U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/16/95 - 06/19/95 ** EVENT NUMBERS ** 28955 28956 28957 28958 28959 28960 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28955 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 06/16/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:25 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: WIDAY |LAST UPDATE DATE: 06/16/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THE BUTTERFLY VALVE MANUFACTURED BY FISHER | | CONTROLS WAS SUPPLIED AS AN AIR-TO-OPEN VALVE INSTEAD OF AN AIR-TO-CLOSE | | VALVE. THIS VALVE IS A BASIC COMPONENT IN THE SERVICE WATER OUTLET FOR | | CONTAINMENT RECIRCULATION FAN COOLERS, A SAFETY HAZARD COULD BE CREATED BY | | SUCH A DEFECT, WHICH WOULD CAUSE THE LOSS OF SERVICE WATER TO THE FAN | | COOLERS. CORRECTIVE ACTION WAS COMPLETED WHEN THEY ALTERED THE ACTUATOR | | LEVER WHICH RESULTED IN THE VALVE FUNCTIONING CORRECTLY. THIS VALVE WAS | | PURCHASED AS A REPLACEMENT FOR A SPECIFIC SERIAL NUMBERED ITEM. THE | | ORIGINAL ENGINEERING REQUIREMENTS FOR THIS VALVE STIPULATED AIR-TO-CLOSE | | OPERATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28956 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/16/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 13:54 [ET]| |RX TYPE: [3] CE |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 12:00[CDT]| |NRC NOTIFIED BY: PENDERGRASS |LAST UPDATE DATE: 06/16/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS - SHUTDOWN COOLING VALVE FOUND TO BE INOPERABLE | | | | ON 6/11/95 AT 1311, WHILE MAKING PREPARATIONS TO PLACE SHUTDOWN COOLING IN | | SERVICE, THE TRAIN "B" SUCTION VALVE (SI-405B) WOULD NOT FULLY OPEN. THE | | VALVE WAS DECLARED INOPERABLE. FURTHER INVESTIGATION REVEALED THAT THE | | HYDRAULIC OIL RESERVOIR LEVEL WAS LOW. THE LICENSEE DISCOVERED A SMALL OIL | | LEAK WHICH EXPLAINED THE LOW LEVEL. REPAIRS WERE MADE AND THE VALVE WAS | | RETURNED TO OPERABILITY. | | | | THE EXACT TIME AT WHICH THE VALVE BECAME INOPERABLE IS UNKNOWN. THEREFORE, | | THE LICENSEE CONCLUDED THAT THEY MAY HAVE OPERATED FOR SOME PROLONGED | | PERIOD OF TIME WITH THE VALVE (AND ONE TRAIN OF SHUTDOWN COOLING) | | INOPERABLE. THE LAST TIME OPERABILITY WAS VERIFIED WAS APRIL 1994. THIS | | PLACED THE PLANT IN A CONDITION OUTSIDE OF DESIGN BASIS. THE ENGINEERING | | REVIEW WHICH LED TO THIS CONCLUSION WAS COMPLETED AT 1200 CDT TODAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28957 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR |NOTIFICATION DATE: 06/16/95 | | CITY: OKLAHOMA CITY REGION: 4 |NOTIFICATION TIME: 15:15 [ET]| | COUNTY: STATE: OK |EVENT DATE: 06/13/95 | |LICENSE#: 35-23359-01MD AGREEMENT: N |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 06/16/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: PELLIGRINO | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBE 30.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SYNCOR - FUME HOOD FAILURE | | | | THE EVENT OCCURRED AT 7801 N. ROBINSON, SUITE D-2, OKLAHOMA CITY, OK 73116 | | | | A FUME HOOD WAS FOUND TURNED OFF AT 1200 ON 6/13/95. THE LAST TIME THE | | HOOD WAS NOTICED TO BE RUNNING WAS AT 0330 ON 6/13/95. THE HOOD CONTAINED | | SEALED VIALS OF IODINE AND XENON. THE HOOD HAS BEEN TURNED ON. | | | | THE LICENSEE PREVIOUSLY NOTIFIED THE REGIONAL OFFICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28958 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 06/16/95 | |UNIT: [1] [ ] [ ] STATE: MD |NOTIFICATION TIME: 20:05 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 