U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/09/98 - 06/10/98 ** EVENT NUMBERS ** 34366 34367 34368 34369 34370 34371 34372 34373 34374 34375 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34366 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/09/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 03:52 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/09/98 | +------------------------------------------------+EVENT TIME: 01:32[EDT]| |NRC NOTIFIED BY: MOKE EMPY |LAST UPDATE DATE: 06/09/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT SUMMERS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION |CURT COWGILL R1 | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 68 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTOMATIC SCRAM FROM 68% DUE TO FAILED MAIN FEEDWATER REGULATING VALVE - | | | | AT 0132 ON 06/09/98, THE 'A' MAIN FEEDWATER REGULATING VALVE FAILED FOR | | UNKNOWN REASONS WHICH CAUSED A HIGH REACTOR VESSEL WATER LEVEL WHICH CAUSED | | THE MAIN TURBINE TO TRIP WHICH CAUSED THE REACTOR TO AUTOMATICALLY SCRAM | | FROM 68% POWER AND THE MAIN FEEDWATER PUMPS TO TRIP. ALL CONTROL RODS | | EXCEPT ROD #42-19 COMPLETELY INSERTED INTO THE CORE. CONTROL ROOM | | OPERATORS RESET THE REACTOR SCRAM SIGNAL AND VERIFIED THAT ALL CONTROL RODS | | WERE FULLY INSERTED INTO THE CORE. CONTROL ROOM OPERATORS WERE CONTROLLING | | REACTOR PRESSURE VIA THE MAIN TURBINE BYPASS VALVES TO THE MAIN CONDENSER. | | | | PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 (RESIDUAL HEAT REMOVAL | | SYSTEM), GROUP 3 (CONTAINMENT VENTILATION SYSTEM), AND GROUP 5 (REACTOR | | WATER CLEANUP SYSTEM) ISOLATED DUE TO LOW REACTOR VESSEL WATER LEVEL | | IMMEDIATELY FOLLOWING THE SCRAM DUE TO WATER SHRINK. CONTROL ROOM | | OPERATORS RESTORED REACTOR VESSEL WATER LEVEL TO ITS NORMAL RANGE. | | | | SAFETY-RELATED 4-KV BUSES #1 AND #3 AND 480-VOLT SAFETY-RELATED BUSES #6 | | AND #11 WERE LOST WHILE CONTROL ROOM OPERATORS WERE ATTEMPTING TO RESTORE A | | MAIN FEEDWATER PUMP TO SERVICE. THE 'B' EMERGENCY DIESEL GENERATOR (EDG) | | AUTOMATICALLY STARTED ON THE LOSS OF BUS #3 VOLTAGE AND LOADED TO SUPPLY | | POWER TO BUS #3. CONTROL ROOM OPERATORS RESTORED POWER TO BUS #6 BY | | CROSS-TYING TO BUS #7. DURING THE RESTORATION OF POWER TO BUS #6, THE | | RESTORATION OF THE AUXILIARY OIL PUMP RESTORED CONTROL OIL TO THE MAIN | | TURBINE BYPASS VALVES AND CAUSED THE MAIN STEAM ISOLATION VALVES TO CLOSE | | DUE TO MOMENTARY HIGH STEAM FLOW. | | | | THE 'A' REACTOR PROTECTION SYSTEM MOTOR-GENERATOR SET TRIPPED DUE TO THE | | VOLTAGE TRANSIENT ON SAFETY-RELATED BUS #3 WHEN THE 'B' RESIDUAL HEAT | | REMOVAL (RHR) PUMP WAS STARTED. BUS #3 WAS BEING SUPPLIED BY THE 'B' EDG | | AT THE TIME. BUS #3 HAS SINCE BEEN TRANSFERRED TO THE STARTUP TRANSFORMER. | | | | CONTROL ROOM OPERATORS ARE STABILIZING REACTOR PRESSURE AND WATER LEVEL IN | | THE NORMAL RANGE USING THE STEAM RELIEF VALVES TO THE TORUS, THE REACTOR | | CORE ISOLATION COOLING SYSTEM, AND CONTROL ROD DRIVE FLOW. TWO SUBSEQUENT | | SCRAM SIGNALS WERE RECEIVED DUE TO LOW REACTOR VESSEL WATER LEVEL AFTER THE | | STEAM RELIEF VALVES WERE OPENED FOR REACTOR PRESSURE CONTROL. THE TORUS IS | | BEING COOLED USING THE 'A' RHR LOOP. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE MAIN FEEDWATER REGULATING VALVE FAILURE AND | | THE ELECTRICAL TRANSIENT EXPERIENCED WHILE ATTEMPTING TO RESTORE POWER TO | | THE MAIN FEEDWATER PUMP. | | | | OFFSITE POWER WAS MAINTAINED THROUGHOUT THIS EVENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A PRESS | | RELEASE. | | | | * * * UPDATE AT 0720 ON 06/09/98 FROM ANDY WISNIEWSKI TO JOLLIFFE * * * | | | | AT 0619 ON 06/09/98, THE LICENSEE ISSUED A PRESS RELEASE ON THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO (BOB SUMMERS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 06/09/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 09:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/09/98 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: CECIL WILLIAMS |LAST UPDATE DATE: 06/09/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION |ED GOODWIN, NRR EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ELECTRICAL FAULT RESULTS IN A MAIN GENERATOR TRIP, TURBINE TRIP, REACTOR | | TRIP, AND SAFETY INJECTION ACTUATION | | | | AN ELECTRICAL FAULT ON THE 2C CONDENSATE PUMP MOTOR CONNECTION CAUSED THE | | LOSS OF THE 2NAB 13.8KV BUS AND THE 2B-UAT TRANSFORMER. THIS SEQUENCE OF | | EVENTS ALSO CAUSED A MAIN GENERATOR TRIP, TURBINE TRIP, AND REACTOR TRIP. | | TWO OF THE FOUR REACTOR COOLANT PUMPS LOST POWER BECAUSE OF THIS PORTION OF | | THE EVENT. | | | | THE LOSS OF THE MAIN GENERATOR CAUSED A LOSS OF POWER TO THE REMAINING | | NON-1E ELECTRICAL LOADS. THESE LOADS SHOULD HAVE TRANSFERRED TO THE | | RESERVE AUXILIARY TRANSFORMER (RAT), BUT THEY DID NOT. THE REASON FOR THIS | | FAILURE IS NOT KNOWN. THE REMAINING REACTOR COOLANT PUMPS AND OTHER NON-1E | | LOADS LOST POWER AS A RESULT OF THE FAILURE TO TRANSFER TO THE RAT. | | | | ALL CONTROL RODS FULLY INSERTED ON THE REACTOR TRIP. THE MAIN STEAM | | ISOLATION VALVES ARE CLOSED. A SAFETY INJECTION (SI) SIGNAL WAS GENERATED | | ON LOW PRESSURIZER PRESSURE AS PART OF THE INITIAL PLANT TRANSIENT. THE SI | | PUMPS INJECTED INTO THE REACTOR COOLANT SYSTEM AND RESTORED PRESSURIZER | | PRESSURE AND RAISED PRESSURIZER LEVEL TO A MAXIMUM OF 86%. PRESSURIZER | | POWER-OPERATED RELIEF VALVES CYCLED DURING THE PLANT TRANSIENT. | | | | THE LICENSEE RESTORED ONE REACTOR COOLANT PUMP AT ABOUT 0955 AND ANOTHER | | PUMP A FEW MINUTES LATER. DECAY HEAT IS BEING REMOVED BY USING THE STEAM | | GENERATOR ATMOSPHERIC DUMPS. STEAM GENERATOR WATER LEVELS ARE BEING | | MAINTAINED BY AUXILIARY FEEDWATER. THE SI SIGNAL HAS BEEN RESET. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34368 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/09/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/09/98 | +------------------------------------------------+EVENT TIME: 08:30[EDT]| |NRC NOTIFIED BY: ART ZAREMBA |LAST UPDATE DATE: 06/09/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT SUMMERS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION NOTIFIED | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION OF THE DISCOVERY OF SOME RESIDUAL DIESEL FUEL IN THE SOIL | | SURROUNDING ONSITE STORAGE TANKS. THE SOIL WAS DISCOVERED IN THE PROCESS | | OF REMOVING THE STORAGE TANKS. APPROXIMATELY 15 CUBIC YARDS OF SOIL HAVE | | BEEN REMOVED FOR DISPOSAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ADAMS CONSTRUCTION COMPANY |NOTIFICATION DATE: 