U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/30/97 - 06/02/97 ** EVENT NUMBERS ** 32401 32411 32412 32413 32414 32415 32416 32417 32418 32419 32420 32421 32422 32423 32424 32425 32426 +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32401 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: HARBIN CLINIC, ROME, GEORGIA |NOTIFICATION DATE: 05/28/97 | | CITY: ROME REGION: 2 |NOTIFICATION TIME: 16:51 [ET]| | COUNTY: FLOYD STATE: GA |EVENT DATE: 05/28/97 | |LICENSE#: GA1278-1 AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/30/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES HOSEY, REG 2 RDO | | | | +------------------------------------------------+ROBERT BORES, REG 1 RDO | |NRC NOTIFIED BY: RICHARD WOODRUFF/REGION 2 |JOHN JACOBSON, REG 3 RDO | |HQ OPS OFFICER: LEIGH TROCINE |CHEN EPA | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT INVOLVING CONTAMINATED LEAD APRONS AT THE HARBIN | | CLINIC LOCATED IN ROME, GEORGIA | | | | AT APPROXIMATELY 1500, THE STATE OF GEORGIA RECEIVED A REPORT FROM THE | | HARBIN CLINIC (A NUCLEAR MEDICAL FACILITY LOCATED IN ROME, GEORGIA) | | REGARDING CONTAMINATED LEAD APRONS. THE STATE OF GEORGIA (TOM HILL) | | NOTIFIED THE NRC REGION 2 OFFICE (RICHARD WOODRUFF) AT APPROXIMATELY 1600. | | THE NRC REGION 2 OFFICE (RICHARD WOODRUFF) NOTIFIED THE NRC OPERATIONS | | CENTER AT 1651. | | | | IT WAS REPORTED THAT THE CONTAMINATED LEAD APRONS WERE NEW AND THAT THEY | | HAD UNIFORM RADIATION (1 MILLIREM ON CONTACT). THE APRONS WERE PURCHASED | | FROM PICKER X-RAY LOCATED IN OHIO AND WERE MANUFACTURED BY EZ-EM LOCATED IN | | PORT CHESTER, NEW YORK. THE LEAD USED IN MANUFACTURING THE APRONS CAME | | FROM BARR-RAY LOCATED IN LITTLESTOWN, PENNSYLVANIA. | | | | THE STATE OF GEORGIA PLANS TO SEND A REPRESENTATIVE TO HARBIN CLINIC TO | | PICK UP AN APRON FOR ANALYSIS. THE STATE OF GEORGIA ALSO NOTIFIED THE | | STATES OF NEW YORK AND PENNSYLVANIA, AND IT WAS REPORTED THAT THE STATES OF | | NEW YORK AND PENNSYLVANIA ARE FOLLOWING UP ON THIS ISSUE. | | | | THE NRC REGION 2 OFFICE NOTIFIED THE NRC REGION 1 OFFICE (CRAIG GORDON), | | NRC OFFICE REGION 3 (MONTE PHILLIPS), AND NRC OFFICE OF STATE PROGRAMS | | (LLOYD BOLLING). THE NRC REGION 2 OFFICE ALSO PLANS TO ISSUE A PRELIMINARY | | NOTIFICATION REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32411 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/29/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 17:40 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/29/97 | +------------------------------------------------+EVENT TIME: 12:45[CDT]| |NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 05/30/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 +------------------------------------------------------------------------------+ | A 2-GPM HPCS RELIEF VALVE LEAK WAS FOUND DURING A SURVEILLANCE TEST. | | | | DURING A SURVEILLANCE TEST OF THE HIGH PRESSURE CORE SPRAY (HPCS) PUMP, | | A 2-GPM LEAK WAS DISCOVERED COMING FROM RELIEF VALVE #E22-RVF035. (THE | | LEAK IS COMING THROUGH THE BELLOWS THEN OUT THE LEAKOFF PORT LOCATED ON THE | | BONNET OF THE 1" THERMAL RELIEF VALVE WHICH IS LOCATED ON THE DISCHARGE OF | | THE HPCS PUMP.) THIS IS A PRIMARY CONTAINMENT ISOLATION VALVE PER | | TECHNICAL SPECIFICATIONS, WHICH DISCHARGES INTO THE SUPPRESSION POOL. AT | | THE TIME OF THE CALL, THE LICENSEE COULD NOT EXACTLY IDENTIFY THE SOURCE OF | | THE LEAKAGE, BUT IT IS EXPECTED TO BE A LEAK OF THE SEALING BELLOWS AROUND | | THE VALVE STEM. BECAUSE THE BELLOWS IS THE ONLY BARRIER BETWEEN THE | | PRIMARY CONTAINMENT