U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/20/97 - 02/21/97 ** EVENT NUMBERS ** 31792 31806 31817 31819 31820 31821 31822 31823 31824 31825 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31792 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 02/15/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 01:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/15/97 | +------------------------------------------------+EVENT TIME: 00:30[EST]| |NRC NOTIFIED BY: DUSTY MILLER |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AHIN 50.72(b)(1)(vi) OTHER HIND TO SAFE OP | | |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 +------------------------------------------------------------------------------+ | CONTAMINATED WATER FROM A LEAKING FILTER HOUSING WOULD HAMPER OPERATIONS IN | | THE AREA SURROUNDING THE LEAK. | | | | THE #1A REACTOR COOLANT LETDOWN FILTER SUDDENLY DEVELOPED A LEAK OF | | APPROXIMATELY 16 GALLONS PER MINUTE THROUGH THE FILTER HOUSING O-RING. | | SLIGHTLY RADIOACTIVE LEAK WATER EXTENDED TO THE 733-FOOT ELEVATION FLOOR. | | THIS WOULD HAMPER OPERATIONS IN THIS AREA DUE TO THE REQUIREMENT FOR | | ANTI-CONTAMINATION CLOTHING. THE LEAK HAS BEEN ISOLATED. REPLACEMENT OF | | THE O-RING IS UNDER WAY. THE UNIT IS ENTERING A REFUELING OUTAGE. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1526 FEBRUARY 20, 1997, FROM IDDINGS RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. SUBSEQUENT | | INVESTIGATIONS AND DISCUSSIONS BETWEEN OPERATIONS AND SAFETY ASSURANCE | | PERSONNEL DETERMINED THAT THE LEAK DID NOT POSE AN ACTUAL THREAT TO THE | | SAFETY OF THE NUCLEAR POWER PLANT BECAUSE MULTIPLE OPTIONS TO CONTROL | | PRESSURIZER PRESSURE (AND THEREBY PREVENT WATER-SOLID CONDITIONS) WERE | | AVAILABLE TO THE OPERATORS. ADDITIONALLY, IT WAS DETERMINED THAT THE | | DONNING OF ANTI-CONTAMINATION CLOTHING, HAD IT BECOME NECESSARY, WOULD HAVE | | HAD MINIMAL IMPACT ON STATION PERSONNEL AND WOULD NOT HAVE SIGNIFICANTLY | | HAMPERED THE PERFORMANCE OF DUTIES NECESSARY FOR THE SAFE OPERATION OF THE | | PLANT. THE LICENSEE DETERMINED THAT REPORTING THIS EVENT WAS REASONABLE AND | | CONSERVATIVE. HOWEVER, AFTER FURTHER REVIEW, THE LICENSEE BELIEVES THAT | | THIS NOTIFICATION WAS NOT REQUIRED. THE LICENSEE NOTIFIED THE NRC RESIDENT | | INSPECTOR. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 02/20/97 | | +-----------------------------+ | |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. | | | | * * * UPDATE @0940 EST ON 02/20/97, FROM SPEIGHT TAKEN BY MACKINNON * * * | | | | THE STATE OF NORTH CAROLINA HAD A STATE REPRESENTATIVE FROM THE CATAWBA | | COUNTY EMERGENCY MANAGEMENT AGENCY GO TO THE SITE ON 02/19/97, TO PERFORM | | AN INSPECTION AND RADIATION SURVEY OF THE MATERIAL. THE MATERIAL APPEARED | | TO BE MADE OF A CERAMIC REFRACTORY MATERIAL (MATERIAL USED INSIDE OF | | FURNACES OR FOUNDRIES). THERE WAS ABOUT 15 POUNDS OF THIS MATERIAL IN THE | | BOTTOM OF THE RAIL CAR. THE RADIATION READING OF THE MATERIAL