U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/24/96 - 12/26/96 ** EVENT NUMBERS ** 31499 31505 31506 31507 31508 31509 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31499 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/22/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 23:18 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/22/96 | +------------------------------------------------+EVENT TIME: 19:56[EST]| |NRC NOTIFIED BY: JEFF KLENK |LAST UPDATE DATE: 12/24/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 2 STARTUP | 2 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC STEAM LINE INBOARD ISOLATION VALVE CLOSED UNEXPECTEDLY DURING STEAM | | LINE WARMING. | | | | INBOARD STEAM LINE ISOLATION VALVE HV49-2F007 RECEIVED AN ISOLATION SIGNAL | | AS THE VALVE WAS BEING INITIALLY BUMPED OPEN FOR STEAM LINE WARM UP. THE | | VALVE AUTOMATICALLY CLOSED POSSIBLY DUE TO A HIGH STEAM FLOW SIGNAL. THE | | HIGH STEAM FLOW MAY HAVE BEEN CAUSED BY CONDENSATION IN THE STILL COOL | | STEAM LINE. THE ISOLATION VALVE WAS SUCCESSFULLY OPENED AT 2130 EST. | | | | THE LICENSEE IS CONTINUING TO EVALUATE THE REPORTABILITY OF THIS EVENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1014 ON 12/24/96 FROM NEFF TAKEN BY SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE ISOLATION SIGNAL WAS | | INVALID, AND THE PRIMARY CONTAINMENT PENETRATION VALVE WAS ALREADY CLOSED | | AT THE TIME OF THE EVENT. THE OPERATOR HAD GIVEN THE VALVE A THREE-SECOND | | OPEN SIGNAL WHEN A MOMENTARY LOW PRESSURE SIGNAL OCCURRED DUE TO STEAM | | FLOWING INTO THE PIPING BETWEEN THE INBOARD AND OUTBOARD ISOLATION VALVES. | | THEREFORE, THIS EVENT IS NOT REPORTABLE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (COWGILL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31505 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/24/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 08:45 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/24/96 | +------------------------------------------------+EVENT TIME: 06:13[EST]| |NRC NOTIFIED BY: STEVE TOTH |LAST UPDATE DATE: 12/24/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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/R Y 37 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 WAS MANUALLY SCRAMMED FOLLOWING THE FAILURE OF THE 2B RECIRC PUMP | | MOTOR GENERATOR SCOOP TUBE POSITIONER. | | | | "DURING UNIT 2 STARTUP AND POWER ASCENSION ACTIVITIES, THE 2B RECIRC PUMP | | MOTOR GENERATOR SET SCOOP TUBE POSITIONER MALFUNCTIONED. THE 2B RECIRC | | PUMP WAS MANUALLY TRIPPED DUE TO A HIGH VIBRATION CONDITION CONFIRMED BY | | THE CONTROL ROOM OPERATORS." | | | | "THIS CONDITION PLACED THE REACTOR IN THE EXCLUSION REGION ON THE REACTOR | | POWER VERSUS CORE FLOW MAP. THE REACTOR WAS MANUALLY SCRAMMED, AND THE | | UNIT WAS PLACED IN A STABLE CONDITION. THERE WERE NO INDICATIONS OF CORE | | THERMAL HYDRAULIC INSTABILITIES PRIOR TO THE MANUAL SCRAM." | | | | THE LICENSEE IS CONTINUING ITS INVESTIGATION INTO THE FAILURE OF THE SCOOP | | TUBE POSITIONER AND EXPECTS TO RESTART THE UNIT WITHIN 24 HOURS. ALL | | CONTROL RODS FULLY INSERTED FOLLOWING THE MANUAL SCRAM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31506 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNITED STATES AIR FORCE |NOTIFICATION DATE: 12/24/96 | | CITY: MANSFIELD REGION: 3 |NOTIFICATION TIME: 12:48 [ET]| | COUNTY: RICHLAND STATE: OH |EVENT DATE: 12/10/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/24/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GARY