U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/18/97 - 02/19/97 ** EVENT NUMBERS ** 31801 31802 31803 31804 31805 31806 31807 31808 31809 31810 31811 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31801 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 02/18/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 01:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/17/97 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: TRIPP FRAHM |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A "C3" REPORTABLE CONDITION FOR THE "2D" STEAM GENERATOR WAS FOUND BY EDDY | | CURRENT TESTING. GREATER THAN 1% OF THE TUBES INDICATE DEFECTS. SEE | | PREVIOUS EVENTS #31794, #31797, AND #31805 FOR ADDITIONAL DETAILS. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31802 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/18/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 02:06 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 02/17/97 | +------------------------------------------------+EVENT TIME: 23:27[EST]| |NRC NOTIFIED BY: STEVE MERRILL |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY FILTRATION FAN DAMPER FAILED TO OPEN UPON RECEIPT OF | | AN ACTUATION SIGNAL. | | | | THE "A" CHANNEL CONTROL ROOM AIR INTAKE RADIATION MONITOR GENERATED A | | SPURIOUS HIGH RADIATION SIGNAL. THE DAMPER FOR THE CONTROL ROOM EMERGENCY | | FILTRATION FAN "HVE-13A" SHOULD HAVE OPENED UPON RECEIPT OF THE SIGNAL, BUT | | DIDN'T. THE CAUSE OF THE DAMPER'S FAILURE TO OPEN IS NOT YET KNOWN. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31803 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/18/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 11:25 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 11:01[EST]| |NRC NOTIFIED BY: DON GERBER |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SCOTT BARBER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TIE BOLTS IN THE RECIRCULATION SPRAY SYSTEM BELLOWS EXPANSION JOINTS WILL | | NOT WITHSTAND DESIGN STRESS LOADS. | | | | THE RECIRCULATION SPRAY SYSTEM HAS TWO BACK-TO-BACK BELLOWS EXPANSION | | JOINTS BETWEEN THE PUMP DISCHARGE AND THE HEAT EXCHANGER. THESE EXPANSION | | JOINTS ARE HELD TOGETHER WITH LONG TIE BOLTS. IN OPERATION, THE BOLTS ARE | | SUBJECTED TO BOTH TENSILE AND BENDING LOADS. THE DESIGN ANALYSIS DID NOT | | CONSIDER THE BENDING LOADS IN CALCULATING THE IMPOSED STRESS. WHEN BOTH | | LOADS ARE CONSIDERED, THE STRESS LIMIT FOR THE TIE BOLTS MIGHT BE EXCEEDED. | | | | THIS ISSUE WILL BE RESOLVED PRIOR TO PLANT RESTART. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL GOVERNMENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31804 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/18/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:26 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 14:12[EST]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THE INITIAL ANALYSIS FOR THE DESIGN OF THE SPENT | | FUEL POOL STORAGE RACK DID NOT USE THE CORRECT DATA. | | | | THE LICENSEE PERFORMED AN ENGINEERING ANALYSIS IN RESPONSE TO AN NRC LETTER | | CONCERNING THE IMPACT ANALYSIS FOR THE DESIGN OF THE SPENT FUEL POOL | | STORAGE RACK. DURING THIS ANALYSIS, IT WAS DISCOVERED THAT THE WEIGHT OF | | THE FUEL GRAPPLE MAST SECTIONS (APPROXIMATELY 830 POUNDS) HAD NOT BEEN | | INCLUDED IN THE ORIGINAL CALCULATIONS. THE PRELIMINARY REVIEW SHOWS THAT | | THERE COULD BE SOME DAMAGE TO THE RACK DURING A FUEL DROP SCENARIO. THE | | LICENSEE WILL CONTINUE THEIR EVALUATION. THE RESIDENT INSPECTOR WAS | | NOTIFIED ALONG WITH THE STATE AND THE TOWN OF WATERFORD. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31805 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 02/18/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 14:54 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 12:16[CST]| |NRC NOTIFIED BY: VALAGURA |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT STEAM GENERATOR "2C" HAS MORE THAN 1% OF | | THE TUBES DEFECTIVE. | | | | ON 02/18/97, THE INSPECTION RESULTS OF THE "2C" STEAM GENERATOR DETERMINED | | THAT MORE THAN 1% OF THE TUBES ARE DEFECTIVE. THE GENERAL AREA OF | | DEGRADATION IS IN THE HOT LEG TUBE SUPPORT PLATE CREVICES. THE CAUSE OF | | THE DAMAGE IS THOUGHT TO BE OUTSIDE DIAMETER STRESS CORROSION CRACKING. | | INSPECTIONS CONSISTED OF 100% BOBBIN COIL FULL LENGTH EDDY CURRENT | | EXAMINATION. ALL DISTORTED SUPPORT PLATE INDICATIONS ARE BEING EXAMINED BY | | MOTORIZED PANCAKE PROBE. COMPLETION OF THE EXAMINATION SCOPE IS IN | | PROGRESS. THE RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | NOTE: SEE RELATED EVENTS #31794, #31797, AND #31805. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31806 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NORTH CAROLINA DIV OF RAD CONTROL |NOTIFICATION DATE: 02/18/97 | | CITY: RALEIGH REGION: 2 |NOTIFICATION TIME: 15:07 [ET]| | COUNTY: STATE: NC |EVENT DATE: 02/18/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 14:00[EST]| | DOCKET: |LAST UPDATE DATE: 02/18/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KERRY LANDIS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SPEIGHT | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NORTH CAROLINA DIVISION OF RADIATION CONTROL REPORTED THAT THEY HAD | | BEEN NOTIFIED BY THE CHARLOTTE PIPE AND FOUNDRY COMPANY THAT A RAIL CAR | | SHIPMENT OF SCRAP METAL SET OFF THE RADIATION ALARM WHEN IT ENTERED THE | | FACILITY. THE COMPANY BELIEVES THAT THERE ARE THREE PIECES (2 TO 3 POUNDS) | | THAT MAY BE CONTAMINATED. THE STATE WILL BE SENDING SOMEONE TO SURVEY THE | | RAIL CAR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31807 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 02/18/97 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 15:41 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 11:45[CST]| |NRC NOTIFIED BY: ODOM |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A CONDITION THAT COULD HAVE PREVENTED FULFILLMENT | | OF THE SAFETY FUNCTION OF SYSTEMS REQUIRED TO SHUTDOWN THE REACTOR AND | | MAINTAIN IT IN A SHUTDOWN CONDITION. | | | | THIS CONDITION WOULD OCCUR WHEN THE BREAKERS FOR THE 4KV SWITCHGEAR WERE | | NOT IN THE "CONNECTED" POSITION WHICH IS THE ONLY SEISMICALLY QUALIFIED | | POSITION. THE EFFECTS OF BREAKER POSITIONS OTHER THAN RACKED TO THE | | "CONNECTED" POSITION WERE NOT CONSIDERED FOR SEISMIC QUALIFICATIONS DURING | | PREVIOUS DESIGN REVIEWS. THE POTENTIAL EXISTS FOR AN IMPACT FROM | | UNRESTRAINED BREAKERS IN THE "DISCONNECTED" POSITION TO CAUSE RELAY CHATTER | | IN ADJACENT BREAKER CUBICLES THAT COULD HAVE COMPROMISED SAFETY RELATED | | EQUIPMENT. ADMINISTRATIVE CONTROLS HAVE BEEN PUT IN PLACE TO PREVENT THIS | | CONDITION FROM OCCURRING. ALL APPLICABLE 4KV BREAKERS NOT IN THE | | "CONNECTED" POSITION HAVE BEEN REMOVED FROM THE SWITCHGEAR TO ALLEVIATE | | THIS SEISMIC CONCERN. | | | | THE RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31808 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 02/18/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 16:38 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: BACALZO |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 90 POWER OPERATION | 73 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT IS BEING SHUTDOWN AT THE RATE OF 30% PER HOUR DUE TO LCO ACTION | | STATEMENTS. | | | | THE PLANT HAS BEEN IN AN LCO ACTION STATEMENT FOR ONE OF SIX SERVICE WATER | | PUMPS ("P32A") BEING OUT OF SERVICE. THIS ACTION STATEMENT WILL BE | | EXCEEDED AT 1558 HOURS FOR THE SERVICE WATER PUMP BEING OUT OF SERVICE. THE | | LCO PROVISIONS FOR HAVING ONE OF TWO COMPONENT COOLING WATER PUMPS | | ("1P11A") OUT OF SERVICE WILL BE EXCEEDED AT 1800 HOURS. THE UNIT SHUTDOWN | | WAS STARTED AT 1500 HOURS AT THE RATE OF 30% PER HOUR IN ANTICIPATION OF | | THE TS REQUIRED SHUTDOWN FOR INOPERABLE SERVICE WATER AND COMPONENT COOLING | | WATER PUMPS. THE RESIDENT HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31809 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 02/18/97 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 18:29 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 14:49[EST]| |NRC NOTIFIED BY: SMITH |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT WAS MANUALLY TRIPPED FROM 90% POWER DUE TO A PARTIAL LOSS OF | | ELECTRICAL POWER TO THE ELECTRO-HYDRAULIC CONTROL (EHC) PANEL. | | | | THE LOSS OF ELECTRICAL POWER TO THE MAIN TURBINE EHC PANEL RESULTED IN THE | | GOVERNOR VALVES MOVING IN THE CLOSED DIRECTION, SO THE REACTOR WAS MANUALLY | | TRIPPED. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE LOSS OF POWER. | | ALL RODS INSERTED INTO THE CORE AS INDICATED BY THE ROD BOTTOM LIGHT | | INDICATION. HOWEVER, THERE WERE THREE INDIVIDUAL ROD POSITION INDICATORS | | (IRPI) (J-13, F-12, & F-6) THAT INITIALLY INDICATED THE RODS WERE 10 TO 15 | | STEPS OUT. BUT IRPI J-13 AND F-12 DRIFTED TO ZERO STEPS APPROXIMATELY 5 | | MINUTES AFTER THE TRIP. THE SHUTDOWN MARGIN WAS DETERMINED TO BE | | SATISFACTORY. THE THIRD IRPI, FOR ROD F-6 DRIFTED IN AT 1624 EST. | | AUXILIARY FEEDWATER AUTOMATICALLY INITIATED AS DESIGNED ON LOW-LOW STEAM | | GENERATOR LEVEL FOLLOWING THE TRIP. PRIMARY RCS TEMPERATURE DECREASED TO | | APPROXIMATELY 547øF FOLLOWING THE TRIP. NO PRIMARY OR SECONDARY SAFETY | | RELIEF OR PORVs ACTUATED DURING THIS EVENT AND NO INJECTION OCCURRED. DECAY | | HEAT IS BEING REMOVED TO THE MAIN CONDENSER VIA THE STEAM DUMP VALVES. THE | | RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31810 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:19 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/18/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/18/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: LAMB | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING A REVIEW OF THE CURRENT NUCLEAR CRITICALITY SAFETY APPROVAL FOR | | BUILDING C-400, UF-6 CYLINDER WASHING OPERATIONS, IT WAS DISCOVERED THAT | | THE DOUBLE CONTINGENCY CONTROLS APPLICABLE TO THESE OPERATIONS WERE NOT | | FOLLOWED PROPERLY. FAILURE TO FOLLOW THE CONTROLS RESULTED IN A LOSS OF | | DOUBLE CONTINGENCY. NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) #3973-04 | | REQUIRES INDEPENDENT VERIFICATION OF 235-U ENRICHMENT ASSAY IN UF-6 | | CYLINDERS BASED ON NUCLEAR MATERIAL CONTROL & ACCOUNTABILITY (NMC&A) | | RECORDS GOING BACK TO THE CYLINDER'S LAST HYDROSTATIC TEST DATE. | | | | SAFETY SIGNIFICANCE OF THE EVENT IS THE LOSS OF ALL DOUBLE CONTINGENCY | | CONTROLS APPLICABLE TO A FISSILE MATERIAL OPERATION. | | | | UF-6 CYLINDERS ARE WASHED WITH HYDROGEN BEARING SOLUTION (NO MODERATION | | CONTROL); THEREFORE, IF URANIUM MATERIAL IS PRESENT WITH ò1 WT% ASSAY | | ENRICHMENT OF U-235, A CRITICALITY COULD OCCUR. | | | | AN ASSAY WITH INDEPENDENT VERIFICATION IS THE CONTROLLING PARAMETER. | | | | THERE WAS LESS THAN 50 POUNDS URANIUM HEEL WEIGHT PER CYLINDER AND THERE | | WERE 22 CYLINDERS AFFECTED WITH ó1.0 WT% U-235 AS A PART OF UF6 (MASS NOT | | CRITICALITY CONTROLLED). | | | | A U-235 ENRICHMENT ASSAY IS DETERMINED ON CYLINDER MATERIAL WHEN AN | | INDEPENDENT VERIFICATION OF THE CYLINDER MATERIAL ENRICHMENT IS | | ACCOMPLISHED. THE REQUIRED INDEPENDENT VERIFICATION PROVIDES DOUBLE | | CONTINGENCY CONTROLS RELIED ON FOR ASSAY DETERMINATION. THERE IS CURRENTLY | | NO ASSURANCE THAT THE ASSAY RECORDS CONSULTED BY OPERATIONS PERSONNEL | | CORRECTLY REFLECT THE ASSAY HISTORY AS REQUIRED BY THE NCSA. THE NCSA | | REQUIRES THAT EACH CYLINDER TO BE WASHED HAS NOT BEEN USED FOR A U-235 | | ENRICHMENT OF ò1.0 WT% BASED ON NMC&A RECORDS (BACK TO THE CYLINDER'S LAST | | HYDROSTATIC TEST DATE) AND A CYLINDER GAS OVER SOLID SAMPLE. | | | | CORRECTIVE ACTIONS WERE TO STOP ALL CYLINDER WASH OPERATIONS UNTIL | | APPROPRIATE ACTIONS ARE IMPLEMENTED. PERSONNEL WERE EVACUATED FROM THE | | AFFECTED AREA AND THE AREA WAS CONTROLLED. AN INVESTIGATION IS UNDERWAY. | | THE NRC AND DOE RESIDENT INSPECTORS WERE NOTIFIED ALONG WITH DOE OAK RIDGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31811 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 02/18/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 22:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 19:30[CST]| |NRC NOTIFIED BY: MORRIS |LAST UPDATE DATE: 02/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT THERE WAS A METAL GALLERY FOR AN EQUIPMENT | | HATCH THAT HAD NOT BEEN ATTACHED TO THE CONCRETE FLOOR OR BUILDING | | STRUCTURE. | | | | DURING A CONTAINMENT WALKDOWN, IT WAS DISCOVERED THAT A METAL GALLERY FOR | | THE 426 FOOT ELEVATION EQUIPMENT HATCH INSIDE CONTAINMENT WAS NOT ATTACHED | | TO THE CONCRETE FLOOR OR BUILDING STRUCTURE STEEL AT THE LEG LOCATIONS. THE | | PLANT MECHANICAL DRAWINGS SHOW THAT THE LEGS SHOULD BE HELD DOWN WITH | | CONCRETE EXPANSION ANCHORS OR BOLTED TO THE STRUCTURAL STEEL UNDER THE | | GRATING. THE LICENSEE CONTINUING THEIR EVALUATION TO DETERMINE HOW THIS | | CONFIGURATION OCCURRED. THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+