06/09/98 | | CITY: REGION: 2 |NOTIFICATION TIME: 11:05 [ET]| | COUNTY: BOTETOURT STATE: VA |EVENT DATE: 06/08/98 | |LICENSE#: 45-17887-01 AGREEMENT: N |EVENT TIME: 22:30[EDT]| | DOCKET: |LAST UPDATE DATE: 06/09/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS CHRISTENSEN RDO | | |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RON ROBSON | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NDAM DAMAGE MEASURE GAUGE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED MOISTURE DENSITY GAUGE | | | | AN AUTOMOBILE EXITED THE ROAD AT A CONSTRUCTION SITE AND HIT A DENSITY | | GAUGE. THIS OCCURRED ON ROUTE 11 IN BOTETOURT COUNTY, VIRGINIA, AT ABOUT | | 2230 ON 06/08/98. THE GAUGE WAS DRAGGED FOR APPROXIMATELY 200 FEET. THE | | GAUGE IS A TROXLER MODEL NUMBER 4640B, SERIAL NUMBER 595, AND IT CONTAINS A | | CESIUM-137 SOURCE. THE CASE WAS DAMAGED, BUT SURVEYS TAKEN AT THE SCENE | | SHOWED NORMAL RADIATION LEVELS NEAR THE GAUGE. THE GAUGE HAS SINCE BEEN | | TRANSFERRED TO THE LICENSEE'S STORAGE FACILITY IN ROANOKE, VIRGINIA. | | | | THE LICENSEE'S CONTACT INFORMATION IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34370 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/09/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:50 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:33[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/09/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |THOMAS KOZAK RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RICK LARSON | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING THE LOSS OF ONE CONTROL OF THE | | DOUBLE CONTINGENCY MATRIX | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "ON JUNE 8, 1998, AT 1933 HOURS, LAUNDRY PERSONNEL DISCOVERED THAT A | | NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING | | MAINTAINED IN THE X-330 PROCESS BUILDING. THREE (3) LAUNDRY HAMPERS | | CONTAINING ANTI-CONTAMINATION CLOTHING WERE FOUND WITHOUT THE REQUIRED LIDS | | IN PLACE FOR MODERATION CONTROL. NCSA-PLANT055.A00, REQUIREMENT #2, STATES | | IN PART: 'CONTAINERS WITH LAUNDRY SHALL BE COVERED WHEN NOT LOADING OR | | UNLOADING BAGS.' THE FACT THAT HAMPERS WITH LAUNDRY IN THEM HAD NO LIDS IN | | PLACE VIOLATES THE NOTED REQUIREMENT, THUS CONSTITUTING A LOSS OF CONTROL | | 'A' (MODERATION) IN THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY EVENT | | A/B.1. CONTROL 'B' (MASS) WAS MAINTAINED THROUGHOUT THIS EVENT. CONTROL | | 'A' WAS RE-ESTABLISHED AT 2035 HOURS UNDER THE DIRECTION OF NUCLEAR | | CRITICALITY SAFETY FIELD PERSONNEL." | | | | "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." | | | | PORTSMOUTH PERSONNEL INFORMED THE NRC RESIDENT INSPECTOR AND THE DEPARTMENT | | OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34371 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ENTEK IRD INTERNATIONAL CORP. |NOTIFICATION DATE: 06/09/98 | | CITY: COLUMBUS REGION: 3 |NOTIFICATION TIME: 13:48 [ET]| | COUNTY: STATE: OH |EVENT DATE: 06/09/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/09/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM JOHNSON RDO | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: HUMPHRIES | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REPORT IN ACCORDANCE WITH 10 CFR PART 21 | | | | ENTEK IRD INTERNATIONAL, CORP., IS