SHEAR, REGION 3 RDO | | |JOHN GREEVES, NMSS EO | +------------------------------------------------+RICH BARRETT, IRD AEOD | |NRC NOTIFIED BY: PETTY OFFICER BLANCHARD |GENE BATES, REGION 4 RDO | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NMAT MATL IN UNCNTRL AREA | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NATIONAL RESPONSE CENTER REPORT OF A DEPARTMENT OF DEFENSE RADIOACTIVE | | INCIDENT INVOLVING GOVERNMENT SCRAP METAL GENERATED BY THE U.S. AIR FORCE | | THAT WAS SOLD TO A PRIVATE PARTY AND SUBSEQUENTLY FOUND TO BE RADIOACTIVE. | | | | SCRAP MATERIAL GENERATED BY THE U.S. AIR FORCE WAS SOLD TO A PRIVATE PARTY | | TWO YEARS AGO; AND WHEN THE PRIVATE PARTY ATTEMPTED TO SELL THE SCRAP | | MATERIAL, IT WAS TESTED AND DETERMINED TO BE RADIOACTIVE. THE MATERIAL | | (2,900 POUNDS OF MAGNESIUM/THORIUM) IS 4% THORIUM BY WEIGHT, AND IT IS | | CURRENTLY LOCATED AT A SCRAP YARD (AUTOJUMBLE) IN MANSFIELD, OHIO. THE | | U.S. AIR FORCE INFORMED THE NATIONAL RESPONSE CENTER THAT THE MATERIAL HAD | | VERY LOW LEVELS OF RADIOACTIVITY. | | | | THE U.S. AIR FORCE NOTIFIED THE NATIONAL RESPONSE CENTER OF THIS EVENT AT | | 1225 ON DECEMBER 24, 1996, AND THE U.S. AIR FORCE WAS INFORMED OF THIS | | INCIDENT ON DECEMBER 10, 1996. WRIGHT-PATTERSON AIR FORCE BASE (THE | | CLOSEST AIR FORCE BASE) IS CURRENTLY HANDLING THIS ISSUE AND IS WORKING | | WITH THE OHIO ENVIRONMENTAL PROTECTION AGENCY (EPA). THE NATIONAL RESPONSE | | CENTER HAS NOTIFIED EPA REGION V AND PLANS TO NOTIFY THE EPA OFFICE OF AIR | | AND RADIATION, THE DEPARTMENT OF ENERGY, THE AGENCY FOR TOXIC SUBSTANCES | | AND DISEASE REGISTRY, AND THE NATIONAL MILITARY COMMAND CENTER. (REFER TO | | THE HOO LOG FOR CONTACT NAMES, ADDRESSES, AND TELEPHONE NUMBERS.) | | | | HOO NOTE: NRC REGION IV WAS NOTIFIED OF THIS EVENT BY THE DEPARTMENT OF | | THE AIR FORCE RADIOISOTOPE COMMITTEE AT 1300 CST ON DECEMBER 19, 1996, AND | | NRC REGION IV ISSUED A PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL | | OCCURRENCE (PNO-IV-96-070) TO DOCUMENT THIS ISSUE ON DECEMBER 20, 1996. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31507 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 12/24/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 13:02 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 12/24/96 | +------------------------------------------------+EVENT TIME: 13:02[EST]| |NRC NOTIFIED BY: SANJEEV ARAB |LAST UPDATE DATE: 12/24/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 7 STARTUP | 7 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO FAILURE OF A DRYWELL | | VACUUM BREAKER TO CLOSE DURING SURVEILLANCE TESTING. | | | | AFTER DISCHARGING STEAM TO THE SUPPRESSION CHAMBER FROM SAFETY RELIEF VALVE | | TESTING, SUPPRESSION CHAMBER-DRYWELL VACUUM BREAKER T2300F400J FAILED TO | | SEAT OR CLOSE AFTER OPENING WHEN THE OPEN PUSH BUTTON WAS RELEASED. | | TECHNICAL SPECIFICATION 3.6.4.1.b WAS ENTERED, AND AN INVESTIGATION WAS | | INITIATED. | | | | VARIOUS ATTEMPTS TO CYCLE THE VACUUM BREAKER COULD NOT MAKE THE VACUUM | | BREAKER CLOSE OR SEAT. PER TECHNICAL SPECIFICATIONS, A SYSTEMATIC PLANT | | SHUTDOWN WAS SUBSEQUENTLY COMMENCED DUE TO THIS FAILURE TO SEAT THE VACUUM | | BREAKER AFTER 2 HOURS. (WITH ONE OR MORE SUPPRESSION CHAMBER TO DRYWELL | | VACUUM BREAKERS OPEN, TECHNICAL SPECIFICATION 3.6.4.1.b REQUIRES THAT THE | | LICENSEE CLOSE THE OPEN VACUUM BREAKER(S) WITHIN 2 HOURS OR BE IN AT LEAST | | HOT SHUTDOWN