U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/02/94 - 12/05/94 ** EVENT NUMBERS ** 28066 28098 28099 28100 28101 28102 28103 28104 28105 28106 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/24/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 02:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/24/94 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: RCHARD KRAMER |LAST UPDATE DATE: 12/02/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |MARTIN VIRGILIO EO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOE LOUZONIS FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 80 POWER OPERATION | 70 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED BASED ON TECH SPEC REQUIRED SHUTDOWN | | | | TECH SPEC 3.6.E.2 REQUIRES THE PLANT TO BE SHUTDOWN AND PRESSURE REDUCED TO | | LESS THAN 90 PSIG WITHIN 24 HOURS WHENEVER ONE SAFETY RELIEF VALVE IS | | DECLARED INOPERABLE. THE PLANT HAS DETERMINED ONE SRV TO BE INOPERABLE | | BASED ON A SLOW HEAT UP OF THE TORUS WATER (ABOUT 4-5 DEGREES F PER DAY). | | CURRENT TORUS TEMPERATURE IS 71 DEGREES F. | | | | THE LICENSEE'S CONCERN IS AN INCREASE IN THE LIFT PRESSURE OF THE SRV | | CAUSED BY AN INCREASE IN THE BACK PRESSURE ACTING ON THE SRV. THE | | LICENSEE'S EMERGENCY PLAN REQUIRES THE DECLARATION OF AN UNUSUAL EVENT | | WHENEVER A SHUTDOWN IS REQUIRED BY TECH SPECS. | | | | THE LICENSEE INTENDS TO SHUTDOWN THE PLANT AND PROCEED TO COLD SHUTDOWN TO | | MAKE REPAIRS TO THE SRV. THE SPECIFIC SRV INVOLVED HAS NOT BEEN | | DETERMINED, BUT IS BELIEVED TO BE THE E SRV BASED ON THE TEMPERATURE | | SENSORS IN THE TORUS. THE UNUSUAL EVENT CAN BE TERMINATED WHEN THE UNIT IS | | SHUTDOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS THE APPROPRIATE | | STATE AND LOCAL OFFICIALS. A PRESS RELEASE IS PLANNED. | | | | * * * UPDATE AT 1805 EST 11/24/94 BY KNOLL TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED WHEN REACTOR PRESSURE WAS REDUCED BELOW 90 | | PSIG AND THE LCO WAS EXITED. RI WILL BE INFORMED. | | | | | | * * * UPDATE AT 1110 ON 12/02/94 BY CLEARY ENTERED BY HOO JOLLIFFE * * * | | | | AFTER SHUTTING UNIT 1 DOWN ON 11/24/94, LICENSEE REMOVED 6 OF 6 SAFETY / | | RELIEF VALVE TOPWORK PILOT ASSEMBLIES AND SENT THEM TO WYLIE LABS TO BE | | BENCH TESTED. THE AS-FOUND LIFT PRESSURE DATA IS LISTED BELOW: | | | | SERIAL SET LIFT % PILOT ASSEMBLY | | NUMBER PRESSURE PRESSURE DIFFERENCE LEAKING | | 1221 1095 1162 6.1 YES | | 1220 1110 1211 9.1 NO | | 1041 1125 1209 7.5 YES | | 1219 1125 1155 2.7 YES | | 1035 1125 1156 2.8 YES | | 1222 1125 1150 2.2 YES | | | | LICENSEE INSTALLED NEW TOPWORK PILOT ASSEMBLIES IN PLACE OF THOSE SENT TO | | WYLIE LABS. | | | | LICENSEE PLANS TO SUBMIT AN LER ON THIS EVENT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO DOERFLEIN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28098 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/02/94 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 01:47 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/02/94 | +------------------------------------------------+EVENT TIME: 00:21[CST]| |NRC NOTIFIED BY: LES ANDERSON |LAST UPDATE DATE: 12/02/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 +------------------------------------------------------------------------------+ | LETDOWN ISOLATED ON LOSS OF THE OPERATING CHARGING PUMP | | | | A CONTAINMENT ISOLATION VALVE SHUT, STOPPING LETDOWN FLOW, DUE TO THE LOSS | | OF THE OPERATING CHARGING PUMP. ANOTHER CHARGING PUMP WAS STARTED AND | | LETDOWN FLOW WAS RESTORED. THE