U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/01/96 - 08/02/96 ** EVENT NUMBERS ** 30707 30748 30770 30815 30816 30817 30818 30819 30820 30821 30822 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30707 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/03/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 11:07 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/03/96 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: GRADA |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EIGHT CONTAINMENT PENETRATIONS DO NOT HAVE RELIEF PROTECTION | | | | DURING TESTING OF MOTOR-OPERATED VALVES IN THE RESIDUAL HEAT REMOVAL (RHR) | | SYSTEM, ONE CONTAINMENT ISOLATION VALVE COULD NOT BE OPENED. INVESTIGATION | | REVEALED THAT THE VALVE DID NOT OPEN BECAUSE OF A BUILDUP OF PRESSURE | | BETWEEN THE INNER AND OUTER CONTAINMENT ISOLATION VALVES. THE LICENSEE | | DISCOVERED A TOTAL OF EIGHT CONTAINMENT PENETRATIONS WITH NO INSTALLED | | RELIEF PROTECTION BETWEEN THE INNER AND OUTER CONTAINMENT ISOLATION VALVES. | | THE SYSTEMS INVOLVED ARE RHR, COMPONENT COOLING WATER, AND FUEL POOL | | PURIFICATION. | | | | THE LICENSEE WILL PARTIALLY DRAIN DOWN THE AFFECTED PIPING TO PREVENT A | | PRESSURE BUILDUP UNTIL A LONGER-TERM SOLUTION IS ADOPTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1426 ON 07/31/96, FROM HUMMEL TAKEN BY KARSCH * * * | | | | THREE CONTAINMENT PENETRATIONS HAVE BEEN IDENTIFIED AS POSSIBLY OVER | | PRESSURIZING DURING A DESIGN BASIS LOSS OF COOLANT ACCIDENT (DB LOCA). | | THESE PENETRATIONS DO NOT HAVE OVER PRESSURIZATION PROTECTION. THE | | AFFECTED LINES ARE BEING DRAINED TO ELIMINATE THE OVER PRESSURIZATION | | POTENTIAL. THESE PENETRATIONS ARE 20 - SAFETY INJECTION (SI) ACCUMULATOR | | FILL, 56-2 - REACTOR COOLANT SYSTEM (RCS) COLD LEG SAMPLE LINE, AND 106 - | | SI ACCUMULATOR TEST. SEVEN ADDITIONAL UNIT 1 PENETRATIONS ARE BEING | | EVALUATED TO ASSES THEIR ABILITY TO WITHSTAND OVER PRESSURIZATION FOLLOWING | | A DB LOCA. THESE PENETRATIONS ARE 46 - RCS LOOP FILL HEADER, 55-1 - SI | | ACCUMULATOR SAMPLE LINE, 56-1 - PRESSURIZER LIQUID SAMPLE LINE, 56-3 - RCS | | HOT LEG SAMPLE LINE, 97-1 - RHR INLET SAMPLE LINE, 97-2 - RHR OUTLET SAMPLE | | LINE, AND 105-2 - PRESSURIZER VAPOR SPACE SAMPLE LINE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (KINNEMAN). | | | | * * * UPDATE AT 2025 ON 08/01/96, FROM THOMAS TO GOULD * * * | | | | UNIT 1 WAS AT 100% POWER AT THE TIME OF THIS UPDATE. | | | | DURING THE CONTINUED REVIEW OF CONTAINMENT PENETRATIONS CONCERNING THE | | POTENTIAL FOR OVER PRESSURIZATION, AN ADDITIONAL FIVE UNIT 1 PENETRATIONS | | HAVE BEEN IDENTIFIED AS HAVING THE POTENTIAL TO OVERPRESSURIZE DURING A DB | | LOCA DUE TO HEATUP AND PRESSURIZATION OF TRAPPED FLUID. THESE PENETRATIONS | | ARE 55-1 - SI ACCUMULATOR SAMPLE, 56-1 - PRESSURIZER LIQUID SAMPLE, 97-1 - | | RHR INLET SAMPLE, 97-2 - RHR OUTLET SAMPLE, AND 105-2 - PRESSURIZER VAPOR | | SPACE SAMPLE. THESE PENETRATIONS WILL BE ISOLATED OUTSIDE CONTAINMENT AND | | VENTED INSIDE CONTAINMENT. A REVISION TO THE LICENSEE EVENT REPORT WILL BE | | SUBMITTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (KINNEMAN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30748 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 07/13/96 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 22:06 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 07/13/96 | +------------------------------------------------+EVENT TIME: 21:30[EDT]| |NRC NOTIFIED BY: JACK BREEN |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LEDYARD MARSH, NRR EO | | |CEGIELSKI FEMA | | |FRANK CONGEL, IRD AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DECLARATION OF UNUSUAL EVENT DUE TO REACTOR COOLANT SYSTEM (RCS) LEAKAGE | | GREATER THAN 10 GALLONS PER MINUTE (GPM) CAUSED BY A PACKING LEAK ON A | | CHARGING PUMP | | | | AT 2130, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO RCS LEAKAGE THAT WAS | | GREATER THAN 10 GPM (IDENTIFIED) IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | 3.4.6.2. THE LEAKAGE WAS DUE TO A PACKING LEAK ON THE '2B' CHARGING PUMP. | | THE SUCTION AND DISCHARGE SIDES OF THIS POSITIVE DISPLACEMENT PUMP WERE | | MECHANICALLY ISOLATED AT 2132, AND THE UNUSUAL EVENT WAS TERMINATED AT 2135 | | WHEN THE '2B' CHARGING PUMP WAS ELECTRICALLY ISOLATED. DURING THIS EVENT, | | ALL CHARGING AND LETDOWN WAS ISOLATED, BUT IT HAS SINCE BEEN RESTORED. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE | | STATE AND LOCAL AGENCIES. | | | | * * * 1014 AUGUST 1, 1996, UPDATE FROM FIELDS RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE UNUSUAL EVENT CLASSIFICATION | | WAS CONSERVATIVELY BASED IN THAT THE LEAKAGE RATE WAS ESTIMATED | | QUALITATIVELY FROM EYE WITNESS ACCOUNTS. LICENSEE ENGINEERING PERSONNEL | | SUBSEQUENTLY PERFORMED A DETAILED QUANTITATIVE EVALUATION OF THE EVENT | | INCLUDING SUPPORTING CALCULATIONS BASED ON EYEWITNESS ACCOUNTS AND | | DETERMINED THAT THE MAXIMUM POSSIBLE LEAKAGE FROM THIS CHARGING PUMP SEAL | | FAILURE EVENT WAS APPROXIMATELY 4.1 GPM. THEREFORE, THE UNUSUAL EVENT | | DECLARATION CRITERIA OF GREATER THAN 10 GPM IDENTIFIED LEAKAGE WAS NOT | | REACHED. THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R2DO (PEEBLES). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30770 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 07/22/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 13:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/22/96 | +------------------------------------------------+EVENT TIME: 12:19[EDT]| |NRC NOTIFIED BY: THAD REAMES |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH P. BARR 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 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED OPENING OF NUCLEAR SERVICE WATER SYSTEM VALVES DURING THE | | PERFORMANCE OF AN AUXILIARY SHUTDOWN PANEL CONTROLS VERIFICATION TEST | | | | WHILE PERFORMING PROCEDURE PT/2/A/4350/26E, AUXILIARY SHUTDOWN PANEL | | CONTROLS VERIFICATION FOR 'B' TRAIN COMPONENTS, THE OPERATOR CLOSED THE 'B' | | AUXILIARY FEEDWATER PUMP SUCTION VALVE. THIS RESULTED IN LOW PUMP SUCTION | | PRESSURE, AND THE NUCLEAR SERVICE WATER SYSTEM UNEXPECTEDLY ALIGNED TO THE | | AUXILIARY FEEDWATER PUMP SUCTION. DURING THE PERFORMANCE OF THIS PORTION | | OF THE PROCEDURE, THE 'B' AUXILIARY FEEDWATER PUMP WAS LOGGED INOPERABLE, | | BUT IT WAS CONSIDERED TO BE FUNCTIONAL. THE PUMP IS CURRENTLY CONSIDERED | | TO BE OPERABLE. | | | | NORMALLY, IF THE AUXILIARY FEEDWATER PUMP SUCTION VALVE IS CLOSED FOR A | | SHORT PERIOD OF TIME, THERE IS NOT A PROBLEM. IN THIS INSTANCE, HOWEVER, | | THE OPEN LIGHT WENT OUT WHEN THE AUXILIARY FEEDWATER PUMP SUCTION VALVE WAS | | CLOSED PER THE PROCEDURE, BUT THE CLOSED LIGHT DID NOT COME ON. AS A | | RESULT, THE OPERATOR CHANGED THE LIGHT BULB, AND APPARENTLY, THE VALVE WAS | | CLOSED FOR APPROXIMATELY ONE MINUTE. THE LICENSEE SPECULATED THAT THIS MAY | | HAVE BEEN A LONG ENOUGH PERIOD OF TIME FOR THE SYSTEM PRESSURE TO DECREASE | | ENOUGH TO CAUSE THE NUCLEAR SERVICE WATER SYSTEM VALVES TO AUTOMATICALLY | | OPEN. WHEN SUCTION PRESSURE IS LOW FOR THREE SECONDS, THE NUCLEAR SERVICE | | WATER SYSTEM VALVES ARE DESIGNED TO AUTOMATICALLY OPEN IN ORDER TO PROVIDE | | ASSURED MAKEUP FLOW TO THE AUXILIARY FEEDWATER SYSTEM. THE LICENSEE ALSO | | BELIEVED THAT THIS WAS THE FIRST TIME THAT THIS PROCEDURE HAD BEEN | | PERFORMED WHILE THE UNIT WAS IN POWER OPERATIONS. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1317 ON 08/01/96, BY WASHAM TO GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT FOLLOWING FURTHER EVALUATION BY | | ENGINEERING AND REGULATORY COMPLIANCE PERSONNEL. THE LICENSEE CONCLUDED | | THAT THE MOVEMENT OF THE SUBJECT VALVES IN AND OF ITSELF DOES NOT MEET THE | | CRITERIA FOR ENGINEERED SAFETY FEATURE ACTUATION. THE BASIS FOR THIS | | CONCLUSION IS THAT THE "CA" AUXILIARY FEEDWATER PUMP DID NOT START, AND THE | | VALVE MOVEMENT ALONE WOULD NOT MITIGATE THE CONSEQUENCES OF AN ACCIDENT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE R2DO | | (PEEBLES) WAS INFORMED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30815 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 08/01/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 09:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/01/96 | +------------------------------------------------+EVENT TIME: 05:33[EDT]| |NRC NOTIFIED BY: RADISHOFSKI |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 98 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM/TURBINE TRIP DUE TO HIGH TURBINE VIBRATION | | | | UNIT 1 SCRAMMED FROM 98 PERCENT POWER DUE TO HIGH MAIN TURBINE VIBRATION. | | ALL CONTROL RODS INSERTED FOLLOWING THE SCRAM, AND ALL SYSTEMS FUNCTIONED | | AS REQUIRED. REACTOR PRESSURE REACHED A PEAK OF 1127 PSIG, AND 4 SAFETY | | RELIEF VALVES OPENED AND RECLOSED TO CONTROL PRESSURE. REACTOR VESSEL | | WATER LEVEL DECREASED TO A LOW OF +6 INCHES FOLLOWING THE SCRAM. THE UNIT | | IS CURRENTLY STABLE IN CONDITION 3. | | | | THE LICENSEE STATED THAT THE HIGH VIBRATION SIGNAL MAY HAVE BEEN SPURIOUS | | AS THE TURBINE HAD NOT BEEN SHOWING SIGNS OF UNUSUAL VIBRATION AND AS LOCAL | | VIBRATION MONITORING EQUIPMENT DID NOT INDICATE AN INCREASED LEVEL OF | | VIBRATION AT THE TIME OF THE TURBINE TRIP. THE LICENSEE INTENDS TO | | INVESTIGATE THE CAUSE OF THE TURBINE TRIP. A PRESS RELEASE WILL BE ISSUED | | BY THE LICENSEE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30816 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 08/01/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 14:42 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 08/01/96 | +------------------------------------------------+EVENT TIME: 13:57[EDT]| |NRC NOTIFIED BY: PACE |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION WHERE THE REACTOR WATER STORAGE TANK | | (RWST) HAS BEEN ALIGNED WITH A NON-SEISMICALLY QUALIFIED SYSTEM. | | | | FOLLOWING A REVIEW, A CONDITION WAS IDENTIFIED WHERE THE FUEL POOL | | PURIFICATION SYSTEM (A NON-SEISMICALLY QUALIFIED SYSTEM) HAS BEEN ALIGNED | | TO THE RWST FOR EXTENDED PERIODS IN THE PAST IN ORDER TO PURIFY THE RWST | | INVENTORY. THIS SYSTEM IS NOT AUTOMATICALLY ISOLATED FROM THE RWST, AN | | THEREFORE, COULD RESULT IN A LOSS OF WATER FROM THE RWST FOLLOWING A | | SEISMIC EVENT. AS AN INTERIM CORRECTIVE MEASURE, THE SEISMICALLY QUALIFIED | | ISOLATION VALVES WILL BE ADMINISTRATIVELY CONTROLLED TO ASSURE THAT THEY | | ARE MAINTAINED CLOSED. THE LICENSEE IS INVESTIGATING WAYS FOR A MORE | | PERMANENT SOLUTION. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30817 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 08/01/96 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:04 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 08/01/96 | +------------------------------------------------+EVENT TIME: 13:16[EDT]| |NRC NOTIFIED BY: KOZYRA |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 LICENSEE MADE OFFSITE NOTIFICATIONS OF AN OIL SPILL. | | | | THE LICENSEE NOTIFIED THE PEE DEE OFFICE OF ENVIRONMENTAL QUALITY CONTROL, | | SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL, OF AN OIL | | LEAK DETECTED IN 1 OF 4 ABOVE-GROUND 25,000-GALLON FUEL OIL STORAGE TANKS | | ON UNIT 1 (THE FOSSIL FIRED PLANT). THE AMOUNT OF LEAKAGE INTO THE SOIL | | HAS NOT YET BEEN DETERMINED. THE LEAK WAS DETECTED DURING A ROUTINE | | INSPECTION PROGRAM. THE OTHER