19:17[EDT]| |NRC NOTIFIED BY: DENTON |LAST UPDATE DATE: 06/16/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF MAIN FEED - MANUAL REACTOR TRIP | | | | THE #12 MAIN FEED PUMP TRIPPED AT 1917 AND COULD NOT BE RESTORED. OPERATORS | | MANUALLY TRIPPED THE REACTOR. THE #11 MAIN FEED PUMP THEN TRIPPED. | | AUXILIARY FEED PUMPS STARTED AND RESTORED STEAM GENERATOR LEVEL. THE UNIT | | IS CURRENTLY STABLE IN HOT STANDBY. | | | | ALL RODS FULLY INSERTED. ALL SAFETY RELATED EQUIPMENT IS OPERABLE. STEAM | | IS BEING DUMPED TO THE MAIN CONDENSER AS NECESSARY TO REMOVE DECAY HEAT. | | | | THE CAUSE OF THE LOSS OF THE FEED PUMPS IS NOT KNOWN AND IS BEING | | INVESTIGATED. CALVERT COUNTY OFFICIALS WERE NOTIFIED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28959 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/18/95 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 11:37 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/18/95 | +------------------------------------------------+EVENT TIME: 10:50[CDT]| |NRC NOTIFIED BY: ANDERSON |LAST UPDATE DATE: 06/18/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI 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 +------------------------------------------------------------------------------+ | - THE "B" RPS MG SET TRIPPED CAUSING AN ESF ACTUATION - | | | | THE "B" RPS MG SET TRIPPED CAUSING PARTIAL GROUP 5 (REACTOR WATER CLEAN UP) | | AND GROUP 2 (SMALL BORE PIPING) ISOLATIONS. THE TRIP ALSO CAUSED A HALF | | SCRAM AND A HALF GROUP 1 (MSIV) ISOLATION. THE CAUSE OF THE MG TRIP IS | | UNKNOWN, BUT IT IS UNDER INVESTIGATION. | | | | THE "B" RPS BUS HAS BEEN POWERED FROM ITS ALTERNATE POWER SOURCE AND ALL | | SIGNALS HAVE BEEN RESET. PLANT RESTORATION IS IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28960 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/18/95 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 19:01 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/18/95 | +------------------------------------------------+EVENT TIME: 18:27[EDT]| |NRC NOTIFIED BY: DENNIS BEMAN |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP | | | | THE LOSS OF A SECONDARY POWER SUPPLY (UNIT SUB 14) CAUSED A LOSS OF BOTH | | EHC PUMPS ASSOCIATED WITH THE MAIN TURBINE. OPERATORS MANUALLY TRIPPED THE | | REACTOR BEFORE EHC PRESSURE LOWERED TO ITS TRIP SETPOINT. ALL RODS FULLY | | INSERTED. | | | | EMERGENCY FEEDWATER (EFW) STARTED ON LOW STEAM GENERATOR LEVELS. S/G LEVEL | | HAS BEEN RECOVERED. DECAY HEAT IS BEING REMOVED VIA THE S/G ATMOSPHERIC | | DUMPS. THE PLANT IS STABLE IN HOT STANDBY. | | | | DURING THE EVENT THE "D" REHEATER DRAIN TANK HIGH LEVEL DUMP STUCK CLOSED | | AND THE "A" HEATER DRAIN PUMP DID NOT TRIP. THE PUMP WAS MANUALLY TRIPPED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. A PRESS RELEASE IS | | PLANNED. | | | | ***UPDATE 06/19/95 @ 0430 EDT BY BEMIS TAKEN BY MACKINNON*** | | | | LOSS OF THE POWER SUPPLY MENTIONED ABOVE CAUSED A LOSS OF THE SEAL STEAM | | SUPPLY TO THE MAIN TURBINE SEALS WHICH CAUSED A PARTIAL LOSS OF MAIN | | CONDENSER VACUUM. THE AUXILIARY BOILER WAS SUPPLYING STEAM TO THE MAIN | | TURBINE SEALS. WHEN POWER WAS LOST IT CAUSED THE AUXILIARY BOILER | | DEMINERALIZER WATER PUMP (SUPPLYING WATER TO THE AUXILIARY BOILER) TO | | DEENERGIZE. THIS IS WHY LICENSEE USED THEIR S/G ATMOSPHERIC DUMPS. STEAM | | DUMP BYPASS CONTROL SYSTEM WAS FULLY OPERABLE WITHIN ONE HOUR AFTER THE | | REACTOR TRIP. | +------------------------------------------------------------------------------+