CAUSE OF THE CHARGING PUMP TRIP IS UNDER | | INVESTIGATION. | | | | THE PLANT HAS THREE POSITIVE DISPLACEMENT PUMPS, ONLY TWO OF WHICH ARE | | REQUIRED TO BE OPERABLE BY TECHNICAL SPECIFICATIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28099 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 12/02/94 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 11:01 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 12/02/94 | +------------------------------------------------+EVENT TIME: 07:13[CST]| |NRC NOTIFIED BY: RON DAVENPORT |LAST UPDATE DATE: 12/02/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 52 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR SCRAM CAUSED BY STATOR COOLING SYSTEM FAILURE SIGNAL | | | | AT 0713 THE MAIN TURBINE TRIPPED BECAUSE OF AN INVALID STATOR COOLING | | SYSTEM FAILURE SIGNAL. THE SIGNAL IS TERMED INVALID BECAUSE RECORDED | | TEMPERATURE AND FLOW READINGS WERE NORMAL. THE TURBINE TRIP CAUSED A | | REACTOR SCRAM. ALL RODS FULLY INSERTED. REACTOR WATER LEVEL REACHED THE | | LOW LEVEL SETPOINT OF 11 INCHES AS EXPECTED. THIS CAUSED CONTAINMENT | | ISOLATION GROUPS II, III, VI & VIII TO ISOLATE. CONTROL ROOM EMERGENCY | | VENTILATION REALIGNED AND THE STANDBY GAS TREATMENT SYSTEM STARTED. THE | | PLANT IS STABLE IN THE HOT SHUTDOWN MODE. | | | | THE CAUSE OF THE INVALID STATOR COOLING WATER SIGNAL IS BEING INVESTIGATED. | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. A PRESS RELEASE IS | | PLANNED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28100 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: RTI (GAMMA RADIATION STERILIZATION) |NOTIFICATION DATE: 12/02/94 | | CITY: SALEM REGION: 1 |NOTIFICATION TIME: 15:04 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 12/02/94 | |LICENSE#: 29-20900-01 AGREEMENT: N |EVENT TIME: 14:05[EST]| | DOCKET: |LAST UPDATE DATE: 12/02/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LARRY DOERFLEIN RDO | | |BILL BRACH EO | +------------------------------------------------+ | |NRC NOTIFIED BY: PAUL SHAPIRO | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |MAAA 36.83(a)(1) UNSHIELD STUCK SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SOURCE COULD NOT BE PLACED IN ITS SHIELDED POSITION FOR APPROXIMATELY 40 | | MINUTES AT RTI (ADDRESS IS 75 TILBURY RD., SALEM, NJ 08079). | | | | COBALT-60 (400,000 CURIES) SOURCE USED FOR GAMMA RADIATION SERIALIZATION OF | | MEDICAL DEVICES AND OTHER CONSUMER GOODS COULD NOT BE PLACED IN ITS | | SHIELDED POSITION FOR APPROXIMATELY 40 MINUTES. RADIATION SAFETY OFFICER | | SAID THAT AN OBJECT ON A CARRIER (CARRIES OBJECTS ON A TRACK WHICH PASSES | | THROUGH THE COBALT-60 RADIATION FIELD) SHIFTED IN ITS CARRIER AND SOMEHOW | | WAS ABLE TO LEAN AGAINST THE SHROUD WHICH PROTECTS THE COBALT-60 SOURCE AND | | PREVENTED IT FROM GOING INTO ITS SHIELDED POSITION. RSO SAID THAT THEY WERE | | ABLE TO EXTERNALLY ACTIVATE THE MOTOR THAT MOVED THE CARRIER AND WERE ABLE | | TO MOVE THE CARRIER FAR ENOUGH SO THAT THE SOURCE WAS ABLE TO GO BACK INTO | | ITS SHIELDED POSITION. RSO SAID THAT NOBODY WAS EXPOSED TO THE UNSHIELDED | | SOURCE. RSO SAID THAT TONY KIRKWOOD OF REGION ONE WAS NOTIFIED OF THIS | | EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28101 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 12/02/94 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 17:37 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 12/02/94 | +------------------------------------------------+EVENT TIME: 14:15[MST]| |NRC NOTIFIED BY: D KANITZ |LAST UPDATE DATE: 12/02/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE ISSUED A PRESS RELEASE STATING THAT APPROXIMATELY 300 DUCKS OUT OF | | 3000 DUCKS DIED OF BACTERIUM CLOSTRIDIUM BOTULINUM. NONE OF THE DUCKS WHICH | | DIED WERE ON THE ENDANGERED SPECIES LIST. LICENSEE NEEDED THE ASSISTANCE OF | | THE ARIZONA GAME & FISH DEPARTMENT AND THE US FISH & WILDLIFE DEPARTMENT TO | | DETERMINE WHAT KILLED THE DUCKS. | | | | NATURAL PHENOMENON APPEARS TO BE THE CAUSE OF DEATH OF APPROXIMATELY 300 | | DUCKS. ARIZONA PUBLIC SERVICE PERSONNEL AT PALO VERDE NUCLEAR GENERATING | | STATION DISCOVERED OVER THE PAST THREE DAYS APPROXIMATELY 300 DUCKS DEAD OR | | DYING OUT OF A POPULATION OF APPROXIMATELY 3000 IN THE FACILITIES | | EVAPORATIVE POND LOCATED APPROXIMATELY TWO MILES SOUTH OF THE PLANT. DURING | | OPERATION, WATER IS RECYCLED THROUGH THE PLANTS COOLING SYSTEM. ULTIMATELY | | THE NON-RADIOACTIVE WATER IS PUMPED INTO THE LINED PONDS FOR NATURAL | | EVAPORATION. SINCE COMMERCIAL OPERATIONS BEGAN IN 1986 THE 500 ACRES OF | | WATER SURFACE AREA HAS SERVED AS AN UNINTENTIONAL REFUGE FOR A LARGE NUMBER | | OF BIRDS. ARIZONA GAME & FISH DEPARTMENT AND THE US FISH & WILDLIFE | | SERVICES INITIAL EXAMINATION OF THE DEAD DUCKS BELIEVE THE CAUSE OF THEIR | | DEMISE WAS FROM AVIAN BOTULISM, A DISEASE RESULTING FROM INGESTION OF A | | TOXIN PRODUCED BY THE BACTERIA CLOSTRIDIUM BOTULINUM. NONE OF THE DUCKS | | WHICH DIED WERE ON THE ENDANGERED SPECIES LIST. | | | | RESIDENT INSPECTOR WAS INFORMED OF THIS PRESS RELEASE BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28102 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 12/02/94 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 19:54 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/02/94 | +------------------------------------------------+EVENT TIME: 15:15[CST]| |NRC NOTIFIED BY: LES ANDERSON |LAST UPDATE DATE: 12/02/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED MINNESOTA STATE POLLUTION CONTROL AGENCY THAT THEY | | SPILLED A FEW GALLONS OF TREATED WASTE WATER. | | | | WHILE DISCHARGING WATER WHICH HAD ALREADY BEEN TREATED AND NEUTRALIZED TO | | THE MISSISSIPPI RIVER, A SPILL OCCURRED AT A LOCATION ALONG THE DISCHARGE | | PIPE TO THE MISSISSIPPI RIVER (PIPE WAS UNDERGOING A MODIFICATION). SPILL | | WAS CONTAINED IN AN EXCAVATION SITE. WATER WAS PUMPED BACK INTO THE PIPE | | AND DISCHARGED TO THE MISSISSIPPI RIVER. LICENSEE NOTIFIED THE MINNESOTA | | STATE POLLUTION CONTROL AGENCY OF THE SPILL. | | | | RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28103 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 12/02/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 23:26 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/02/94 | +------------------------------------------------+EVENT TIME: 20:35[EST]| |NRC NOTIFIED BY: VICTOR WALZ |LAST UPDATE DATE: 12/02/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARY DOERFLEIN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT OPENING OF WRONG BREAKER CAUSED LOSS OF SHUTDOWN COOLING (SDC) | | FOR 39 MINUTES AND AUTOSTART OF TRAIN "B" OF THEIR STANDBY GAS TREATMENT | | SYSTEM (SBGT). | | | | LICENSEE WAS PERFORMING A SCHEDULED PROTECTIVE TAGOUT IN PREPARATION FOR | | WORK ON THEIR "B" EMERGENCY SERVICE WATER PUMP WHEN AN INCORRECT BREAKER | | WAS OPENED CAUSING A LOSS OF 600VAC VITAL BUS POWER TO MOTOR CONTROL | | CENTERS (MCCs) 261 & 263. THE LOSS OF POWER TO MCC- 261 & 263 RESULTED IN A | | SERIES OF AUTOMATIC ACTUATIONS OF THEIR