U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/19/96 - 07/22/96 ** EVENT NUMBERS ** 30766 30767 30768 30769 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30766 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY |NOTIFICATION DATE: 07/19/96 | | CITY: FORT SILL REGION: 4 |NOTIFICATION TIME: 11:28 [ET]| | COUNTY: STATE: OK |EVENT DATE: 06/28/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 14:20[CDT]| | DOCKET: |LAST UPDATE DATE: 07/19/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ILES | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE ARMY HAS INSPECTED ABOUT ALL OF THE BUILDINGS BEING DEMOLISHED WHICH | | THEY SUSPECT HAVE TRITIUM EXIT SIGNS AND ONLY FOUND ONE SIGN THAT WAS | | BROKEN. THEY HAD A RELEASE OF LESS THAN 3 CURIES FROM THE DAMAGED EXIT | | LIGHT. THE EXIT LIGHT HAS BEEN CLEANED UP, DOUBLE BAGGED, PLACED INTO A | | RADIOACTIVE WASTE DRUM AND STORED IN THE DESIGNATED RADIOACTIVE STORAGE | | AREA AT FORT SILL. THEY HAVE EVALUATED PERSONNEL IN THE AREA WHO MAY HAVE | | BEEN EXPOSED AND HAVE DETERMINED THAT NO ONE HAS BEEN CONTAMINATED. THE | | BUILDING HAS NOT YET BEEN CLEANED UP. THE REGION HAS BEEN NOTIFIED. | | | | HOO NOTE: SEE EVENT #30699. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30767 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 07/19/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:42 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 07/19/96 | +------------------------------------------------+EVENT TIME: 10:45[EDT]| |NRC NOTIFIED BY: JOE SKLARCZYK |LAST UPDATE DATE: 07/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 88 POWER OPERATION | 88 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SUCTION UNEXPECTEDLY SWITCHED FROM | | THE CONDENSATE STORAGE TANK TO THE SUPPRESSION POOL. | | | | INSTRUMENTATION AND CONTROL SYSTEM TECHNICIANS WERE WORKING ON EQUIPMENT IN | | THE CABINET CONTAINING THE INSTRUMENTS MEASURING CONDENSATE STORAGE TANK | | LEVEL AND SUPPLYING LOGIC SIGNALS CONTROLLING HPCI SUCTION. THE HPCI | | SUCTION FLOW PATH UNEXPECTEDLY SHIFTED FROM THE NORMAL SOURCE, THE | | CONDENSATE STORAGE TANK, TO THE SUPPRESSION POOL DUE TO AN INVALID LOW | | LEVEL SIGNAL FROM THE CONDENSATE STORAGE TANK. THE LICENSEE SUSPECTS THAT | | THE I&C TECHS WORKING IN THE CABINET MAY HAVE INADVERTENTLY CAUSED THE | | ACTUATION. THE SUCTION PATH HAS BEEN RESET AND THE LICENSEE IS CONTINUING | | TO INVESTIGATE THE ROOT CAUSE. HPCI WAS OPERABLE THROUGHOUT THIS EVENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30768 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/19/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 18:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/19/96 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: FRED PRIESTLEY |LAST UPDATE DATE: 07/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NON-SEISMICALLY QUALIFIED PURIFICATION LINE COULD BREAK DIVERTING FLOW TO | | THE SUCTION OF SAFETY RELATED ECCS PUMPS RESULTING IN INSUFFICIENT VOLUME | | OF WATER. | | | | THE LICENSEE DETERMINED THAT A BREAK IN THE PURIFICATION LINE FOR THE | | REFUELING WATER STORAGE TANK COULD DIVERT FLOW FROM THE SUCTION OF THE | | SAFETY-RELATED ECCS PUMPS PLACING THE PLANT IN AN UNANALYZED CONDITION AND | | SIGNIFICANTLY COMPROMISE PLANT SAFETY. THE PURIFICATION LINE IS NOT | | SEISMICALLY QUALIFIED AND IS NOT AUTOMATICALLY ISOLATED DURING A DESIGN | | BASIS EVENT. THE LICENSEE IS CONTINUING TO EVALUATE THE CONSEQUENCES OF | | THE BREAK ON ACCIDENT MITIGATION. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30769 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/19/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 20:29 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/19/96 | +------------------------------------------------+EVENT TIME: 19:40[EDT]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 07/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DESIGN INADEQUACIES OF PRIMARY COMPONENT COOLING (PCC) PIPING FOR COOLERS | | INSIDE CONTAINMENT COULD RUPTURE TUBING WITHIN THE COOLERS COMPROMISING | | CONTAINMENT INTEGRITY AND RENDERING THE "A" TRAIN OF ECCS INOPERABLE. | | | | THE LICENSEE DETERMINED THAT UPON ACTUATION OF CONTAINMENT SPRAY AN | | AUTOMATIC VALVE ISOLATES THE PCC RETURN FLOW FROM THE AIR COOLER AND AN | | INLET CHECK VALVE PREVENTS BACK FLOW TO THE PCC SYSTEM. SINCE THERE IS NO | | RELIEF VALVE IN THE ISOLATED PIPING LEG, AS CONTAINMENT HEATS UP THE | | TRAPPED FLUID PRESSURE INCREASES UNTIL THE PIPE'S DESIGN LIMIT IS EXCEEDED. | | | | RUPTURE OF THIS PIPING WOULD AFFECT BOTH THE CONTAINMENT'S INTEGRITY AND | | THE "A" TRAIN OF ECCS. THE LOSS OF PCC INVENTORY WHICH WOULD RESULT FROM | | THE FAILURE OF THE PCC PIPING COULD AFFECT THE PCC COOLED "A" TRAIN | | COMPONENTS. | | | | THE LICENSEE IS ADDING RELIEF VALVES IN THE AFFECTED SECTIONS OF PIPING. | | THE PLANT WILL BE SHUT DOWN IF THE RELIEF VALVES CANNOT BE INSTALLED PRIOR | | TO THE EXPIRATION OF A FOUR HOUR LCO PER TECH SPEC 3.11. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2232 EDT FROM EBERT TAKEN BY KARSCH * * * | | THE LICENSEE INITIATED A PLANT SHUTDOWN AT 2200 EDT. THE PRESENT POWER | | LEVEL IS 82%. POWER WILL DECREASE AT 15% PER HOUR. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. R1DO (TRAPP) NOTIFIED. | +------------------------------------------------------------------------------+