U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/24/95 - 03/27/95 ** EVENT NUMBERS ** 28467 28558 28571 28572 28580 28581 28582 28583 28584 28585 28586 28587 28588 28589 28590 28591 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28467 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 03/02/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/02/95 | +------------------------------------------------+EVENT TIME: 15:45[EST]| |NRC NOTIFIED BY: ALAN RABENOLD |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCCORMICKBARGER 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 +------------------------------------------------------------------------------+ | REACTOR WATER CLEANUP BLOWDOWN ISOLATION VALVES SEEING 1050psid INSTEAD OF | | SEEING 140psid. | | | | A PRELIMINARY REVIEW OF DATA OBTAINED FROM TROUBLESHOOTING OF CONTAINMENT | | ISOLATION VALVES G33-F028 AND G33-F034 (RWCU BLOWDOWN ISOLATION VALVES) | | INDICATES THAT THE VALVES ARE SEEING A DIFFERENTIAL PRESSURE OF 1050psid, | | NOT THE 140psid DIFFERENTIAL PRESSURE THE VALVE TORQUE SWITCHES ARE | | CURRENTLY ADJUSTED TO, WHICH WAS THE ORIGINAL WORSE CASE DESIGN PRESSURE. | | GENERIC LETTER 89-10 TESTING ASSUMES WORST CASE CONDITIONS (1050psid). THE | | CONTAINMENT PENETRATION IS CURRENTLY ISOLATED AND BOTH VALVES ARE CLOSED. | | ENGINEERING EVALUATION IS STILL IN PROGRESS AND THEY ARE THINKING ABOUT | | POSSIBLY INCREASING THE TORQUE SETTING OF RWCU BLOWDOWN ISOLATION VALVES. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE 03/24/95 1743EST FROM:SOCHIA BY:SCARFO * * * | | THE LICENSEE IS RETRACTING THIS EVENT ON THE BASIS OF AN ENGINEERING | | EVALUATION WHICH FOUND THAT THE VALVES WERE OPERABLE AND COULD PERFORM | | THEIR SAFETY FUNCTION UNDER THE DESIGN DELTA-P CONDITION. THE LICENSEE | | WILL NOT BE SUBMITTING AN LER. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. HOO NOTIFIED R3DO KROPP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28558 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/19/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 17:04 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/19/95 | +------------------------------------------------+EVENT TIME: 16:30[EST]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 03/25/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MORE THAN 1% OF THE TUBES IN A STEAM GENERATOR WERE DETERMINED TO BE | | DEFECTIVE DURING EDDY CURRENT TESTING. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "RESULTS OF EDDY CURRENT TESTING OF #1 STEAM GENERATOR TUBES WERE | | CLASSIFIED AS CATEGORY 'C-3' BECAUSE GREATER THAN 1% OF THE SAMPLE WERE | | DEFECTIVE (58 OF THE 5472 ACTIVE TUBES). THE DEFECTIVE TUBES CONTAINED | | IMPERFECTIONS WHICH EXCEEDED THE PLUGGING LIMIT DEPTH OF 40% OF NORMAL WALL | | THICKNESS. STEAM GENERATORS #2 AND #3 WERE PREVIOUSLY REPORTED AS HAVING | | EXCEEDED THE 1% DEFECTIVE LIMIT ON 3/10/95 AND 3/13/95 (EVENT REPORTS | | #28513 AND #28517) RESPECTIVELY." | | | | STEAM GENERATOR #2 HAD 64 OF 5608 DEFECTIVE TUBES AND STEAM GENERATOR # 3 | | HAD 55 OUT OF 5461 DEFECTIVE TUBES. THE LICENSEE WILL INFORM THE RESIDENT | | INSPECTOR. | | | | NOTE: ALSO SEE EVENT #28482 FOR A RELATED EVENT. | | | | * * * UPDATE AT 1711 ON 3/25/95 BY GRIMARD TAKEN BY WEAVER * * * | | "ON GOING EDDY CURRENT TESTING