U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/19/95 - 06/20/95 ** EVENT NUMBERS ** 28960 28961 28962 28963 28964 +----------------------------------+ +-----------------------+ |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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28961 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/19/95 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 10:24 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: K KORTH |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI 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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF NORMAL AND EMERGENCY POWER TO THE EMERGENCY OPERATIONS FACILITY | | (EOF). | | | | AT APPROXIMATELY 0700 EDT THE BUILDING ATTENDANT ARRIVED AT THE FACILITY TO | | FIND THE EMERGENCY DIESEL GENERATOR RUNNING AND SUPPLYING POWER TO THE | | BUILDING. POWER WAS AVAILABLE TO THE ADJACENT SUBSTATION. AT APPROXIMATELY | | 0930 EDT THE DIESEL FAILED RESULTING IN A TOTAL LOSS OF POWER TO THE | | FACILITY. AT 0950 EDT THE NUCLEAR PLANT SUPERVISOR WAS INFORMED OF THE | | EVENT. REPAIRS AND ROOT CAUSE ANALYSIS ARE CURRENTLY UNDER WAY. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1201 EDT FROM KELLY KORTH TAKEN BY R. KARSCH * * * | | NORMAL OFF-SITE POWER WAS RESTORED AT 1025 EDT. THE CAUSE OF THE EDG START | | WAS AN AUTOMATIC TRANSFER SWITCH MALFUNCTION. THE EDG RAN FOR 62 HOURS | | UNTIL IT RAN OUT OF FUEL. R2DO (VERRELLI) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28962 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 06/19/95 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 12:14 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 09:30[EDT]| |NRC NOTIFIED BY: TERRY JONES |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FOLLOWING IS THE TEXT OF A FAX SUBMITTED BY THE LICENSEE: | | | | "IN NOVEMBER OF 1994, FPL DISCOVERED A DEFECT IN THE EMERGENCY BUS LOAD | | SEQUENCER SOFTWARE. THE DEFECT WAS REPORTED IN LER 250/94-005. AS PART OF | | THE CORRECTIVE ACTION FOR THAT DEFECT, FPL PERFORMED A DETAILED REVIEW OF | | ALL OF THE SEQUENCER SOFTWARE TO DETERMINE IF OTHER DEFECTS EXISTED." | | | | "AS A RESULT OF THAT REVIEW, A CONDITION HAS BEEN IDENTIFIED THAT, ABSENT | | MANUAL ACTION, COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION | | OF THE 480 VOLT LOAD CENTERS. IF A SAFETY INJECTION (SI) SIGNAL OCCURS | | 15.5 TO 16 SECONDS AFTER A LOSS OF OFFSITE POWER (LOOP) SIGNAL, THE 4.16 KV | | BREAKERS WHICH FEED THE 480 VOLT LOAD CENTER WILL RECEIVE SIMULTANEOUS | | CLOSE AND STRIP PULSES. WITH CONFLICTING SIGNALS, THE BREAKERS WILL NOT | | CLOSE." | | | | "THE UFSAR SAFETY ANALYSIS FOR SMALL BREAK LOCAs ASSUMES A LOOP COINCIDENT | | WITH THE REACTOR TRIP SIGNAL. FOR THE CASES ANALYZED IN THE UFSAR, THE SI | | SIGNAL IS ASSUMED TO OCCUR APPROXIMATELY 10 TO 40 SECONDS AFTER THE TRIP, | | DEPENDING ON THE SIZE OF THE BREAK. THE LOAD CENTERS MAY NOT PERFORM AS | | DESIGNED FOR A 0.5 SECOND PERIOD, DURING A SPECIFICALLY ANALYZED LOCA WITH | | NON-CONCURRENT LOOP." | | | | "TECHNICAL SPECIFICATION SAFETY LIMITS ARE NOT CHALLENGED AS A RESULT OF | | LOSS OF THE AUTOMATIC CLOSURE OF THE 480 VOLT