U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/10/97 - 10/14/97 ** EVENT NUMBERS ** 32908 32922 33059 33061 33062 33063 33064 33065 33066 33067 33068 33069 33070 33071 33072 33073 33074 33075 33076 33077 33078 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32908 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/11/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/97 | +------------------------------------------------+EVENT TIME: 10:20[EDT]| |NRC NOTIFIED BY: AL YODER |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DENSITY FOR THE BORAFLEX IN UNIT 1 AND 2 SPENT FUEL POOLS FOUND TO BE BELOW | | INPUT ASSUMPTIONS IN THE SAFETY ANALYSIS | | | | TECHNICAL SPECIFICATION 3.9.13 SPENT FUEL STORAGE IS POTENTIALLY | | NON-CONSERVATIVE DUE TO POTENTIAL BORAFLEX DEGRADATION. PRELIMINARY VENDOR | | RESULTS FROM BORAFLEX TESTING SHOWED BELOW THE INPUT ASSUMPTION IN THE | | SAFETY ANALYSIS. WITH CONSERVATISMS SUCH AS BORON AND CURRENT LOADING | | CONFIGURATION, Keff < 0.95 IS BEING MET. FINAL BORAFLEX TESTING RESULTS | | WILL DETERMINE ACTUAL REPORTABILITY. THE LICENSEE IS ADDING BORON TO THE | | UNIT 1 AND UNIT 2 SPENT FUEL POOLS TO INCREASE THE BORON CONCENTRATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THE EVENT BY THE LICENSEE. | | | | ***UPDATE ON 10/10/97 @ 0823 BY WASHAM TO GOULD*** AFTER FURTHER REVIEW, | | THE LICENSEE IS RETRACTING THIS EVENT. THE PREVIOUS NOTIFICATION REPORTED | | A POTENTIALLY NON-CONSERVATIVE TECH SPEC BASED PRELIMINARY INDICATION OF | | BORAFLEX DENSITY DEGRADATION IN REGION 1 OF THE SPENT FUEL POOL. | | | | SUBSEQUENT CALCULATIONS USING THE CURRENT DEGRADATION LEVELS INDICATED THAT | | THE VALUE OF Keff HAS BEEN MAINTAINED LESS THAN 0.95% AS REQUIRED. | | THEREFORE, THE PLANT WAS NEVER OPERATED IN A DEGRADED CONDITION AND SHOULD | | NOT HAVE BEEN REPORTED. AS A CONSERVATIVE MEASURE, CONTROLLING PROCEDURES | | HAVE BEEN REVISED TO ENSURE Keff REMAINS BELOW 0.95%. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | THE RDO (LESSER) WAS NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32922 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/12/97 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 18:50 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/12/97 | +------------------------------------------------+EVENT TIME: 15:22[CDT]| |NRC NOTIFIED BY: KURT RATHGABER |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 +------------------------------------------------------------------------------+ | UNEXPECTED TRIP OF ONE OF THE OPERATING CHARGING PUMPS DURING SOLID PLANT | | OPERATION POSSIBLY DUE TO MAINTENANCE ACTIVITIES. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1522 CDT, WHILE MAINTAINING UNIT 2 IN COLD SHUTDOWN IN SOLID PLANT | | OPERATIONS, ONE OF TWO OPERATING CHARGING PUMPS BEING USED TO MAINTAIN | | REACTOR COOLANT SYSTEM INVENTORY AND PRESSURE TRIPPED. PRESSURE CONTROL | | WAS MAINTAINED BY INCREASING FLOW FROM THE REMAINING CHARGING PUMP AND | | REDUCING RCS LETDOWN FLOW. THE CAUSE OF THIS EVENT APPEARS TO BE ACTUATION | | OF AN 'A' TRAIN SAFEGUARDS 480 VOLT BUS UNDERVOLTAGE PROTECTION FOLLOWER | | RELAY. ACTUATION OF THIS RELAY WOULD TRIP THE OPERATING CHARGING PUMP, | | THREE BANKS OF PRESSURIZER HEATERS AND THE 'A' TRAIN RHR PUMP IF IT WERE | | OPERATING. THE RHR PUMP AND PRESSURIZER HEATERS WERE NOT OPERATING AT THE | | TIME. ANOTHER CHARGING PUMP THAT WOULD HAVE TRIPPED FOLLOWING THE RELAY | | ACTUATION DID NOT START WHEN ATTEMPTED. TAKING THE CONTROL SWITCH TO OFF | | AND BACK TO START ALLOWED THE PUMP TO START. ACTUATION OF THE FOLLOWER | | RELAY IS CONSIDERED TO BE A PARTIAL ACTUATION OF AN ENGINEERED SAFEGUARDS | | FEATURE. | | | | THE FOLLOWER RELAY ACTUATION IS BELIEVED TO HAVE BEEN CAUSED BY WORK | | ACTIVITIES ASSOCIATED WITH A MODIFICATION INSTALLATION. AN INADVERTENT | | BUMP OF THE RELAY WOULD CAUSE THE OBSERVED EQUIPMENT TRIPS. THIS | | INADVERTENT BUMP HAS NOT BEEN CONFIRMED AND IS STILL BEING INVESTIGATED. | | THERE WAS NO INDICATION OF AN UNDERVOLTAGE CONDITION AND THE ACTUATION | | LOGIC WAS NOT SATISFIED. | | | | CURRENTLY ACTIVITIES IN THE CABINET HAVE STOPPED. PRESSURE AND INVENTORY | | CONTROL ARE RETURNED TO NORMAL AND ALL RELATED EQUIPMENT HAS BEEN RETURNED | | TO A NORMAL STATUS. INVESTIGATION OF THE CAUSE IN