AND ANALYSIS IN STEAM GENERATORS #1 AND #3 | | HAS REVEALED ADDITIONAL TUBES WITH CIRCUMFERENTIAL CRACKS EXCEEDING AVERAGE | | THROUGH WALL PENETRATION CRITERIA OF 79 %. | | | | THIS IS AN UPDATE OF THE ON-GOING EDDY CURRENT TESTING AT MAINE YANKEE. | | EIGHT ADDITIONAL TUBES HAVE BEEN FOUND TO HAVE EXCEEDED THE 79% AVERAGE | | THROUGH WALL PENETRATION CRITERIA. FOUR OF THE TUBES ARE IN STEAM | | GENERATORS #3, AND FOUR ARE LOCATED IN STEAM GENERATOR #1. ALL OF THE | | CRACKS ARE LOCATED IN THE T-HOT, EXPANSION TRANSITION ZONE REGION. THESE | | CRACKS ARE IN ADDITION TO PREVIOUSLY REPORTED CRACKS; ONE IN STEAM | | GENERATOR #2, AND ONE IN STEAM GENERATOR #3. | | | | AN AGREEMENT HAS BEEN MADE WITH THE NRC TO REPORT ALL TUBES WITH | | CIRCUMFERENTIAL CRACKS EXCEEDING 79% THROUGH WALL AS A SIGNIFICANT | | DEGRADATION TO A PRINCIPAL SAFETY BARRIER. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28571 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/22/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 08:58 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/22/95 | +------------------------------------------------+EVENT TIME: 08:12[EST]| |NRC NOTIFIED BY: McKENNY |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WITH THE PLANT IN CONDITION 4 (COLD SHUTDOWN) DURING A REFUELING OUTAGE, | | THE PLANT RECEIVED A HIGH HIGH SRM Rx SCRAM SIGNAL FOR UNKNOWN REASONS. | | | | A REACTOR SCRAM OCCURRED DUE TO A MANUAL SCRAM CHANNELS' ACTIVATION - SRM | | "A" SPIKED HI - HI. THE APPARENT CAUSE APPEARS TO BE "NOISE" RELATED. THERE | | WAS NO ROD MOTION BECAUSE ALL RODS HAD BEEN INSERTED PRIOR TO THE SCRAM. | | THERE WERE SHORTING LINKS REMOVED IN THE SRMS SO THAT ANY ONE OF THE SRM | | COULD GENERATE A SCRAM. LICENSEE IS INVESTIGATING THE CAUSE. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1605 ON 3/24/95 BY MCKENNEY TAKEN BY WEAVER * * * | | THE LICENSEE HAS RETRACTED THIS EVENT. THE RETRACTION IS BASED ON THE | | FOLLOWING. 1) THE SIGNAL FROM THE SRM WAS NOISE AND THEREFORE INVALID. | | 2) THE SAFETY FUNCTION WAS ALREADY COMPLETED SINCE ALL RODS WERE FULLY | | INSERTED. HOO NOTIFIED R1DO ANDERSON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28572 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/22/95 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 10:29 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/22/95 | +------------------------------------------------+EVENT TIME: 10:08[EST]| |NRC NOTIFIED BY: LANGAN |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT THEY COULD HAVE A MALFUNCTION WITH THEIR | | SUPPLEMENTAL LEAK COLLECTION AND RELEASE FILTERS AND THE CONTROL ROOM | | FILTERS. | | | | THIS PROBLEM WAS DISCOVERED DURING AN ENGINEERING REVIEW OF A CONDITION FOR | | WHICH HISTORICAL BREACHES OF THE CONTROL ROOM BOUNDARY MAY HAVE RENDERED | | THE CONTROL ROOM FILTERS INCAPABLE OF PERFORMING THEIR SAFETY FUNCTION OF | | MAINTAINING POSITIVE PRESSURE IN THE CONTROL ROOM. THIS CONDITION COULD | | HAVE EXISTED SINCE 1986. THERE WILL BE AN ENGINEERING EVALUATION TO | | DETERMINE THE REQUIRED ACTIONS TO BE TAKEN. | | | | THE RI, STATE AND LOCAL AGENCIES HAVE BEEN NOTIFIED. | | | | ***UPDATE 3/24/94 @ 0953 FROM KULTERMAN TAKEN BY SEBROSKY *** | | DUE TO THE INVESTIGATION DONE BECAUSE OF THIS EVENT THE LICENSEE HAS | | IDENTIFIED THAT BREACHES IN THE SECONDARY BOUNDARY COULD RENDER THE | | SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM INOPERABLE. THE LICENSEE | | HAS ISSUED A SEPARATE REPORT FOR THIS PROBLEM (SEE EVENT # 28582). THE | | LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED R1DO(ANDERSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28580 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FEDERAL EXPRESS |NOTIFICATION DATE: 03/24/95 | | CITY: MEMPHIS REGION: 2 |NOTIFICATION TIME: 06:44 [ET]| | COUNTY: SHELBY STATE: TN |EVENT DATE: 03/24/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 01:16[EST]| | DOCKET: |LAST UPDATE DATE: 03/24/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JACK CRLENJAK RDO | | |COOL EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CHEN/NAT RESPONCE CTR | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER NOTIFIED THE NRC OPERATIONS CENTER THAT | | FEDERAL EXPRESS HAD TOLD THEM A PACKAGE CONTAINING GALLIUM 67 WAS DAMAGED | | AT THE MEMPHIS AIRPORT. | | | | THIS PACKAGE WAS DAMAGED IN TRANSIT AND APPROXIMATELY 1 MILLILITER OF | | GALLIUM 67 SPILLED ON THE CONCRETE PAD. THE ACTIVITY OF THE GALLIUM 67 WAS | | 47 MILLICURIES AND THE AREA OF THE SPILL HAS BEEN ISOLATED AND CLEANUP WILL | | BEGIN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28581 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/24/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 09:50 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 03/24/95 | +------------------------------------------------+EVENT TIME: 07:51[EST]| |NRC NOTIFIED BY: ANDERSON |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE MANUALLY SCRAMMED THE REACTOR FROM APPROXIMATELY 60% POWER DUE | | TO HIGH STATOR COOLING WATER TEMPERATURES. | | | | WHILE AT 100% THE LICENSEE NOTICED THAT THE STATOR COOLING WATER | | TEMPERATURE WAS INCREASING. THEY STARTING INVESTIGATING THE CAUSE OF THE | | TEMPERATURE INCREASE WHILE THEY COMMENCED POWER REDUCTION. THEY WERE UNABLE | | TO CORRECT THE HIGH TEMPERATURE CONDITION SO THEY REDUCED THE THE RECIRC | | PUMPS OUTPUT TO WHERE THE REACTOR WAS ONLY AT ABOUT 60% POWER. AT THIS | | POINT THE TEMPERATURE WAS STILL INCREASING(TO APPROX 97F), SO THE OPERATOR | | MANUALLY SCRAMMED THE REACTOR. ALL RODS FULLY INSERTED. NO ECCS INJECTION | | OCCURRED AND NO SAFETY RELIEF VALVES LIFTED. AFTER A FURTHER INVESTIGATION, | | IT WAS DETERMINED THAT THE PROBLEM WAS DUE TO THE TEMPERATURE CONTROL VALVE | | FAILING IN THE BYPASS POSITION AND THE COOLING WATER WAS BYPASSING THE | | COOLER. THE PROBLEM WAS CORRECTED, BUT NOT BEFORE THE MANUAL SCRAM. | | | | THEY ALSO RECEIVED INDICATION THAT 2 SECONDARY CONTAINMENT DAMPERS(IN THE | | FAN ROOM) WERE NOT FULLY CLOSED. UPON FURTHER INVESTIGATION, THEY | | DISCOVERED THAT ONE OF THE DAMPERS WAS ALMOST CLOSED AND THE OTHER WAS | | FULLY CLOSED, SO THERE WAS A PROBLEM WITH THE LIMIT SWITCH ON THE FULLY | | CLOSED VALVE. THE REACTOR BUILDING WAS ISOLATED. | | | | THEY ALSO EXPERIENCED A SLOW TRANSFER ON THEIR 4160 BUS, WHICH RESULTED IN | | A HALF GROUP 1 ISOLATION WHICH WAS IMMEDIATELY RESET. THEY ARE | | INVESTIGATING THE CAUSE OF THE SLOW TRANSFER. | | | | THEY ARE CURRENTLY DE-INERTING AND TRYING TO MAINTAIN PRESSURE SINCE THEY | | HAVE NOT YET STARTED COOLDOWN. THE RI WAS INFORMED. THEY