U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/17/95 - 02/21/95 ** EVENT NUMBERS ** 28404 28405 28406 28407 28408 28409 28410 28411 28412 28413 28414 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28404 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/17/95 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 08:17 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/16/95 | +------------------------------------------------+EVENT TIME: 18:00[EST]| |NRC NOTIFIED BY: DAVID NEFF |LAST UPDATE DATE: 02/17/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 0 STARTUP | 0 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A THIRD SUPERVISOR HAS ADMITTED TO DRUG USE. (SEE RELATED EVENT #28396) | | | | THE LICENSEE HAS BEEN CONDUCTING AN INVESTIGATION AS A RESULT OF A CREDIBLE | | ALLEGATION. THE TWO SUPERVISORS WHO WERE INVOLVED IN THE PREVIOUS REPORT | | (28396) IMPLICATED THE THIRD INDIVIDUAL. THIS INDIVIDUAL WAS QUESTIONED | | AND ADMITTED TO DRUG USE DURING AN INTERVIEW ON 2/16/95. RESULTS OF A DRUG | | TEST DONE ON THIS INDIVIDUAL CONDUCTED BETWEEN 2/11/95 AND 2/15/95 WERE | | NEGATIVE. THIS INDIVIDUAL DID NOT PERFORM SAFETY RELATED WORK. THIS | | INDIVIDUAL IS BEING EVALUATED UNDER THE EMPLOYEE ASSISTANCE PROGRAM. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE ALLEGATION. NO MORE | | SUPERVISORS ARE INVOLVED WITH THE ALLEGATION, HOWEVER, IT ALSO INVOLVES | | NON-SUPERVISORY PERSONNEL. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28405 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/17/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:00 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/17/95 | +------------------------------------------------+EVENT TIME: 09:50[EST]| |NRC NOTIFIED BY: BRYAN CROKE |LAST UPDATE DATE: 02/17/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPENDIX R LIGHTING REQUIREMENT NOT MET | | | | SUFFICIENT EMERGENCY LIGHTING WAS NOT PRESENT IN THE SERVICE WATER BAY TO | | MEET THE EIGHT HOUR REQUIREMENT OF APPENDIX R. THE EVENT CONSIDERED WAS A | | LOSS OF SERVICE WATER PUMPS DUE TO A FIRE IN THE CABLE VAULT ROOM. PRIOR TO | | RESTORING POWER TO THE PUMPS THE DISCHARGE VALVE MUST BE SHUT TO PREVENT | | WATER HAMMER. INADEQUATE EMERGENCY LIGHTING WAS PRESENT IN THE AREA OF THE | | DISCHARGE VALVES IN THE JUDGMENT OF THE ENGINEERING REVIEW PERSONNEL. THIS | | PROBLEM WAS DISCOVERED ON 2/3/95 DURING AN ENGINEERING REVIEW AND REPORTED | | TO THE CONTROL ROOM OPERATORS TODAY. | | | | THE LICENSEE TOOK THE IMMEDIATE CORRECTIVE ACTION OF PLACING FLASHLIGHTS IN | | THE AREA. PERMANENT CORRECTIVE ACTION CONSISTED OF INSTALLING EMERGENCY | | LIGHTING IN THE AREA OF THE DISCHARGE VALVES. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28406 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 02/17/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 15:28 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 02/17/95 | +------------------------------------------------+EVENT TIME: 14:50[EST]| |NRC NOTIFIED BY: NEUMAN |LAST UPDATE DATE: 02/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CASTO 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT NOTIFIED BY BABCOCK & WILCOX OF NON-CONSERVATIVE CALCULATIONAL | | RESULTS FROM EMERGENCY CORE COOLING SYSTEM COMPUTER CODE. | | | | THE LICENSEE WAS NOTIFIED BY B&W OF PROBLEMS WITH COMPUTER CODES USED TO | | PREDICT POST-LOCA MAXIMUM FUEL CLADDING TEMPERATURES, AS DESCRIBED IN 10 | | CFR 50.46(b)(1). (SEE RELATED NOTIFICATIONS FROM DAVIS-BESSE #28284 AND | | OCONEE #28286 REGARDING THIS PROBLEM.) THIS PROBLEM DOES NOT AFFECT THE | | CURRENTLY UTILIZED SAFETY LIMITS FOR CRYSTAL RIVER 3. WHEN PRESENT LIMITS | | ARE APPLIED TO THE COMPUTER CODES, THE CALCULATED ECCS WILL CONFORM TO THE | | ACCEPTANCE CRITERIA OF 10 CFR 50.46(b). THE LICENSEE STATED THAT THE | | PRESENT SAFETY LIMITS ARE NOT BASED UPON CALCULATED PEAK CLADDING | | TEMPERATURES AT THE 2 FOOT CORE ELEVATION AS AT OTHER B&W PLANTS. | | | | ALTHOUGH THIS CONDITION DOES NOT AFFECT CRYSTAL RIVER 3, THE LICENSEE IS | | MAKING THIS REPORT BASED UPON SUBSEQUENT DISCUSSIONS WITH THE NRC. THE NRC | | RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28407 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 02/18/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 02:00 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/18/95 | +------------------------------------------------+EVENT TIME: 01:00[CST]| |NRC NOTIFIED BY: J TILLS |LAST UPDATE DATE: 02/18/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |NINF INFORMATION ONLY |JACK ROE EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 93 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A 0.374 GALLON PER MINUTE (gpm) LEAK COMING FROM | | CONTROL ROD DRIVE (CRDM) # 35 SEAL. | | | | TOTAL REACTOR COOLANT SYSTEM LEAKAGE HAS INCREASED TO 0.571gpm OF WHICH | | APPROXIMATELY 0.374gpm HAS BEEN IDENTIFIED TO BE LEAKING FROM CONTROL ROD | | DRIVE # 35 SEAL. LEAKOFF TAILPIPE TEMPERATURE FOR CRDM # 35 INCREASED FROM | | 120 DEGREES F TO 248.1 DEGREES F. LICENSEE FIRST SAW AN INCREASE IN REACTOR | | COOLANT LEAKAGE AROUND 1600CST 02/17/95. AS A PRECAUTIONARY MEASURE | | LICENSEE IS GOING TO SLOWLY BRING THE UNIT DOWN IN POWER. IF NO SIGNIFICANT | | CHANGES IN LEAKAGE OCCUR, THE UNIT WILL BE OFF LINE IN APPROXIMATELY TWO OR | | THREE DAYS TO REPAIR THE LEAKING CRDM SEAL. LICENSEE SAID THAT THEY | | INITIALLY SAW A SLIGHT INCREASE IN CONTAINMENT AIRBORNE ACTIVITY BUT IT | | WENT BACK TO ITS NORMAL LEVEL WITHIN A SHORT PERIOD OF TIME. THERE HAS BEEN | | NO INCREASE IN CONTAINMENT HUMIDITY OR TEMPERATURE. | | LICENSEE SAID THAT ALL THEIR EMERGENCY CORE COOLING SYSTEMS AND THEIR | | EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED. | | | | RESIDENT INSPECTOR WILL BE NOTIFIED. | | | | HOO NOTE: | | DURING MORNING STATUS CHECK (0450EST 02/18/95) LICENSEE SAID THAT | | CONTAINMENT PARTICULATE IS AT 14,000cpm (NORMAL IS ABOUT 11,000cpm). | | HIGHEST CONTAINMENT PARTICULATE SEEN WAS AROUND 19,000cpm. LICENSEE SAID | | THAT THEY HAVE ORDERS TO MANUALLY TRIP THE PLANT IF IDENTIFIED REACTOR | | COOLANT SYSTEM LEAKAGE INCREASES TO 4gpm. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28408 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/18/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 02:06 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/18/95 | +------------------------------------------------+EVENT TIME: 00:50[EST]| |NRC NOTIFIED BY: D. MURPHY |LAST UPDATE DATE: 02/18/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BOB BORES RDO | |NINF INFORMATION ONLY |JACK ROE EO | | |MINDY LANDAU PAO | | |COWGILL REG1 | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FIRE BETWEEN # 22 & # 23 MAIN CONDENSER LASTED ABOUT 20 MINUTES BEFORE IT | | WAS EXTINGUISHED. NOBODY WAS INJURED BY THE FIRE. THIS EVENT WAS REPORTED | | PER MANAGEMENT DISCRETION. | | | | LICENSEE WAS IN THE PROCESS OF BURNING HOLES (15' ELEVATION) IN THE BOTTOM | | OF MAIN CONDENSER # 23 IN PREPARATIONS FOR REMOVING THE CONDENSER. FIRE | | WATCH WAS STATIONED INSIDE MAIN CONDENSER # 23 MONITORING THE PERSONS | | BURNING HOLES THROUGH THE BOTTOM OF THE CONDENSER. AT 0050EST STATION FIRE | | BRIGADE WAS DISPATCHED TO PUT OUT A FIRE BETWEEN MAIN CONDENSER # 22 & # | | 23. FLAMES WERE SEEN AS HIGH AS 36' ELEVATION AND SMOKE WAS SEEN AS HIGH AS | | THE 53' ELEVATION. BETWEEN 20 TO 25 PEOPLE WERE EVACUATED FROM THE TURBINE | | BUILDING BECAUSE OF THE FIRE. AT 0055EST LICENSEE CALLED THE VERPLANCK FIRE | | DEPARTMENT AND ASKED FOR THEIR ASSISTANCE. AT 0110EST THE FIRE WAS | | EXTINGUISHED AND A REFLASH FIRE WATCH WAS STATIONED. VERPLANCK FIRE | | DEPARTMENT ARRIVED ONSITE AFTER THE FIRE HAD ALREADY BEEN EXTINGUISHED. | | NOBODY WAS INJURED OR SUFFERED SMOKE INHALATION FROM THE FIRE. NO EQUIPMENT | | OR SYSTEMS WERE DAMAGED BY THE FIRE. LICENSEE THINKS THAT DEBRIS OR MAYBE | | OIL SOAKED CEMENT BETWEEN THE TWO CONDENSERS WAS IGNITED BY A SPARK FROM | | BURNING HOLES IN CONDENSER # 23. | | | | RESIDENT INSPECTOR WILL BE NOTIFIED. | | | | | | ****UPDATE 0650EST 02/18/95 BY EISENHUT TAKEN BY MACKINNON**** | | | | PLANT EMPLOYEE ON 15' LEVEL SAID THAT THE FLAME HEIGHT WAS ABOUT 3' IN | | HEIGHT AND THE PERSON ON THE 36' LEVEL COULD SEE THE FLAME BELOW. FIRE | | WATCH WAS A CONTRACTOR AND HE WAS INSIDE THE CONDENSER (THIS IS WHERE HE | | WAS SUPPOSED TO BE POSITIONED) BECAUSE THE DISTANCE BETWEEN CONDENSER # 22 | | & # 23 IS ABOUT 6". A NEWS REPORTER CAMERAMAN SHOWED UP AT THE FRONT GATE | | WITH A CAMERA. REGION (COWGILL) NOTIFIED. | | | | RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28409 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 02/18/95 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 02/18/95 | +------------------------------------------------+EVENT TIME: 12:28[PST]| |NRC NOTIFIED BY: HANCOCK |LAST UPDATE DATE: 02/18/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH 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 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM DURING TURBINE THROTTLE VALVE TESTING DUE TO | | PERSONNEL ERROR | | | | DURING MONTHLY SURVEILLANCE TESTING OF THE MAIN TURBINE THROTTLE VALVES, AN | | OPERATOR INADVERTENTLY OPERATED THE "RESET" LEVER INSTEAD OF THE "TEST" | | LEVER ON THE MAIN TURBINE FRONT STANDARD. WHEN THE TEST WAS PERFORMED, THE | | MAIN TURBINE AUTOMATICALLY TRIPPED, CAUSING AN AUTOMATIC REACTOR SCRAM DUE | | TO