CONTINUING. | | | | WE ARE REPORTING THIS EVENT UNDER 10CFR50.72(b)(2)(ii) ESF ACTUATION. THE | | ESF DEVICE THAT ACTUATED IS AN UNDERVOLTAGE LOAD SHEDDING FOLLOWER RELAY | | DESIGNED TO STRIP LOAD ON THE SAFEGUARDS 480 VOLT BUSES PRIOR TO DIESEL | | START AND LOAD. THIS PARTIAL ESF ACTUATION WAS NOT THE RESULT OF A VALID | | ACTUATION SIGNAL." | | | | UNIT 2 HAS THREE CHARGING PUMPS; THE "A" AND "B" PUMPS ASSOCIATED WITH THE | | "A" TRAIN AND THE REMAINING "C" PUMP ASSOCIATED WITH THE "B" TRAIN. AT THE | | TIME OF THE EVENT, BOTH THE "B" AND "C" CHARGING PUMPS WERE OPERATING. | | AFTER THE "B" CHARGING PUMP TRIPPED, OPERATORS STARTED THE "A" CHARGING | | PUMP TO RESTORE PRESSURE. PRESSURE DECREASED TO A MINIMUM OF 260 PSIG | | DURING THE TRANSIENT PRIOR TO BEING RETURNED TO THE OPERATING BAND OF | | 350 TO 400 PSIG. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1406 ON 10/10/97 BY RICK WOOD ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE DOES NOT CONSIDER THE ABOVE ACTUATION TO BE VALID BECAUSE | | THERE WAS NO INDICATION OF AN UNDERVOLTAGE CONDITION ON THE BUS AND THE | | ACTUATION LOGIC WAS NOT SATISFIED BECAUSE ONLY A SINGLE FOLLOWER RELAY | | WAS PICKED UP. THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R3DO BRENT CLAYTON. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/09/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 23:22 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 23:10[EDT]| |NRC NOTIFIED BY: GREG RUPPERT |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BECKNER, NRR EO | | |STORER FEMA | | |JOE GIITTER AEOD | | |BILL BEECHER PAO | | |DUNCAN DOE | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ALERT DECLARED DUE TO A FIRE IN THE #D21 EDG EXHAUST STACK - | | | | WHILE PERFORMING AN OPERABILITY TEST OF THE #D21 EDG WHICH WAS LOADED TO | | THE 4 KV EMERGENCY BUS, FLAMES SHOT OUT OF THE EDG EXHAUST STACK. | | | | AT 2310 ON 10/09/97, THE LICENSEE DECLARED AN ALERT DUE TO EMERGENCY CORE | | COOLING SYSTEM EQUIPMENT BEING INOPERABLE DUE TO A FIRE. | | | | THE LICENSEE STOPPED THE EDG AND THE FLAMES EXTINGUISHED. THE ONSITE | | FIRE BRIGADE RESPONDED TO THE FIRE. THE FIRE LASTED 10 TO 15 MINUTES. | | THE LICENSEE POSTED A FIRE REFLASH WATCH. | | | | THERE WAS NO RELEASE OF RADIATION. THE WIND IS BLOWING FROM THE SOUTH | | AT 3.5 MPH. THERE WERE NO INJURIES TO PERSONNEL. | | | | UNIT 2 IS STABLE AT 100% POWER. THE OTHER THREE UNIT 2 EDGs ARE OPERABLE. | | OFFSITE POWER IS AVAILABLE AND STABLE. | | | | THE LICENSEE ACTIVATED THEIR TECHNICAL SUPPORT CENTER. | | | | THE #D21 EDG IS IN A 30 DAY LIMITING CONDITION FOR OPERATION. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR AND ISSUED A PRESS RELEASE. | | | | IN ADDITION TO THE ABOVE NOTIFICATIONS, THE NRC OPERATIONS OFFICER NOTIFIED | | USDA (BICKERTON), EPA (FLETCHER), AND HHS (GRAY). | | | | * * * UPDATE AT 0200 ON 10/10/97 BY JOLLIFFE * * * | | | | AN NRC CONFERENCE CALL WAS CONDUCTED AT 0200 ON 10/10/97. THIS CALL | | INCLUDED PARTICIPANTS FROM REGION 1 (ANDERSON, HEHL, MILLER, WIGGINS, | | CHAWAGA, BURRITT, SHEEHAN, AND NICHOLSON); RI (PERRY); NRR EO (BECKNER); | | AND AEOD (GIITTER). | | | | * * * UPDATE AT 0319 ON 10/10/97 BY RUPPERT ENTERED BY GOULD * * * | | | | THE LICENSEE TERMINATED THE ALERT AT 0305 AFTER ELECTRICAL INSPECTIONS | | HAD BEEN SATISFACTORILY COMPLETED. THE FIRE REMAINED EXTINGUISHED AND | | NO APPARENT DAMAGE TO THE OTHER THREE EDGs WAS DETECTED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED NRR EO (BECKNER), R1DO (CONTE), DOE (DUNCAN), FEMA (STORER), EPA | | (FLETCHER), USDA (BARNES), AND HHS (SNOW) OF THE TERMINATION OF THE ALERT. | | | | * * * UPDATE AT 0700 ON 10/10/97 BY TROCINE * * * | | | | AN NRC CONFERENCE CALL WAS CONDUCTED AT 0700 ON 10/10/97. THIS CALL | | INVOLVED THE SENIOR RESIDENT INSPECTOR (BURRITT) AND NRC REGION 1 (HEHL, | | CHAWAGA, SHEEHAN) AMONG OTHERS. | | | | * * * UPDATE AT 0900 ON 10/10/97 BY TROCINE * * * | | | | A COMMISSIONERS' ASSISTANTS BRIEFING WAS CONDUCTED AT 0900 ON 10/10/97, AND | | THE FOLLOWING NOTIFICATIONS WERE MADE (*INDICATES THAT THE OFFICE DID NOT | | PARTICIPATE): AEOD (*BARRETT, GIITTER, JOLICOEUR, MARKSBERRY, AND ROSSI); | | CHAIRMAN JACKSON (MILLER); COMMISSIONER DICUS (KOKAJKO AND McDANIEL); | | COMMISSIONER DIAZ (HSIA); COMMISSIONER McGAFFIGAN (BEALL); DEDO (MITCHELL); | | DEDO REGION (KENNEDY); NRR EO (DENNIG), NRR (BENEDICT AND ZWOLINSKI); NRR | | PROJECT MANAGER (*); R1DO (*WHITE); PAO (BEECHER); STATE PROGRAMS (*); | | INTERNATIONAL PROGRAMS (UPSHAW); CAO (*MADDEN); SECY (BATES); REGION 1 | | (ANDERSON, HEHL/BRIEFER, AND SCRENCI); AND REGION 1 SRI (BURRITT). | | | | * * * UPDATE AT 0930 ON 10/10/97 BY TROCINE * * * | | | | AN NRC CONFERENCE CALL WAS CONDUCTED AT 0930 ON 10/10/97. THIS CALL | | INVOLVED EVENTS ASSESSMENT (DENNIG), NRR (ZWOLINSKI), REGION 1 (NICHOLSON), | | AND SITE (ANDERSON AND BURRITT) AMONG OTHERS. | | | | * * * UPDATE AT 1100 ON 10/10/97 FROM STEWART TO GOULD * * * | | | | THE LICENSEE PROVIDED ADDITIONAL INFORMATION AS A CLOSEOUT TO THIS EVENT | | NOTIFICATION. THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM | | THE LICENSEE: | | | | "THIS REPORT IS TO SATISFY THE 8-HOUR WRITTEN SUMMARY REQUIREMENT FOR A | | CLOSURE OF AN ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY IN | | ACCORDANCE WITH NUREG-0654, APPENDIX 1, AND THE 24-HOUR WRITTEN SUMMARY | | REQUIREMENT FOLLOWING CLOSEOUT OF AN UNUSUAL EVENT." | | | | "AT 2302 ON OCTOBER 9, 1997, THE UNIT 2 D21 EMERGENCY DIESEL GENERATOR | | (EDG) FAILED DURING A TEST RUN FOLLOWING PLANNED MAINTENANCE. THE FAILURE | | INVOLVED A FIRE IN THE D21 EDG EXHAUST MANIFOLD AT THE NUMBER ONE CYLINDER. | | OPERATIONS PERSONNEL TOOK PROMPT ACTIONS TO MANUALLY SEPARATE THE EDG | | FROM THE GRID AND SECURE THE ENGINE. THE EXHAUST STACK FIRE EXTINGUISHED | | IMMEDIATELY UPON SECURING THE ENGINE. THE EXHAUST MANIFOLD FIRE WAS | | EXTINGUISHED USING A PORTABLE FIRE EXTINGUISHER. ALL FLAMES WERE | | EXTINGUISHED BY 2304 ON OCTOBER 9, 1997. AN ALERT WAS DECLARED AT 2310 ON | | OCTOBER 9, 1997, DUE TO A FIRE WHICH COULD HAVE RENDERED THE D21 CLASS 1E | | POWER SUPPLY INOPERABLE." | | | | "INSPECTIONS OF ALL UNIT 2 EDG ENGINES AND UNIT 2 CLASS 1E POWER SUPPLY | | BUSSES WERE COMPLETED AT 0237 ON OCTOBER 10, 1997. NO ABNORMALITIES WERE | | IDENTIFIED, AND THE UNIT 2 CLASS 1E POWER SUPPLY BUSSES WERE VERIFIED TO | | BE OPERABLE. BASED UPON THIS VERIFICATION AND THE DETERMINATION THAT THE | | EVENT WAS LIMITED TO THE FAILURE OF THE D21 EDG ENGINE, THE ALERT WAS | | TERMINATED AT 0305 ON OCTOBER 10, 1997. THE REMAINING THREE UNIT 2 EDGs | | WILL BE RUN BY 2302 ON OCTOBER 10, 1997, IN ACCORDANCE WITH TECHNICAL | | SPECIFICATIONS." | | | | "AN INVESTIGATION TO IDENTIFY THE CAUSE OF THE D21 EDG FIRE AND CORRECTIVE | | ACTIONS REQUIRED TO PREVENT RECURRENCE IS IN PROGRESS. THE RESIDENT | | INSPECTORS WILL BE UPDATED AS THE INVESTIGATION PROGRESSES. THE RESULTS OF | | THE INVESTIGATION WILL BE DOCUMENTED IN A SPECIAL REPORT TO BE SUBMITTED BY | | NOVEMBER 10, 1997, IN ACCORDANCE WITH TECHNICAL SPECIFICATION 4.8.1.1.3." | | THE LICENSEE ALSO PLANS TO ISSUE A LICENSEE EVENT REPORT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO (WHITE) AND NRR EO (DENNIG). | | | | * * * UPDATE AT 1230 ON 10/10/97 BY TROCINE * * * | | | | AN NRC CONFERENCE CALL WAS CONDUCTED AT 1230 ON 10/10/97. THIS CALL | | INVOLVED REGION 1 (HEHL), NRR PROJECT MANAGER (PADOVAN), AND SENIOR | | RESIDENT INSPECTOR (BURRITT) AMONG OTHERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 07:56 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 07:00[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 +------------------------------------------------------------------------------+ | REACTOR WATER CLEANUP ISOLATION DUE TO A PERSONNEL ERROR DURING THE | | PERFORMANCE OF A LOSS OF OFFSITE POWER (LOOP) TEST | | | | DURING THE PERFORMANCE OF A DIVISION 1 LOSS OF OFFSITE POWER TEST, THE LEAK | | DETECTION BYPASS SWITCH FOR REACTOR WATER CLEANUP WAS IN THE 'NORMAL' | | POSITION INSTEAD OF THE 'BYPASS' POSITION AS REQUIRED BY THE TEST. AS A | | RESULT, WHEN THE LOSS OF OFFSITE POWER SIGNAL WAS INITIATED, THE REACTOR | | WATER CLEANUP SYSTEM ISOLATED. ALL SYSTEMS FUNCTIONED AS REQUIRED, AND | | THERE WAS NOTHING UNUSUAL OR MISUNDERSTOOD. REACTOR WATER CLEANUP HAS | | SINCE BEEN RESTORED TO NORMAL OPERATION, AND THE LOSS OF OFFSITE POWER TEST | | HAS BEEN RE-COMMENCED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 11:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: SIMPKIN |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 +------------------------------------------------------------------------------+ | THE PLANT DETERMINED A MAIN STEAMLINE BREAK COULD RESULT IN EXCEEDING THE | | MAXIMUM SITE ALLOWABLE PRIMARY-TO-SECONDARY LEAKAGE LIMIT. | | | | THE LICENSEE DECLARED UNIT 1 IS OUTSIDE OF DESIGN BASIS IN THAT ALLOWABLE | | OFF SITE DOSES MAY BE EXCEEDED. THE PROJECTED PRIMARY-TO-SECONDARY | | ACCIDENT LEAKAGE IN THE EVENT OF A MAIN STEAMLINE BREAK COULD RESULT IN | | EXCEEDING THE MAXIMUM SITE ALLOWABLE PRIMARY-TO-SECONDARY LEAKAGE LIMIT. IN | | CONJUNCTION WITH REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY AT THE MAXIMUM | | ALLOWED BY TS (0.35MICROCURIES/GRAM), COULD ALSO RESULT IN EXCEEDING | | ALLOWABLE OFF SITE DOSES. | | | | ON 10/10/97 THE PLANT EXCEEDED 144 DAYS OPERATING ABOVE 500øF. AT THAT | | TIME, CONTRIBUTION TO PRIMARY-TO-SECONDARY STEAM GENERATOR LEAKAGE DUE TO | | CIRCUMFERENTIAL CRACKING EVALUATED ALONG WITH OTHER CONTRIBUTORS(I.E., | | INTERIM PLUGGING CRITERIA, THE WESTINGHOUSE REPAIR METHODOLOGY FOR | | RETURNING STEAM GENERATOR TUBES TO SERVICE) DID NOT ENSURE THE MAXIMUM SITE | | ALLOWABLE PRIMARY-TO-SECONDARY LEAKAGE LIMIT WAS STILL MET. WITH | | CONSIDERATION OF THE CURRENT DOSE EQUIVALENT I-131 LIMIT OF 0.35 | | MICROCURIES/GRAM, THE PREDICTED PRIMARY-TO-SECONDARY LEAKAGE IN THE EVENT | | OF AN ACCIDENT COULD NOT ENSURE THAT THE OFF SITE DOSE WOULD BE A SMALL | | PERCENTAGE OF THE 10CFR100 LIMITS. | | | | THE PLANT'S OPERATION WILL PROCEED ON THE BASIS OF AN OPERABILITY | | ASSESSMENT OF CURRENT PLANT CONDITIONS (NO INDICATED LEAKAGE FROM | | CIRCUMFERENTIAL CRACKS, CONSERVATIVE TS REQUIRED PLANT SHUTDOWN AT 150GPD | | PRIMARY-TO-SECONDARY LEAKAGE). IN ADDITION THE LICENSEE WILL ENSURE THAT | | REACTOR COOLANT SYSTEM DOSE EQUIVALENT I-131 IS MAINTAINED AT OR BELOW 0.10 | | MICROCURIES/GRAM AS REQUESTED IN A 8/2/97 LICENSE AMENDMENT REQUEST | | SUBMITTAL. (NOTE: THE CURRENT UNIT 1 REACTOR COOLANT SYSTEM DOSE | | EQUIVALENT I-131 CONCENTRATION IS APPROXIMATELY 2.8E-4 MICROCURIES/GRAM.) | | WITH CONSIDERATION OF THE REDUCED DOSE EQUIVALENT I-131 LIMIT OF 0.10 | | MICROCURIES/GRAM, THE PREDICTED PRIMARY-TO-SECONDARY LEAKAGE IN THE EVENT | | OF AN ACCIDENT DOES NOT EXCEED THE REVISED MAXIMUM ALLOWABLE SITE LEAKAGE | | AND THE OFF SITE DOSE WOULD STILL REMAIN A SMALL PERCENTAGE OF THE 10CFR100 | | LIMITS. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:13 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 09:00[CDT]| |NRC NOTIFIED BY: DAVID GRONEK |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROD 46-55 INSERTED TO FULL IN FROM FULL WITHDRAWN. | | | | "WHILE ADJUSTING A LIMIT SWITCH ON THE SCRAM INLET VALVE FOR CONTROL ROD | | 46-55, THE ROD INSERTED TO FULL IN (00) FROM FULLY WITHDRAWN (48) POSITION. | | THIS ROD IS A PERIPHERAL ROD. NO CORE THERMAL LIMITS WERE EXCEEDED OR | | CHALLENGED. THE CONTROL ROD HAS BEEN ELECTRICALLY AND HYDRAULICALLY | | ISOLATED AND DECLARED INOPERABLE PENDING COMPLETION OF A ROOT CAUSE | | INVESTIGATION." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:19 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 11:12[CDT]| |NRC NOTIFIED BY: JEFF HEATON |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 99 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO Rx TRIP FROM 99% DUE TO DEGRADED CONTROL ROD DRIVE POWER SUPPLY - | | | | AT 1112 CDT, THE REACTOR AUTOMATICALLY TRIPPED FROM 99% POWER APPARENTLY | | DUE TO A DEGRADED POWER SUPPLY IN THE CONTROL ROD DRIVE SYSTEM. ALL | | CONTROL RODS INSERTED COMPLETELY. THE AUXILIARY FEEDWATER SYSTEM ACTUATED, | | AS EXPECTED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. NO SAFETY OR | | RELIEF VALVES LIFTED. | | | | UNIT 2 RECEIVED AN INVALID CONTAINMENT VENTILATION ISOLATION SIGNAL | | APPARENTLY CAUSED BY A VOLTAGE SPIKE ASSOCIATED WITH THE NORMAL POST TRIP | | AUTOMATIC BUS POWER TRANSFER. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE AND DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 13:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: MARY BETH DEPUYDT |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INSPECTION FOUND FIVE LOCA FLOODUP TUBES (CONDUIT) DAMAGED. | | | | FLOODUP TUBE INSPECTIONS HAVE BEEN PERFORMED AS A RESULT OF A PREVIOUS | | PROBLEM RELATED TO STRESS CRACKING IN THE LOWER TUBE AREA. AS A RESULT OF | | INSPECTION, FIVE FLOODUP TUBES WERE FOUND TO BE DAMAGED IN A DIFFERENT AREA | | OF THE TUBES. THREE OF THE FIVE TUBES CONTAIN CABLES WHICH ARE CONNECTED | | TO COMPONENTS REQUIRED TO FUNCTION FOLLOWING A LOCA. THESE COMPONENTS | | INCLUDE STEAM GENERATORS 1 AND 2 LEVEL TRANSMITTERS, REACTOR VESSEL LEVEL | | INDICATING SYSTEM THERMOCOUPLES AND RTDS, AND A HIGH RANGE RADIATION | | MONITOR. | | | | IN ALL CASES, THE DAMAGE TO THE TUBES PROVIDE A PATHWAY FOR WATER TO ENTER | | AND ABSENT ANY QUALIFICATION DATA FOR THE IMMERSED CABLES, CONTINUED | | OPERATION OF THE ASSOCIATED COMPONENTS CAN NOT BE GUARANTEED. THE AFFECTED | | EQUIPMENT HAS BEEN DECLARED INOPERABLE AND THE FLOODUP TUBES WILL BE | | REPLACED PRIOR TO UNIT RESTART. A SIMILAR INSPECTION IS BEING PERFORMED IN | | UNIT 1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 14:25[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON, R3 RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |JIM BELANGER, R3 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SECURITY EVENT - | | | | DISCOVERY OF PREVIOUS DRUG USE BY CONTRACTOR GRANTED UNESCORTED ACCESS | | TO THE SITE. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG | | FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MALLINCKRODT, INC, WARREN, MI |NOTIFICATION DATE: 10/10/97 | | CITY: WARREN REGION: 3 |NOTIFICATION TIME: 15:45 [ET]| | COUNTY: STATE: MI |EVENT DATE: 10/10/97 | |LICENSE#: 24-04206-10MD AGREEMENT: N |EVENT TIME: 14:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/10/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRENT CLAYTON RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: PAUL LUKAS | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAMINATED EMPTY RADIOACTIVE MEDICAL SUPPLIES DELIVERY SUITCASE - | | | | AN EMPTY RADIOACTIVE MEDICAL SUPPLIES DELIVERY SUITCASE WAS TRANSPORTED | | BY VAN FROM HARPER HOSPITAL, DETROIT, MI, TO THE MALLINCKRODT FACILITY IN | | WARREN, MI, 15 MILES AWAY. UPON ARRIVAL AT MALLINCKRODT, THE REMOVABLE | | CONTAMINATION ON THE OUTSIDE OF THE SUITCASE WAS DETERMINED TO BE | | 1.2M DPM/100 CMý. THE DELIVERY VAN AND ITS DRIVER HAD NO DETECTABLE | | CONTAMINATION ON THEM. THE LICENSEE PLACED THE SUITCASE IN CONTROLLED | | STORAGE FOR RADIOACTIVE DECAY. | | | | THE LICENSEE ALSO REPORTED THIS EVENT TO R3 TOM YOUNG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33068 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/10/97 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 16:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 14:54[CDT]| |NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF AN EMERGENCY DIESEL GENERATOR (EDG) COULD CAUSE A REDUCTION IN THE | | REQUIRED NUMBER OF RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) PUMPS | | AVAILABLE. | | | | DURING A REVIEW OF THE BROWNS FERRY (BFN) PROPOSED IMPROVED STANDARD | | TECHNICAL SPECIFICATION CONVERSION, A DISCREPANCY WAS DISCOVERED BETWEEN | | THE CURRENT TECHNICAL SPECIFICATION (TS) AND THE FINAL SAFETY ANALYSIS | | REPORT (FSAR). THE RHRSW SYSTEM IS A COMMON SYSTEM FOR ALL 3 BFN UNITS. | | THE FSAR REQUIRES 2 RHRSW PUMPS PER UNIT TO PROVIDE COOLING FOR DESIGN | | BASIS ACCIDENT CONDITIONS FOR THE ACCIDENT UNIT AND THE NON-ACCIDENT | | UNIT(S). THERE ARE 8 PUMPS THAT CAN BE ALIGNED FOR RHRSW SERVICE, AND TS | | REQUIRES 4, 5, AND 7 OPERABLE PUMPS FOR 1, 2, AND 3 FUELED UNITS. THE | | NUMBER OF REQUIRED PUMPS IS ONE GREATER THAN THE FSAR MINIMUM. HOWEVER, | | THE EDG POWER SOURCES FOR THE PUMPS ARE SUCH THAT 2 OF THE PUMPS ALIGNED | | FOR RHRSW COULD BE POWERED FROM THE SAME EDG. IN THIS CASE A SINGLE | | FAILURE OF THE EDG WOULD RESULT IN ONLY ONE RHRSW PUMP AVAILABLE TO | | SHUTDOWN THE NON-ACCIDENT UNIT. | | | | DURING THE POSTULATED SCENARIO, THE SUPPRESSION CHAMBER, IN CONJUNCTION | | WITH THE RHRSW PUMPS VIA THE RHR HEAT EXCHANGER, IS THE ONLY SAFETY-RELATED | | METHOD OF HEAT REJECTION FROM THE REACTOR VESSEL. ANALYSIS INDICATES THE | | POTENTIAL BULK SUPPRESSION POOL TEMPERATURE WILL PEAK AT 193øF WITH ONLY | | ONE RHRSW PUMP AVAILABLE ON THE NON-ACCIDENT UNIT WITH A LOSS OF OFF-SITE | | POWER. THIS EXCEEDS THE DESIGN BASIS TEMPERATURE LIMIT OF 177øF FOR THE | | SUPPRESSION POOL. | | | | ADMINISTRATIVE CONTROLS ARE IN EFFECT TO PLACE ADDITIONAL