U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/03/94 - 10/04/94 ** EVENT NUMBERS ** 27852 27853 27854 27855 27856 27857 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27852 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 10/03/94 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 10:08 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 10/02/94 | +------------------------------------------------+EVENT TIME: 16:37[EDT]| |NRC NOTIFIED BY: BRANTLEY |LAST UPDATE DATE: 10/03/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DURR 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 +------------------------------------------------------------------------------+ | MOMENTARY LOSS OF 4160 VOLT ESF BUS "1E" DUE TO ACTUATION OF OVERCURRENT | | RELAY DURING MAINTENANCE | | | | WHILE CALIBRATING INSTRUMENTATION FOR THE "1E" 4160 VOLT ESF BUS, THE | | ELECTRICAL MAINTENANCE DEPARTMENT WAS PREPARING TO CALIBRATE AN AMMETER | | ASSOCIATED WITH THE FEEDER BREAKER (1SBE2) FOR THE BUS. THE "1E" BUS | | PROVIDES POWER TO THE TRAIN B ESF LOADS. WHEN MAINTENANCE PERSONNEL | | REMOVED LEADS FROM THE CURRENT TRANSFORMER FOR THE AMMETER, SEVERAL RELAYS | | ACTUATED, INCLUDING THE 86B OVERCURRENT RELAY. ACTUATION OF THE 86B RELAY | | CAUSED THE 87 LOCKOUT RELAY TO ACTUATE, CAUSING THE FEEDER BREAKER TO TRIP, | | AND THE BUS TO BECOME DEENERGIZED. LOSS OF THIS BUS DID NOT CAUSE ANY | | PLANT TRANSIENTS. | | | | WHEN THE "1E" BUS BECAME DEENERGIZED, THE ASSOCIATED EMERGENCY DIESEL | | GENERATOR (EG101B) STARTED, BUT DID NOT LOAD TO THE BUS DUE TO THE | | ACTUATION OF THE 87 LOCKOUT RELAY. MAINTENANCE TECHNICIANS RELANDED THE | | LEADS AND WERE ABLE TO RESET THE 86B AND 87 RELAYS WITHIN 3 MINUTES. WHEN | | THE 87 RELAY WAS RESET, THE EDG LOADED TO THE BUS AND CONTINUED TO SUPPLY | | POWER UNTIL THE NORMAL POWER SUPPLY WAS RESTORED. THE EDG WAS SECURED AND | | ALL COMPONENTS SUPPLIED BY THE BUS HAD BEEN RESTORED TO NORMAL | | CONFIGURATIONS BY 1807. THE LICENSEE STATED THAT A DIESEL-DRIVEN FIRE PUMP | | FAILED TO START AS EXPECTED WHEN THE "1E" BUS WAS LOST. THE CAUSE OF THIS | | FAILURE IS STILL UNDER INVESTIGATION. | | | | THIS REPORT WAS MADE AFTER THE PLANT REVIEW GROUP RECOGNIZED THE | | REPORTABILITY OF THE EVENT. THE RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27853 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/03/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:23 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/02/94 | +------------------------------------------------+EVENT TIME: 09:20[CDT]| |NRC NOTIFIED BY: RONALD RUSTIC |LAST UPDATE DATE: 10/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT 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 Y 31 POWER OPERATION | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DIFFERENTIAL TEMPERATURE LIMIT EXCEEDED BETWEEN OPERATING AND IDLE | | RECIRCULATION LOOPS | | | | ON 10/2/94 AT 0920 WHILE IN SINGLE RECIRCULATION LOOP OPERATION, A | | PROCEDURAL LIMIT FOR DIFFERENTIAL TEMPERATURE BETWEEN THE IDLE AND | | OPERATING LOOPS WAS EXCEEDED. PIPING SUPPORTS, WHIP RESTRAINTS, SPRING | | CANS AND SNUBBERS WERE DETERMINED TO BE ADEQUATELY PROTECTED FROM THERMAL | | STRESSES