SUPPRESSION POOL AND THE SECONDARY CONTAINMENT | | AUXILIARY BUILDING, THIS IS CONSIDERED AN EVENT OR CONDITION THAT ALONE | | COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF CONTAINMENT | | TO PREVENT THE RELEASE OF RADIOACTIVE MATERIALS. MITIGATING THIS EVENT IS | | THAT THE OPEN END OF THE DISCHARGE PIPING IS SUBMERGED (UNDERWATER) IN THE | | SUPPRESSION POOL. | | | | THE LICENSEE HAS ENTERED TECHNICAL SPECIFICATION 3.6.1.1, PRIMARY | | CONTAINMENT INTEGRITY. THE LICENSEE IS CURRENTLY TAKING ACTION TO REPLACE | | THE VALVE OR INSTALL A BLIND FLANGE TO RESTORE CONTAINMENT. THE LICENSEE | | SAID THAT HPCS IS STILL CONSIDERED FULLY OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 05/30/97, @ 0624 EDT FROM KELLEY TAKEN BY MACKINNON * * * | | | | THE HPCS SYSTEM WAS DECLARED INOPERABLE PER TECHNICAL SPECIFICATION 3.5.1 | | WHEN THE LICENSEE TAGGED IT OUT OF SERVICE TO REPLACE THE THERMAL RELIEF | | VALVE. THE LICENSEE EXITED TECHNICAL SPECIFICATION 3.6.1.1 AT 2013 CDT | | ON 05/29/97 WHEN THE RELIEF VALVE WAS REPLACED AND EXITED TECHNICAL | | SPECIFICATION 3.5.1 AT 0006 CDT ON 5/30/97 AFTER THE HPCS SYSTEM WAS | | RESTORED TO OPERABLE STATUS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE OPERATIONS | | OFFICER NOTIFIED THE R4DO (JOHN PELLET). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32412 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GONZALES X-RAY COMPANY |NOTIFICATION DATE: 05/30/97 | | CITY: GONZALES REGION: 4 |NOTIFICATION TIME: 11:30 [ET]| | COUNTY: STATE: LA |EVENT DATE: 05/22/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:01[CDT]| | DOCKET: |LAST UPDATE DATE: 05/30/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN PELLET, REG 4 RDO | | |LARRY CAMPER, NMSS EO | +------------------------------------------------+PATRICIA HOLAHAN NMSS | |NRC NOTIFIED BY: NOBLE(LA DPT OF ENV QUAL) |CHARLES HOSEY, REG 2 RDO | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TWO RADIOGRAPHERS EXPOSED TO A 70 CURIE IR-192 CAMERA SOURCE - | | | | ON 05/22/97, TWO RADIOGRAPHERS FROM GONZALES X-RAY COMPANY, A LOUISIANA | | LICENSEE (LICENSE #LA4641-L01), EXPERIENCED A "SPEC" DRIVE CABLE CONNECTOR | | PULLING FREE FROM THE END OF A CAMERAS DRIVE CABLE WHILE WORKING ON A JOB | | SITE IN COUNCE, TN. AT THE TIME OF THE DISCONNECT, THE SOURCE WAS NEAR THE | | PORT ON THE CAMERA, AND THE DRIVE CABLE WAS USED TO RETURN THE SOURCE TO | | THE SHIELDED POSITION. EXPOSURES TO THE TWO RADIOGRAPHERS WERE 480 AND 500 | | mR AS OBTAINED FROM THEIR POCKET DOSIMETERS. THE SOURCE INVOLVED WAS A | | 70-CURIE IR-192 RADIOGRAPHY SOURCE LOADED IN A "SPEC-150" CAMERA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32413 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 05/30/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 13:28 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 05/30/97 | +------------------------------------------------+EVENT TIME: 12:28[EDT]| |NRC NOTIFIED BY: MARSHALL |LAST UPDATE DATE: 05/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | A SAFEGUARDS SYSTEM DEGRADATION RELATED TO THE PLANT ALARM SYSTEM WAS | | DISCOVERED. COMPENSATORY MEASURES WERE NOT IMMEDIATELY TAKEN. THE NRC | | RESIDENT INSPECTOR WILL BE NOTIFIED. (REFER TO HOO LOG FOR ADDITIONAL | | INFORMATION.