U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/13/94 - 05/16/94 ** EVENT NUMBERS ** 27244 27245 27246 27247 27248 27249 27250 27251 27252 27253 27254 27255 27256 27257 27258 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 05/13/94 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 03:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/13/94 | +------------------------------------------------+EVENT TIME: 02:51[EDT]| |NRC NOTIFIED BY: SMITH |LAST UPDATE DATE: 05/13/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAD A TRIP OF THE CONTAINMENT GASEOUS RADIATION MONITOR, WHICH | | CAUSED A CONTAINMENT VENTILATION ISOLATION. | | | | WHILE ATTEMPTING TO DRAIN COLD LEG ACCUMULATORS TO THE REACTOR COOLANT | | DRAIN TANK (RCDT), THE DRAIN VALVES WERE OPENED PRIOR TO THE RCDT's PUMPS | | BEING STARTED. THIS CAUSED THE TANK TO FILL UP, WHICH CAUSED APPROXIMATELY | | FIVE GALLONS OF WATER TO COME OUT OF THE DRAIN TANK VENT. THE CONTAMINATED | | WATER CAUSED THE CONTAINMENT BUILDING GAS MONITOR TO REACH THE "TRIP 2" | | SETPOINT. THIS EVENT CAUSED THE "B" TRAIN CONTAINMENT PURGE VALVES TO | | CLOSE, THE REACTOR BUILDING EVACUATION ALARM TO SOUND AND OCCURRED DURING | | CORE ALTERATIONS. THERE WAS A FUEL ASSEMBLY IN THE MANIPULATOR CRANE AT | | THE TIME, AND IT WAS PLACED IN THE UPENDER, SET DOWN AND SENT TO THE POOL. | | THE EVACUATION WAS THEN COMPLETED. | | | | THE WATER THAT CAME OUT THE VENT AND ONTO THE FLOOR HAS RAISED THE | | BACKGROUND COUNT RATE, AND WILL BE CLEANED UP. THE SETPOINT FOR THE RAD | | MONITOR WILL NOW BE ADJUSTED BASED ON THE NEW BACKGROUND, AND THEN CORE | | ALTERATIONS WILL BE RESUMED. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27245 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 05/13/94 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 07:12 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/13/94 | +------------------------------------------------+EVENT TIME: 03:37[EDT]| |NRC NOTIFIED BY: STRICKLAND |LAST UPDATE DATE: 05/13/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE 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 +------------------------------------------------------------------------------+ | HPCI DECLARED INOP WHEN THE CONTROL POWER FUSE BLEW FOR A COOLING WATER | | VALVE. | | | | FOLLOWING A PARTIAL PERFORMANCE OF OPT-09.2 (HPCI SYSTEM OPERABILITY TEST), | | IT WAS NOTED BY THE AUXILIARY OPERATOR THAT THE HPCI COOLING WATER SUPPLY | | VALVE (1-E41-FO59) MOTOR CONTROL CENTER CUBICLE CLOSED INDICATION WAS NOT | | LIGHTED. EXPECTING A BLOWN BULB, THE OPERATOR PROCEEDED TO ATTEMPT TO | | REPLACE THE BULB. UPON REMOVAL OF THE BULB COVER, BUT PRIOR TO REMOVAL OF | | THE BULB, THE BULB BLEW OUT OF THE SOCKET WITH AN ACCOMPANYING FLASH. THIS | | RESULTED IN DAMAGE TO THE BULB SOCKET, AND A BLOWN CONTROL POWER FUSE. | | | | A LOSS OF THE COOLING WATER VALVE REMOVES THE ABILITY TO COOL THE HPCI LUBE | | OIL, THUS RENDERING HPCI INOPERABLE. HPCI WAS THEREFORE DECLARED | | INOPERABLE. ACTIONS TO REPLACE THE BULB SOCKET AND BULB WERE IMMEDIATELY | | INITIATED. THE "1-E41-F059" VALVE WAS SUCCESSFULLY STROKED AT 0616 EDT, | | AND HPCI WAS DECLARED OPERABLE. ALL OTHER ECCS's WERE OPERABLE DURING THIS | | EVENT. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/13/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 07:30 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/13/94 | +------------------------------------------------+EVENT TIME: 07:15[EDT]| |NRC NOTIFIED BY: STRONG |LAST UPDATE DATE: 05/13/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CHAFFEE EO | | |BAGWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CHARGING PUMP STARTED AND INJECTED TO VESSEL WHEN RE-SETTING ACTUATION | | RELAYS ASSOCIATED WITH THE PERFORMANCE OF LOSS OF NORMAL POWER TESTING. | | | | MILLSTONE 2 WAS PERFORMING LOSS OF NORMAL POWER TESTING THIS MORNING ON THE | | "Z2" EMERGENCY FACILITY. DURING THE COURSE OF RE-SETTING ACTUATION RELAYS | | (PRESSED THE SIAS RESET PUSHBUTTON), SOME ACTUATION MODULES ACTUATED. | | SPECIFICALLY, THE "B" CHARGING PUMP STARTED AND PROVIDED FLOW TO THE | | VESSEL, WHICH PROMPTED THE DECLARATION OF THE UNUSUAL EVENT. THE CHARGING | | PUMP WAS IMMEDIATELY SECURED AND THE UNUSUAL EVENT WAS TERMINATED AT THE | | SAME TIME AS THE DECLARATION. THE LICENSEE IS INVESTIGATING THE CAUSE OF | | THE ACTUATION, WHICH MAY BE RELATED TO THE NOISE GENERATED FROM THE NUMBER | | OF RELAYS BEING RESET AT THE SAME TIME. | | | | IN THE FUTURE (NEXT REFUELING OUTAGE), THEY MAY BE PUTTING IN SOME | | MODIFICATIONS TO INSTALL NOISE SUPPRESSION TO PREVENT FUTURE SIMILAR | | OCCURRENCES. THE UNIT IS IN THE PROCESS OF COMING OUT OF A SHORT OUTAGE | | FOR RCP SEAL REPLACEMENT AND A "B" EDG 18 MONTH SURVEILLANCE. THE LICENSEE | | INFORMED STATE AND LOCAL AUTHORITIES AND THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27247 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SHOREHAM REGION: 1 |NOTIFICATION DATE: 05/13/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 14:39 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/13/94 | +------------------------------------------------+EVENT TIME: 05:00[EDT]| |NRC NOTIFIED BY: PETER MILLER |LAST UPDATE DATE: 05/13/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NON-LICENSED CONTRACT SUPERVISOR TESTED POSITIVE FOR ALCOHOL. THE | | EMPLOYEE WAS TESTED FOR CAUSE. ACCESS TO THE SITE HAS BEEN TERMINATED. SEE | | HOO LOG FOR DETAILS. | | | | THE LICENSEE HAS INFORMED THE LOCAL NRC INSPECTOR (MIMITZ) OF THE EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27248 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/13/94 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:11 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/13/94 | +------------------------------------------------+EVENT TIME: 16:20[EDT]| |NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 05/13/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |NINF INFORMATION ONLY |MIKE BELL NMSS EO | | |DENNIS SOLLENBERGER SP | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS MAKING A REPORT DUE TO A CONTAMINATED DRUM BEING RECEIVED | | AT THE SITE. THE NOTIFICATION IS REQUIRED TO BE MADE TO THE NRC IN | | ACCORDANCE