052-801-2) WITH UNIT 2 AT 92% POWER, AN INADVERTENT UNIT 2 DIVISION 1 | | LOCA SIGNAL WAS RECEIVED. AN ESF ACTUATION ('D21' DIESEL GENERATOR START) | | OCCURRED. REACTOR POWER, LEVEL, AND PRESSURE WERE VERIFIED TO BE UNCHANGED | | AND STEADY. EQUIPMENT RESPONDED AS EXPECTED ON THE LOCA SIGNAL, AND IT WAS | | RESET AND RESTORED. AN INVESTIGATION IS CONTINUING TO IDENTIFY THE CAUSE | | OF THE EVENT. THE CORE SPRAY SURVEILLANCE TEST WAS COMPLETED, AND THE '2A' | | LOOP OF CORE SPRAY WAS RETURNED TO NORMAL STATUS/LINEUP. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31396 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/02/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:00 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/02/96 | +------------------------------------------------+EVENT TIME: 16:58[EST]| |NRC NOTIFIED BY: DEVON PRICE |LAST UPDATE DATE: 12/02/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 +------------------------------------------------------------------------------+ | AUTOMATIC START OF THE 'A' SAFETY AUXILIARY COOLING SYSTEM (SACS) PUMP DUE | | TO HUMAN ERROR, A MISSED PROCEDURAL STEP. | | | | DURING A SWAP OF THE SAFETY-RELATED PANEL ROOM CHILL WATER SYSTEMS FROM THE | | 'B' TRAIN TO THE 'A' TRAIN, A STEP IN THE ASSOCIATED PROCEDURE WAS MISSED. | | THIS MISSED STEP RESULTED IN THE AUTOMATIC START OF THE 'A' SACS PUMP. THE | | STEP MISSED WAS TO PLACE THE 'A' SAFETY-RELATED PANEL ROOM CHILL WATER PUMP | | IN MANUAL PRIOR TO SECURING THE 'B' SAFETY-RELATED PANEL ROOM CHILL WATER | | PUMP. WHEN THE 'B' SAFETY-RELATED PANEL CHILL WATER PUMP WAS SECURED, THE | | 'A' SAFETY-RELATED PANEL ROOM CHILL WATER PUMP AUTOMATICALLY STARTED. THIS | | RESULTED IN AN AUTOMATIC START OF THE 'A' SACS PUMP. THE AUTOMATIC START | | OF THE 'A' SACS PUMP IS AN ESF ACTUATION. ALL AUTOMATIC ACTUATIONS | | OCCURRED PER DESIGN. THE 'A' CONTROL ROOM EMERGENCY FILTRATION SYSTEM IS | | NOT AVAILABLE DUE TO A NORMAL SYSTEM OUTAGE. ALL OTHER SAFETY-RELATED | | EQUIPMENT IS AVAILABLE. | | | | THE LICENSEE INFORMED THE LOWER ALLOWAYS CREEK TOWNSHIP AND THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+