ENGINEERED SAFETY FEATURES (ESF) | | SYSTEMS. THE ESF CAUSED A 1/2 REACTOR SCRAM SIGNAL TO THEIR RPS SYSTEM AND | | A PRIMARY CONTAINMENT GROUP 2 ISOLATION, WHICH IN TURN CAUSED SECONDARY | | CONTAINMENT ISOLATION SIGNAL. THE GROUP 2 PRIMARY CONTAINMENT ISOLATION | | SIGNAL CAUSED A LOSS OF THE "A" RHR PUMP WHICH WAS BEING USED FOR SDC. SBGT | | "B" AUTOMATICALLY AUTOSTARTED ON THE SECONDARY CONTAINMENT ISOLATION | | SIGNAL. LICENSEE RESTORED ELECTRICAL POWER TO MCC-261 & 263 AND THEN | | RESTORED OPERATION OF THE "A" RHR PUMP (SDC). SDC WAS LOST FOR | | APPROXIMATELY 39 MINUTES. REACTOR VESSEL WATER TEMPERATURE DURING THE 39 | | MINUTES WHEN SDC WAS NOT OPERATING INCREASED FROM 161 DEGREES F TO 165.5 | | DEGREES F. DOCUMENTATION USED FOR THE TAGGING OUT OF THE "B" ESW PUMP | | IDENTIFIED THE CORRECT BREAKER TO BE OPENED, AND THE LABEL ON THE BREAKER | | THAT WAS INCORRECTLY OPENED WAS PROPERLY LABELED. LICENSEE IS INVESTIGATING | | WHY THE INCORRECT BREAKER WAS OPENED. ALL SYSTEMS HAVE BEEN RESTORED TO | | THEIR PREVIOUS LINE UPS. LICENSEE SHUTDOWN THEIR REACTOR THREE DAYS AGO FOR | | A REFUELING OUTAGE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28104 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 12/04/94 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 12:26 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/04/94 | +------------------------------------------------+EVENT TIME: 00:43[EST]| |NRC NOTIFIED BY: McDOUGOLD |LAST UPDATE DATE: 12/04/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOERFLEIN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMPONENT COOLING WATER SYSTEM MAY NOT HAVE MET DESIGN REQUIREMENTS DURING | | ACCIDENT CONDITIONS DUE TO INCORRECT VALVE LINEUP. | | | | WHILE ALTERNATING HEAT EXCHANGERS IN THE COMPONENT COOLING WATER SYSTEM, AN | | OPERATOR MANIPULATED INCORRECT VALVES SUCH THAT ONE OF TWO SECONDARY | | COMPONENT COOLING (SCC) WATER HEAT EXCHANGERS HAD NO COMPONENT COOLING | | WATER FLOW, WHILE THE OTHER HAD NO SERVICE WATER FLOW, MAKING THE SCC TRAIN | | INOPERABLE. (THE SCC SYSTEM SUPPLIES COOLING WATER TO THE EMERGENCY DIESEL | | GENERATORS, ONE CVCS CHARGING PUMP, AND ONE RHR HEAT EXCHANGER, AMONG OTHER | | HEAT LOADS.) THE OPERATOR ALSO MISALIGNED THE PRIMARY COMPONENT COOLING | | (PCC) WATER HEATER EXCHANGERS SUCH THAT BOTH WERE BEING SUPPLIED BY THE | | SERVICE WATER SYSTEM, BUT ONLY ONE HEAT EXCHANGER HAD COMPONENT COOLING | | WATER FLOW. (THE PCC SYSTEM SUPPLIES COOLING WATER TO THE LOW PRESSURE | | INJECTION PUMPS, ONE CVCS CHARGING PUMP, AND ONE RHR HEAT EXCHANGER, AMONG | | OTHER LOADS.) | | | | THE OPERATOR IMMEDIATELY NOTICED HIS MISTAKE, WHICH WAS ALSO OBSERVED IN | | THE CONTROL ROOM DUE TO AN INCREASE IN SCC TEMPERATURE, AND RESTORED BOTH | | THE SCC AND PCC SYSTEMS TO THEIR CORRECT ALIGNMENTS. AFTER DISCUSSIONS | | WITH THE PLANT ENGINEERING STAFF, THE LICENSEE HAS DETERMINED THAT THE PCC | | SYSTEM MAY NOT HAVE PERFORMED ITS INTENDED FUNCTION DURING AN ACCIDENT DUE | | TO THE ISOLATION OF ONE OF THE HEAT EXCHANGERS. HOWEVER, THE LICENSEE DID | | NOT DECLARE THE PCC SYSTEM INOPERABLE, BECAUSE ONLY ONE OF THE HEAT | | EXCHANGERS IS REQUIRED TO BE IN SERVICE DURING NORMAL OPERATION. THE RI | | WILL BE INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28105 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/04/94 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 14:08 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/04/94 | +------------------------------------------------+EVENT