WILL NOTIFY STATE | | AND LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28582 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/24/95 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 09:53 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/24/95 | +------------------------------------------------+EVENT TIME: 09:50[EST]| |NRC NOTIFIED BY: TIM KULTERMAN |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | IN THE PAST THERE HAVE BEEN BREACHES OF THE SECONDARY CONTAINMENT BOUNDARY | | WHICH MAY HAVE RENDERED THE SUPPLEMENTARY LEAK COLLECTION AND RELEASE | | SYSTEMS (SLCRS) INCAPABLE OF PERFORMING THEIR SAFETY FUNCTION. | | | | ONE OF THE PURPOSES OF SLCRS IS TO MAINTAIN A SLIGHT NEGATIVE PRESSURE ON | | THE SECONDARY CONTAINMENT (e.g. AUXILIARY BUILDING, AND PORTIONS OF THE ESF | | AND MAIN STEAM VALVE BUILDING). IN THE PAST SECONDARY BREACHES OF | | CONTAINMENT HAVE BEEN ALLOWED AND THE APPROPRIATE LCO FOR SECONDARY | | CONTAINMENT WAS ENTERED. WHAT WAS NOT EVALUATED WAS THE POSSIBILITY THAT | | THE SIZE OF THE SECONDARY BREACH COULD BE SUCH THAT SLCRS WOULD BE UNABLE | | TO MAINTAIN A NEGATIVE PRESSURE ON SECONDARY CONTAINMENT. THERE MAY HAVE | | BEEN CASES GOING BACK TO 1986 IN WHICH THE SIZE OF THE BREACH WAS LARGE | | ENOUGH TO RENDER THE SLCRS INOPERABLE. | | | | CURRENTLY THE SECONDARY CONTAINMENT ENVELOPE IS INTACT. THE LICENSEE IS | | CONTINUING TO INVESTIGATE PAST OCCURRENCES WHERE THE SLCRS MAY HAVE BEEN | | INOPERABLE AND IS NOT CURRENTLY IN ANY LCO BECAUSE OF THIS PROBLEM. THE | | LICENSEE WILL NOT ALLOW ANY BREACHES OF SECONDARY CONTAINMENT UNTIL THIS | | ISSUE IS RESOLVED. THE LICENSEE IS ALSO INVESTIGATING A SIMILAR PROBLEM | | WITH THE CONTROL ROOM ENVELOPE (SEE EVENT # 28572). | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR, AND STATE AND LOCAL | | OFFICIALS OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28583 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 03/24/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 13:11 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 03/24/95 | +------------------------------------------------+EVENT TIME: 11:01[EST]| |NRC NOTIFIED BY: RANDY HAIFLET |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TORUS VACUUM BREAKER OPENED DURING DRYWELL DEINERTING | | | | THE DRYWELL TO TORUS VACUUM BREAKERS CYCLED OPEN DUE TO DRYWELL PRESSURE | | DROPPING BELOW TORUS PRESSURE DURING DRYWELL DEINERTING. DRYWELL | | DEINERTING WAS DISCONTINUED UNTIL A PURGE PATH WAS ESTABLISHED. THE VACUUM | | BREAKER IS NOW CLOSED. DEINERTING WAS REESTABLISHED & ALL SYSTEMS OPERATED | | PROPERLY. | | | | THE LICENSEE STATED THAT THE OPENING OF THE VACUUM BREAKER WAS CAUSED BY AN | | INADEQUATE PROCEDURE. A PURGE VALVE THAT WAS OPENED BY PROCEDURE REQUIRED | | OPERATION AT BOTH A LOCAL AND REMOTE STATION. THE PROCEDURE IN USE DID NOT | | SPECIFY OPERATION AT BOTH STATIONS. THIS CAUSED A DELAY IN OPENING THE | | PURGE VALVE AND LED TO THE OPENING OF THE TORUS VACUUM BREAKER, SINCE THE | | STANDBY GAS TREATMENT SYSTEM WAS ALREADY TAKING A SUCTION ON THE DRYWELL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28584 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AMERSHAM |NOTIFICATION DATE: 03/24/95 | | CITY: BURLINGTON REGION: 1 |NOTIFICATION TIME: 15:23 [ET]| | COUNTY: MIDDLESEX STATE: MA |EVENT DATE: 03/24/95 | |LICENSE#: 20-12836-01 AGREEMENT: N |EVENT TIME: 11:15[EST]| | DOCKET: |LAST UPDATE DATE: 03/24/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CLIFFORD ANDERSON RDO | | | | +------------------------------------------------+DICK BANGART SP | |NRC NOTIFIED BY: LORI PODOLAK | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PERSONNEL OVEREXPOSURE FROM AN IRIDIUM 192 PARTICLE | | | | AMERSHAM PRODUCES RADIOGRAPHY SOURCES. A MAN WORKING WITH IR-192 | | DISCOVERED A HOT PARTICLE ON HIS COLLAR UPON EXITING FROM A CONTROLLED WORK | | AREA. HE HAD BEEN WORKING IN THE AREA FOR ABOUT 2 HOURS. THE TOTAL DOSE | | TO THE MAN'S NECK WAS ESTIMATED AT 139.6 REM. THE PRIMARY CONCERN WAS THE | | BETA DOSE TO THE SKIN OF THE NECK. WHOLE BODY GAMMA DOSE WAS ESTIMATED AT | | 100 mR. NO ADVERSE HEALTH EFFECTS ARE EXPECTED. THE LICENSEE WILL FOLLOW | | UP WITH ADDITIONAL MONITORING. | | | | A CONTACT PHONE NUMBER IS LOCATED IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28585 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: INTEGRATED RESOURCES INC. |NOTIFICATION DATE: 03/24/95 | | CITY: NEBRASKA CITY REGION: 4 |NOTIFICATION TIME: 16:16 [ET]| | COUNTY: STATE: NE |EVENT DATE: 03/24/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 16:16[CST]| | DOCKET: |LAST UPDATE DATE: 03/24/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN BROSSEMER |WALT HAASS NRR | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEF 21.21(b)(2) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 -- POWER SUPPLIES USED IN APRMs ARE SUBJECT TO RANDOM FAILURES | | | | THE POWER SUPPLIES IN QUESTION WERE BUILT BY TDK OF JAPAN AND SUPPLIED TO | | KEPCO, INC. THE KEPCO PART NUMBER IS RMX24-D-20804. KEPCO SOLD THE PARTS | | TO GE. THE GE PART NUMBER IS 169C8805PO2. | | | | INTEGRATED RESOURCES RECEIVED THE POWER SUPPLIES FROM PERRY AND NINE MILE | | POINT TWO FOR REFURBISHMENT AND REPAIR. FOUR OF TWELVE POWER SUPPLIES HAD | | FAILED IN USE. TWO MORE FAILED DURING TESTING AT INTEGRATED RESOURCES. ALL | | FAILURES WERE CAUSED BY THE FAILURE OF TWO OUTPUT TRANSISTORS IN THE POWER | | SUPPLIES. OTHER PLANTS OF THIS VINTAGE MAY ALSO BE USING THIS POWER | | SUPPLY. WHEN THIS FAILURE OCCURS THE APRM WILL FAIL DOWNSCALE. | | | | THE CONTACT PHONE NUMBER IS 402-873-5859. INTEGRATED RESOURCES WILL | | FOLLOWUP THIS PHONE REPORT WITH A WRITTEN REPORT ON 3/27/95. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28586 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/24/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 18:49 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/24/95 | +------------------------------------------------+EVENT TIME: 15:55[EST]| |NRC NOTIFIED BY: DAVE WALSH |LAST UPDATE DATE: 03/24/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SHUTDOWN REQUIRED BY TECH SPECS | | | | A SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS HAS COMMENCED AT 1822 DUE | | TO THE INOPERABILITY OF A JET PUMP EXCESS FLOW CHECK VALVE. | | | | AN EXCESS FLOW CHECK VALVE ON JET PUMP #20 FLOW INDICATION INSTRUMENT LINE | | FAILED IT'S REQUIRED, 18 MONTH SURVEILLANCE TEST. AS A RESULT, TECH SPEC | | 3.6.3.B WAS ENTERED AT 1555 ON 3/24/95. THE UNIT WAS SCHEDULED TO COMMENCE | | A DOWN POWER IN PREPARATION FOR THE UNIT'S 8TH REFUELING