BY A CONSERVATIVELY CHOSEN PROCEDURAL LIMIT OF 50øF DELTA TEMP. | | THE ACTUAL MAXIMUM DELTA OBSERVED WAS APPROXIMATELY 120øF. THE LICENSEE | | COULD NOT PROVIDE THE VALUE OF THE DESIGN BASIS DELTA T. | | | | AN ORDERLY SHUTDOWN WAS COMMENCED AND THE UNIT PLACED IN COLD SHUTDOWN AS | | REQUIRED BY PROCEDURE. NO TECHNICAL SPECIFICATIONS OR SPECIFIC KNOWN | | DESIGN LIMITS WERE VIOLATED. THE STATION HAS NOT FOUND THE SPECIFIC | | DOCUMENTATION TO DETERMINE WHETHER OR NOT THEY WERE IN AN UNANALYZED | | CONDITION. THE LICENSEE IS CONTINUING ITS ENGINEERING ANALYSIS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27854 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 10/03/94 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 14:48 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 10/03/94 | +------------------------------------------------+EVENT TIME: 11:15[EDT]| |NRC NOTIFIED BY: KNORR |LAST UPDATE DATE: 10/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |AL CHAFFEE EO | | |DROGGITIS SP | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAMINATION FOUND ON TWO CONTRACTORS DURING SITE ENTRY WHOLE BODY COUNT | | | | TWO CONTRACTORS WERE FOUND TO HAVE A TOTAL CONTAMINATION OF 0.7 E-06 Ci. | | THE ISOTOPES FOUND WERE CO-60, CO-58, CS-137 AND MN-54. THE CONTAMINATION | | WAS FOUND ON THEIR CLOTHING AND SKIN. THE LICENSEE DECONTAMINATED THE | | INDIVIDUALS AND IS REPERFORMING THE WHOLE BODY COUNTS. THE LICENSEE DID NOT | | YET KNOW IF THERE WAS ANY INTERNAL CONTAMINATION. | | | | THESE INDIVIDUALS LAST WORKED AT PLANTS IN BULGARIA AND FRANCE. THE | | LICENSEE NOTIFIED THE FLORIDA DEPARTMENT OF HEALTH AND REHABILITATION | | SERVICES RADIATION PROTECTION SECTION AND THE APPROPRIATE LOCAL OFFICIALS. | | THE STATE OFFICIALS INTEND TO PERFORM A SURVEY WHERE THE TWO INDIVIDUALS | | ARE LODGING. | | | | THERE HAS ALREADY BEEN SOME LOCAL MEDIA INTEREST IN THIS EVENT. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27855 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/03/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:50 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/03/94 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 10/03/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI AND RCIC DECLARED INOPERABLE | | | | THE PLANT ENTERED A 24 HOUR SHUTDOWN LCO ACTION STATEMENT WHEN BOTH HPCI | | AND RCIC WERE DECLARED INOPERABLE. HPCI AND RCIC WERE DECLARED INOPERABLE | | WHEN ONE CHANNEL OF THE REACTOR VESSEL HIGH WATER LEVEL TRIP BECAME | | INOPERABLE. THE SIGNAL WHICH TRIPS HPCI AND RCIC REQUIRES 2 OUT OF 2 TO | | ACTIVATE, THEREFORE THE HPCI AND RCIC HIGH VESSEL WATER LEVEL TRIP IS | | INOPERABLE. BASED ON THE LOSS OF THIS TRIP, HPCI AND RCIC HAVE BEEN | | DECLARED INOPERABLE AS OF 1600 EDT. | | | | ALL OTHER ECCS EQUIPMENT IS OPERABLE. HPCI AND RCIC WOULD STILL | | AUTOMATICALLY INITIATE IF CALLED UPON, THEY WOULD HAVE TO BE MANUALLY | | SECURED. IF THE LICENSEE COMMENCES A SHUTDOWN REQUIRED BY TECH SPECS THEY | | ARE REQUIRED TO DECLARE AN UNUSUAL EVENT IAW THEIR EMERGENCY PLAN. | | | | THE LICENSEE PLANS TO CONTINUE TROUBLESHOOTING UNTIL AN ESTIMATED REPAIR | | TIME CAN BE OBTAINED. THEY WILL THEN DECIDE WHETHER THEY NEED TO SHUTDOWN. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 27856 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MQS, INC |NOTIFICATION DATE: 10/03/94 | | CITY: PROVIDENCE REGION: 1 |NOTIFICATION TIME: 23:45 [ET]| | COUNTY: PROVIDENCE STATE: RI |EVENT DATE: 10/03/94 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 22:25[EDT]| | DOCKET: |LAST UPDATE DATE: 10/03/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOYNER RDO | | |HAUGHNEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: USDOE(TANNER) | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RECEIVED CALL FROM USDOE OPERATIONS CENTER REGARDING AN IRRETRACTABLE | | RADIOGRAPHY SOURCE. | | | | THE PROVIDENCE, RI FIRE DEPARTMENT SPECIAL HAZARDS UNIT (401-274-3344) | | CONTACTED THE USDOE REGARDING AN IRRETRACTABLE 60Ci IR-192 RADIOGRAPHY | | SOURCE. AT THIS TIME, IT IS UNCLEAR WHETHER THE SOURCE HAS BECOME DETACHED | | FROM ITS DRIVE CABLE OR WHETHER THE CABLE HAS BECOME JAMMED. THE SOURCE | | WAS BEING USED BY MQS, INC. OF HARTFORD, CT (AN NRC LICENSEE) TO PERFORM | | RADIOGRAPHIC INSPECTIONS AT THE MANCHESTER STREET ELECTRICAL PLANT IN | | PROVIDENCE, RI. REPRESENTATIVES FROM AMERSHAM HAVE BEEN DISPATCHED TO | | RETRIEVE THE SOURCE, AND SHOULD BE AT THE SITE AT APPROXIMATELY 0130 | | 10/4/94. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27857 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/04/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 03:13 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/04/94 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: HENRY |LAST UPDATE DATE: 10/04/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS CONTAINMENT GROUPS 2 AND 4 INBOARD ISOLATIONS DUE TO BLOWN FUSE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 0000 ON 10/4/94 A DIVISION 1 [INBOARD] GROUP 2 AND 4 ISOLATION SIGNAL | | WAS RECEIVED. AFTER VERIFICATION THAT NO VALID ISOLATION SIGNAL WAS | | PRESENT, THE ABNORMAL PROCEDURE FOR A SPURIOUS ISOLATION WAS ENTERED AND | | ISOLATIONS DEFEATED FOR THE HIGH STEAM TUNNEL TEMPERATURE AND DIFFERENTIAL | | TEMPERATURE ON BOTH UNITS. THE UNIT 2 STANDBY GAS TRAIN, WHICH AUTO | | STARTED, WAS SHUT DOWN (UNIT 1 STANDBY GAS WAS PREVIOUSLY RUNNING FOR ITS | | MONTHLY SURVEILLANCE). THE PROBLEM WAS TRACED TO A BLOWN FUSE FOR THE | | DIVISION 1 LEVEL 2 AND HIGH DRYWELL PRESSURE LOGIC. THE FUSE WAS REPLACED | | AND SYSTEMS RESTORED TO NORMAL. AT 0055 ALL ISOLATIONS DEFEATED BY THE | | SPURIOUS ISOLATION PROCEDURE WERE RESTORED TO NORMAL. WHILE THE CAUSE OF | | THE BLOWN FUSE IS UNCERTAIN, IT SHOULD BE NOTED AN INSTRUMENT MAINTENANCE | | SURVEILLANCE WAS IN PROGRESS ON THAT LOGIC CIRCUIT AT THE TIME THE SIGNAL | | WAS RECEIVED." | | | | AT LASALLE, A CONTAINMENT GROUP 2 ISOLATION CAUSES DRYWELL HUMIDITY | | MONITORS AND RECIRCULATION SYSTEM FLOW CONTROL VALVE HYDRAULIC LINES TO | | ISOLATE, AND THE DRYWELL POST-ACCIDENT MONITORS TO ACTIVATE. A GROUP 4 | | ISOLATION CAUSES THE REACTOR BUILDING VENTILATION SYSTEM TO ISOLATE AND THE | | STANDBY GAS TREATMENT SYSTEMS FOR BOTH UNITS TO START. | | | | THE RI HAS BEEN INFORMED. | | | +------------------------------------------------------------------------------+