TIME: 12:15[CST]| |NRC NOTIFIED BY: COYLE |LAST UPDATE DATE: 12/04/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHILLIPS 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 1 STARTUP | 1 STARTUP | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SUPPLY BREAKERS TO SEVERAL VALVES COULD TRIP IF VALVES ARE GIVEN SIGNAL TO | | REVERSE DIRECTION DURING MID-STROKE. | | | | ENGINEERING DEPARTMENT INVESTIGATION OF THE TRIP OF THE SUPPLY BREAKER FOR | | ISOLATION CONDENSER VALVE 2-1301-4, WHICH OCCURRED WHILE PLACING THE UNIT 2 | | ISOLATION CONDENSER INTO SERVICE (SEE EVENT #28074), DISCOVERED THAT THE | | CURRENT TRIP SETTING OF THE BREAKER WAS ADJUSTED TOO LOW TO PERMIT VALVE | | DIRECTION REVERSAL DURING STROKING OF THE VALVE (A DESIGN BASIS OF THE | | VALVE). IF VALVE DIRECTION IS REVERSED MID-STROKE, AN ELECTRICAL | | COUNTER-CURRENT OCCURS MOMENTARILY, CAUSING THE BREAKER TO TRIP ON | | INSTANTANEOUS OVERCURRENT. THE LICENSEE REPORTED THAT THE CURRENT TRIP | | SETTING HAD BEEN ADJUSTED IN ACCORDANCE WITH ESTABLISHED PROCEDURES, BUT | | THAT THESE PROCEDURES DID NOT TAKE THE COUNTER-CURRENT EFFECT INTO | | CONSIDERATION. | | | | THE ENGINEERING DEPARTMENT DETERMINED THAT UNIT 2 FEEDER BREAKERS 2-1301-1, | | 2-1301-4, 2-1301-1/4, AND 2/3-7504-A WERE ALL SUSCEPTIBLE TO TRIPPING IN | | THE EVENT OF VALVE DIRECTION REVERSAL. THESE BREAKERS HAVE BEEN READJUSTED | | TO PREVENT A RECURRENCE OF THE PROBLEM. ON UNIT 3, BREAKERS 3-1201-1, | | 3-1301-1, 3-1301-4, 3-1301-2, 3-1301-1/4, AND 3-2301-4 HAVE BEEN IDENTIFIED | | BY THE LICENSEE AS BEING SUSCEPTIBLE TO TRIPPING UNDER THE ABOVE | | CONDITIONS. THE LICENSEE PLANS TO READJUST THESE BREAKERS DURING A SHORT | | OUTAGE SCHEDULED FOR 1/16/95. THE RI HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28106 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 12/04/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 23:20 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/04/94 | +------------------------------------------------+EVENT TIME: 19:59[CST]| |NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 12/04/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |COLLINS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM FROM 100% POWER DUE TO CLOSURE OF ALL MSIVs. | | | | WHILE PERFORMING SURVEILLANCE TEST PROCEDURE STP-058-4501, "CONTAINMENT AND | | DRYWELL MANUAL ISOLATION ACTUATION MONTHLY FUNCTIONAL TEST," A FULL MAIN | | STEAM ISOLATION VALVE ISOLATION OCCURRED AS A DIRECT RESULT OF THE TEST. | | THE MSIV ISOLATION CAUSED AN AUTOMATIC REACTOR SCRAM. ALL RODS FULLY | | INSERTED. SEVERAL SAFETY/RELIEF VALVES LIFTED TO RELIEVE PRESSURE, WHICH | | REACHED A MAXIMUM OF 1064 PSIG IMMEDIATELY FOLLOWING THE SCRAM. THE MSIVs | | HAVE BEEN REOPENED, AND PRESSURE IS BEING CONTROLLED USING THE MAIN | | CONDENSER. REACTOR VESSEL WATER LEVEL DECREASED TO APPROXIMATELY +10 | | INCHES FOLLOWING THE SCRAM, AND NORMAL FEEDWATER MAKEUP WAS USED TO CONTROL | | VESSEL LEVEL. ALL OTHER SYSTEMS FUNCTIONED AS DESIGNED. | | | | THE MANUAL INITIATION LOGIC FOR MSIV ISOLATION REQUIRES THAT 2/4 | | PUSHBUTTONS BE DEPRESSED TO SEAL IN THE ISOLATION. DEPRESSING ONE BUTTON | | SEALS IN A HALF-ISOLATION, BUT DOES NOT CAUSE ANY VALVES TO CLOSE. THE | | LICENSEE BELIEVES THAT, DUE TO A PROCEDURAL ERROR, THE OPERATOR DID NOT | | RESET ONE OF THE PUSHBUTTONS BEFORE DEPRESSING A SECOND. THE LICENSEE | | INTENDS TO PROCEED INTO A SHORT OUTAGE BEFORE RESTARTING THE UNIT. THE RI | | HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+