WITHIN THE NEXT 12 HOURS AND IN COLD SHUTDOWN WITHIN THE | | FOLLOWING 24 HOURS.) THE VACUUM BREAKER FAILED TO CLOSE AT APPROXIMATELY | | 0550. THE LICENSEE WILL PROCEED TO COLD SHUTDOWN FOR REPAIRS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31508 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/24/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 20:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/24/96 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: DOUG HITZEL |LAST UPDATE DATE: 12/24/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INDICATION OF AN 8-SECOND STANDBY GAS TREATMENT TRAIN 'A' START AND RUN. | | | | AT APPROXIMATELY 1600 CST ON DECEMBER 24, 1996, DURING THE INVESTIGATION OF | | A STANDBY GAS TREATMENT SYSTEM AUTOMATIC REACTOR BUILDING DIFFERENTIAL | | PRESSURE CONTROL VALVE PROBLEM, THE LICENSEE IDENTIFIED AN INDICATION OF A | | STANDBY GAS TREATMENT TRAIN 'A' START AND RUN FOR APPROXIMATELY 8 SECONDS | | AT APPROXIMATELY 1703 CST ON DECEMBER 23, 1996. THIS ANOMALY WAS | | IDENTIFIED AS RELAY ACTUATIONS DURING A REVIEW OF DATA FROM THE PLANT | | MANAGEMENT INFORMATION SYSTEM COMPUTER. THIS IS POSSIBLY DUE TO A LOOSE | | CONNECTION IN STANDBY GAS TREATMENT/REACTOR BUILDING ISOLATION LOGIC RELAYS | | PC-REL-ISO1AX (SYSTEM 'A' ISOLATION RELAY) AND PC-REL-ISO2AX (SYSTEM 'A' | | ISOLATION RELAY). THESE RELAYS FAIL SAFE UPON A LOSS OF POWER, AND A | | POSSIBLE LOOSE CONNECTION WOULD CAUSE THE ISOLATION LOGIC TO ACTUATE. | | | | THE LICENSEE IS REPORTING THIS ISSUE AS A CONSERVATIVE MEASURE DUE TO THE | | LOGIC TIE TO VALVES REC-MO-711MV (NORTH CRITICAL LOOP COOLING SUPPLY FOR | | EMERGENCY CORE COOLING SYSTEMS) AND SW-MO-650MV (RESIDUAL HEAT REMOVAL HEAT | | EXCHANGER 'A' OUTLET). THIS LOGIC INCLUDES A 30-SECOND TIME DELAY FOR | | VALVE REC-MO-711MV ACTUATION (OPENING). HOWEVER, SINCE THE INITIATION | | SIGNAL WAS ONLY PRESENT FOR APPROXIMATELY 8 SECONDS, THIS ACTUATION DID NOT | | OCCUR. HAD THE INITIATION BEEN PRESENT FOR 30 SECONDS, VALVE REC-MO-711MV | | ACTUATION WOULD HAVE OCCURRED. THE CAUSE OF THIS CONDITION IS CURRENTLY | | UNDER INVESTIGATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31509 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 12/25/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:20 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 12/25/96 | +------------------------------------------------+EVENT TIME: 11:28[EST]| |NRC NOTIFIED BY: KEVIN McLAUGHLIN |LAST UPDATE DATE: 12/25/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 +------------------------------------------------------------------------------+ | ENGINEERED SAFETY FEATURE (ESF) ACTUATION INVOLVING THE MANUAL START OF A | | SERVICE WATER PUMP FOLLOWING THE TRIP OF A RUNNING SERVICE WATER PUMP. | | | | PRIOR TO THIS EVENT, THE 'B' AND 'C' SERVICE WATER PUMPS WERE RUNNING, AND | | THE 'A' AND 'D' SERVICE WATER PUMPS WERE SELECTED FOR ESF ACTUATION. WHEN | | THE 'C' SERVICE WATER PUMP TRIPPED, AN OPERATOR MANUALLY STARTED THE 'D' | | SERVICE WATER PUMP TO RESTORE SERVICE WATER FLOW. BECAUSE THE 'D' SERVICE | | WATER PUMP WAS SELECTED FOR ESF ACTUATION, THE LICENSEE BELIEVES THAT THIS | | ACTION CONSTITUTED AN ESF ACTUATION. FURTHER INVESTIGATION REVEALED THAT | | THE 'C' SERVICE WATER PUMP HAD TRIPPED DUE TO A SHORT CIRCUIT IN THE MOTOR. | | THE UNIT IS NOT IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION AS A RESULT OF THIS INCIDENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+