U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/22/95 - 09/25/95 ** EVENT NUMBERS ** 29325 29361 29362 29363 29364 29365 29366 29367 29368 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29325 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/13/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 13:41 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/13/95 | +------------------------------------------------+EVENT TIME: 08:20[CDT]| |NRC NOTIFIED BY: REED |LAST UPDATE DATE: 09/22/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARNES RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | |BLANCHARD EPA | | |GEORGE PANGBORN NMSS | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 93 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STATE OF NEBRASKA NOTIFIED OF A CONTAMINATED SHIPMENT. | | | | AT 08:20 ON 9/13/95, THE STATE OF NEBRASKA DEPARTMENT OF PUBLIC HEALTH WAS | | NOTIFIED OF THE RECEIPT OF A CONTAMINATED SHIPMENT ONSITE. THE SHIPMENT | | CONSISTED OF SCAFFOLDING WHICH WAS TRANSPORTED TO THE SITE BY A CARRIER | | WHICH WAS NOT LICENSED TO SHIP RADIOACTIVE MATERIALS. THE SHIPMENT WAS NOT | | EXPECTED TO BE CONTAMINATED. | | | | AT 16:00 ON 9/12/95, A CONTRACT EMPLOYEE WORKING IN THE AREA WHERE THE | | SCAFFOLDING WAS STAGED NOTICED THE REMNANTS OF "CONTAMINATED MATERIAL" | | STICKERS ON THE SCAFFOLDING AND NOTIFIED RADIOLOGICAL PROTECTION PERSONNEL. | | AT 16:15, THE SCAFFOLDING WAS SURVEYED, AND VARIOUS LEVELS OF FIXED | | CONTAMINATION WERE DETECTED (UP TO 150,000 DPM/100 CMý). NO LOOSE | | CONTAMINATION WAS FOUND. THE LICENSEE HAS ERECTED RADIOLOGICAL BARRIERS | | AROUND THE SCAFFOLDING. FURTHER SURVEYS HAVE FOUND NO TRANSFER OF | | CONTAMINATION TO PLANT PERSONNEL OR EQUIPMENT. | | | | THE LICENSEE IS CURRENTLY ATTEMPTING TO CONTACT THE SHIPPER REGARDING THIS | | EVENT. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * * UPDATE 1742EDT 9/22/95 FROM JIM DEDIC BY S. SANDIN * * * | | | | "ON 9/20/95, AN ADDITIONAL LOAD OF SCAFFOLDING WAS DELIVERED TO THE SITE BY | | THE SAME SHIPPING COMPANY. DURING THE MORNING OF 9/21/95, A SURVEY WAS | | PERFORMED TO SEE IF ANY OF THESE MATERIALS WERE SIMILARLY CONTAMINATED. ONE | | PIECE OF SCAFFOLDING WAS FOUND TO HAVE A FIXED CONTAMINATION LEVEL OF | | APPROXIMATELY 20,000 DPM/100 CM2 ON ONE AREA. NO REMOVABLE CONTAMINATION | | WAS DETECTED. THE SCAFFOLDING HAS BEEN PLACED IN A STAGING AREA WHICH HAS | | BEEN ROPED OFF AS CONTAINING RADIOACTIVE MATERIALS. THE STATE OF NEBRASKA | | WAS INFORMED OF THIS OCCURRENCE AT 1455 CDST ON 9/22/95. THIS ENS | | NOTIFICATION IS BEING MADE AS A FOLLOWUP TO THE ONE MADE ON 9/13/95 | | PURSUANT TO 10CFR50.72(b)(2)(vi)." THE LICENSEE INFORMED THE STATE AND | | OTHER GOVERNMENT AGENCIES INCLUDING THE NRC RESIDENT INSPECTOR. NOTIFIED | | R4DO(MURRAY), NMSS EO(PIERSON) AND EPA(RUTHERFORD) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29361 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 09/22/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 11:26 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 09/22/95 | +------------------------------------------------+EVENT TIME: 08:33[CDT]| |NRC NOTIFIED BY: KANAKARES |LAST UPDATE DATE: 09/22/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 80 POWER OPERATION | 80 POWER OPERATION | | 2 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECORDED A POSITIVE ALCOHOL TEST ON A CONTRACT SUPERVISOR AS THE | | RESULT OF AN ALLEGATION. THE INDIVIDUAL'S ACCESS WAS DENIED AS OF 08:33 CDT | | (ON 9/22/95). A WORK PERFORMANCE INVESTIGATION WILL BE PERFORMED TO | | DETERMINE IF THE INDIVIDUAL'S WORK WAS AFFECTED BY THIS CONDITION. THE RI | | WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29362 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ROBERTS EXPRESS |NOTIFICATION DATE: 09/22/95 | | CITY: MADISON REGION: 1 |NOTIFICATION TIME: 11:31 [ET]| | COUNTY: STATE: PA |EVENT DATE: 09/22/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 09:41[EDT]| | DOCKET: |LAST UPDATE DATE: 09/22/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MCLAUGHLIN | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER REPORTED THAT THEY WERE NOTIFIED BY ROBERTS | | EXPRESS OF A SITUATION WHICH OCCURRED AT A WESTINGHOUSE FACILITY, THE WALTZ | | MILL SITE IN MADISON, PA. A DRIVER FOR ROBERTS EXPRESS HAD RADIOACTIVE | | CONTAMINATION ON HIS SHOES AND THEY ARE ALSO CHECKING TO SEE IF THE TRUCK | | WAS CONTAMINATED. BOTH TRUCK AND SHOES HAVE BEEN CONFISCATED FOR TESTING | | AND CLEANING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29363 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GRD STEEL MILL |NOTIFICATION DATE: 09/22/95 | | CITY: MONONGAHELA REGION: 1 |NOTIFICATION TIME: 14:40 [ET]| | COUNTY: ALLEGHENY STATE: PA |EVENT DATE: 09/22/95 | |LICENSE#: 37-30147-01 AGREEMENT: N |EVENT TIME: 00:30[EDT]| | DOCKET: |LAST UPDATE DATE: 09/22/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MAURO CORUZZI | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CO-60 LEVEL CONTROL DEVICE WAS ACCIDENTLY DISPLACED FROM ITS FIXED | | LOCATION DURING CRANE OPERATION AT A STEEL MILL. | | | | AT APPROXIMATELY 0030EDT ON 9/22/95 ONE OF TWO AUTOMATIC LEVEL CONTROL | | DEVICES CONTAINING A 3.3 MILLICURIE CO-60 SOURCE BECAME ENTANGLED WITH A | | CRANE AT THE GRD STEEL MILL LOCATED IN MONONGAHELA, PA. THE DEVICE, A | | BERTHOLD MODEL # LB352 WAS RECOVERED INTACT AND REMOVED TO A CONCRETE | | STORAGE AREA. RADIATION SURVEYS CONFIRMED THAT THE SOURCE WAS INTACT AND | | NOT EXPOSED. A SHIFT SUPERVISOR CONTACTED THE MANUFACTURER FOR DISPOSAL. | | SEE THE HOO LOG FOR TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/22/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:52 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/22/95 | +------------------------------------------------+EVENT TIME: 15:40[EDT]| |NRC NOTIFIED BY: WILLIAM NOLL |LAST UPDATE DATE: 09/22/95 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A NON-SEISMIC PORTION OF PIPING INSTALLED BETWEEN | | THE REACTOR CAVITY AND THE SPENT FUEL POOL. | | | | "DURING THE SEISMIC VERIFICATION OF ALL LINES ATTACHED TO THE SPENT FUEL | | POOL AND REACTOR CAVITY (CORRECTIVE ACTION FOR LER 95-006), DESIGN | | ENGINEERS DISCOVERED THAT PORTIONS OF THE 4" SPENT FUEL POOL COOLING RETURN | | LINES TO THE REACTOR CAVITY, WHICH ARE NOT SEISMICALLY QUALIFIED, ARE A | | POTENTIAL LEAK PATH. DURING REFUELING, A POSTULATED LINE BREAK COULD | | POSSIBLY DRAIN DOWN BOTH THE REACTOR CAVITY AND SPENT FUEL POOL. NO SIPHON | | HOLES OR CHECK VALVES EXIST TO PREVENT INADVERTENT DRAINAGE. THE WORST | | CASE SCENARIO WOULD BE A LINE BREAK OUTSIDE THE REACTOR CAVITY LOCATED | | BELOW THE 91'-3" ELEVATION OF THE REACTOR