U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/31/97 - 08/01/97 ** EVENT NUMBERS ** 32704 32705 32706 32707 32708 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32704 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/31/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:38 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 00:52[EDT]| |NRC NOTIFIED BY: MICHELLE SAVINO |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 91 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR BLOWDOWN RADIATION MONITOR ACTUATION AND STEAM GENERATOR | | BLOWDOWN ISOLATION DUE TO HIGH ACTIVITY (COBALT) DURING POWER ASCENSION | | | | DURING A POWER ASCENSION, A STEAM GENERATOR BLOWDOWN RADIATION MONITOR | | TRIPPED ON HIGH ACTIVITY AND CAUSED THE STEAM GENERATOR BLOWDOWN VALVES TO | | ISOLATE. THE ALARM AND SETPOINT WERE RESET PER PLANT PROCEDURES, AND A | | MANUAL CHEMISTRY SAMPLE WAS TAKEN. THIS SAMPLE INDICATED AN INCREASE IN | | ACTIVITY, AND THE ISOTOPE CAUSING THE INCREASE WAS COBALT. THE LICENSEE | | STATED THAT SMALL AMOUNTS OF COBALT ARE EXPECTED WITH AN INCREASE IN | | REACTOR POWER AND THAT THIS WAS NOT AN INDICATION OF STEAM GENERATOR TUBE | | LEAKAGE. STEAM GENERATOR BLOWDOWN HAS BEEN RE-ESTABLISHED. ALL SYSTEMS | | FUNCTIONED AS REQUIRED, AND THERE WAS NOTHING THAT WAS UNUSUAL OR NOT | | UNDERSTOOD. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32705 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 07/31/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 05:56 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 03:55[CDT]| |NRC NOTIFIED BY: E. ROAN |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF SPDS AND OTHER COMPUTER FUNCTIONS | | | | DURING MAINTENANCE TO THE ALTERNATE POWER SUPPLY TO THE INVERTER FOR THE | | PLANT VAX COMPUTER, THE INVERTER TRIPPED AND CAUSED A LOSS OF THE PLANT | | COMPUTER. THIS RESULTED IN THE LOSS OF SPDS (SAFETY PARAMETER DISPLAY | | SYSTEM), ERDS (EMERGENCY RESPONSE DISPLAY SYSTEM), ERIS (EMERGENCY RESPONSE | | INFORMATION SYSTEM), AND DRMS (DIGITAL RADIATION MONITOR SYSTEM). THE | | INVERTER HAS BEEN RE-ENERGIZED, AND DRMS HAS BEEN RESTORED. THE LICENSEE | | IS WORKING TO RESTORE THE ERDS, SPDS, AND ERIS FUNCTIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1343 ON 7/31/97, FROM TURNER TAKEN BY WEAVER | | | | THE ERDS, SPDS, AND ERIS FUNCTIONS WERE RETURNED TO SERVICE AT 0915 CDT | | THIS MORNING. | | | | THE HEADQUARTERS OPERATIONS CENTER INFORMED THE R4DO (YANDELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32706 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/31/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:22 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/17/97 | +------------------------------------------------+EVENT TIME: 15:45[CDT]| |NRC NOTIFIED BY: DON COVEYOU |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A BROKEN SECTION OF A FUEL PIN IN A CONTROL BLADE STORAGE CELL | | | | THE FOLLOWING TEXT IS A PORTION OF THE LICENSEE'S FACSIMILE: | | | | "ON JULY 17, 1997, FUEL HANDLERS DISCOVERED A BROKEN SECTION OF A FUEL PIN | | IN A UNIT 2 CONTROL BLADE STORAGE CELL PREVIOUSLY BELIEVED TO BE EMPTY. | | THREE FEET AWAY, IN ANOTHER CELL, IS A FUEL PIN STORAGE CANISTER CONTAINING | | TWO FUEL PINS FROM A 1989 FUEL BUNDLE RECONSTITUTION." | | | | "BECAUSE CURRENT PLANT CONDITIONS DO NOT ALLOW FUEL MOVES, INITIAL VISUAL | | INSPECTIONS WERE UNABLE TO POSITIVELY IDENTIFY THE BROKEN SECTION. IT IS | | POSTULATED THAT THE BROKEN SECTION IS A PORTION OF ONE OF THE FUEL PINS IN | | THE CANISTER." | | | | "QUARTERLY SPECIAL NUCLEAR MATERIAL (SNM) PHYSICAL INVENTORIES FAILED TO | | VISUALLY IDENTIFY THE BROKEN SECTION, DUE TO ITS DEEP