U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/19/94 - 09/20/94 ** EVENT NUMBERS ** 27797 27798 27799 27800 27801 27802 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27797 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 09/19/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 10:06 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/19/94 | +------------------------------------------------+EVENT TIME: 08:25[CDT]| |NRC NOTIFIED BY: HODEL |LAST UPDATE DATE: 09/19/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PEDERSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A LCO ACTION STATEMENT THAT REQUIRES THEM TO BE IN HOT | | SHUTDOWN WITHIN 12 HRS. | | | | THIS OCCURRED WHEN THEY RECEIVED AN ALARM/ANNUNCIATOR SIGNALING THE LOSS OF | | CONTROL POWER FOR THE STANDBY GAS TREATMENT SYSTEM AC POWER SUPPLY. UPON | | INVESTIGATION, THEY DETERMINED THE LOSS OF THE AC POWER SUPPLY MAY HAVE | | AFFECTED MULTIPLE CHANNELS (4 RAD MONITORS, 16 LOCA ISOLATION SIGNALS & THE | | AUTO START FOR SAFE SHUTDOWN WATER SUPPLY). THE TS FOR CONTAINMENT AND | | REACTOR VESSEL ISOLATION CONTROL, STATES THAT WITH THE NUMBER OF OPERABLE | | CHANNELS LESS THEN REQUIRED, THEY ARE TO TAKE ACTION BY PLACING ONE TRIP | | SYSTEM IN THE TRIP CONDITION AND BE IN AT LEAST HOT S/D WITHIN 12 HRS. THE | | PROBLEM APPEARS TO HAVE BEEN CAUSED BY A BLOWN FUSE IN A MAIN CONTROL ROOM | | PANEL, BUT THEY ARE STILL INVESTIGATING THIS PROBLEM. THE RI WILL BE | | INFORMED. | | | | ***UPDATE AT 10:43 ET BY HODEL TO GOULD*** | | THE LCO WAS EXITED AT 09:17CT WHEN A FUSE REPLACEMENT WAS MADE TO THE DIV 2 | | VG (STANDBY GAS TREATMENT SYSTEM) LOGIC CIRCUITRY. INVESTIGATING AS TO WHY | | THE FUSE BLEW IS STILL IN PROGRESS. NO POWER DECREASE WAS INITIATED DURING | | THIS EVENT. THE RI WILL BE INFORMED. R3DO (PEDERSON) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27798 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/19/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:23 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/19/94 | +------------------------------------------------+EVENT TIME: 11:30[CDT]| |NRC NOTIFIED BY: VERCELLI |LAST UPDATE DATE: 09/19/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN STEAM LINE DRAIN LINE PIPING STRESSES EXCEEDED UFSAR CODE ALLOWABLE | | LIMITS BUT ARE WITHIN REQUIREMENTS OF THEIR SAFETY RELATED PIPING SYSTEM | | OPERABILITY CRITERIA. | | | | AN ANALYSIS OF THE MAIN STEAM LINE DRAIN PIPING (BEING PERFORMED FOR DESIGN | | CHANGE TO REPLACE 220-1 AND 2); IDENTIFIED THAT THE PIPING STRESSES | | EXCEEDED UFSAR CODE ALLOWABLES. THE PIPING STRESSES ARE WITHIN THE | | REQUIREMENTS OF THE SAFETY RELATED PIPING SYSTEM OPERABILITY CRITERIA. A | | NEW DESIGN IS BEING MADE AND THE PIPING WILL BE REPLACED DURING THE NEXT | | REFUELING OUTAGE (SCHEDULED FOR MARCH 1995). | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27799 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 09/19/94 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 15:22 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 09/19/94 | +------------------------------------------------+EVENT TIME: 13:55[CDT]| |NRC NOTIFIED BY: PAT DECKER |LAST UPDATE DATE: 