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32414 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/30/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:46 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/30/97 | +------------------------------------------------+EVENT TIME: 11:43[CDT]| |NRC NOTIFIED BY: SPECHT |LAST UPDATE DATE: 05/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 ENTERED A 14-DAY LIMITING CONDITION FOR OPERATION (LCO) ACTION | | STATEMENT WHEN THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM WAS | | DECLARED INOPERABLE. | | | | THIS OCCURRED WHILE PERFORMING PROCEDURE #QCOS-2300-26, "QUARTERLY HPCI | | CLEAN AND CONTAMINATED STORAGE TANK SUCTION CHECK VALVE CLOSURE TEST," | | WHICH DEMONSTRATED THAT THE SUCTION VALVE DID NOT MEET ITS PERFORMANCE | | ACCEPTANCE CRITERIA. THEREFORE, THIS COMPONENT AND THE HPCI SYSTEM WERE | | DECLARED INOPERABLE AND THIS PLACED UNIT 1 IN A 14-DAY LCO ACTION | | STATEMENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 32415 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AMERISTEEL, INC. |NOTIFICATION DATE: 05/30/97 | | CITY: JACKSON REGION: 2 |NOTIFICATION TIME: 14:33 [ET]| | COUNTY: STATE: TN |EVENT DATE: 05/30/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:01[EDT]| | DOCKET: |LAST UPDATE DATE: 05/30/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES HOSEY RDO | | | | +------------------------------------------------+CHEN EPA | |NRC NOTIFIED BY: TROJANOWSKI (NRC REG 2) |HOLAHAN NMSS | |HQ OPS OFFICER: CHAUNCEY GOULD |MYERS DOT | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -RAILCAR CARRYING SCRAP METAL ACTIVATED RAD MONITOR UPON ENTERING SCRAPYARD | | | | THE STATE OF TENNESSEE REPORTED TO THE NRC REGION 2 OFFICE THAT A RAILCAR | | CONTAINING SCRAP METAL ENTERED THE AMERISTEEL, INC FACILITY IN JACKSON, TN, | | AND ACTIVATED THE RADIATION MONITOR. THE RADIOACTIVITY HAS BEEN DETERMINED | | TO BE LOCATED TOWARD ONE END AND SIDE OF THE RAILCAR. AT A DISTANCE OF | | FIVE FEET FROM THE SOURCE OF ACTIVITY, THE INSTRUMENTATION PEGGED ON THE 5 | | MILLIREM/HOUR SCALE. THE STATE OF TN IS SENDING A REPRESENTATIVE TO THE | | SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32416 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COOPER ENERGY SERVICES |NOTIFICATION DATE: 05/30/97 | | CITY: GROVE CITY REGION: 1 |NOTIFICATION TIME: 14:53 [ET]| | COUNTY: STATE: PA |EVENT DATE: 05/30/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/30/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAURIE PELUSO, REG 1 RDO | | | | +------------------------------------------------+JOHN PELLET, REG 4 RDO | |NRC NOTIFIED BY: COTE (FAX) |JOHN JACOBSON, REG 3 RDO | |HQ OPS OFFICER: CHAUNCEY GOULD |CHARLES HOSEY, REG 2 RDO | +------------------------------------------------+VERN HODGE, RVIB NRR | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PART 21 - POTENTIAL MANUFACTURING DEFECT IN COOPER-BESSEMER KSV EDGs - | | | | COOPER ENERGY SERVICES MADE A 10 CFR PART 21 NOTIFICATION FOR THEIR | | COOPER-BESSEMER KSV EMERGENCY DIESEL GENERATORS DUE TO A POTENTIAL | | MANUFACTURING DEFECT. THE POTENTIAL DEFECT CONCERNS THE THICKNESS OF THE | | PISTON CROWN IN THE VALVE CUTOUT AREA THAT PROVIDES CLEARANCE FOR THE | | INTAKE AND EXHAUST VALVES. THE NOMINAL DESIGN THICKNESS OF THIS AREA IS | | 0.438, BUT A FAILED PISTON HAD AN AREA THAT TAPERED DOWN TO A MINIMUM | | THICKNESS OF 0.040. | | | | FINITE ELEMENT ANALYSIS PERFORMED SUBSEQUENT TO THE FAILURE HAS INDICATED | | AN ACCEPTABLE MINIMUM THICKNESS IN THE VALVE CUTOUT AREA OF 0.100. THE | | ANALYSIS ALSO INDICATED THAT A 0.040 THICK PISTON SHOULD NOT FAIL IN NORMAL | | OPERATION, BUT THE FACTOR OF SAFETY IS BELOW NORMALLY ACCEPTED VALUES. | | EXAMINATION OF PISTONS IN COOPER ENERGY SERVICES STORES NOTED MANY IN THE | | 0.25 TO 0.31 RANGE AND ONE AS