THE SUPPLIER OF CALIBRATION SERVICES FOR | | NIST TRACEABILITY OF VIBRATION MEASUREMENTS FOR PORTABLE VIBRATION | | MEASUREMENT EQUIPMENT. | | | | PRIOR TO A MERGER BETWEEN ENTEK SCIENTIFIC AND IRD MECHANALYSIS, INC., IN | | 1996, AUDITS WERE PERFORMED BY PACIFIC GAS & ELECTRIC AGAINST 10 CFR PART | | 50, APPENDIX B, AND THERE WAS A QUESTION OF THE ACCURACY OF THE CALIBRATION | | CERTIFICATES BEING PROVIDED BY IRD MECHANALYSIS, INC. IRD MECHANALYSIS, | | INC., HAD BEEN PROVIDING CALIBRATION CERTIFICATES INDICATING ACCURACY FOR | | TRANSDUCERS CALIBRATED ON ITS UNHOLTZ-DICKIE SHAKER TABLES WITH A 4:1 | | ACCURACY RATIO WHEN IT ACTUALLY HAD A 3.125:1 ACCURACY RATIO. THE COMPANY | | IS ADVISING LICENSEES TO EVALUATE THE IMPACT OF A CHANGE FROM A 4:1 | | ACCURACY RATIO TO A 3.125:1 ACCURACY RATIO. | | | | (REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34372 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 06/09/98 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 17:08 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/09/98 | +------------------------------------------------+EVENT TIME: 14:40[CDT]| |NRC NOTIFIED BY: HUSTON |LAST UPDATE DATE: 06/09/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE LOUISIANA OFFICE OF ENVIRONMENTAL PROTECTION, THE | | LOUISIANA RADIATION PROTECTION DIVISION, AND THE FIVE LOCAL PARISHES OF AN | | INADVERTENT SOUNDING OF THE EMERGENCY SIRENS. | | | | WHILE PERFORMING SIREN SYSTEM TROUBLESHOOTING/MAINTENANCE, AN INADVERTENT | | SOUNDING OF THE EMERGENCY SIRENS OCCURRED. STATE AND LOCAL AGENCIES WERE | | NOTIFIED THAT THIS WAS AN INADVERTENT SOUNDING AND THAT THERE WAS NO ACTUAL | | EMERGENCY. ALL ACTIVE SIRENS SOUNDED FOR ABOUT 1 MINUTE BEFORE BEING | | SECURED. THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34373 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/09/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:09 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 22:29[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/09/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |THOMAS KOZAK RDO | | DOCKET: 0707002 |JOE HOLONICH, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LARSON | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SURVEILLANCE ON AN AUTOCLAVE WAS PERFORMED WITH UN-CALIBRATED PRESSURE | | GAUGES. | | | | IT WAS DETERMINED THAT UN-CALIBRATED PRESSURE GAUGES HAVE BEEN USED TO | | PERFORM A TECHNICAL SPECIFICATION REQUIRED SURVEILLANCE ON THE AUTOCLAVE'S | | SHELL HIGH PRESSURE RELIEF SYSTEM (A SAFETY SYSTEM). THESE GAUGES MEASURE | | THE PRESSURE IN THE PIPE BETWEEN THE AUTOCLAVE RUPTURE DISC AND RELIEF | | VALVE, AND THEY MUST BE CHECKED AT THE BEGINNING OF EACH HEATING CYCLE. | | | | THE PRESSURE CHECK IS USED TO ASSURE THE INTEGRITY OF THE RUPTURE DISC AND | | THAT THERE IS NOT AN UNWANTED PRESSURE BUILDUP BETWEEN THE DISC AND RELIEF | | VALVE REDUCING THE DIFFERENTIAL PRESSURE ACROSS THE DISC. THIS REDUCTION | | OF PRESSURE DIFFERENTIAL ACROSS THE DISC WOULD INCREASE THE ULTIMATE | | BURSTING PRESSURE OF THE DISC, POSSIBLY INCREASING THE DISC'S RUPTURE | | PRESSURE ABOVE THE MAXIMUM ALLOWABLE WORKING PRESSURE OF THE AUTOCLAVE | | VESSEL. | | | | THE AUTOCLAVES HAVE BEEN MADE INOPERABLE. THERE WAS NO LOSS OF | | HAZARDOUS/RADIOACTIVE MATERIAL OR RADIOACTIVE/RADIOLOGICAL CONTAMINATION | | EXPOSURE AS A RESULT OF THIS EVENT. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO NOTIFY | | THE DEPARTMENT OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34374 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 06/09/98 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 18:23 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 06/09/98 | +------------------------------------------------+EVENT TIME: 09:02[PDT]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 06/09/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL DURING A RANDOM CHECK. | | | | A LICENSED OPERATOR WAS RANDOMLY SELECTED FOR FITNESS-FOR-DUTY TESTING. THE | | OPERATOR TESTED POSITIVE FOR ALCOHOL USING A 'BREATHALYZER.' THE | | INDIVIDUAL'S ACCESS TO THE PROTECTED AREA WAS TERMINATED, AND HE WAS PLACED | | ON ADMINISTRATIVE LEAVE. AN APPEAL TEST SAMPLE (BLOOD) WAS SENT TO AN | | INDEPENDENT LAB FOR CONFIRMATION OF THE INITIAL TEST RESULTS. THE RESULTS | | WERE RECEIVED ON 06/09/98, AND THE RESULTS CONFIRMED THE POSITIVE TEST FOR | | ALCOHOL. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34375 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 06/10/98 | |UNIT: [ ] [4] [ ] STATE: FL |NOTIFICATION TIME: 03:27 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 06/10/98 | +------------------------------------------------+EVENT TIME: 02:37[EDT]| |NRC NOTIFIED BY: DAVE SPENCE |LAST UPDATE DATE: 06/10/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JACK STROSNIDER/NRR EO | | |CIBOCH FEMA | | |RICHARD BARRETT/AEOD IRD | | |ROY ZIMMERMAN/NRR ET | | |TIM MARTIN/AEOD ET | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARATION DUE TO AN UNCONTROLLED FIRE WITHIN THE POWER | | BLOCK LASTING GREATER THAN 10 MINUTES | | | | AT 0237, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO AN UNCONTROLLED FIRE | | WITHIN THE POWER BLOCK LASTING GREATER THAN 10 MINUTES. THE FIRE OCCURRED | | IN THE UNIT 4 MOTOR-GENERATOR SET ROOM, AND THE SOURCE OF THE FIRE WAS THE | | '4A' MOTOR-GENERATOR SET. THE LICENSEE'S FIRE TEAM RESPONDED AND | | SUCCESSFULLY EXTINGUISHED THE FIRE. OFFSITE ASSISTANCE WAS NOT REQUIRED. | | THE LICENSEE'S EMERGENCY COORDINATOR TERMINATED THE UNUSUAL EVENT AT 0300. | | (THE EXACT DURATION OF THE FIRE WAS NOT AVAILABLE AT THE TIME OF THIS EVENT | | NOTIFICATION.) | | | | THE LICENSEE STATED THAT THE FIRE DETECTION AND HALON SYSTEMS FUNCTIONED AS | | DESIGNED. THE APPROPRIATE FIRE DAMPERS CLOSED, AND HALON DUMPED IN THE | | INVERTER ROOM LOCATED ONE FLOOR ABOVE THE UNIT 4 MOTOR-GENERATOR SET ROOM. | | HALON DID NOT ENTER THE THE UNIT 4 MOTOR-GENERATOR SET ROOM, AND IT WAS NOT | | EXPECTED TO ENTER THIS AREA. | | | | THE FIRE CAUSED A LOSS OF A REDUNDANT MOTOR-GENERATOR SET, BUT THE UNIT IS | | NOT CURRENTLY IN A LIMITING CONDITION FOR OPERATION AS A RESULT OF THIS | | EVENT. PLANT OPERATION WAS NOT AFFECTED, AND UNIT 4 REMAINS OPERATING AT | | 100% POWER. THERE WERE NO PERSONNEL INJURIES, AND THERE WERE NO | | RADIOACTIVE RELEASES. | | | | THE LICENSEE NOTIFIED THE STATE AND LOCAL OFFICIALS AS WELL AS THE NRC | | RESIDENT INSPECTOR. THE NRC SENIOR RESIDENT INSPECTOR RESPONDED TO THE | | SITE. | +------------------------------------------------------------------------------+