09/19/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOCAL LEAK RATE TESTING DETERMINED THAT ALL OUTBOARD MAIN STEAM LINE | | ISOLATION VALVES (4) EXCEEDED THEIR LEAKAGE LIMIT OF 11.5scfh AS SPECIFIED | | IN TECH SPEC 3.7.2.1. | | | | DURING THE PLANT REFUELING OUTAGE, WHILE PERFORMING APPENDIX "J" LOCAL LEAK | | RATE TESTING, MAIN STEAM LINE "B" (INBOARD & OUTBOARD MSIVs) HAD A LEAK | | RATE OF 2298scfh (TECH SPEC 3.7.2.1 LIMIT IS 11.5scfh). MAIN STEAM LINE (A, | | C, & D) OUTBOARD ISOLATION VALVES EXCEEDED THEIR LEAK RATE TECH SPEC LIMITS | | OF 11.5scfh. LICENSEE WILL REMOVE AND INSTALL ALL NEW OUTBOARD MSIVs AND | | REPAIR INBOARD MSIV "B". | | | | RESIDENT INSPECTION WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 27800 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 09/19/94 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 19:03 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 09/18/94 | | FABRICATION & SCRAP RECOVERY |EVENT TIME: 18:00[PDT]| | COMMERICAL LWR FUEL |LAST UPDATE DATE: 09/19/94 | | CITY: RICHLAND REGION: 4 +-----------------------------+ | COUNTY: BENTON STATE: WA |PERSON ORGANIZATION| |LICENSE#: SNM-1227 AGREEMENT: Y |TOM STETKA RDO | | DOCKET: 07001257 |JACK LINEHAN EO | +------------------------------------------------+ | |NRC NOTIFIED BY: L MAAS | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY TECHNICIAN DISCOVERED APPROXIMATELY 41kg OF 3.78 wt.% U-235 | | ENRICHED URANIUM DIOXIDE SPILLED OUT OF A POWDER PREPARATION HOOD. IT WAS | | CLEANED UP WITHIN TWO HOURS OF DISCOVERY. | | | | Mr. L MAAS OF SIEMENS POWER CORPORATION - NUCLEAR DIVISION, RICHLAND, WA | | MADE THIS REPORT PER NRC BULLETIN 91-01. | | | | ON 09/18/94 AT ABOUT 1800 PST, A HEALTH AND SAFETY TECHNICIAN (HST) | | DISCOVERED APPROXIMATELY 41kg OF 3.78 wt.% U-235 ENRICHED URANIUM DIOXIDE | | POWDER THAT HAD SPILLED OUT OF A HOOD IN THE POWDER PREPARATION AREA. THIS | | MATERIAL REMAINED IN A MODERATION CONTROL AREA ON A METAL DECK LOCATED | | APPROXIMATELY 15 FEET ABOVE THE MAIN FLOOR. | | | | THE HST NOTIFIED OPERATIONS MANAGEMENT WHO IMMEDIATELY SHUT DOWN THE | | AFFECTED EQUIPMENT AND IMMEDIATELY CONTACTED CRITICALITY SAFETY. THE | | AFFECTED EQUIPMENT REMAINED SHUT DOWN UNTIL COMPLETION OF NEEDED CORRECTIVE | | ACTIONS AND THE OBTAINING OF RESTART PERMISSION FROM SAFETY AND OPERATIONS | | MANAGEMENT. SPILL WAS CLEANED UP WITHIN TWO HOURS OF DISCOVERY . LICENSEE | | NOTIFIED WALNUT CREEK FIELD OFFICE (FRANK WENSLAWSKI & CHUCK HOOKER BY | | TELEPHONE OF THIS EVENT). | | | | THE SPILL DID NOT RESULT IN ANY UNDUE EXPOSURE TO PLANT PERSONNEL AND DID | | NOT RESULT IN ANY OFFSITE RELEASE OF RADIOACTIVE MATERIAL. CONDITIONS | | REQUIRED FOR CRITICALITY WERE NOT APPROACHED. A SIEMENS POWER CORPORATION | | INVESTIGATION IS CURRENTLY IN PROGRESS TO DETERMINE THE CAUSE OF THE SPILL | | AND APPROPRIATE CORRECTIVE ACTIONS. NO PRESS RELEASE OR FURTHER | | NOTIFICATIONS TO REGULATORY AGENCIES ARE ANTICIPATED. | | | | AREA WHERE SPILL OCCURRED WAS LAST CHECKED AT 1400 PST. THE SPILL WAS FOUND | | BY A PERSON DOING ROUTINE AIR SAMPLES IN THE AREA AT 1800 PST. LICENSEE | | SAID THAT IT APPEARS THAT THE DOOR TO THE HOOD ENCLOSURE WAS NOT PROPERLY | | LATCHED