LOW AS 0.070. THE ROOT CAUSE OF THE | | DEFICIENT CONDITION WAS AN INCORRECT FOUNDRY PATTERN. | | | | THE FOLLOWING PLANTS ARE AFFECTED: PALO VERDE, BRAIDWOOD, BYRON, ZION, | | WATERFORD, SOUTH TEXAS, COOPER, NINE MILE POINT UNIT 2, AND SUSQUEHANNA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32417 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/30/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/30/97 | +------------------------------------------------+EVENT TIME: 15:00[CDT]| |NRC NOTIFIED BY: CROW |LAST UPDATE DATE: 05/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING THE 1997 REFUELING OUTAGE, BOTH TRAINS OF STANDBY GAS TREATMENT | | SYSTEM EXCEEDED TECHNICAL SPECIFICATION (TS) UPPER FLOW LIMITS. | | | | ON 04/21/97 AND 04/22/97, THE STANDBY GAS TREATMENT SYSTEM, TRAINS 'A' AND | | 'B' FLOW RATES WERE FOUND TO BE 2,028 AND 2,006 SCFM RESPECTIVELY. THE | | TECH SPEC ACCEPTANCE CRITERIA FOR SGT FLOW IS 1780 SCFM ñ 10% OR 1,602 TO | | 1,958 SCFM RESPECTIVELY. THEREFORE, IN THE AS-FOUND CONDITION, BOTH TRAINS | | EXCEEDED TS UPPER FLOW LIMITS. | | | | WHILE EVALUATION HAS YET TO IDENTIFY A SINGLE FACTOR OR COMBINATION OF | | FACTORS RESULTING IN THE OBSERVED HIGH FLOW RATE, IT HAS BEEN CONCLUDED | | THAT A COMMON CAUSE EXISTS. ACCORDINGLY, THIS CONDITION IS CONSIDERED TO | | BE REPORTABLE AS AN EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE | | FULFILLMENT OF THE SAFETY FUNCTION OF SYSTEMS THAT ARE NEEDED TO CONTROL | | THE RELEASE OF RADIOACTIVE MATERIAL. | | | | PRIOR TO RESTART FROM THIS REFUELING OUTAGE, FLOW DAMPERS WERE ADJUSTED TO | | RETURN FLOW RATES TO WITHIN THE TS LIMITS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 32418 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WINDHAM COUNTY MEMORIAL HOSPITAL |NOTIFICATION DATE: 05/30/97 | | CITY: WILLIMANTIC REGION: 1 |NOTIFICATION TIME: 15:46 [ET]| | COUNTY: STATE: CT |EVENT DATE: 05/30/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/30/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAURIE PELUSO RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: PETERSON | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HOSPITAL EMPLOYEE FALSIFIED DOSE CONSTANCY RECORD - | | | | THE WINDHAM COUNTY MEMORIAL HOSPITAL REPORTED THAT ONE OF THEIR EMPLOYEES | | WAS FALSIFYING A DOSE CONSTANCY RECORD. THE DOSE CALIBRATION FOR COBALT-57 | | WAS FALSIFIED. IT WAS NOT PROPERLY PERFORMED, YET THE INDIVIDUAL HAD | | RECORDED THAT IT WAS PERFORMED. NUMBERS WERE ERRONEOUSLY FILLED IN TO THE | | CONSTANCY RECORD BY THE EMPLOYEE. THE LICENSEE IS CONTINUING ITS | | INVESTIGATION OF THIS EMPLOYEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32419 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 05/31/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/31/97 | +------------------------------------------------+EVENT TIME: 03:03[CDT]| |NRC NOTIFIED BY: PETER KNARR |LAST UPDATE DATE: 05/31/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A SINGLE TRAIN FAILURE OF | | THE '1A' MAIN STEAM LINE ISOLATION HYDRAULIC ACTUATOR CIRCUIT | | | | AT 0303 CDT ON MAY 31, 1997, A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN | | WAS COMMENCED DUE TO A SINGLE TRAIN FAILURE OF THE '1A' MAIN STEAM LINE | | ISOLATION HYDRAULIC ACTUATOR CIRCUIT. THE FAILURE WAS IDENTIFIED AT 1114 | | CDT ON MAY 29, 1997, DURING ROUTINE SURVEILLANCE TESTING. THE REQUIRED | | ACTION PER TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION 3.3.2 | | IS TO RESTORE THE INOPERABLE CIRCUIT TO OPERABLE STATUS WITHIN 48 HOURS OR | | TO