ON CONTACT | | WAS 0.1 MILLIREM/HOUR, AND THE RADIATION READING OF THE MATERIAL AT ONE | | FOOT WAS 0.08 MILLIREM/HOUR. | | | | THE MATERIAL WILL BE SHIPPED BACK FROM THE SCRAP METAL YARD IN CHARLOTTE TO | | CSX TRANSPORTATION WHICH IS ALSO LOCATED IN CHARLOTTE. CSX WILL DISPOSE OF | | THE MATERIAL. | | | | THE STATE OF NORTH CAROLINA DIVISION OF RADIATION CONTROL NOTIFIED NRC | | REGION II OF THIS EVENT UPDATE. THE R2DO (LANDIS) WAS NOTIFIED BY THE NRC | | OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31817 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 02/19/97 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 23:28 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/19/97 | +------------------------------------------------+EVENT TIME: 22:40[EST]| |NRC NOTIFIED BY: GOODHOPE |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 55 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM 55% POWER DUE TO LOSS OF REACTOR COOLANT SYSTEM | | (RCS) PRESSURE | | | | THE UNIT ENTERED A 4-HOUR LIMITING CONDITION FOR OPERATION TO REDUCE | | REACTOR POWER TO LESS THAN 5% IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | 3.12.F. POWER WAS BEING REDUCED BECAUSE REACTOR COOLANT PRESSURE WAS BELOW | | 2205 PSIG. AT 2300 HOURS, THE REACTOR WAS MANUALLY TRIPPED DUE TO | | DECREASING RCS PRESSURE. ALL RODS FULLY INSERTED, NO EMERGENCY CORE COOLING | | SYSTEM ACTUATIONS OCCURRED, AND NO SAFETY/RELIEF VALVES OR PORVs LIFTED. | | AUXILIARY FEEDWATER INITIATED DUE TO LOW-LOW STEAM GENERATOR LEVEL. THE | | LOWEST OBSERVED RCS PRESSURE WAS 1790 PSIG, AND IT HAS NOW RECOVERED TO | | 2065 PSIG. THE CAUSE OF THE LOSS OF RCS PRESSURE WAS THE FAILURE OF THE | | PROPORTIONAL HEATER BANK (400 KW OUTPUT). WHEN THAT BANK FAILED, THE BACKUP | | HEATER BANK (750 KW OUTPUT) COULD NOT MAINTAIN RCS PRESSURE. AN | | INVESTIGATION IS BEING PERFORMED TO DETERMINE THE CAUSE OF THE FAILURE. THE | | HEAT SINK IS VIA THE MAIN CONDENSER. THE 'A' REACTOR COOLANT PUMP TRIPPED | | DURING SWAPOVER TO THE RESERVE STATION SERVICE. THE LICENSEE IS | | INVESTIGATING THE CAUSE. THE NRC RESIDENT INSPECTOR WAS NOTIFIED. | | | | * * * UPDATE @ 0142 EST ON 02/20/97, FROM HELM TAKEN BY MACKINNON * * * | | | | THE LICENSEE STATED THAT THE REACTOR TRIP OCCURRED AT 2259, NOT 2300 AS | | ORIGINALLY REPORTED. AN INVESTIGATION IS STILL IN PROGRESS TO DETERMINE THE | | CAUSE OF THE PRESSURIZER HEATER FAILURE. INITIAL REACTOR POWER AT THE START | | OF THE EVENT WAS 86%, AND RCS PRESSURE WAS AT ITS NORMAL OPERATING PRESSURE | | OF 2,235 PSIG. THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY | | THE LICENSEE. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31819 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 02/20/97 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/19/97 | +------------------------------------------------+EVENT TIME: 22:59[EST]| |NRC NOTIFIED BY: JAMES HELM |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANDIS 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 HOT SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING THE ELECTRICAL SWAPOVER IN EVENT # 31817, MAIN FEEDWATER PUMP "A", | | THE ONLY OPERATING MAIN FEEDWATER PUMP, TRIPPED, INITIATING BOTH MOTOR | | DRIVEN AUXILIARY FEEDWATER PUMPS ON A LOSS OF ALL FEEDWATER SIGNAL. | | | | DURING THE ELECTRICAL SWAPOVER FROM THE MAIN STATION TRANSFORMER TO THE | | RESERVE STATION SERVICE TRANSFORMERS (DUE TO SURRY UNIT 1 BEING MANUALLY | | TRIPPED), MAIN FEEDWATER PUMP "A" TRIPPED AND INITIATED THE MOTOR DRIVEN | | AUXILIARY FEEDWATER PUMPS. THE REACTOR OPERATORS MAINTAINED REACTOR COOLANT | | TEMPERATURE AND MAINTAINED PROPER STEAM GENERATOR WATER LEVELS. THE TURBINE | | DRIVEN AUXILIARY FEEDWATER PUMP IS TAGGED OUT OF SERVICE FOR INVESTIGATION | | WHY ITS TRIP THROTTLE VALVE TRIPPED CLOSED (SEE EVENT # 31809 UPDATE). | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31820 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 02/20/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 05:33 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/20/97 | +------------------------------------------------+EVENT TIME: 03:47[EST]| |NRC NOTIFIED BY: ROLAND |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 94 POWER OPERATION | 94 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | "A" REACTOR PROTECTION SYSTEM (RPS) BUS NORMAL POWER SUPPLY FAILED CAUSING | | SEVERAL ESF ACTUATIONS. | | | | THE FOLLOWING EVENT OCCURRED DUE TO THE "A" RPS NORMAL POWER SUPPLY | | FAILURE: | | | | 1. RECEIVED A DIVISION 1 HALF SCRAM | | 2. RECEIVED A QUARTER MAIN STEAM LINE ISOLATION VALVE ISOLATION | | 3. ISOLATION OF THE REACTOR WATER CLEANUP SYSTEM | | 4. ISOLATION OF DIVISION 1 SECONDARY CONTAINMENT ZONES II AND III | | 5. INITIATION OF THE "A" TRAIN OF THE STANDBY GAS TREATMENT SYSTEM | | 6. INITIATION OF THE "A" TRAIN OF THE CONTROL ROOM EMERGENCY OUTSIDE AIR | | SUPPLY SYSTEM | | 7. ISOLATION OF BOTH DIVISIONS OF THE CONTAINMENT RADIATION MONITORING | | SYSTEM. | | | | THE RPS BUS WAS PLACED ON ITS ALTERNATE POWER SUPPLY. AN EVALUATION OF | | PLANT RESPONSE TO THE LOSS OF POWER WAS PERFORMED. ALL EQUIPMENT ACTUATED | | AS EXPECTED FOR THIS OCCURRENCE. THE HALF SCRAM AND QUARTER ISOLATION | | SIGNALS WERE RESET. ALL OTHER EQUIPMENT INITIATIONS AND ISOLATIONS WERE | | SECURED AND RESET IN ACCORDANCE WITH PLANT PROCEDURES. | | | | THE "A" RPS NORMAL POWER SUPPLY MOTOR GENERATOR SET WAS DE-ENERGIZED AND | | REMOVED FROM SERVICE FOR INVESTIGATION AND REPAIR. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31821 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WASHINGTON HOSPITAL CENTER |NOTIFICATION DATE: 02/20/97 | | CITY: WASHINGTON D.C. REGION: 1 |NOTIFICATION TIME: 11:07 [ET]| | COUNTY: STATE: DC |EVENT DATE: 02/22/96 | |LICENSE#: 08-03604-03 AGREEMENT: N |EVENT TIME: 10:30[EST]| | DOCKET: |LAST UPDATE DATE: 02/20/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LARRY NICHOLSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: Dr. BILLY BASS | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISSING IODINE-125 SEED | | | | THE RADIATION SAFETY OFFICER (RSO) FOR THE WASHINGTON D.C HOSPITAL CENTER | | LOCATED AT 110 IRVING ST. RECENTLY HAD AN NRC REGION 1 INSPECTOR AUDIT | | THEIR RECORDS. THE INSPECTOR DETERMINED THAT THE FOLLOWING EVENT SHOULD | | HAVE BEEN REPORTED TO THE NRC. | | | | ON 2/22/96, A PATIENT WAS SCHEDULED TO HAVE 90 IODINE-125 SEEDS IMPLANTED | | IN HIS PROSTATE. AFTER THE SEEDS HAD BEEN IMPLANTED, THE PATIENT WAS | | X-RAYED AND IT WAS DETERMINED THAT ONLY 89 SEEDS HAD BEEN IMPLANTED. THE | | LICENSEE COULD NOT FIND THE MISSING SEED AFTER PERFORMING RADIATION SURVEYS | | AND SEARCH OF THE SURROUNDING AREA. THE NEXT DAY, THE PATIENT WAS X-RAYED | | AGAIN AND IT WAS CONFIRMED THAT ONLY 89 I-125 SEEDS HAD BEEN IMPLANTED. | | EACH SEED CONTAINS 200 ęCi OF I-125. THE DOSE RATE AT ONE CENTIMETER FROM | | ONE SEED IS 770mr/hr. AT ONE METER, THE DOSE RATE FROM ONE SEED IS | | 0.2mr/hr. THE RADIATION SAFETY OFFICER STATED THAT THE INNER CLOTHING OF | | THE ONCOLOGIST WHO HAD PERFORMED THE SURGERY HAD NOT BEEN SURVEYED. THE | | HALF LIFE OF IODINE-125 IS 60 DAYS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31822 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/20/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 15:13 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/18/97 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: K. LAMPMAN, M. McCORMICK |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERN HODGE, RVIB NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION REGARDING THE EXCESSIVE FAILURE RATE OF | | BORG-WARNER (BWIP) PRESSURE SWITCHES USED IN THE GAS TREATMENT, SERVICE | | WATER, AND HEATING AND VENTILATION SYSTEMS | | | | SEVERAL BWIP PRESSURE SWITCHES FAILED DURING OPERATION AND INITIAL | | CALIBRATION, AND AN EVALUATION CONCLUDED THAT THE SWITCHES ARE UNABLE TO | | MAINTAIN THE CORRECT RESET POINT WHEN THE SETPOINT IS ADJUSTED. ACCORDING | | TO THE MANUFACTURER, THE SUBJECT SWITCHES DO NOT HAVE AN ACCURATELY | | ADJUSTABLE RESET VALUE. THE RELATIONSHIP BETWEEN THE SETPOINT OF THE | | SWITCHES AND THEIR RESET POINT IS NOT LINEAR NOR CONSISTENT BETWEEN | | DIFFERENT SWITCHES OF THE SAME MODEL. THEY ARE DESIGNED TO OPERATE WITH A | | MAXIMUM SETPOINT AND MINIMUM RESET WINDOW ONLY. AS A RESULT, THE SWITCHES | | ARE NOT CONSISTENTLY ABLE TO BE INITIALLY CALIBRATED TO THE DESIRED | | SETPOINT; AND ONCE INSTALLED AND CALIBRATED, MINOR SETPOINT DRIFT MAY PLACE | | THE SWITCHES OUTSIDE THEIR ACCEPTABLE TOLERANCES. | | | | THERE ARE A TOTAL OF 40 QUESTIONABLE BWIP PRESSURE SWITCHES INSTALLED IN | | THE PLANT (22 IN THE GAS TREATMENT SYSTEM, 6 IN THE SERVICE WATER SUPPLY TO | | COOLERS AND CHILLERS, AND 12 IN THE CONTROL BUILDING VENTILATION SYSTEM). | | EACH OF THE ASSOCIATED VALVES HAS TWO OR THREE OF THE SWITCHES WITHIN ITS | | HYDRAULIC CONTROLS. THE TYPE OF FAILURE ASSOCIATED WITH THE SWITCH DEPENDS | | ON WHICH SWITCH HAS FAILED. THE EFFECTS OF A FAILED SWITCH CAN BE A VALVE | | FAILING TO OPEN AND BEING UNABLE TO CLOSE OR A VALVE FAILING CLOSED AND | | BEING UNABLE TO OPEN. | | | | THE LICENSEE PERFORMED AN OPERABILITY DETERMINATION AND CONCLUDED THAT | | THERE IS REASONABLE ASSURANCE THAT THE SWITCHES WILL OPERATE AS REQUIRED. | | THIS DETERMINATION WAS BASED ON SUCCESSFUL INITIAL CALIBRATION TESTING, | | POSITIVE TEST DATA OF INSTALLED CALIBRATIONS, AND IMPLEMENTATION OF | | ADDITIONAL ADMINISTRATIVE CONTROLS TO SHORTEN THE CALIBRATION FREQUENCY. | | | | THE LICENSEE HAS BEEN IN CONTACT WITH ENERTECH (THE VENDOR) IN CALIFORNIA | | AND WITH BORG-WARNER (THE MANUFACTURER). THE LICENSEE ALSO BELIEVES THAT | | ENERTECH HAS BEEN IN CONTACT WITH THE NRC. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO | | LOG FOR SITE CONTACT TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31823 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/20/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:44 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/20/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:00[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/20/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON, REG 3 RDO | | DOCKET: 0707001 |MICHAEL WEBER, NMSS EO | +------------------------------------------------+STUART RUBIN, IRD AEOD | |NRC NOTIFIED BY: TONY CARVER | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NRC NOTIFICATION DUE TO OFFSITE NOTIFICATION OF AN OIL LEAK | | | | LUBRICATION OIL WAS DISCOVERED ACCUMULATING IN A COOLING TOWER BASIN. THE | | LICENSEE CURRENTLY BELIEVES THAT A LEAK MAY EXIST IN A HEAT EXCHANGER THAT | | IS DESIGNED TO COOL THE LUBRICATION OIL. THE LICENSEE HAS ESTIMATED THAT | | APPROXIMATELY 300 GALLONS OF LUBRICATING OIL WERE RELEASED FROM THE PRIMARY | | CONTAINMENT BUILDING. THE LICENSEE BELIEVES THAT THE OIL LEAK HAS REMAINED | | ONSITE AND THAT THIS WAS NOT A RADIOLOGICAL EVENT. | | | | THE LICENSEE PLANS TO ISOLATE THE HEAT EXCHANGER AND REPAIR THE LEAK. THE | | LICENSEE ALSO PLANS TO REMOVE THE OIL FROM THE COOLING TOWER BASIN USING AN | | OIL SKIMMER AND TO INSPECT OTHER LAGOONS OR AREAS WITHIN THE PLANT | | PERIMETER FOR OIL SHEENS. | | | | AS A RESULT OF THIS EVENT, THE LICENSEE NOTIFIED THE KENTUCKY ENVIRONMENTAL | | RESPONSE TEAM (WHICH IS PART OF THE KENTUCKY DEPARTMENT OF ENVIRONMENTAL | | PROTECTION) AND THE DEPARTMENT OF ENERGY. THE LICENSEE ALSO PLANS TO | | NOTIFY THE NRC RESIDENT INSPECTOR. THESE NOTIFICATIONS WERE MADE UNDER THE | | MISCELLANEOUS CATEGORY IN ACCORDANCE WITH APPENDIX F, CRITERION P, OF THE | | LICENSEE'S EVENT CLASSIFICATION PROCEDURE. (REFER TO THE HOO LOG FOR A | | SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31824 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 02/20/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:50 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 02/20/97 | +------------------------------------------------+EVENT