U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/28/95 - 11/29/95 ** EVENT NUMBERS ** 29648 29649 29650 29651 29652 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29648 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/28/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 08:05 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/28/95 | +------------------------------------------------+EVENT TIME: 05:19[CST]| |NRC NOTIFIED BY: SMART |LAST UPDATE DATE: 11/28/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLAYTON 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 87 POWER OPERATION | 87 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR PROTECTION SYSTEM HALF SCRAM SIGNAL AND PRIMARY CONTAINMENT | | ISOLATIONS DUE TO TRIP OF RPS MOTOR GENERATOR SET | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THE UNIT ONE 'B' REACTOR PROTECTION SYSTEM (RPS) MOTOR GENERATOR TRIPPED | | RESULTING IN A LOSS OF POWER TO THE 'B' RPS BUS. THIS CAUSED A REACTOR | | HALF-SCRAM AND PRIMARY CONTAINMENT ISOLATION BY GROUPS 2, 3, 4, 5, AND 10. | | POWER TO 'B' RPS BUS WAS RESTORED FROM ITS ALTERNATE SOURCE, AND SYSTEMS | | ARE BEING RESTORED TO A NORMAL LINEUP. ALL SYSTEMS PERFORMED AS EXPECTED. | | THE CAUSE OF THE TRIP OF THE MOTOR GENERATOR IS NOT KNOWN AT THIS TIME." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29649 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ATLANTIC GEOTECHNICAL SERVICES |NOTIFICATION DATE: 11/28/95 | | CITY: ASHLAND REGION: 2 |NOTIFICATION TIME: 13:17 [ET]| | COUNTY: STATE: VA |EVENT DATE: 11/28/95 | |LICENSE#: 45-25191-01 AGREEMENT: N |EVENT TIME: 00:32[EST]| | DOCKET: |LAST UPDATE DATE: 11/28/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KERRY LANDIS (R2) RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JINNY NOGGLE |ROGER HANNAH (R2) PAO | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |FLOM 20.402(a) THEFT/DIVERSION LNM | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THEFT OF RADIOLOGICAL MATERIALS | | | | CALL BACK NUMBER: REFER TO THE OPERATIONS CENTER LOG FOR CONTACT NUMBERS | | | | ISOTOPE: AMERICIUM/BERYLLIUM-241 AND CESIUM-137 | | | | QUANTITY(Ci): 50 MILLICURIES AND 10 MILLICURIES, RESPECTIVELY | | | | CHEMICAL/PHYSICAL FORM: TWO SOURCES INSIDE AN MC3-SERIES CAMPBELL-PACIFIC | | MOISTURE DENSITY GAUGE (THE GAUGE WAS LABELLED WITH A RADIOACTIVE | | YELLOW-II LABEL.) | | | | DESCRIPTION OF CAUSE OF THE LOSS/THEFT: AT APPROXIMATELY 00:30 ON NOVEMBER | | 28, 1995, AN MC3-SERIES CAMPBELL-PACIFIC MOISTURE DENSITY GAUGE WAS STOLEN | | FROM THE BACK OF A TRUCK WHICH WAS PARKED IN FRONT OF A RESIDENCE IN | | HOPEWELL, VIRGINIA. THE GAUGE HAD BEEN SECURED TO THE TRUCK WITH A CHAIN | | AND PADLOCK. THE THEFT WAS REPORTED TO THE LICENSEE'S OFFICE AT | | APPROXIMATELY 06:00. | | | | ACTIONS TAKEN/PLANNED TO RECOVER THE MATERIAL: THE LICENSEE CONTACTED THE | | HOPEWELL POLICE DEPARTMENT (OFFICER FRANK RILEY) AT APPROXIMATELY 06:00, | | AND AN OFFICER (DETECTIVE STEVENS) HAS BEEN ASSIGNED TO THE CASE. THE FIRE | | MARSHALL (JAMES R. KUHNS) ALSO CALLED THE LICENSEE FOR INFORMATION | | REGARDING THIS EVENT. IN ADDITION, THE LICENSEE CONTACTED THE NRC REGION 2 | | OFFICE (JERRY D. ENNIS). THE LICENSEE MAY CONTACT THE LOCAL NEWS PAPER AND | | TELEVISION STATIONS AND MAY OFFER A REWARD FOR THE RETURN OF THE GAUGE. | | | | * * * 16:30 NOVEMBER 28, 1995, UPDATE FROM NOGGLE TAKEN BY TROCINE * * * | | | | ONE OF THE SOURCES WAS INTERNAL TO THE GAUGE, AND THE HANDLE FOR THE OTHER | | SOURCE WAS LOCKED IN PLACE. THE GAUGE WAS LOCKED IN THE BACK OF THE TRUCK | | WITH A LOCKED CABLE AND CHAIN, AND IT WAS COVERED UP. APPARENTLY, A | | NEIGHBOR HEARD NOISES AT APPROXIMATELY 02:00 AND WOKE UP THE INDIVIDUAL | | RESPONSIBLE FOR THE GAUGE. THE INDIVIDUAL THAN NOTICED THAT THE GAUGE WAS | | NO LONGER IN THE TRUCK. | | | | THE DOSE RATE IF THE SOURCE WAS UNSHIELDED WOULD BE 10 MILLIREM PER HOUR AT | | 3 FEET. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (LANDIS) AND THE R2PAO | | (HANNAH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29650 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/28/95 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 14:13 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/28/95 | +------------------------------------------------+EVENT TIME: 12:33[CST]| |NRC NOTIFIED BY: JOE POWELL |LAST UPDATE DATE: 11/28/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE/REACTOR TRIP DUE TO TURBINE CONTROL SYSTEM POWER SUPPLY FAILURE | | | | WHILE REPLACING A DIGITAL ELECTRO-HYDRAULIC (DEH) SYSTEM QBO CARD (BINARY | | OUTPUT BOARD) THAT FEEDS ONE OF THE ALTERNATE TURBINE OVERSPEED PROTECTION | | CIRCUITRY CONTROLLERS, THE UNIT RECEIVED AN APPARENT DEH TURBINE CONTROL | | SYSTEM DC SUPPLY FAILURE WHICH RESULTED IN A TURBINE TRIP AND SUBSEQUENT | | AUTOMATIC REACTOR TRIP. ALL RODS FULLY INSERTED ON THE AUTOMATIC REACTOR | | TRIP, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. LETDOWN ISOLATED ON LOW | | PRESSURIZER LEVEL (15%) AS A RESULT OF THE COOLDOWN, AND AUXILIARY | | FEEDWATER AUTOMATICALLY STARTED. BOTH OF THESE ACTIONS WERE EXPECTED. STEAM | | DUMPS HANDLED THE DEMAND LOAD, AND NONE OF THE POWER OPERATED RELIEF VALVES | | LIFTED. THERE WERE NO TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR | | OPERATION ENTERED AS A RESULT OF THIS EVENT. THE CAUSE OF THE DC POWER | | SUPPLY FAILURE IS CURRENTLY UNDER INVESTIGATION. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3, AND LETDOWN HAS BEEN RETURNED TO | | SERVICE. AUXILIARY FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS, | | AND SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. PRESSURIZER HEATERS | | AND SPRAYS, NORMAL CHARGING AND LETDOWN, AND THE REACTOR COOLANT PUMPS ARE | | CURRENTLY BEING USED FOR PRIMARY PRESSURE, INVENTORY, AND TRANSPORT | | CONTROL. ALL EMERGENCY DIESEL GENERATORS ARE OPERABLE, AND OFFSITE POWER | | IS AVAILABLE. | | | | PRIOR TO THE EVENT, INTERMEDIATE RANGE CHANNEL 36 WAS OUT OF SERVICE. THE | | LICENSEE IS CURRENTLY EVALUATING THE PERFORMANCE OF THIS CHANNEL. IT IS | | REQUIRED TO BE REPAIRED PRIOR TO ENTRY INTO MODE 2. THE LICENSEE ALSO | | PLANS TO MAKE A CONTAINMENT ENTRY TO LOOK FOR OTHER