RHRSW PUMPS IN | | SERVICE OR ENSURE THAT RHRSW PUMPS ARE POWERED BY DIFFERENT EDGs UNTIL A | | LICENSE AMENDMENT CAN BE PROCESSED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33069 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 17:45 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE BARRIER FOUND WITH INADEQUATE ELECTRICAL PENETRATION SEAL. | | | | A WALKDOWN OF ELECTRICAL PENETRATIONS WAS PERFORMED. IT WAS NOTICED THAT | | ELECTRICAL CABLE PENETRATIONS IN THE TURBINE BUILDING/AUXILIARY BUILDING | | WALL, A FIRE RATED SEPARATION BARRIER, WERE INADEQUATELY SEALED. AN | | EVALUATION OF THE AFFECTED BARRIER DETERMINED THAT THE LACK OF PENETRATION | | SEALS MAY INTRODUCE A FIRE HAZARD INTO AN ADJACENT AREA. ONE SIDE OF THE | | BARRIER IS PROTECTED BY FULL SUPPRESSION AND DETECTION, WHILE THE OTHER | | SIDE HAS FIRE DETECTION ONLY. | | | | A ONE HOUR FIRE WATCH HAS BEEN ESTABLISHED. FURTHER EVALUATION IS IN | | PROGRESS AND WILL INCLUDE A DETERMINATION OF THE AFFECT ON THE DESIGN | | BASIS. | | | | NOTIFICATION IS MADE BASED ON A NONCOMPLIANCE WITH LICENSE CONDITION | | 2.C(9), CONDITIONS FOUND THAT ARE NOT IN COMPLIANCE WITH THE APPROVED FIRE | | PROTECTION PROGRAM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33070 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/10/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 19:57 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 19:14[EDT]| |NRC NOTIFIED BY: JIM KRITZER |LAST UPDATE DATE: 10/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - INADEQUATE CABLE SEPARATION IN SAFETY-RELATED ALTERNATE COOLING SYSTEM - | | | | DURING A DESIGN REVIEW, THE LICENSEE DISCOVERED THAT ELECTRICAL CABLES FROM | | DIVISION I MOTOR CONTROL CENTER (MCC) #8C AND DIVISION 2 MCC #9C MERGE INTO | | A COMMON CLASS 1E CABLE FEEDING SAFETY-RELATED ALTERNATE COOLING SYSTEM | | COOLING TOWER FAN #2-1. THIS COMMON CABLE INSTALLATION IS CONTRARY TO THE | | CABLE SEPARATION CRITERIA OF UFSAR SECTION 8.4.6. | | | | THE LICENSEE OPENED THE CIRCUIT BREAKERS ON MCC #8C AND #9C AND DECLARED | | THE ALTERNATE COOLING SYSTEM INOPERABLE. TECH SPEC LCO A/S 3.5.D.3 | | REQUIRES THE ALTERNATE COOLING SYSTEM TO BE RESTORED TO OPERABLE STATUS | | WITHIN 7 DAYS OR TO SHUT THE PLANT DOWN. | | | | THE LICENSEE IS INVESTIGATING THIS CONDITION AND DETERMINING CORRECTIVE | | ACTIONS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33071 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 10/11/97 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 00:56 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 20:57[PDT]| |NRC NOTIFIED BY: JEANNE KITTLER |LAST UPDATE DATE: 10/11/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 81 POWER OPERATION | 81 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM DECLARED INOPERABLE DUE TO FAILURE | | OF THE HPCS BATTERY CHARGER. | | | | "FAILURE OF THE HPCS BATTERY CHARGER 'HPCS-C1-1' OCCURRED AT 2057PDT. IN | | ACCORDANCE WITH WNP-2 TECHNICAL SPECIFICATION 3.8.4.B, THE HPCS SYSTEM WAS | | DECLARED INOPERABLE IMMEDIATELY. INOPERABILITY OF THE HPCS SYSTEM IS BEING | | REPORTED PER 10CFR50.72(b)(2)(iii) DUE TO THE FAILURE OF A SINGLE TRAIN | | SAFETY SYSTEM." | | | | OPERATORS WERE ALERTED TO THE FAILURE BY A CHARGER TROUBLE ALARM AND A DC | | BUS UNDERVOLTAGE ALARM. THERE WAS NO MAINTENANCE BEING PERFORMED AT THE | | TIME WHICH COULD HAVE CAUSED THE FAILURE. THE LICENSEE IS INVESTIGATING TO | | DETERMINE ROOT CAUSE. AT THE TIME, RCIC WAS INOPERABLE FOR MAINTENANCE. | | POST MAINTENANCE TESTING WAS COMPLETED AND RCIC DECLARED OPERABLE AT | | 2114PDT. WITH HPCS INOPERABLE UNIT 2 IS CURRENTLY IN THE 14 DAY LCO A/S | | 3.5.1. ALL OTHER ECCS EQUIPMENT IS OPERABLE. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33072 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/11/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 16:38 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/11/97 | +------------------------------------------------+EVENT TIME: 14:20[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 10/11/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 | M N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL SCRAM USED TO STOP REACTOR VESSEL LEVEL DECREASE DUE TO MAINTENANCE. | | | | DURING WORK ON SCRAM AIR HEADER VALVE C11-F110A, A TAGOUT WAS HUNG TO | | ISOLATE AIR TO THE SYSTEM. THIS CAUSED THE SCRAM DISCHARGE VOLUME (SDV) TO | | FILL WITH INVENTORY FROM THE REACTOR VESSEL. REACTOR VESSEL LEVEL | | DECREASED APPROXIMATELY 15 INCHES. THE SDV LEVEL WAS BYPASSED IN THE | | REACTOR PROTECTION SYSTEM TO ALLOW SURVEILLANCES TO CONTINUE CONCURRENT | | WITH THE VALVE C11-F110A WORK. THE LOSS OF REACTOR VESSEL INVENTORY | | REQUIRED ENTRY INTO AN OFF NORMAL PROCEDURE FOR THE LOSS OF DECAY HEAT | | REMOVAL. REACTOR VESSEL LEVEL DECREASE WAS TERMINATED BY A MANUAL SCRAM. | | THERE WAS NO ROD MOTION AS RODS WERE ALREADY AT THE FULL IN POSITION. | | | | THERE WAS NO ACTUAL LOSS OF DECAY HEAT REMOVAL AND NO CHANGE IN REACTOR | | VESSEL TEMPERATURE. REACTOR VESSEL LEVEL IS BEING RESTORED TO NORMAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33073 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 10/11/97 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 16:39 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/11/97 | +------------------------------------------------+EVENT TIME: 14:22[EDT]| |NRC NOTIFIED BY: MIKE SMITH |LAST UPDATE DATE: 10/11/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 +------------------------------------------------------------------------------+ | -ELECTRICAL SHORT ACTUATED THE HIGH CONSEQUENCE LIMITING SAFEGUARDS SYSTEM- | | | | UNIT 2 IS IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE. | | | | DURING THE REPLACEMENT OF RELAY #1B12 IN THE UNIT 2 TRAIN 'B' HIGH | | CONSEQUENCE LIMITING SAFEGUARDS (HCLS) SYSTEM, AN INADVERTENT ELECTRICAL | | SHORT OCCURRED WHICH ACTUATED THE UNIT 2 HCLS SYSTEM. THIS CAUSED THE | | ACTUATION OF THE UNIT 2 TRAIN 'B' SAFETY INJECTION SYSTEM AND THE AUTO | | START OF THE UNIT 2 #3 EMERGENCY DIESEL GENERATOR. | | | | AFTER VERIFYING THAT THE HCLS SYSTEM WAS NOT REQUIRED, THE LICENSEE | | RESTORED ALL EQUIPMENT TO THE NORMAL CONFIGURATION. APPROXIMATELY | | 150 GALLONS WAS INJECTED INTO THE REACTOR COOLANT SYSTEM. | | | | UNIT 1 REMAINED STABLE AT 100% POWER AND WAS UNAFFECTED BY THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33074 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/12/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 10:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/12/97 | +------------------------------------------------+EVENT TIME: 05:59[CDT]| |NRC NOTIFIED BY: DONALD C. SMITH |LAST UPDATE DATE: 10/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 | A N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN INVALID ESF ACTUATION CAUSED BY AN ELECTRICAL SHORT | | WHILE INSTALLING A JUMPER DURING POST MODIFICATION TESTING. | | | | "AT 0559CDT ON 10/12/97, UNIT 2 RECEIVED AN INVALID ACCIDENT SIGNAL ON -122 | | REACTOR WATER LEVEL DURING REFUEL ACTIVITIES. ADDITIONALLY, A FULL REACTOR | | SCRAM WAS ALSO RECEIVED DUE TO LOW SCRAM PILOT AIR HEADER PRESSURE CAUSED | | BY ATWS/ARI. CORE SPRAY LOOP I INITIATED AND INJECTED TO THE VESSEL | | RESULTING IN REFUELING ACTIVITIES BEING TERMINATED DUE [TO] VESSEL WATER | | CLARITY. DIVISION I OF RHR DID NOT INJECT DUE TO [THE] SHUTDOWN COOLING | | ALIGNMENT (SUCTION VALVES CLOSED). ALL EIGHT DIESEL GENERATORS ALONG WITH | | THEIR ASSOCIATED RHRSW PUMPS STARTED AS EXPECTED. UNIT 3 WAS AT 100% POWER | | AND WAS UNAFFECTED BY THE EVENT. INVESTIGATION HAS REVEALED THAT THE CAUSE | | OF THIS EVENT WAS ASSOCIATED WITH THE POST MODIFICATION TESTING OF THE UNIT | | 2 MAIN STEAM RELIEF VALVE PRESSURE SWITCH MODIFICATION. DURING JUMPER | | INSTALLATION, TWO TERMINALS WERE SHORTED CAUSING THE INVALID SIGNAL FOR | | -122 REACTOR WATER LEVEL COMMON ACCIDENT TO BE MADE UP TO UNIT 2." | | | | ALL SYSTEMS WERE RESTORED BY 0642CDT AND RETURNED TO STANDBY WITH THE | | EXCEPTION OF SEVERAL ISOLATED RELAYS AND DAMAGED CIRCUIT CARDS. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33075 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/12/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 20:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/12/97 | +------------------------------------------------+EVENT TIME: 15:25[CDT]| |NRC NOTIFIED BY: MICHAEL MCWILLIAMS |LAST UPDATE DATE: 10/12/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF SUPPORT SYSTEMS TO THE RESIDUAL HEAT REMOVAL PUMPS. | | | | DURING A PROCEDURE TO SPLIT THE SERVICE WATER (SW) SYSTEM HEADER, COOLING | | WATER WAS INADVERTENTLY ISOLATED TO THE #2B EMERGENCY DIESEL GENERATOR | | (EDG). ALSO, IN PROGRESS WAS A ROUTINE PROCEDURE FOR ROLLING THE #0 EDG | | AND AS A PART OF THE SW SYSTEM SPLIT PROCEDURE, THE #1C SW PUMP WAS PLACED | | IN THE PULL-TO-LOCK POSITION. THIS LEFT ONLY 1 OPERABLE SW PUMP AND THE | | CONSEQUENT LOSS OF SUPPORT SYSTEMS TO THE UNIT 2 RESIDUAL HEAT REMOVAL | | PUMPS. TECHNICAL SPECIFICATION INTERPRETATION 91-05 CONDITION 11 REQUIRES | | 3 OPERABLE SW PUMPS. THE CONDITION LASTED FROM 1525 TO 1710 CDT WHEN | | COOLING WAS RESTORED TO THE #2B EDG. THE #0 EDG WAS RESTORED TO OPERABLE | | STATUS AT 1650 CDT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33076 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/13/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 09:58 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/13/97 | +------------------------------------------------+EVENT TIME: 08:50[EDT]| |NRC NOTIFIED BY: SANJEEV ARAB |LAST UPDATE DATE: 10/13/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TARGET ROCK SRV PILOTS SENT TO WYLE LABS FOR TESTING FAILED TO MEET THE | | SPECIFIED SETPOINT TOLERANCE. | | | | "TECH SPEC 3.4.2.1 REQUIRES THE SAFETY FUNCTION OF AT LEAST ELEVEN (11) OF | | THE 15 SAFETY RELIEF VALVES (SRVs) TO BE OPERABLE WITHIN THE SPECIFIED | | SETPOINT TOLERANCE OF ñ1%. ALL 15 SRV PILOTS WERE REMOVED DURING THE | | CURRENT MID-CYCLE OUTAGE AND SENT TO WYLE LABS FOR TESTING. THE RESULTS OF | | THE FIRST EIGHT VALVES TESTED SHOW THAT ALL EIGHT FAILED THE ñ1% SETPOINT | | TOLERANCE CRITERIA. THE REMAINING 7 SRV PILOTS ARE STILL UNDERGOING | | SETPOINT TESTING. THE SRVs ARE TARGET ROCK 2-STAGE SAFETY RELIEF VALVES." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33077 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 10/13/97 | | CITY: WINDSOR REGION: 1 |NOTIFICATION TIME: 13:42 [ET]| | COUNTY: STATE: CT |EVENT DATE: 08/06/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/13/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN PELLET RDO | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: HESS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ABB COMBUSTION REPORTED A PART 21 ON CERTAIN MODELS OF POTTER & BRUMFIELD | | RELAYS. THEY HAVE IDENTIFIED THE "DEFECT" AS CONTAMINATION OF LUBRICANT | | WHICH HAS LEAD TO THE HARDENING OF THE LUBRICANT IN CERTAIN POTTER & | | BRUMFIELD PRODUCTS DIVISION MDR RELAYS(MODELS "170-1" AND "7032"). THIS | | "DEFECT" COULD RESULT IN RELAY FAILURE. THESE RELAYS ARE USED IN THE PLANT | | PROTECTION SYSTEM. THERE IS ALSO THE POTENTIAL FOR RELAY MODELS "7033" AND | | "7034" TO FAIL TO FUNCTION CORRECTLY. THESE RELAYS HAVE BEEN SUPPLIED TO | | PALO VERDE 1, 2 AND 3, ARKANSAS NUCLEAR ONE UNIT 2, WATERFORD 3, AND SAN | | ONOFRE 2 AND 3. ABB-CE IS CURRENTLY EVALUATING POTENTIAL CORRECTIVE | | ACTIONS WHICH WILL BE PROVIDED TO THE UTILITIES WITH ABB-CE DESIGNED | | NUCLEAR STEAM SUPPLY SYSTEMS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33078 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/14/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 04:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/14/97 | +------------------------------------------------+EVENT TIME: 03:18[EDT]| |NRC NOTIFIED BY: LEE MANSFIELD |LAST UPDATE DATE: 10/14/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A CONTAINMENT VENTILATION ISOLATION DURING REMOVAL OF A | | CONTROL ROD DRIVE SHAFT. | | | | "WHILE REMOVING A CONTROL ROD DRIVE SHAFT FROM THE REACTOR CAVITY, A | | CONTAINMENT VENTILATION ISOLATION SIGNAL WAS RECEIVED. RADIATION MONITOR | | 1RE-002 HIGH ALARM WAS SET FOR 15 mR/HR, AND THE MAXIMUM IT RECORDED WAS | | APPROXIMATELY 25mR/HR. ALL COMPONENTS ACTUATED AS REQUIRED. | | | | "INVESTIGATION REVEALED THAT THE INDIVIDUAL DESIGNATED DURING THE PRE-JOB | | BRIEFING TO NOTIFY THE CONTROL ROOM FAILED TO DO SO PRIOR TO THE BEGINNING | | OF THE EVOLUTION. | | | | "AN EVENT REVIEW IS UNDERWAY." | | | | CONTROL ROOM OPERATORS NORMALLY BLOCK THE ISOLATION SIGNAL AFTER | | NOTIFICATION PRIOR TO MOVEMENT OF THESE COMPONENTS SO AS TO PREVENT THE ESF | | ACTUATION. THE ISOLATION SIGNAL AND ASSOCIATED COMPONENTS HAVE BEEN RESET. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+