PLACE THE UNIT IN AT LEAST HOT STANDBY WITHIN 6 HOURS AND IN AT LEAST | | HOT SHUTDOWN WITHIN THE FOLLOWING 6 HOURS. THE UNIT SHUTDOWN WAS INITIATED | | AT 0303 CDT TO ENSURE THAT THE PLANT WILL BE IN HOT STANDBY BY 1714 CDT ON | | MAY 31, 1997. THE FAILURE WILL HAVE NO IMPACT ON THE ABILITY TO SHUT DOWN | | THE PLANT TO A HOT SHUTDOWN CONDITION. REPAIRS OF THE FAILED HYDRAULIC | | ACTUATOR CIRCUIT CONTINUE TO PROGRESS. | | | | THE FAILURE APPEARS TO BE A PROBLEM WITH AN ELECTRICALLY-OPERATED SOLENOID | | VALVE THAT ACTS WITH THE HYDRAULIC SYSTEM TO RECHARGE THE MAIN STEAM | | ISOLATION VALVE. THE LICENSEE HAS SUCCESSFULLY PERFORMED A PARTIAL STROKE | | TEST OF THE MAIN STEAM ISOLATION VALVE TO DEMONSTRATE FREEDOM OF MOVEMENT. | | HOWEVER, FOLLOWING THE PARTIAL STROKE, THE HYDRAULIC SYSTEM IS EXPECTED TO | | RESTORE (RECHARGE) THE VALVE TO FULL HYDRAULIC AND PNEUMATIC PRESSURE. THE | | PROBLEM IS ONLY ON THE ACTIVE TRAIN, AND THE STANDBY TRAIN REMAINS | | AVAILABLE. IN ADDITION, THE LICENSEE HAS DEMONSTRATED THAT IF THE SHUTTLE | | VALVE (WHICH RE-ALIGNS THE HYDRAULICS) FOR THE ACTIVE TRAIN IS REPOSITIONED | | MANUALLY, THE MAIN STEAM ISOLATION VALVE WILL RECHARGE ITSELF. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32420 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/31/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 07:36 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/31/97 | +------------------------------------------------+EVENT TIME: 07:03[EDT]| |NRC NOTIFIED BY: RON WARRINER |LAST UPDATE DATE: 05/31/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |RICHARD WESSMAN, NRR EO | | |STUART RUBIN, IRD AEOD | | |AL AUSTIN FEMA | | |CURTIS COWGILL REG1 | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARATION DUE TO THE DETECTION OF AN EARTHQUAKE ONSITE | | | | AT 0703 ON MAY 31, 1997, ONSITE EARTHQUAKE DETECTION EQUIPMENT ALARMED | | INDICATING THAT AN EARTHQUAKE WAS SENSED ONSITE. (THIS EQUIPMENT IS SET TO | | ALARM AT 0.01 G.) PLANT PROCEDURES REQUIRE THE LICENSEE TO DECLARE AN | | UNUSUAL EVENT IF AN EARTHQUAKE IS SENSED BY INDIVIDUALS OR BY PLANT | | DETECTION EQUIPMENT. ACCORDINGLY, AN UNUSUAL EVENT WAS DECLARED AT 0725. | | | | THE LICENSEE IS CURRENTLY IMPLEMENTING PROCEDURE OP-3127, NATURAL | | PHENOMENA, AND PLANT WALKDOWNS ARE CONTINUING. AT THE TIME OF THIS | | NOTIFICATION, THERE WERE NO OBVIOUS PROBLEMS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATES OF VERMONT, | | NEW HAMPSHIRE, AND MASSACHUSETTS. | | | | * * * 0915 MAY 31, 1997, UPDATE FROM JIM BROOKS RECEIVED BY TROCINE * * * | | | | THE LICENSEE PLANS TO ISSUE A PRESS RELEASE REGARDING THIS EVENT. | | | | PLANT WALKDOWNS HAVE BEEN COMPLETED, AND NO PROBLEMS WERE IDENTIFIED. THE | | EARTHQUAKE MONITOR INDICATED READINGS OF 0.124 G IN THE NORTH/SOUTH PLANE | | FOR A DURATION OF 0.0032 G-SECONDS. READINGS IN THE EAST/WEST PLANE AND | | VERTICAL DIRECTION WERE BOTH 0.001 G. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (PELUSO), REGION 1 (COWGILL), | | AEOD IRD (RUBIN), AND NRR EO (WESSMAN). REGION 1 (COWGILL) STATED THAT HE | | WOULD NOTIFY REGION 1 PUBLIC AFFAIRS OFFICE (SCRENCI). | | | | * * * 0952 MAY 31, 1997, UPDATE FROM JIM BROOKS RECEIVED BY TROCINE * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0935. THE LICENSEE DETERMINED | | THAT A SEISMIC EVENT DID NOT ACTUALLY OCCUR. PHYSICALLY, THERE COULD NOT | | HAVE BEEN A READING IN THE NORTH/SOUTH PLANE OF THAT MAGNITUDE (AND FOR | | SUCH A SHORT DURATION) WITHOUT HAVING LARGER INDICATIONS IN OTHER PLANES AS | | WELL. | | | | THE LICENSEE