AND CAME OPEN CAUSING THE URANIUM DIOXIDE TO SPILL ONTO THE FLOOR. | | SPILL WAS IN LINE 2 (POWDER PREPARATION AREA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27801 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/20/94 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 05:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/20/94 | +------------------------------------------------+EVENT TIME: 01:05[CDT]| |NRC NOTIFIED BY: KRUGER |LAST UPDATE DATE: 09/20/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED AN AUTOMATIC REACTOR/TURBINE TRIP ON A LO-LO LEVEL | | SIGNAL ON THE "1C" S/G. | | | | IMMEDIATELY PRIOR TO THE TRIP, EFFORTS WERE IN PROGRESS TO REDUCE REACTOR | | POWER AND TURBINE LOAD FOLLOWING THE UNANTICIPATED TRIP OF THE #13 TURBINE | | DRIVEN MAIN FEEDWATER PUMP (THE CAUSE OF THIS PUMP TRIP IS BEING | | INVESTIGATED). AN AUX FEEDWATER ACTUATION(ESF) WAS RECEIVED, AS EXPECTED, | | DUE TO THE LO-LO S/G LEVEL SIGNAL. ALL COMPONENTS ACTUATED TO THEIR | | REQUIRED ESF POSITIONS. FOLLOWING THE REACTOR TRIP, ALL SYSTEMS RESPONDED | | AS DESIGNED WITH THE FOLLOWING EXCEPTIONS: | | | | 1) CONTROL BANK "D" ROD "M4" ROD BOTTOM LIGHT DID NOT FULLY ILLUMINATE. (AN | | INVESTIGATION IS BEING MADE TO DETERMINE THE CAUSE) | | | | 2) STARTUP S/G FEEDWATER PUMP RECIRC VALVE DID NOT CLOSE AFTER THE PUMP | | RECEIVED AN AUTO START SIGNAL FOLLOWING THE TRIP OF THE #13 TURBINE DRIVEN | | MAIN FEEDWATER PUMP. (THE CAUSE OF THIS FAILURE IS ALSO BEING INVESTIGATED) | | | | TROUBLESHOOTING IS IN PROGRESS ON THE DIGITAL ROD POSITION INDICATION | | SYSTEM TO DETERMINE THE CAUSE OF THE ROD BOTTOM LIGHT FAILURE. IT APPEARS | | THAT ALL RODS DID FULLY INSERT, HOWEVER, THEY DO USE THE ROD BOTTOM LIGHTS | | TO VERIFY ACCURATE ROD POSITION ON THE BOTTOM. THERE WAS NO SI AND NO | | SAFETY RELIEF VALVES OPENED. THE CURRENT HEAT SINK IS THE MAIN CONDENSER. | | ANOTHER PROBLEM SUBSEQUENT TO THE TRIP WAS THAT A STAINLESS STEEL FLEX TUBE | | BROKE ON THE "C" FEEDWATER ISOLATION BYPASS FLOW SWITCH. | | | | THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27802 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 09/20/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 06:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/20/94 | +------------------------------------------------+EVENT TIME: 02:05[CDT]| |NRC NOTIFIED BY: BEST |LAST UPDATE DATE: 09/20/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD THE RUNNING MAIN CONTROL ROOM VENTILATION TRAIN TO | | AUTOMATICALLY SHIFT TO THE MAKEUP MODE DUE TO A HIGH RADIATION SIGNAL. | | | | THIS SIGNAL WAS RECEIVED WHEN THE INTAKE RAD MONITOR "OPA233" REACHED ITS | | ALARM SETPOINT. SUBSEQUENTLY SEVERAL OTHER RAD MONITORS REACHED THEIR ALARM | | SETPOINTS. AS A RESULT OF THIS, SEVERAL AIR SAMPLES WERE TAKEN THROUGH OUT | | THE PLANT AND THE READINGS APPEARED TO BE NORMAL. IT APPEARS THAT THE CAUSE | | OF THE RAD MONITORS REACHING THEIR ALARM SETPOINTS WAS DUE TO AN | | ATMOSPHERIC TEMPERATURE INVERSION WHICH OCCURRED PRIOR TO THE ALARMS. ALL | | RADIATION MONITOR LEVELS RETURNED TO NORMAL WITHIN 45 MINS. THE RI WILL BE | | INFORMED. | +------------------------------------------------------------------------------+