TURBINE GOVERNOR VALVE FAST CLOSURE. ALL CONTROL RODS INSERTED | | FOLLOWING THE SCRAM, ALTHOUGH ONE CONTROL ROD DOES NOT INDICATE ITS | | POSITION AT THIS TIME. THE LICENSEE STATED THAT THE AUTOMATIC SCRAM TIMER | | SYSTEM CONFIRMED THE INSERTION OF THIS PARTICULAR CONTROL ROD. THE ROD | | POSITION INDICATION SYSTEM IS PRESENTLY INDICATING A DATA FAULT ALARM. | | | | FOLLOWING THE SCRAM, REACTOR LEVEL SHRANK TO A LOW OF -4", THEN SWELLED TO | | A HIGH OF +60", CAUSING THE MAIN FEEDWATER PUMPS TO TRIP. (THE LICENSEE | | INDICATED THAT THIS IS NORMAL PLANT RESPONSE TO THIS TYPE OF EVENT.) THE | | LICENSEE USED THE REACTOR CORE ISOLATION COOLING SYSTEM TO CONTROL REACTOR | | VESSEL WATER LEVEL, AND HAS SINCE RESTARTED ONE OF THE MAIN FEEDWATER | | PUMPS. ALL OTHER SYSTEMS FUNCTIONED AS REQUIRED. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE 2319 2/18/95 BY CONSERRIERE TAKEN BY STRANSKY * * * | | | | LICENSEE PLANS TO MAKE A PRESS RELEASE REGARDING THIS EVENT. THE UNIT IS | | CURRENTLY PROCEEDING TO COLD SHUTDOWN. THE NRC RESIDENT HAS BEEN INFORMED. | | NOTIFIED R4DO (VANDENBURGH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28410 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/19/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 03:55 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/19/95 | +------------------------------------------------+EVENT TIME: 02:32[EST]| |NRC NOTIFIED BY: STAUBER |LAST UPDATE DATE: 02/19/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BOB BORES 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 +------------------------------------------------------------------------------+ | WHILE PREPARING FOR A CONTAINMENT ISOLATION PHASE "B" SURVEILLANCE TEST AN | | OPERATOR ERROR CAUSED AN INADVERTENT SAFETY INJECTION ACTUATION SIGNAL. | | | | WHILE PLACING "A" TRAIN OF THEIR SOLID STATE PROTECTION SYSTEM (SSPS) BACK | | IN SERVICE FOR A CONTAINMENT ISOLATION PHASE "B" SURVEILLANCE TEST | | PROCEDURE, AN OPERATOR PLACED THE "MODE SELECTION" SWITCH TO 'NORMAL' | | POSITION INSTEAD OF PLACING THE "INPUT ERROR INHIBIT" SWITCH TO ITS | | 'INHIBIT' POSITION (BOTH SWITCHES ARE LOCATED IN THE SAME CABINET). LOW | | PRESSURIZER PRESSURE AND LOW MAIN STEAM LINE PRESSURE SAFETY INJECTION | | SIGNALS WERE ALREADY IN BECAUSE OF PLANT CONDITIONS. WHEN THE MODE | | SELECTION SWITCH WAS REPOSITIONED TO ITS 'NORMAL' POSITION IT CAUSED THE | | FOLLOWING SAFETY INJECTION ACTUATIONS: EMERGENCY DIESEL GENERATOR "1" | | AUTOSTARTED - BUT DID NOT LOAD; VOLUME CONTROL TANK SUCTION ISOLATION VALVE | | TO THE CHARGING PUMPS ISOLATED; REFUELING WATER STORAGE TANK TO CHARGING | | PUMP SUCTION VALVE OPENED; BORIC ACID INJECTION TANK RECIRCULATION VALVE | | CLOSED (PVSS 884 'A'); BORIC ACID RECIRCULATION PUMP TRIPPED; NORMAL | | CHARGING HEADER MOTOR OPERATED ISOLATION VALVE (MOV CH289) SHUT; AND | | SEVERAL CONTAINMENT ISOLATION VALVES SHUT. ALL SYSTEMS HAVE BEEN RETURNED | | TO THEIR NORMAL LINEUP. PRESSURIZER LEVEL INCREASED A LITTLE DUE TO SEAL | | INJECTION. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28411 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/20/95 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 02:20 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/18/95 | +------------------------------------------------+EVENT TIME: 04:00[MST]| |NRC NOTIFIED BY: GRIGSBY |LAST UPDATE DATE: 02/20/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STARTUP (S/U) STRAINERS FOUND INSTALLED ON THE INLET SPOOL PIECE OF BOTH | | CONTAINMENT SPRAY (CS) PUMPS, "A" & "B". THIS CONDITION HAS EXISTED SINCE | | INITIAL STARTUP TESTING PERFORMED IN 1984. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE. | | | | "ON 02/17/95 AT 0330, A S/U STRAINER WAS FOUND INSTALLED ON THE INLET SPOOL | | PIECE OF "B" CS PUMP. ON 02/18/95 AT 0400, THE SAME CONDITION WAS FOUND TO | | EXIST ON THE "A" SIDE. AT THIS TIME, THE EFFECT ON THE OPERABILITY OF | | SYSTEMS HAS NOT BEEN DETERMINED, BUT THERE IS THE POTENTIAL FOR IMPACT TO | | EXIST, THEREFORE WE ARE REPORTING THE EVENT AT THIS TIME. THE EVENT SHOULD | | HAVE BEEN REPORTED WITHIN 4 HOURS OF DISCOVERY". | | | | THE STARTUP STRAINERS WERE INSTALLED DURING STARTUP TESTING BACK IN 1984. | | THEY SHOULD HAVE BEEN REMOVED AFTER STARTUP TESTING. THE STRAINERS WERE | | DISCOVERED WHILE DISASSEMBLING THE SPOOL PIECE FOR GASKET REPLACEMENT PER | | AN INSPECTION & MAINTENANCE PROCEDURE. LICENSEE SAID THAT THERE ARE NO | | PROCEDURES THAT CHECK THE SPOOL PIECES OF THE CS DURING PLANT OUTAGES. | | UNIT 3 AND UNIT 1 CONTAINMENT SPRAY SYSTEMS HAVE BEEN EVALUATED FOR STARTUP | | STRAINERS BEING INSTALLED AND THEY HAVE DETERMINED THAT NEITHER UNIT HAS | | STARTUP STRAINERS INSTALLED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28412 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 02/20/95 | | CITY: PITTSBURGH REGION: 1 |NOTIFICATION TIME: 10:30 [ET]| | COUNTY: STATE: PA |EVENT DATE: 02/20/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 10:00[EST]| | DOCKET: |LAST UPDATE DATE: 02/20/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: H SEPP |HAASS RVIB | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEF 21.21(b)(2) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FOLLOWING IS A PARTIAL TEXT OF A FACSIMILE FROM WESTINGHOUSE ELECTRIC | | CORPORATION, PITTSBURGH, PA. THIS PART 21 PERTAINS TO AN IDENTIFIED | | PRESSURE REDUCING SLEEVE LOCKNUT DEFECT FOR JHF MODEL SAFETY INJECTION PUMP | | MANUFACTURED BY INGERSOLL DRESSER PUMP (IDP) COMPANY. | | | | THIS FACSIMILE IS AN "UPDATE TO 10CFR21 REPORT CONTAINED IN WESTINGHOUSE | | LETTER NTD-NRC-94-4320, DATED 10/19/94 AND STATUS REPORT CONTAINED IN | | WESTINGHOUSE LETTER NTD-NRC-94-4361, DATED 12/21/94. | | REVIEW HAS BEEN COMPLETED AND INDICATES THAT SOME OF THE ADDITIONAL PUMP | | PARTS MAY ALSO CONSTITUTE A DEFECT, AS DEFINED IN 10CFR21, WHICH COULD | | CREATE A SUBSTANTIAL SAFETY HAZARD. IDP's EVALUATION RESULTS INDICATE THAT | | ALL 416 SS PARTS PROCESSED UNDER IDP HEAT NUMBERS # 15899 AND # 28144 ARE | | SUSCEPTIBLE TO THE SAME FAILURE MECHANISM AS THE PRESSURE REDUCING SLEEVE | | LOCKNUTS. " | | | | THIS ELEVEN PART FACSIMILE CALLS OUT THE FOLLOWING REACTOR PLANTS USING | | PARTS FROM HEAT # 15899 & HEAT # 28144: | | KANSAI, OHI 1 & 2; TVA, WATTS BARR 