PROBLEMS. THE LICENSEE | | NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29651 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 11/28/95 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 17:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/28/95 | +------------------------------------------------+EVENT TIME: 15:37[CST]| |NRC NOTIFIED BY: PAUL COX |LAST UPDATE DATE: 11/28/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPARENT FAILURE TO MAINTAIN THE HEIGHT LIMIT FOR MOVING NEW FUEL OVER THE | | NEW FUEL STORAGE RACKS | | | | DURING A REVIEW OF A SIMILAR EVENT AT MILLSTONE (REFER TO EVENT NUMBER | | 29634 FOR ADDITIONAL INFORMATION.), THE LICENSEE DISCOVERED THAT THE | | 3.5-FOOT HEIGHT LIMIT FOR MOVING NEW FUEL OVER THE NEW FUEL STORAGE RACKS | | WAS APPARENTLY EXCEEDED. THE FSAR FUEL DAMAGE ESTIMATES FOR AN ASSEMBLY | | DROPPED IN THE AREA OF THE NEW FUEL STORAGE RACKS WAS BASED UPON THE | | ASSEMBLIES BEING NO HIGHER THAN 3.5 FEET ABOVE THE FUEL RACKS. HOWEVER, | | FUEL HAS ACTUALLY BEEN MOVED APPROXIMATELY 6 FEET ABOVE THE RACK. | | | | THERE IS AN INTERLOCK ON THE FUEL HANDLING BRIDGE CRANE THAT WOULD PREVENT | | THIS FROM OCCURRING. HOWEVER, THE LARGE OVERHEAD CRANE THAT IS REQUIRED TO | | TO BE USED TO MOVE THE NEW FUEL FROM THE NEW FUEL RECEIPT AREA OTHER TO THE | | RACK DOES NOT HAVE THIS LIMIT. | | | | FUEL IS NOT BEING MOVED AT THIS TIME. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29652 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 11/29/95 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 03:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/28/95 | +------------------------------------------------+EVENT TIME: 22:15[PST]| |NRC NOTIFIED BY: BOB MAGRUDER |LAST UPDATE DATE: 11/29/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 | M/R Y 50 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIPPED MANUALLY IN ANTICIPATION OF AN AUTOMATIC TRIP FOLLOWING THE | | LOSS OF A MAIN FEED PUMP. | | | | THE UNIT HAD REACHED 50% POWER, AND WAS STABLE FOLLOWING A REFUELING | | OUTAGE. ONE MAIN FEEDWATER PUMP WAS IN SERVICE AND THE OTHER PUMP WAS OUT | | OF SERVICE FOR MAINTENANCE. THE OPERATING PUMP TRIPPED FOR REASONS THAT | | ARE NOT YET UNDERSTOOD. THE OPERATORS MANUALLY TRIPPED THE REACTOR IN | | ANTICIPATION OF A LOW LOW STEAM GENERATOR LEVEL AUTOMATIC TRIP. ALL | | CONTROL RODS INSERTED FULLY FOLLOWING THE TRIP. DECAY HEAT REMOVAL IS VIA | | STEAM DUMP VALVES TO THE MAIN CONDENSER. | | | | EMERGENCY DIESEL GENERATOR (EDG) "1-1" STARTED DUE TO LOW VOLTAGE ON BUS 1. | | EDG "1-1" DID NOT LOAD BECAUSE VOLTAGE TO BUS 1 RECOVERED DURING THE EDG | | START SEQUENCE. THE LICENSEE SUSPECTS THAT THE AUTOMATIC TRANSFER OF BUS 1 | | FROM THE MAIN TRANSFORMER TO THE START UP TRANSFORMER IS SLIGHTLY SLOWER | | THAN THE ACTUATION OF THE UNDER VOLTAGE RELAY THAT STARTS THE EDG. THE | | START OF EDG "1-1" HAS BEEN OBSERVED BY THE LICENSEE IN THE PAST. ALL | | AUXILIARY FEED WATER PUMPS ALSO STARTED DUE TO SHRINK IN THE STEAM | | GENERATORS FOLLOWING THE REACTOR TRIP. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+