OUTAGE AT 1800 | | TODAY. THE SHUTDOWN REQUIREMENTS OF TECH SPEC 3.6.3 ARE BEING MET THROUGH | | ADHERENCE TO THE PRE-PLANNED SHUTDOWN SCHEDULED DEVELOPED FOR THE OUTAGE. | | UPON SHUTDOWN, OUTAGE ACTIVITIES WILL BEGIN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0538 ON 03/25/95 ENTERED BY HOO JOLLIFFE * * * | | | | AT 0120 ON 03/25/95, UNIT 1 ENTERED CONDITION 3 (HOT SHUTDOWN) TO BEGIN A | | 45 DAY REFUELING OUTAGE. HOO NOTIFIED R1DO ANDERSON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28587 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 03/25/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 01:12 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 03/24/95 | +------------------------------------------------+EVENT TIME: 23:30[EST]| |NRC NOTIFIED BY: HARDAGE |LAST UPDATE DATE: 03/25/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - INDIVIDUAL KILLED IN TRUCK ACCIDENT NEXT TO THE PLANT ACCESS ROAD - | | | | AT APPROXIMATELY 2330 ON 03/24/95, AN INDIVIDUAL WAS KILLED WHEN THE PICKUP | | TRUCK HE WAS DRIVING RAN OVER A GUARDRAIL AND OFF THE PLANT ACCESS ROAD. TO | | THE BEST OF THE LICENSEE'S KNOWLEDGE, THE INDIVIDUAL WAS NOT A LICENSEE | | EMPLOYEE OR A LICENSEE CONTRACTOR. THE ACCIDENT OCCURRED ON THE LICENSEE | | CONTROLLED PROPERTY BUT NOT IN THE PLANT PROTECTED AREA. | | | | LICENSEE NOTIFIED THE LOCAL POLICE AND THE POLICE HOMICIDE TEAM IS | | INVESTIGATING THE FATALITY. | | | | LICENSEE HAS NOT ISSUED A PRESS RELEASE BUT CONSIDERS THIS EVENT | | POTENTIALLY NEWSWORTHY. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28588 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/25/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [3] CE |EVENT DATE: 03/25/95 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: JEFF RILEY |LAST UPDATE DATE: 03/25/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ELINOR ADENSAM EO | | |WRIGHT FEMA | | |BILL BEACH RIV | | |ROBERTSON DOT | | |ED JORDAN AEOD | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 93 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED BASED ON A CHEMICAL RELEASE AT A NEARBY UNION CARBIDE PLANT | | | | THE PLANT DECLARED AN ALERT AT 1500 CST BASED ON A RELEASE OF | | TETRAHYDRONAPTHALENE AT A UNION CARBIDE PLANT LOCATED ABOUT ONE MILE AWAY | | FROM WATERFORD 3. THE WIND WAS BLOWING IN THE DIRECTION OF WATERFORD 3. | | THE UNIT'S CONTROL ROOM VENTILATION WAS PLACED INTO A RECIRCULATION MODE. | | NO TOXIC GAS MONITORS ALARMED. NO INJURIES OR SICKNESS HAVE BEEN REPORTED. | | THE ALERT WAS DECLARED BECAUSE THE PARISH EMERGENCY RESPONSE OFFICIALS | | RECOMMENDED SHELTERING ON THE WATERFORD 3 SITE. | | | | THE EVENT WAS DOWNGRADED TO AN UNUSUAL EVENT AT 1531 CST BECAUSE OF A | | REDUCED RELEASE RATE. SHELTERING WAS TERMINATED AT THE SAME TIME. | | | | * * * UPDATE AT 2018 ON 3/25/95 BY RODRIGUE TAKEN BY WEAVER * * * | | THE UNUSUAL EVENT WAS TERMINATED AT 1900 CST. HOO NOTIFIED RDO (STETKA); | | EO (ADENSAM); FEMA (HERSKO) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28589 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/25/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/25/95 | +------------------------------------------------+EVENT TIME: 16:44[CST]| |NRC NOTIFIED BY: RON WYNGET |LAST UPDATE DATE: 03/25/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 +------------------------------------------------------------------------------+ | AN EMERGENCY DIESEL GENERATOR STARTED INADVERTENTLY DURING MAINTENANCE | | | | EDG G04 FAST STARTED INADVERTENTLY DUE TO PERSONNEL ERROR ASSOCIATED WITH | | CONSTRUCTION ACTIVITIES ON A NEW 4160 VOLT SAFEGUARDS BUS (1A06). THE NEW | | 1A06 BUS WAS NOT IN SERVICE AND THE EDG DID NOT CLOSE IN ON THE BUS. | | | | G04 IS A SHARED B TRAIN DIESEL FOR BOTH UNITS. G04 REMAINED OPERABLE. NO | | SAFEGUARDS LOADS ON 1A06 ARE REQUIRED TO BE OPERABLE AT THIS TIME. UNIT 1 | | IS DEFUELED. | | | | THE PERSONNEL ERROR WAS RELATED TO THE TESTING OF THE UNDERVOLTAGE RELAYS | | ON THE 1A06 BUS. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28590 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 03/26/95 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 13:54 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/26/95 | +------------------------------------------------+EVENT TIME: 11:22[EST]| |NRC NOTIFIED BY: PAUL RUSHTON |LAST UPDATE DATE: 03/26/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION DURING DIESEL TESTING | | | | DURING ESFAS TESTING OF TRAIN B EQUIPMENT, A LOSS OF VOLTAGE WAS SENSED ON | | THE TRAIN B 4160 VAC ESF BUS. THE PLANT IS IN A REFUELING OUTAGE, | | CURRENTLY IN MODE 5. AT THE TIME OF THE EVENT, ESFAS TESTING WAS IN | | PROGRESS IAW PROCEDURE 14667-2, "TRAIN B DIESEL GENERATOR AND ESFAS TEST". | | PREPARATIONS WERE BEING MADE TO TEST DIESEL GENERATOR LOAD REJECT | | CAPABILITIES WITH THE EDG CARRYING THE 4160 VAC ESF BUS. AT 1122, THE EDG | | HAD AN APPARENT VOLTAGE REGULATOR MALFUNCTION WHICH RESULTED IN A DROP IN | | VOLTAGE ON THE BUS. THE SAFEGUARDS LOAD SEQUENCER SENSED THIS VOLTAGE DROP | | AND ACTUATED THE LOP (LOSS OF POWER) SEQUENCE. | | | | THE SEQUENCER SHED ALL THE LOADS FROM THE BUS AND THEN RESTARTED THE | | VARIOUS ESF LOADS AFTER VOLTAGE RETURNED TO NORMAL. THE EDG REMAINED | | RUNNING THROUGHOUT THE EVENT. SUBSEQUENT TO THE EDG VOLTAGE REGULATOR | | MALFUNCTION, ALL EQUIPMENT FUNCTIONED CORRECTLY. ALL B TRAIN ELECTRICAL | | BUSSES ARE ENERGIZED AND THE EDG TROUBLESHOOTING IS IN PROGRESS. TECH | | SPECS REQUIRE ONLY ONE EDG TO BE OPERABLE UNDER CURRENT PLANT CONDITIONS. | | THE A TRAIN EDG IS OPERABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28591 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 03/27/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 00:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/26/95 | +------------------------------------------------+EVENT TIME: 23:25[EST]| |NRC NOTIFIED BY: LOCY |LAST UPDATE DATE: 03/27/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 20 POWER OPERATION | 20 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HPCI TURBINE TRIPPED ON OVERSPEED UNEXPECTEDLY DURING A TEST - | | | | AT 1622 ON 03/26/95, LICENSEE DECLARED THE HPCI SYSTEM INOPERABLE IN ORDER | | TO PERFORM A QUICK START TRANSIENT MONITORING SURVEILLANCE TEST AND ENTERED | | A 7 DAY TO HOT SHUTDOWN TECH SPEC LCO A/S (#3.5.C.2). | | | | AT 2325 ON 03/26/95, DURING PERFORMANCE OF THE QUICK START PORTION OF THE | | TEST, THE HPCI TURBINE TRIPPED ON OVERSPEED UNEXPECTEDLY. | | | | LICENSEE STOPPED THE TEST AND IS INVESTIGATING THE CAUSE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+