1 & 2; DUKE POWER, MCGUIRE 1& 2, CATAWBA | | 1 & 2; COMMONWEALTH EDISON, BRAIDWOOD 1 & 2,BYRON 1 & 2; WOLF CREEK NUCLEAR | | OPERATING COMPANY, WOLF CREEK. | | | | FOLLOWING REACTOR PLANTS COULD BE USING THE DEFECTIVE PARTS FROM THE HEAT | | NUMBERS LISTED ABOVE: | | ALABAMA POWER, FARLEY 2; COMMONWEALTH EDISON, ZION 1; CONSOLIDATED EDISON, | | INDIAN POINT; DUQUESNE LIGHT, BEAVER VALLEY 1; INDIANA MICHIGAN POWER, COOK | | 2; KANSAI ELECTRIC, OHI 1 & 2; NORTHERN STATES POWER, PRAIRE ISLAND 1 & 2; | | PORTLAND GENERAL ELECTRIC, TROJAN; PACIFIC GAS & ELECTRIC, DIABLO CANYON 2; | | AND PUBLIC SERVICE ELECTRIC AND GAS, SALEM 1 & 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28413 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/20/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 16:07 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/20/95 | +------------------------------------------------+EVENT TIME: 14:17[EST]| |NRC NOTIFIED BY: PATON |LAST UPDATE DATE: 02/20/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 Y 86 POWER OPERATION | 86 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RAD MONITOR FAILURES CAUSE MULTIPLE SYSTEM ISOLATIONS | | | | AT 1417 ON 2/20/95 VARIOUS NSSSS ACTUATIONS OCCURRED AS A RESULT OF | | FAILURES OF THE 'D' CHANNEL REACTOR ENCLOSURE VENTILATION RAD MONITOR AND | | THE 'D' CHANNEL REFUEL ENCLOSURE VENTILATION RAD MONITOR. SYSTEMS AFFECTED | | BY THESE SIGNALS INCLUDED THE 'B' POST ACCIDENT HYDROGEN RECOMBINER, | | DRYWELL NITROGEN BACKUP BLOCK VALVES, DRYWELL AND SUPPRESSION POOL | | ATMOSPHERIC SAMPLE ISOLATION VALVES, REACTOR RECIRCULATION PUMP SEAL PURGE | | BARRIER BLOCK, AND INSTRUMENT AIR TO INSTRUMENT GAS BARRIER BLOCK AND VENT. | | | | ALL SYSTEMS FUNCTIONED AS DESIGNED. | | | | THE 'D' MAIN STEAM LINE HIGH RADIATION MONITOR WAS ALSO AFFECTED, BUT DID | | NOT RESULT IN AN ACTUATION. THIS CHANNEL RESULTED IN A 'B2' HALF SCRAM AND | | A 'D' CHANNEL MSIV ISOLATION SIGNAL. | | | | INVESTIGATION BY PLANT STAFF FOUND A FAILED FUSE. THE FUSE WAS IN THE | | POWER SUPPLY TO THE NSSSS LOGIC TRAIN. THE FUSE WAS REPLACED AND THE | | ISOLATIONS WERE RESET AT 1512. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28414 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 02/20/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 02/20/95 | +------------------------------------------------+EVENT TIME: 16:54[EST]| |NRC NOTIFIED BY: PAUL CROGEN |LAST UPDATE DATE: 02/20/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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' EDG STARTED AND LOADED ON TO BUS 1DB WHEN BUS 1DB WAS INADVERTENTLY | | DEENERGIZED | | | | WHILE PERFORMING ELECTRICAL BREAKER MAINTENANCE IN THE VICINITY OF THE 1DB | | BUS DISCONNECT BREAKER, THE OPERATING SWITCH WAS BUMPED CAUSING THE BREAKER | | TO OPEN, WITH SUBSEQUENT LOSS OF OFFSITE POWER TO BUS 1DB. THE LOAD | | SEQUENCER ACTUATED AND ENERGIZED BUS 1DB FROM THE 'B' EDG. | | | | ALL SYSTEMS AND EQUIPMENT FUNCTIONED AS REQUIRED. OFFSITE POWER WAS | | RESTORED WITH THE EDG RETURNED TO THE STANDBY CONDITION IN 24 MINUTES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+