WITH 10 CFR 20.1906. | | | | AT 16:20 HOURS TWO DRUMS OF CONTAMINATED REACTOR COOLANT PUMP PARTS WERE | | RECEIVED AT INDIAN POINT STATION FROM A WESTINGHOUSE FACILITY IN CHESWICK | | PENNSYLVANIA VIA A COMMON CARRIER (YELLOW FREIGHT). ONE PACKAGE HAD A | | SURFACE CONTAMINATION LEVEL OF 2600 DPM PER 100 SQUARE CENTIMETERS | | EXCEEDING THE DOT LIMIT OF 2200 DPM PER 100 SQUARE CENTIMETERS FOR | | NON-EXCLUSIVE USE SHIPMENTS. | | | | THE PACKAGE IS CURRENTLY STORED IN A RADIOLOGICALLY CONTROLLED AREA. THE | | OTHER PACKAGE, PALLET, THE TRAILER BED, AND THE IMMEDIATE AREA AROUND THE | | TRUCK WERE SURVEYED AND FOUND TO BE CLEAN. THE TRUCK IS BEING RECALLED TO | | INDIAN POINT SO THE DRIVER OF THE TRUCK MAY ALSO BE SURVEYED. INDIAN POINT | | OFFICIALS HAVE BEEN IN CONTACT WITH WESTINGHOUSE AND YELLOW FREIGHT | | OFFICIALS CONCERNING THIS EVENT. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27249 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/15/94 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 00:49 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/14/94 | +------------------------------------------------+EVENT TIME: 22:56[EDT]| |NRC NOTIFIED BY: MICHAEL NEMCEK |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN GROBE 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | "B" TRAIN ANNULUS EXHAUST GAS TREATMENT SYSTEM AUTOSTARTED WHEN PLACED IN | | STANDBY. | | | | THE M15 "B" TRAIN ANNULUS EXHAUST GAS TREATMENT SYSTEM RECEIVED AN | | AUTOSTART SIGNAL WHILE BEING PLACED IN STANDBY READINESS. CAUSE OF THE | | AUTOSTART IS UNDER INVESTIGATION ALTHOUGH THE LICENSEE BELIEVES THAT IT MAY | | BE RELATED TO A DEFECTIVE DELTA-P LOW FLOW SWITCH SIGNALING THAT THE "A" | | TRAIN FAN IS EXPERIENCING LOW FLOW. WHEN THE "B" FAN WAS PLACED IN STANDBY, | | IT AUTOSTARTED. OPERATORS THEN PLACED THE SWITCH IN THE OFF POSITION | | STOPPING THE FAN. THE SWITCH WAS AGAIN PLACED IN STANDBY AND RESULTED IN A | | SECOND AUTOSTART. THE FAN WAS SECURED AND A TROUBLE REPORT INITIATED. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27250 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/15/94 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 00:49 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: MICHAEL NEMCEK |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN GROBE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE INTENDS TO PERFORM DYNAMIC VALVE TESTING PER NRC GENERIC | | LETTER 89-10 IN THE NEXT SEVERAL HOURS. A PREPLANNED ECCS INJECTION PER | | TEST INSTRUCTION TXI199 WILL OCCUR USING LPCI "B" PUMP THROUGH LPCI | | INJECTION VALVE "1E12F042B". A SPECIAL NON-PERIODIC REPORT "NP41" OF THE | | TEST RESULTS WILL BE FORWARDED TO THE NRC. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27251 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/15/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 05:36 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 01:49[CDT]| |NRC NOTIFIED BY: GREG NORRIS |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 +------------------------------------------------------------------------------+ | UNIT EXPERIENCED A LOSS OF NORMAL SERVICE WATER DURING TESTING POSSIBLY DUE | | TO A PROCEDURAL INADEQUACY. | | | | "DURING PERFORMANCE OF A DIVISION 2 SSW INSERVICE CHECK VALVE TEST, A LOW | | PRESSURE CONDITION WAS CREATED WHICH CAUSED A LOSS OF NORMAL SERVICE WATER | | WHEN THE DIVISION 2 HEADER REALIGNED TO THE STANDBY COOLING TOWER. THE LOSS | | OF NORMAL SERVICE WATER RESULTED IN A DIVISION 1 STANDBY SERVICE WATER | | INITIATION. DIVISION 2 STANDBY SERVICE WATER PUMPS WERE LOCKED OUT DURING | | THE EVENT. DIVISION 1 CONTROL BUILDING VENTILATION/CHILLERS TRIPPED DURING | | THE EVENT DUE TO LOW FLOW. TESTING WAS SUSPENDED AND THE AFFECTED SYSTEMS | | WERE RESTORED UNTIL THE INVESTIGATION IS COMPLETED." | | | | DIVISION 1 SHUTDOWN COOLING WAS INSERVICE AT THE TIME AND WAS NOT AFFECTED. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 27252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SPERRY-SUN DRILLING SERVICES |NOTIFICATION DATE: 05/15/94 | | CITY: HOUSTON REGION: 4 |NOTIFICATION TIME: 08:14 [ET]| | COUNTY: HARRIS STATE: TX |EVENT DATE: 05/06/94 | |LICENSE#: 42-26844-01 AGREEMENT: Y |EVENT TIME: 06:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/15/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM JOHNSON RDO | | | | +------------------------------------------------+DWIGHT CHAMBERLAIN REG4 | |NRC NOTIFIED BY: RICHARD ARSENAULT | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE REQUESTED PERMISSION TO ABANDON STUCK WELL LOGGING SOURCES. | | | | SPERRY-SUN DRILLING SERVICES LOCATED IN HOUSTON, TX REQUESTED PERMISSION TO | | ABANDON TWO SOURCES (AMERICIUM BERYLLIUM-241 [3 Ci] AND CESIUM-137 [2Ci]) | | STUCK IN THE VASTAR RESOURCES WELL "OCSG2137D-4" SIDETRACK #2 IN THE SOUTH | | PASS BLOCK #60 OF THE GULF OF MEXICO. THE SOURCES BECAME STUCK AT DEPTHS OF | | 11359 AND 11368 FT ON 5/6/94. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27253 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/15/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 14:00 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 10:30[PDT]| |NRC NOTIFIED BY: NORM HANCOCK |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL OFFSITE EMERGENCY SIRENS WERE RENDERED INOPERABLE DUE TO FLOODING AT | | THE BENTON COUNTY EMERGENCY DISPATCH CENTER IN KENNEWICK, WASHINGTON. | | | | THE OFFSITE EMERGENCY SIRENS ARE OPERATED FROM THIS LOCATION. THE AREA | | AFFECTED BY THE LOSS OF THE SIRENS INCLUDES; THE COLUMBIA RIVER, THE YAKIMA | | RIVER, SHOOTING RANGES AND AN RV PARK. THE LICENSEE WILL ATTEMPT TO REGAIN | | THE CAPABILITY TO OPERATE THE OFFSITE SIRENS FROM THE EOF. THE TIME | | ESTIMATE TO REGAIN THE CAPABILITY IS APPROXIMATELY 1 HOUR. OTHER FUNCTIONS | | THAT WOULD HAVE BEEN PERFORMED FROM THE EMERGENCY DISPATCH CENTER IN THE | | EVENT OF A PROBLEM AT THE PLANT HAVE ALREADY BEEN MOVED TO ALTERNATE | | LOCATIONS. | | | | THERE HAS BEEN HEAVY RAINFALL IN THE AREA WHICH CAUSED THE FLOODING. THE | | RAINFALL/FLOODING HAS NOT AFFECTED THE PLANT. | | | | THE LICENSE WILL INFORM THE RESIDENT INSPECTOR. | | | | * * * UPDATE 5/15/94 1635 FROM HANCOCK TAKEN BY SEBROSKY * * * | | THE ABILITY TO OPERATE THE EMERGENCY OFFSITE SIRENS FROM THE EMERGENCY | | DISPATCH CENTER IN KENNEWICK, WASHINGTON WAS REESTABLISHED AT 13:10 PDT. | | THE FLOODING HAS BEEN CONTROLLED AT THIS LOCATION, AND THE LICENSEE EXPECTS | | THE EMERGENCY DISPATCH CENTER TO BE FULLY OPERATIONAL AT 16:00 PDT. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. IN ADDITION THE DIVISION | | OF EMERGENCY MANAGEMENT FOR THE STATE OF WASHINGTON HAS BEEN INFORMED OF | | THE PROBLEM. HOO NOTIFIED R4DO(JOHNSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27254 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/15/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 13:25[EDT]| |NRC NOTIFIED BY: TOM BRADLEY |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 96 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM FROM 96% DUE TO LOW REACTOR VESSEL LEVEL. | | | | THE LICENSEE HAD REDUCED POWER TO 95% TO REMOVE THE 'A' REACTOR FEED PUMP | | FROM SERVICE IN PREPARATION FOR MAINTENANCE ON THE PUMP. THE LICENSEE WAS | | RETURNING TO 100% POWER WHEN REACTOR VESSEL LEVEL FLUCTUATIONS WERE | | NOTICED. REACTOR VESSEL LEVEL REACHED A HIGH OF 53 INCHES BEFORE THE LEVEL | | 3 REACTOR SCRAM SETPOINT (12 INCHES) WAS REACHED. | | | | ALL RODS FULLY INSERTED ON THE SCRAM AND THE LOWEST REACTOR VESSEL LEVEL | | REACHED WAS -9 INCHES. ALL ELECTRICAL BUSSES TRANSFERRED AS EXPECTED AND | | NO SAFETY RELIEF VALVES LIFTED. REACTOR VESSEL LEVEL IS BEING MAINTAINED | | BY THE REACTOR FEED PUMPS AND THE MAIN CONDENSER IS AVAILABLE AS A HEAT | | SINK. ALL ECCS AND EDGS ARE OPERABLE. | | | | FOR BACKGROUND INFORMATION HOPE CREEK HAS 3 REACTOR FEED PUMPS EACH WITH | | 50% CAPACITY. NORMALLY ALL THREE REACTOR FEED PUMPS ARE RUNNING. NORMAL | | OPERATING LEVEL IS 35 INCHES, LEVEL 5 IS 54 INCHES, LEVEL 4 IS 30 INCHES, | | LEVEL 3 IS 12 INCHES AND LEVEL 2 IS -38 INCHES. IN ADDITION A NEW DIGITAL | | FEEDWATER CONTROL SYSTEM WAS ADDED DURING THE LAST REFUELING OUTAGE. | | | | THE OPERATORS FIRST NOTICED THE LEVEL FLUCTUATIONS WHEN REACTOR VESSEL | | LEVEL REACHED LEVEL 4. WHEN REACTOR VESSEL LEVEL REACHED LEVEL 4 IT CAUSED | | RECIRC PUMP 'A' TO RUNBACK (WHICH IS EXPECTED WITH ONE OF THE THREE REACTOR | | FEED PUMPS REMOVED FROM SERVICE) HOWEVER, THE 'B' RECIRC PUMP DID NOT | | AUTOMATICALLY RUNBACK AS EXPECTED. | | | | IT WAS ALSO NOTED BY THE OPERATORS THAT THE TWO RUNNING REACTOR FEED PUMPS | | HAD AUTOMATICALLY SWITCHED TO THE MANUAL MODE OF OPERATION PRIOR TO THE | | SCRAM. AN OPERATOR WAS ATTEMPTING TO STABILIZE REACTOR VESSEL LEVEL | | MANUALLY AND ANOTHER OPERATOR WAS MANUALLY RUNNING BACK THE 'B' RECIRC PUMP | | WHEN THE SCRAM OCCURRED. THE OPERATOR WHO WAS CONTROLLING REACTOR VESSEL | | WATER LEVEL CONSIDERED THE CONTROLS TO BE RESPONDING SLOWLY. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE LEVEL FLUCTUATIONS. THE | | LICENSEE IS ALSO INVESTIGATING WHY THE FEEDWATER CONTROL SYSTEM | | AUTOMATICALLY SWITCHED TO THE MANUAL MODE OF OPERATIONS AND WHY THE | | FEEDWATER CONTROL SYSTEM APPEARED TO REACT SLOWLY IN THE MANUALLY MODE. IN | | ADDITION THE LICENSEE IS INVESTIGATING WHY THE 'B' RECIRC PUMP DID NOT | | AUTOMATICALLY RUNBACK WHEN LEVEL 4 WAS REACHED. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR AND HAS INFORMED LOWER | | ALLOWAYS CREEK TOWNSHIP OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27255 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 05/15/94 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 16:40[CDT]| |NRC NOTIFIED BY: JAMES BARNES |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE. | | | | THE HPCI SYSTEM WAS DECLARED INOPERABLE DUE TO A FLOW CONTROLLER FOR THE | | SYSTEM BEING REMOVED FROM SERVICE FOR REPAIR. THE LICENSEE HAS ENTERED A | | 14 DAY LCO DUE TO THE PROBLEM. ALL OTHER ECCS ARE OPERABLE AND THE RCIC | | SYSTEM IS ALSO OPERABLE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27256 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/15/94 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 19:25 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: PAUL HINNENKAMP |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 85 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM DUE TO AN APRM HI FLUX RPS SIGNAL. | | | | THE PLANT WAS AT APPROXIMATELY 85% DUE TO A PROBLEM WITH THE 'D' MOISTURE | | SEPARATOR DRAIN TANK CONTROLLER WHEN THE 'A' RECIRC PUMP FLOW SPIKED HIGH | | FOR UNKNOWN REASONS. THE 'B' RECIRC PUMP FLOW REMAINED ESSENTIALLY | | UNCHANGED. THE SPIKE IN THE 'A' RECIRC FLOW CAUSED POWER TO SPIKE TO | | APPROXIMATELY 105%. THE REACTOR SCRAMMED DUE TO AN APRM HI FLUX NEUTRON | | MONITORING RPS SIGNAL. | | | | ALL RODS FULLY INSERTED AND NO SAFETY RELIEF VALVES LIFTED. THE LOWEST | | REACTOR VESSEL LEVEL REACHED WAS -25 INCHES. (HPCI AND RCIC INITIATE AT | | -48 INCHES). REACTOR VESSEL LEVEL IS BEING MAINTAINED BY THE FEED SYSTEM. | | THE MAIN CONDENSER IS AVAILABLE AS A HEAT SINK. ALL ECCS AND EDGs ARE | | OPERABLE. THE NON-VITAL BUSSES HAVE BEEN ALIGNED TO OFFSITE POWER PER | | NORMAL OPERATING PROCEDURE. | | | | WHEN REACTOR VESSEL LEVEL REACHED ZERO INCHES DURING THE POST SCRAM | | RESPONSE IT GENERATED AN ADDITIONAL SCRAM SIGNAL AND ALSO CAUSED A GROUP 2 | | AND 3 PRIMARY CONTAINMENT ISOLATION SIGNAL. THE ISOLATION SIGNAL HAS BEEN | | RESET AND THE SYSTEMS AFFECTED HAVE BEEN RETURNED TO THEIR NORMAL | | ALIGNMENTS. | | | | THE CAUSE OF THE 'A' RECIRC PUMP SPIKE IN FLOW IS STILL BEING INVESTIGATED | | AND THE LICENSEE PLANS TO GO TO COLD SHUTDOWN CONDITIONS UNTIL THE | | INVESTIGATION IS COMPLETE. THE LICENSEE HAS INFORMED THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27257 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/15/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 22:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/15/94 | +------------------------------------------------+EVENT TIME: 18:27[CDT]| |NRC NOTIFIED BY: ROYCE BROWN |LAST UPDATE DATE: 05/15/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS START OF ONE OF THE THREE EMERGENCY DIESEL GENERATORS (EDG) | | ASSOCIATED WITH UNIT 2. (SEE EVENT # 27243 FOR A SIMILAR EVENT ASSOCIATED | | WITH UNIT 1) | | | | AT 18:27 CDT THE #22 