LOCATION IN THE CELL. | | THEY ALSO DID NOT IDENTIFY THE REMAINDER OF THE BROKEN PIN IN THE CANISTER, | | BECAUSE A BROKEN END WAS EXPECTED TO BE VISIBLE. THE PIN WAS KNOWN TO HAVE | | A LOWER END PLUG THAT SEVERED DURING OPERATION. THIS PIN WAS BELIEVED TO | | HAVE BEEN PLACED IN THE STORAGE CANISTER UPSIDE DOWN, EXPOSING THE EXPECTED | | BROKEN LOWER END PLUG. IT IS NOW BELIEVED THAT THE PIN WAS ORIGINALLY | | PLACED IN THE CANISTER WITH ITS BROKEN LOWER END PLUG AT THE BOTTOM, AND AN | | INTACT UPPER END PLUG AT THE TOP. THIS UPPER, INTACT, PORTION IS | | POSTULATED TO HAVE SUBSEQUENTLY BROKEN OFF, LANDING IN THE NEARBY CELL IN | | WHICH IT HAS BEEN DISCOVERED." | | | | "THIS EVENT IS BEING REPORTED UNDER 10 CFR 20.2201(a)[1](ii) DUE TO THE | | POTENTIAL FOR MISSING FUEL. INITIAL INSPECTIONS DID NOT IDENTIFY ANY STRAY | | PELLETS IN THE CELL CONTAINING THE BROKEN SEGMENT, BUT IT IS NOT POSSIBLE | | TO ACCOUNT FOR ALL PELLETS UNTIL FUEL MOVES ARE ALLOWED. THEREFORE, THE | | EXACT LOCATION OF ALL PELLETS IS NOT UNDERSTOOD." | | | | "RADIOLOGICAL HAZARDS FROM STRAY PELLETS OR A GASEOUS RELEASE HAVE BEEN | | EVALUATED AND ARE NEGLIGIBLE. A CRITICALITY ASSESSMENT HAS ALSO BEEN | | PERFORMED, WITH SATISFACTORY RESULTS." | | | | "A WRITTEN REPORT DETAILING THE EVENT AND THE INITIAL CORRECTIVE ACTIONS | | WILL FOLLOW WITHIN 30 DAYS OF THIS PHONE CALL, AS REQUIRED BY 10 CFR | | 20.2201(b)." | | | | "WHEN PLANT CONDITIONS ALLOW, THE FUEL PINS WILL BE MOVED AND INSPECTED. | | FOLLOWING THIS, A COMPLETE ROOT CAUSE EVALUATION WILL BE PERFORMED. A | | SUPPLEMENTAL [LICENSEE EVENT REPORT] WILL BE ISSUED." | | | | HOO COMMENTS: | | THE PLANT IS UNABLE TO MOVE FUEL BECAUSE OF SEVERAL INOPERABLE VENTILATION | | SYSTEMS (STANDBY GAS TREATMENT, CONTROL ROOM VENTILATION, AND OTHERS). THE | | LICENSEE IS POSTULATING THAT THE UPPER PORTION OF THE PIN WAS BROKEN OFF BY | | SOME OTHER MOVEMENT WITHIN THE SPENT FUEL POOL AND THAT THIS INITIAL PUSH | | CAUSED THE SEGMENT TO FALL INTO THE NEARBY CELL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32707 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/31/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 18:31 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 17:29[EDT]| |NRC NOTIFIED BY: TONY DINELLI |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A GASOLINE SPILL | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION OF A GASOLINE SPILL ONSITE. THE SPILL OCCURRED FROM A | | CONTRACTOR'S VEHICLE, AND IT HAS BEEN CLEANED UP. THE TOTAL AMOUNT SPILLED | | WAS ESTIMATED TO BE ONE GALLON. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32708 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/31/97 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 22:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 21:02[EDT]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 07/31/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED AUTOMATIC START OF THE TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP | | | | A PLANT OPERATOR CLEARED TAGS ON THE '23' AUXILIARY FEEDWATER (AFW) PUMP | | AND RESET THE TRIP VALVE AND OVERSPEED DEVICE FOR THE PUMP. THE PUMP THEN | | AUTOMATICALLY STARTED ABOUT FOUR TO FIVE MINUTES LATER WITHOUT A VALID | | ACTUATION SIGNAL. THE CAUSE OF THE AUTOMATIC START IS UNKNOWN, BUT IT WILL | | BE INVESTIGATED. | | | | THE AFW PUMP DID NOT INJECT WATER INTO THE STEAM GENERATORS. PUMP | | DISCHARGE WAS DIRECTED THROUGH A RECIRCULATION LINE BACK TO THE AFW TANK. | | STEAM GENERATOR LEVELS ARE BEING MAINTAINED BY THE MOTOR-DRIVEN AFW PUMPS. | | THE LICENSEE PLANS TO REMAIN IN MODE 4 UNTIL REPAIRS ARE COMPLETE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+