TIME: 14:15[CST]| |NRC NOTIFIED BY: JAY HOUSTON |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | QUESTION REGARDING WHETHER OR NOT THE CLOSURE TIME OF PRIMARY CONTAINMENT | | PURGE VALVES WOULD BE FAST ENOUGH TO PROTECT THE STANDBY GAS TREATMENT | | (SBGT) TRAIN FROM THE PRESSURE AFFECTS OF A LOSS OF COOLANT ACCIDENT (LOCA) | | OCCURRING WHILE THE PRIMARY CONTAINMENT VENTILATION VALVES ARE OPEN | | | | AS PART OF THE REVIEW OF IMPROVED TECHNICAL SPECIFICATION SECTION 3.1.6.3, | | A QUESTION WAS RAISED AS TO WHETHER OR NOT THE CLOSURE TIME (ó10 SECONDS) | | FOR 26-INCH PRIMARY CONTAINMENT PURGE ISOLATION VALVES 1/2VQ034, 036, 031, | | AND 040 WOULD BE FAST ENOUGH TO PROTECT THE SBGT TRAIN FROM THE PRESSURE | | EFFECTS OF A LOCA OCCURRING WHILE THE PRIMARY CONTAINMENT VENTILATION | | VALVES WERE OPEN. THE BASIS FOR THIS CONCERN IS THAT THE ONLY ISOLATION | | BETWEEN THE SBGT TRAINS AND THE PRESSURIZED PRIMARY CONTAINMENT VENTILATION | | PIPING ARE THE 1/2VG02Y DAMPERS (THE UNIT 1 AND UNIT 2 SBGT INLET DAMPERS). | | THESE DAMPERS ARE DESIGNED FOR A MAXIMUM DIFFERENTIAL PRESSURE OF 56 INCHES | | OF WATER OR 2 PSID. | | | | NEITHER THE SAFETY EVALUATION REPORT NOR THE UPDATED FINAL SAFETY ANALYSIS | | REPORT (UFSAR) CLEARLY STATES THAT PRESSURIZATION WAS EVALUATED FOR THE | | SBGT TRAINS. UFSAR QUESTION AND ANSWER (Q&A) Q21-54 STATES THAT IF THE | | 2-INCH LINE BLOWS DOWN TO THE 26-INCH LINE, THE SBGT DAMPER IS CAPABLE OF | | HANDLING THE RESULTANT BLOWDOWN. UFSAR Q&A Q21-54 DID NOT EVALUATE THE | | AFFECT ON THE SBGT IF THE 26-INCH VALVES WERE OPEN, WHICH IS THE LICENSEE'S | | METHOD OF VENTING CONTAINMENT. | | | | THE SECOND CONCERN ONLY APPLIES TO THE REVIEW OF THE IMPROVED TECHNICAL | | SPECIFICATIONS. THIS CONCERN IS WHETHER OR NOT TECHNICAL SPECIFICATION | | 3.6.1.8, WHICH LIMITS THE PURGING OF CONTAINMENT THROUGH SBGT TO LESS THAN | | 90 HOURS PER YEAR, SHOULD BE INCORPORATED INTO THE IMPROVED TECHNICAL | | SPECIFICATIONS. ONE REASON TO INCORPORATE THIS LIMIT WOULD BE IF A RUNNING | | TRAIN OF SBGT (PURGING CONTAINMENT) WOULD BE MADE INOPERABLE BY THE | | PRESSURIZATION EFFECTS OF A LOCA. THIS LIMIT WOULD THEN SERVE TO MINIMIZE | | THE POSSIBILITY OF A LOCA OCCURRING CONCURRENT WITH SBGT OPERATION. HAVING | | 26-INCH PRIMARY CONTAINMENT PURGE ISOLATION VALVES 1/2VQ034, 036, 031, AND | | 040 OPEN FOR VENTING THE DRYWELL AND SUPPRESSION CHAMBER ALSO CREATES A | | DRYWELL FLOOR BYPASS WHILE THE VALVES ARE OPEN. THIS BYPASS PATH IS ALSO | | CREATED BY THE HYDROGEN RECOMBINER SYSTEM SYSTEM DURING SURVEILLANCE | | TESTING. | | | | SINCE BOTH OF THE SBGT TRAINS ARE DIRECTLY CONNECTED TO THE PRIMARY | | CONTAINMENT PURGE PIPING OF BOTH UNITS, IT IS POSSIBLE THAT IF A LOCA | | OCCURRED WHILE VENTING EITHER CONTAINMENT AT POWER, THE PRESSURE IN THE | | PRIMARY CONTAINMENT PURGE PIPING COULD EXCEED 2 PSID AT BOTH THE 1 AND | | 2VG02Y DAMPERS. EXCEEDING THE DESIGN DIFFERENTIAL PRESSURE OF THE SBGT | | DAMPERS COULD RESULT IN A TOTAL