LOAD CENTER SUPPLY BREAKERS. | | SUFFICIENT TIME IS AVAILABLE FOR CREDIBLE MANUAL OPERATOR ACTION TO | | MANUALLY CLOSE THE BREAKERS. THEREFORE THE LOAD CENTERS REMAIN OPERABLE." | | | | "THE PROBABILITY OF A SB LOCA OF THE EXACT SIZE TO RESULT IN THE SI SIGNAL | | 15.5 TO 16 SECONDS AFTER THE LOOP/REACTOR TRIP IS EXTREMELY LOW. | | PROBABILISTIC SAFETY ANALYSIS OF THE ANOMALY INDICATES AN INCREASE IN CORE | | DAMAGE FREQUENCY ON THE ORDER OF 1E-8 PER YEAR (BELOW THE EPRI PSA | | APPLICATION GUIDELINES), ASSUMING NO CREDIT FOR OPERATOR RECOVERY. | | THEREFORE THE ANOMALY IS NOT SAFETY SIGNIFICANT." | | | | "THE CONDITION WILL BE CORRECTED DURING THE NEXT REFUELING OUTAGE ON EACH | | UNIT. BOTH UNITS REMAIN IN MODE 1." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28963 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/19/95 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 14:05[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE FLOW CONTROL VALVE SETPOINT WHICH ISOLATES | | NON-SAFETY LOADS FROM THE EMERGENCY EQUIPMENT COOLING WATER (EECW) SYSTEM | | IS OUTSIDE ITS DESIGN BASIS. | | | | "2 FCV-67-50" (EECW ISOLATION VALVE) WAS FOUND BY POST MODIFICATION TESTING | | TO BE OUTSIDE THE DESIGN BASIS OF THE PLANT. IT WAS DETERMINED THAT THE | | AUTOMATIC CLOSURE SETPOINT FOR THE VALVE, WHICH CROSS CONNECTS EECW TO THE | | UNIT 2 REACTOR BUILDING CLOSED COOLING WATER (RBCCW), WAS SET IN A | | NON-CONSERVATIVE DIRECTION. A PRESSURE OF 67.5 PSI WAS DETERMINED TO BE | | REQUIRED TO ASSURE ADEQUATE COOLING OF THE EMERGENCY DIESEL, BUT THE | | CURRENT PRESSURE SETPOINT IS 64 PSI. THAT PRESSURE SETPOINT WAS ESTABLISHED | | DURING THE UNIT 2 RESTART TEST PROGRAM USING A TEST BASIS OF ONE EECW PUMP | | PER HEADER AND THE NEW TEST BASIS PROVIDES TWO EECW PUMPS PER HEADER. | | | | THE LICENSEE'S IMMEDIATE CORRECTIVE ACTION HAS BEEN TO CLOSE "2 FCV-67-50" | | TO PREVENT EECW FROM FEEDING RBCCW FOR NONESSENTIAL LOADS. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2114 EDT FROM MORROW TAKEN BY KARSCH * * * | | THE LICENSEE IS RETRACTING THIS EVENT. THE ACTUAL SETPOINT FOR THE VALVE | | WAS DETERMINED TO BE 69.8 +/- 1.0 PSIG. THE MINIMUM VALUE AT WHICH | | ISOLATION WOULD OCCUR IS 68.8 PSIG, WHICH IS SUFFICIENTLY ABOVE THE MINIMUM | | VALUE TO ASSURE ADEQUATE COOLING OF EMERGENCY EQUIPMENT LOADS. BASED ON THE | | ACTUAL VALVE SETPOINT, NO DESIGN-BASIS PROBLEM EXISTS. THEREFORE, THE | | LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. R2DO (VERRELLI) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28964 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 06/19/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 18:59 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/19/95 | +------------------------------------------------+EVENT TIME: 18:05[EDT]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 06/19/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL NORMAL AND EMERGENCY PHONE COMMUNICATIONS IN AND OUT OF THE SITE ARE | | INOPERABLE. THE CAUSE IS UNKNOWN. ALL FUEL HAS BEEN REMOVED FROM THE CORE. | | COMMUNICATION TO THE SITE VIA VERMONT YANKEE IS POSSIBLE. THE LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+