EDG AUTO STARTED IN THE NON-EMERGENCY MODE FOR NO | | APPARENT REASON. THE EDG DID NOT LOAD ONTO THE BUS AND RAN NORMALLY UNTIL | | IT WAS SHUTDOWN AT 19:19 CDT. AT 21:32 THE STANDBY LINEUP FOR THE EDG WAS | | COMPLETED AND THE EDG WAS PLACED IN STANDBY. THE LICENSEE CONSIDERS THE | | #22 EDG OPERABLE. THE OTHER TWO DIESEL GENERATORS FOR UNIT 2 ARE ALSO | | CONSIDERED OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE AUTO-START OF THE #22 EDG. | | THE LICENSEE SUSPECTS THAT THE AUTO START OF THE #13 EDG ON 5/12/94 (EVENT | | #27243) AND THE AUTO-START OF THE #22 EDG ARE BOTH DUE TO NOISE IN THE DC | | CONTROL POWER FOR THE EDGS. THE #21 EDG ALSO HAD A PROBLEM WITH AUTO | | STARTS IN THE PAST (SEE EVENTS #26854, AND 27185). THE #21 EDG HAD A | | MODIFICATION THAT WAS DONE TO ITS CIRCUITRY TO PREVENT THE PROBLEM AND IT | | IS THE ONLY EDG AT SOUTH TEXAS TO HAVE SUCH A MODIFICATION. A VENDOR WILL | | BE AT THE SITE ON 5/16/94 TO PERFORM NOISE TRACES ON THE #13 AND THE #22 | | EDG. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/16/94 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 06:12 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/16/94 | +------------------------------------------------+EVENT TIME: 04:23[EDT]| |NRC NOTIFIED BY: C.N. SWENSON |LAST UPDATE DATE: 05/16/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED A RHR HIGH PRESSURE ISOLATION DURING FLUSHING DUE TO | | POSSIBLE OUT OF CALIBRATION PRESSURE SWITCHES. | | | | "WITH REACTOR PRESSURE APPROXIMATELY 33 PSIG THE RHR SHUTDOWN COOLING | | PIPING WAS BEING FLUSHED IN PREPARATION FOR RHR SHUTDOWN COOLING MODE. | | REACTOR LEVEL WAS RAISED TO +40 INCHES PER PROCEDURE TO ACCOMMODATE THE | | FLUSH. FOLLOWING THE FIRST FLUSH THE REACTOR LEVEL CONTROLLER OVERSHOT TO | | APPROXIMATELY +50 INCHES. THE COMBINATION OF REACTOR DOME PRESSURE AND THE | | WATER LEG PRESSURE CAUSED BY THE HIGH REACTOR LEVEL CAUSED THE SHUTDOWN | | COOLING HIGH PRESSURE ISOLATION SIGNAL TO ACTUATE. THE ISOLATION WENT TO | | COMPLETION AS EXPECTED. HOWEVER, THE ISOLATION WAS NOT EXPECTED AND THE | | POTENTIAL WAS NOT ADDRESSED IN THE OPERATING PROCEDURE. INVESTIGATION IS | | CONTINUING INTO POSSIBLE PROCEDURE ENHANCEMENT OR POSSIBLE OVERLY | | CONSERVATIVE OR OUT OF CALIBRATION PRESSURE SWITCHES." | | | | THE LICENSEE IS REVIEWING CALIBRATION SHEETS TO VERIFY THAT NORMAL +23 | | INCHES STATIC HEAD IS INCLUDED IN THE PRESSURE SWITCH SETPOINT OF 60.5 | | PSIG. WITH +50 INCHES STATIC HEAD AND A DOME PRESSURE OF 33 PSIG THE | | LICENSEE ESTIMATES THAT THE COMBINED PRESSURE SEEN BY THE HIGH PRESSURE | | SWITCH IS 57.5 PSIG. CURRENT INFORMATION SUGGESTS THAT A PRESSURE SWITCH IS | | OUT OF CALIBRATION. THE LICENSEE NOTED THAT THE LEVEL OVERSHOOT TO +50 | | INCHES HAD NOT BEEN EXPERIENCED IN THE PAST AND ATTRIBUTED THE CAUSE TO | | SLUGGISH CONTROLLER RESPONSE. THE LEVEL CONTROLLER SETPOINT WAS READJUSTED | | TO +33 INCHES WHICH RESULTED IN A LEVEL OVERSHOOT OF +40 INCHES AND THE RHR | | FLUSHES COMPLETED. CURRENTLY RHR LOOP "A" WITH PUMP "C" IS IN SERVICE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+