CAVITY DIFFUSERS. THIS COULD | | RESULT IN THE REACTOR CAVITY AND SPENT FUEL POOL DRAIN DOWN (CONSIDERING NO | | MAKE-UP) OF APPROXIMATELY 15 FEET. THE HEIGHT OF WATER LEFT ABOVE THE | | SPENT FUEL RACKS WOULD BE APPROXIMATELY 7 FEET." | | | | "NO IMMEDIATE ACTION IS REQUIRED AT THIS TIME AND OPERABILITY OF THE SPENT | | FUEL POOL IS MAINTAINED AT THIS TIME DUE TO THE FOLLOWING REASONS: THE | | CONDITION EXISTS ONLY DURING REFUELING. OPERATION ENGINEERING STATED THAT | | THESE LINES ARE USED ONLY TO PROVIDE COOLING DURING LONG TERM REFUELING | | OUTAGES AND THAT THESE LINES HAVE NOT BEEN UTILIZED FOR MANY REFUELING | | CYCLES. THESE LINES HAVE BEEN ISOLATED FROM THE SPENT FUEL COOLING SYSTEM | | VIA VALVE 1-FP-47. WITH THE REACTOR WELL CAVITY DRAINED DURING POWER | | OPERATION, THESE LINES WOULD FILL WITH AIR AT THE HIGH POINT, THEREFORE, | | DESIGN ENGINEERING POSTULATES THAT AIR HAS SINCE ENTERED AND BEEN TRAPPED | | IN THESE LINES, THEREBY PREVENTING ANY SIPHONING TO OCCUR. DESIGN | | ENGINEERING IS DETERMINING THE REQUIRED CORRECTIVE ACTIONS PRIOR TO RF015 | | FOR THE REMOTE POSSIBILITY THAT THESE LINES NEED TO BE OPERATED DURING | | RF015." | | | | "ORIGINAL NON-SEISMIC DESIGN OF THE SPENT FUEL POOL COOLING SYSTEM, DID NOT | | POSTULATE THIS EVENT. IN ADDITION, PAST ENGINEERING EVALUATIONS OF | | INADVERTENT DRAINAGE OF THE REACTOR CAVITY AND SPENT FUEL POOL DID NOT | | DISCOVER THE POTENTIAL DRAIN DOWN PATH." | | | | "A PRUDENT ACTION IS TO LOCK VALVE 1-FP-47 CLOSED AND BLOCK THE FLOW OF | | WATER IN EACH LINE NEAR THE CAVITY. DESIGN ENGINEERING PROPOSES TO INSTALL | | SPECTACLE FLANGES IN THE ISOLATE POSITION AT TWO EXISTING FLANGES IN TRAIN | | "A" AND TRAIN "B" LOCATED JUST OUTSIDE THE REACTOR CAVITY PRIOR TO RF015." | | | | THE LICENSEE INFORMED STATE AND LOCAL AGENCIES AND WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29365 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 09/23/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 04:13 [ET]| |RX TYPE: [3] CE |EVENT DATE: 09/23/95 | +------------------------------------------------+EVENT TIME: 02:50[CDT]| |NRC NOTIFIED BY: TIM TULLOS |LAST UPDATE DATE: 09/23/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A BOTTLE OF WHISKEY WAS FOUND INSIDE THE PROTECTED AREA. | | | | A BOTTLE OF WHISKEY CONTAINING APPROXIMATELY ONE SHOT OF WHISKEY WAS | | DISCOVERED IN THE ELECTRICAL MAINTENANCE SHOP LOCATED INSIDE THE PROTECTED | | AREA. WHEN THE BOTTLE WAS DISCOVERED BY THE REPORTING INDIVIDUALS THE | | BOTTLE APPEARED TO CONTAIN THE PRESENCE OF ALCOHOL. PRIOR TO THE SECURITY | | DEPARTMENT BEING NOTIFIED THE CONTENTS WERE DRAINED. AFTER THE BOTTLE WAS | | DELIVERED TO THE SECURITY DEPARTMENT THE PRESENCE OF ALCOHOL COULD NOT BE | | DETECTED BY SMELL. THE LICENSEE IS CONTINUING TO INVESTIGATE THE EVENT. | | | | THE LICENSEE HAS NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29366 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 09/23/95 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 15:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/23/95 | +------------------------------------------------+EVENT TIME: 09:11[PDT]| |NRC NOTIFIED BY: GOELZER |LAST UPDATE DATE: 09/23/95 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |ARPS 50.72(b)(2)(ii) RPS 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 STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 REACTOR WAS MANUALLY TRIPPED FOLLOWING A FAILURE OF BOTH CIRCULATING | | WATER (CW) PUMP TRAVELING SCREENS DUE TO HIGH KELP LOADING. | | | | EACH UNIT HAS TWO CW PUMPS WITH SEPARATE INTAKE BAYS AND THREE TRAVELING | | SCREENS PER CW PUMP. BOTH CW PUMPS ARE REQUIRED FOR OPERATION ABOVE 50% | | POWER. KELP LOADING INITIALLY OCCURRED ON THE OPERATING TRAVELING SCREEN | | FOR THE "2-2" CW PUMP. OPERATORS REDUCED POWER AND SECURED THE "2-2" CW | | PUMP AT WHICH TIME THE KELP MOVED TO THE "2-1" CW PUMP TRAVELING SCREEN. | | THE "2-1" CW PUMP TRIPPED RESULTING IN A LOSS OF CW TO UNIT 2. THE | | OPERATORS MANUALLY TRIPPED THE REACTOR FROM APPROXIMATELY 50% POWER. | | | | ALL RODS FULLY INSERTED. AUXILIARY FEEDWATER INITIATED AS DESIGNED. NO | | PRIMARY SAFETIES OR RELIEFS LIFTED, HOWEVER, THE LEAD SAFETIES, I.E., THE | | FIRST OF FIVE INSTALLED ON EACH OF THE FOUR SGs FOR SGs "2-1", "2-2" AND | | "2-3" LIFTED AT LOWER THAN SETPOINT VALUES (1065#). THE SAFETY ON SG "2-3" | | RESEATED BUT THE OTHER TWO WERE GAGGED. BOTH MOTOR DRIVEN AFW PUMPS ARE | | MAINTAINING NORMAL POST TRIP SG WATER LEVELS WITH DECAY HEAT BEING REMOVED | | VIA THE 10% ATMOSPHERIC STEAM DUMPS. THERE IS NO KNOWN PRIMARY-SECONDARY | | TUBE LEAKAGE. A NORMAL TRANSFER TO OFFSITE POWER OCCURRED FOLLOWING THE | | TRIP WITH NO SAFETY EQUIPMENT OUT OF SERVICE. | | | | A PRELIMINARY EVALUATION OF THE DAMAGE TO THE TWO TRAVELING SCREENS | | SUGGESTS THAT THE "2-2" CW PUMP MAY BE RECOVERED SOMETIME LATER THIS | | EVENING. IT APPEARS THAT THE SHEAR PINS FAILED ON THIS SCREEN. THE | | TRAVELING SCREEN FOR THE "2-1" CW PUMP IS HEAVILY DAMAGED. THE LICENSEE | | ESTIMATES THAT RESTART MAY OCCUR AS SOON AS MONDAY 9/25. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR AND PLANS ON MAKING A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/24/95 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 06:03 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/24/95 | +------------------------------------------------+EVENT TIME: 05:45[EDT]| |NRC NOTIFIED BY: GERALD KAHN |LAST UPDATE DATE: 09/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO AN INOPERABLE EMERGENCY | | DIESEL GENERATOR (EDG) WITH A COMPONENT IN THE OPPOSITE TRAIN ALSO | | INOPERABLE. | | | | AT 05:45 THE UNIT ENTERED TECHNICAL SPECIFICATION 3.8.1.1.e DUE TO THE | | INOPERABILITY OF THE DIVISION II EDG WITH A COMPONENT SUPPLIED BY THE | | OPERABLE EDG (DRYWELL GASEOUS AND PARTICULATE MONITOR) ALSO INOPERABLE. THE | | TECHNICAL SPECIFICATION REQUIRES THE UNIT TO BE IN A COLD SHUTDOWN | | CONDITION WITHIN 12 HOURS. | | | | THE EDG WAS DECLARED INOPERABLE WHEN IT WAS DISCOVERED, DURING A PANEL | | WALKDOWN, THAT A RECIRCULATION VENTILATION DAMPER IN AN AIR HANDLING UNIT | | FOR THE EDG ROOM HAD A DUAL POSITION INDICATION. THE ROOM HAS TWO AIR | | HANDLING UNITS THAT SUPPLY VENTILATION AND COOLING TO THE EDG ROOM. ONE OF | | THE UNITS WAS OUT OF SERVICE FOR MAINTENANCE WHEN THE PROBLEM WITH THE | | OPERABLE AIR HANDLING UNIT WAS DISCOVERED. | | | | THE LICENSEE IS ALSO IN A SECOND TECHNICAL SPECIFICATION ACTION STATEMENT | | FOR THE REACTOR COOLANT LEAKAGE DETECTION SYSTEM WHICH REQUIRES TWO | | CHANNELS OF DRYWELL GASEOUS AND PARTICULATE MONITORING TO BE OPERABLE. THIS | | TECHNICAL SPECIFICATION ALSO REQUIRES THE UNIT TO BE IN A COLD SHUTDOWN | | CONDITION WITHIN 12 HOURS. | | | | AT 06:10 THE UNIT EXITED BOTH OF THE 12 HOUR LCOs WHEN DIVISION I OF THE | | DRYWELL GASEOUS AND PARTICULATE MONITOR WAS DECLARED OPERABLE. THE UNIT | | HAD DECREASED POWER BY 50 MEGAWATTS ELECTRIC PRIOR TO THE MONITOR BEING | | RETURNED TO SERVICE. THE UNIT REMAINS IN A 72 HOUR LCO DUE TO THE DIVISION | | II EDG BEING DECLARED INOPERABLE. THE WEATHER IN THE AREA IS CLEAR AND ALL | | SOURCES OF OFFSITE POWER ARE OPERABLE. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29368 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 09/24/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 07:38 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 09/24/95 | +------------------------------------------------+EVENT TIME: 04:08[CDT]| |NRC NOTIFIED BY: MICHAEL ENTWISTLE |LAST UPDATE DATE: 09/24/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 98 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM JUST PRIOR TO RECEIVING AN AUTOMATIC SCRAM DUE TO | | REACTOR VESSEL LEVEL PROBLEMS. | | | | UNIT ONE SCRAMMED DUE TO A FEED WATER TRANSIENT THAT OCCURRED WHILE | | PERFORMING A SURVEILLANCE ON THE UNIT 1B TURBINE DRIVEN REACTOR FEEDWATER | | PUMP (1BTDRFP). THE SURVEILLANCE BEING PERFORMED WAS LOS-FW-SR1, 'TURBINE | | DRIVEN FEED PUMP SURVEILLANCE'. THE SURVEILLANCE IS INTENDED TO TEST THE | | OVERSPEED TRIP FUNCTION OF THE 1B TDRFP WHILE THE PUMP REMAINS IN | | OPERATION. | | | | PRIOR TO THE SURVEILLANCE BOTH THE 1A AND 1B TDRFPs WERE IN OPERATION | | SUPPLYING APPROXIMATELY 7 MILLION POUNDS PER HOUR FEEDWATER FLOW EACH TO | | THE REACTOR. DURING THE PERFORMANCE OF THE SURVEILLANCE, THE 1B TDRFP FLOW | | UNEXPECTEDLY DROPPED OFF TO LESS THAN 1 MILLION POUNDS PER HOUR, AND THE 1A | | TDRFP INCREASED FLOW TO COMPENSATE. | | | | DURING THE LEVEL TRANSIENT, THE FOLLOWING OCCURRED: | | | | 1. BOTH REACTOR RECIRCULATION (RR) PUMPS DOWN SHIFTED DUE TO THE 12.5 INCH | | LOW LEVEL INTERLOCK. | | | | 2. AN OPERATOR MANUALLY STARTED THE MOTOR DRIVEN FEEDWATER PUMP WHICH IS | | CAPABLE OF SUPPLYING 30% FEEDWATER FLOW DUE TO THE LOW REACTOR VESSEL | | LEVEL. THE RESULTANT REACTOR LEVEL SWELL FROM THE DOWN SHIFTING OF THE | | REACTOR RECIRCULATION PUMPS, COUPLED WITH THE STARTING OF THE MOTOR DRIVEN | | FEEDWATER PUMP AND THE UNEXPECTED RETURN OF THE 1B TDRFP CAUSED AN INCREASE | | IN REACTOR LEVEL AND A HIGH LEVEL TRIP OF THE MAIN TURBINE GENERATOR. | | | | 3. SIMULTANEOUS WITH THE MAIN TURBINE TRIP WAS A MANUAL SCRAM INSERTED BY | | THE UNIT NUCLEAR STATION OPERATOR. A REVIEW OF THE SEQUENCE OF EVENTS | | RECORDER INDICATES THAT A MANUAL SCRAM WAS INSERTED IMMEDIATELY PRIOR TO | | THE SCRAM SIGNAL GENERATED BY THE MAIN TURBINE GENERATOR TRIP ON HIGH | | REACTOR WATER LEVEL. | | | | THE POST SCRAM RESPONSE WAS NORMAL. ALL RODS INSERTED AND NO SAFETY RELIEF | | VALVES LIFTED. ALL ELECTRICAL BUSSES TRANSFERRED AS EXPECTED. ALL | | EMERGENCY CORE COOLING SYSTEMS AND EMERGENCY DIESEL GENERATORS ARE | | OPERABLE. REACTOR VESSEL WATER LEVEL IS BEING MAINTAINED BY THE MOTOR | | DRIVEN FEEDWATER PUMP AND THE MAIN CONDENSER IS AVAILABLE AS A HEAT SINK. | | | | REACTOR VESSEL LEVEL DID DROP TO MINUS 10 INCHES DUE TO SHRINK AFTER THE | | SCRAM. THIS IS ABOVE THE LEVEL SETPOINT OF -50 INCHES WHERE HPCS AND RCIC | | AUTOMATICALLY START. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+