NOTIFIED THE STATES OF VERMONT, NEW HAMPSHIRE, AND | | MASSACHUSETTS AS WELL AS THE STATE OF VERMONT NUCLEAR ENGINEER (SHERMAN). | | THE LICENSEE ALSO PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (PELUSO), REGION 1 (COWGILL), AEOD IRD | | (RUBIN), NRR EO (WESSMAN), AND FEMA (SWEETSER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32421 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 05/31/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 09:29 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 05/31/97 | +------------------------------------------------+EVENT TIME: 06:21[EDT]| |NRC NOTIFIED BY: JERRY FREEMAN |LAST UPDATE DATE: 05/31/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT EMERGENCY DIESEL GENERATOR START DUE TO A PERSONNEL ERROR | | DURING THE PERFORMANCE OF SURVEILLANCE TESTING | | | | DURING THE PERFORMANCE OF SURVEILLANCE TESTING FOR THE #1 EMERGENCY DIESEL | | GENERATOR, A CONTROL ROOM OPERATOR MADE AN ERROR AND INADVERTENTLY STARTED | | THE #2 EMERGENCY DIESEL GENERATOR. THE #2 EMERGENCY DIESEL GENERATOR CAME | | UP TO IDLE SPEED AND DID NOT LOAD. IT HAS SINCE BEEN SECURED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32422 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/31/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:10 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/30/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/31/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JOHN JACOBSON RDO | | DOCKET: 0707001 |SUSAN SHANKMAN, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: HALICKS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THE CASCADE CELL TRIP FUNCTION HAD BEEN SHUT OFF | | DURING TROUBLESHOOTING WITHOUT MEETING TECHNICAL SPECIFICATION REQUIREMENTS | | (TSR). (24-HOUR REPORT) | | | | DURING A REVIEW OF TROUBLESHOOTING CONDUCTED IN THE C-533 SWITCHYARD, IT | | WAS DISCOVERED THAT DC POWER TO THE CELL TRIP FUNCTION FOR ONE HALF OF THE | | C-333 CELL AIR CIRCUIT BREAKERS (ACB) HAD BEEN REMOVED FOR A FEW SECONDS IN | | AN EFFORT TO LOCATE A 250-VOLT DC GROUND. THE CONTROL POWER WAS | | IMMEDIATELY RESTORED. POWER WAS THEN REMOVED FROM THE OTHER HALF OF THE | | C-333 ACBs. THE GROUND CLEARED, AND CONTROL POWER WAS IMMEDIATELY RESTORED. | | FURTHER TROUBLESHOOTING PIN-POINTED THE LOCATION OF THE GROUND. DC POWER | | FOR THE CELL TRIP FUNCTION WAS NOT REMOVED FOR MORE THAN A FEW SECONDS. | | HOWEVER, TSR LIMITING CONDITION FOR OPERATION (LCO) 2.4.4.12 REQUIRES THAT | | DC CONTROL POWER AND AIR PRESSURE FOR CELL TRIP OF STAGE MOTORS BE OPERABLE | | DURING CASCADE MODES 1 AND 2 WHEN STAGE MOTORS ARE ENERGIZED. | | | | THE REQUIRED LCO ACTIONS ARE 1) NOTIFY CASCADE COORDINATOR OF POTENTIAL | | NEED TO UTILIZE ALTERNATE MEANS FOR CELL SHUTDOWN AND 2) RESTORE VOLTAGE TO | | GREATER THAN 210 VOLTS IN 48 HOURS. DURING THE TROUBLESHOOTING, POWER WAS | | RESTORED IN LESS THAN 48 HOURS, BUT NO NOTIFICATION WAS MADE TO THE CASCADE | | OPERATOR AS REQUIRED BY TSRs. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32423 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 05/31/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 13:04 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/31/97 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 05/31/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS IDENTIFIED A CONDITION WHICH RESULTED IN ONE OF THE | | PRINCIPAL SAFETY BARRIERS BEING DEGRADED. | | | | DURING THE FIFTH REFUELING OUTAGE, THE LICENSEE IDENTIFIED FOUR FUEL | | ASSEMBLIES THAT HAVE LEAKING FUEL