LOSS OF THE SBGT FILTER SYSTEM FUNCTION. | | THE LOSS OF THE SBGT FILTER FUNCTION WOULD SIGNIFICANTLY INCREASE POST-LOCA | | RADIOLOGICAL RELEASES AT THE EXCLUSION AREA BOUNDARY, LOW POPULATION ZONE, | | AND IN THE CONTROL ROOM. THE SIGNIFICANCE OF EXCESSIVE DRYWELL TO | | SUPPRESSION CHAMBER (LEAKAGE DUE TO EITHER THE PRIMARY CONTAINMENT PURGE | | VALVES BEING OPEN FOR 10 SECONDS OR HYDROGEN RECOMBINER SYSTEM VALVES | | DURING A SURVEILLANCE) IS A LOSS/REDUCTION IN SUPPRESSION CHAMBER STEAM | | QUENCHING (i.e., CONTAINMENT BYPASS). | | | | BOTH TRAINS OF SBGT, THE PRIMARY CONTAINMENT PURGE SYSTEM, AND THE HYDROGEN | | RECOMBINER SYSTEM HAVE BEEN LISTED IN THE OPERATIONS DEGRADED EQUIPMENT LOG | | MAKING THEM ADMINISTRATIVELY INOPERABLE IN MODES 1, 2, AND 3. ENGINEERING | | DETERMINED THAT CHANGES NEED TO BE MADE TO THE PRIMARY CONTAINMENT PURGE | | AND SBGT SYSTEMS BOTH PHYSICALLY AND OPERATIONALLY TO ELIMINATE THESE | | PROBLEMS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO LOG | | FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31825 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/20/97 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 20:40 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/20/97 | +------------------------------------------------+EVENT TIME: 16:15[MST]| |NRC NOTIFIED BY: DANIEL LARKIN |LAST UPDATE DATE: 02/20/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |NINF INFORMATION ONLY | | | |WILLIAM BEECHER, HQ OPA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 79 POWER OPERATION | 79 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION REGARDING A PRESS RELEASE | | | | AT 1615 MST, THE LICENSEE ISSUED A PRESS RELEASE REGARDING A WATER PIPELINE | | BREAK BETWEEN PHOENIX, ARIZONA, AND THE PALO VERDE WATER RECLAMATION | | FACILITY. THE PIPELINE CONSISTS OF PRE-STRESSED CONCRETE PIPE WITH A STEEL | | LINER, AND THE WATER CARRIED BY THIS 96-INCH PIPELINE IS TREATED BY THE | | CITY OF PHOENIX BEFORE IT IS PUMPED TO PALO VERDE. AT PALO VERDE, THE | | WATER IS TREATED A SECOND TIME AND USED IN SECONDARY COOLING SYSTEMS AT THE | | PLANT. THE WATER IS NOT EXPOSED TO RADIOACTIVE SYSTEMS OR ANY MATERIALS | | HAZARDOUS TO THE ENVIRONMENT. IF THE WATER WAS NOT USED BY PALO VERDE, IT | | WOULD BE TREATED AND USED FOR IRRIGATION OR REDIRECTED TO THE RIVER. THERE | | IS NO IMPACT TO PLANT OPERATIONS. | | | | THE LICENSEE DOES NOT BELIEVE THAT THIS EVENT MEETS THE CRITERIA FOR | | REPORTING IN ACCORDANCE WITH 10 CFR 50.72(b)(2)(vi). HOWEVER, THE LICENSEE | | DOES BELIEVE THAT THIS EVENT MAY CREATE MEDIA ATTENTION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, ARIZONA DEPARTMENT OF | | ENVIRONMENTAL QUALITY, ENVIRONMENTAL PROTECTION AGENCY, AND MARICOPA | | COUNTY. (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | | | | NOTE: THE R4DO (CAIN) STATED THAT HE WOULD NOTIFY A REGION 4 PUBLIC | | AFFAIRS OFFICER. | +------------------------------------------------------------------------------+