RODS. SPECIFICALLY, THREE FUEL | | ASSEMBLIES CONTAIN ONE LEAKING FUEL ROD EACH, AND THE FOURTH ASSEMBLY | | CONTAINS TWO LEAKING FUEL RODS. PREVIOUS ESTIMATES OF THE NUMBER OF | | LEAKING FUEL RODS WERE BETWEEN TWO AND TEN, BUT FIVE WERE ACTUALLY FOUND. | | | | DURING THE REMOVAL OF TWO OF THE FUEL RODS TO FACILITATE RECONSTITUTION | | ACTIVITIES, THE RODS BROKE AT APPROXIMATELY MID-LENGTH. ONE ROD EXHIBITED | | A CLEAN CIRCUMFERENTIAL BREAK AND THE OTHER A JAGGED BREAK. NONE OF THE | | FUEL PELLETS ESCAPED FROM THE FUEL RODS AS A RESULT OF THE BREAKS. | | | | THE SUBJECT FUEL ASSEMBLIES ARE WESTINGHOUSE VANTAGE "5H" UTILIZING "ZIRLO" | | CLADDING. THESE FUEL ASSEMBLIES WERE ONCE BURNED AND WERE IN HIGH POWER | | LOCATIONS DURING THE PREVIOUS OPERATING CYCLE. ALL FAILED RODS ARE | | INTEGRAL FUEL BURNABLE ABSORBER RODS. THE LICENSEE IS STILL INVESTIGATING | | THE CAUSE FOR THE FUEL ROD CLADDING FAILURE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32424 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 06/01/97 | |UNIT: [ ] [ ] [3] STATE: AZ |NOTIFICATION TIME: 05:46 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 05/31/97 | +------------------------------------------------+EVENT TIME: 23:12[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 06/01/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP POSSIBLY DUE TO TROUBLESHOOTING OF THE REACTOR TRIP | | CIRCUIT BREAKERS | | | | AT APPROXIMATELY 2312 MST ON MAY 31, 1997, AN UNCOMPLICATED AUTOMATIC | | REACTOR TRIP OCCURRED. PRIOR TO THE TRIP, INSTRUMENTATION AND CONTROL | | TECHNICIANS WERE PERFORMING TROUBLESHOOTING TO DETERMINE THE ROOT CAUSE OF | | TWO (OF FOUR) REACTOR TRIP CIRCUIT BREAKERS SPURIOUSLY OPENING ON MAY 19, | | 1997, AND THEN AGAIN ON MAY 31, 1997. THE CAUSE OF THE REACTOR TRIP IS | | UNDER INVESTIGATION AND MAY BE ATTRIBUTED TO THE TROUBLESHOOTING OF THE | | REACTOR TRIP CIRCUIT BREAKERS. (THE FIRST OUT ANNUNCIATOR WAS DEPARTURE | | FROM NUCLEATE BOILING RATIO LOW ON THE CORE PROTECTION CALCULATORS.) | | | | ALL CONTROL RODS FULLY INSERTED FOLLOWING THE REACTOR TRIP. ALL SAFETY | | SYSTEMS FUNCTIONED AS REQUIRED. THERE WERE NO ENGINEERED SAFETY FEATURES | | ACTUATIONS, AND NONE WERE REQUIRED. STEAM BYPASS WAS DIRECTED TO THE | | CONDENSER. NONE OF THE PRIMARY RELIEF VALVES OR SAFETY VALVES LIFTED. | | THERE WERE NO BUS TRANSFER PROBLEMS, AND THE ELECTRICAL GRID WAS STABLE. | | | | THE EVENT DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER | | OR RESULT IN ANY RELEASES OF RADIOACTIVE MATERIALS. IN ADDITION, THE EVENT | | DID NOT ADVERSELY AFFECT THE SAFE OPERATION OF THE PLANT OR THE HEALTH AND | | SAFETY OF THE PUBLIC. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3 AT NORMAL OPERATING TEMPERATURE AND | | NORMAL OPERATING PRESSURE. SECONDARY STEAM IS BEING BYPASSED TO THE | | CONDENSER, AND MAIN FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS. | | OPERATORS ARE ALSO UTILIZING NORMAL CHARGING AND MAKEUP, THE PRESSURIZER | | HEATERS AND SPRAYS, AND THE REACTOR COOLANT PUMPS FOR PRIMARY SYSTEM | | INVENTORY, PRESSURE, AND TRANSPORT CONTROL. IN ADDITION, ALL CONTAINMENT | | PARAMETERS ARE CURRENTLY NORMAL. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32425 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/01/97 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 07:20 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/01/97 | +------------------------------------------------+EVENT TIME: 06:17[CDT]| |NRC NOTIFIED BY: WESS CUMBEE |LAST UPDATE DATE: 06/01/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY RDO | |NINF INFORMATION ONLY | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION REGARDING ENTRY INTO TECHNICAL SPECIFICATION 3.0.3 IN | | ORDER TO CHANGE FROM MODE 4 TO MODE 3 | | | | THE LICENSEE IS CURRENTLY PREPARING TO CHANGE THE OPERATING MODE OF UNIT 1 | | FROM MODE 4 TO MODE 3. IN DOING SO, THE LICENSEE IS REQUIRED TO PROVIDE | | POWER TO SOME EMERGENCY CORE COOLING (ECCS) VALVES IN ORDER TO HAVE THEM IN | | THE PROPER CONFIGURATION FOR MODE 3. HOWEVER, THIS IS NOT PERMITTED BY THE | | LICENSEE'S TECHNICAL SPECIFICATIONS WHICH REQUIRE THE BREAKERS FOR CERTAIN | | VALVE OPERATORS TO BE LOCKED OPEN WHILE THE UNIT IS IN MODE 4. | | | | THE BREAKERS FOR THE VALVE OPERATORS FOR RESIDUAL HEAT REMOVAL DISCHARGE TO | | CHARGING PUMP SUCTION VALVES 8706A AND 8706B WERE CLOSED AT 0617 CDT. THIS | | IS THE REQUIRED POSITION FOR THESE VALVES WHEN THE UNIT IS IN MODE 3. AS A | | RESULT, THE LICENSEE IS CURRENTLY EXCEEDING THE ACTION STATEMENTS OF | | TECHNICAL SPECIFICATION 3.5.3 FOR MODE 4, ECCS SYSTEMS LESS THAN 350øF, IN | | ORDER TO ENTER MODE 3; AND THE UNIT WILL BE IN TECHNICAL SPECIFICATION | | 3.0.3 UNTIL MODE 3 IS ENTERED. THE LIMITING CONDITION FOR OPERATION WILL | | BE CLEARED WHEN THE UNIT ENTERS MODE 3. THIS IS EXPECTED TO OCCUR SHORTLY. | | (THIS SITUATION OCCURS EVERY TIME THE UNIT IS RESTARTED.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * 0927 EDT JUNE 1, 1997, UPDATE FROM ISLER RECEIVED BY TROCINE * * * | | | | ENTRY INTO MODE 3 WAS DELAYED. AS A RESULT, THE AFFECTED BREAKERS WERE | | LOCKED OPEN AGAIN AT 0709 CDT. (TECHNICAL SPECIFICATION 3.0.3 HAS A | | ONE-HOUR ACTION STATEMENT.) THE BREAKERS WERE RECLOSED AT 0812 CDT, AND | | THE LICENSEE PLANS TO PLACE THE UNIT IN MODE 3 WITHIN ONE HOUR. AT THIS | | TIME, REACTOR COOLANT SYSTEM TEMPERATURE IS APPROXIMATELY 345øF. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R2DO (HOSEY). | | | | * * * 1007 EDT JUNE 1, 1997, UPDATE FROM ISLER RECEIVED BY TROCINE * * * | | | | UNIT 1 ENTERED MODE 3 AT 0835 CDT. TECHNICAL SPECIFICATION 3.0.3 WAS | | EXITED AT THAT TIME. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R2DO (HOSEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32426 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 06/01/97 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:58 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 06/01/97 | +------------------------------------------------+EVENT TIME: 13:01[EDT]| |NRC NOTIFIED BY: NAVIN |LAST UPDATE DATE: 06/01/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM WAS INOPERABLE DUE TO | | LOSS OF THE AUTOMATIC START CAPABILITY OF THE AUXILIARY OIL PUMP. | | | | WHILE LIFTING A LEAD IN A CABLE SPREADING ROOM PANEL IN PREPARATION FOR | | INSTALLING A JUMPER, A PORTION OF THE UNIT 2 HPCI LOGIC POWER WAS | | DEENERGIZED. THE LEAD WAS RELANDED WITHIN TWO MINUTES. UNEXPECTED HPCI | | ALARMS WERE RECEIVED, INCLUDING CONDENSATE STORAGE TANK LOW-LOW LEVEL AND | | HPCI LOGIC BUS POWER FAILURE. THESE ALARMS CLEARED WHEN THE LEAD WAS | | RELANDED. FURTHER REVIEW OF THE IMPACT OF HAVING THE LEAD LIFTED | | DETERMINED THAT THE HPCI SYSTEM WAS INOPERABLE DUE TO THE LOSS OF THE | | AUTOMATIC START CAPABILITY OF THE AUXILIARY OIL PUMP. THE JUMPER THAT WAS | | BEING INSTALLED WAS TO INSERT A ONE-HALF ISOLATION DUE TO AN INOPERABLE | | HPCI STEAM LINE TEMPERATURE SWITCH. UNIT 2 WAS IN A LIMITING CONDITION FOR | | OPERATION ACTION STATEMENT ONLY FOR TWO MINUTES WHEN THE HPCI SYSTEM WAS | | INOPERABLE. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+