THREE TANKS WERE INSPECTED AND FOUND TO BE | | FREE OF LEAKS. INVENTORY FROM THE LEAKING TANK HAS BEEN TRANSFERRED TO A | | NON-LEAKING TANK. A PLAN FOR OIL RECOVERY IS BEING FORMULATED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30818 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 08/01/96 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 16:39 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/01/96 | +------------------------------------------------+EVENT TIME: 14:40[CDT]| |NRC NOTIFIED BY: BUENKEL |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B.J. HOLT 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 | | 2 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT AN EXISTING PLANT CONFIGURATION MAY RESULT IN | | VOIDING IN THE CONTAINMENT ACCIDENT FAN COOLERS DURING CERTAIN CONDITIONS. | | | | VOIDING IN THE CONTAINMENT ACCIDENT FAN COOLERS COULD POSSIBLY OCCUR DURING | | A LOSS OF COOLANT ACCIDENT COINCIDENT WITH LOSS OF OFFSITE POWER TO BOTH | | UNITS. THIS CONDITION MAY BE POTENTIALLY OUTSIDE THE DESIGN BASIS OF THE | | PLANT WHICH ASSUMES NO VOIDING IN THE FAN COILS. PRELIMINARY ENGINEERING | | ANALYSIS AND JUDGMENT INDICATES THIS SYSTEM REMAINS FUNCTIONAL, BUT A MORE | | DETAILED ANALYSIS CONTINUES. HOWEVER, ALL EQUIPMENT IS CONSIDERED | | OPERATIONAL AT THIS TIME. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30819 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: V.A. MEDICAL CENTER |NOTIFICATION DATE: 08/01/96 | | CITY: LOMALINDA REGION: 4 |NOTIFICATION TIME: 17:33 [ET]| | COUNTY: SAN BERNADINO STATE: CA |EVENT DATE: 08/01/96 | |LICENSE#: 04-17862-01 AGREEMENT: Y |EVENT TIME: 10:00[PDT]| | DOCKET: |LAST UPDATE DATE: 08/01/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BLAINE MURRAY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: RAISZADEH | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE RECEIVED A SHIPMENT OF TECHNETIUM-99m FROM MALLINCKRODT IN A | | CONTAINER THAT WAS CONTAMINATED ON THE OUTSIDE MEASURING 2,200 DPM/SQCM OF | | TECHNETIUM. THE INSIDE OF THE CONTAINER WAS CLEAN. THE CONTAINER WAS | | PLACED IN STORAGE FOR DECAY. NO OTHER AREAS IN THE FACILITY WERE | | CONTAMINATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30820 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 08/01/96 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 17:35 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/01/96 | +------------------------------------------------+EVENT TIME: 16:55[EDT]| |NRC NOTIFIED BY: WEBSTER |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAS A MALFUNCTION IN THE EMERGENCY RESPONSE FACILITY COMPUTER | | SYSTEM (ERFCS). | | | | THIS OCCURRED WHILE THE LICENSEE WAS ATTEMPTING TO RE-INITIALIZE ERFCS | | FOLLOWING MAINTENANCE. AFTER AN HOUR OF UNSUCCESSFUL ATTEMPTS TO RESTORE | | THE SYSTEM, THE LICENSEE EXCEEDED THE TIME LIMIT FOR RETURNING THE SYSTEM | | TO OPERABLE STATUS, AND IT WAS CONSIDERED A MAJOR LOSS OF EMERGENCY | | ASSESSMENT CAPABILITY. THE LICENSEE IS CURRENTLY TROUBLESHOOTING THE | | PROBLEM BUT SUSPECTS THAT IT MIGHT BE IN THE SOFTWARE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30821 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 08/01/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:20 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/01/96 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: RYAN |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 DETERMINED THAT A CONDITION EXISTS WHERE POST-ACCIDENT | | LONG-TERM CORE COOLING COULD BE LOST. | | | | DURING AN ANALYSIS, IT WAS DETERMINED THAT WHILE IN LONG-TERM CORE COOLING | | DURING SUMP RECIRCULATION, THE NET POSITIVE SUCTION HEAD TO THE RESIDUAL | | HEAT REMOVAL PUMP WOULD BE INSUFFICIENT. THIS WOULD RESULT IN THE LOSS OF | | POST-ACCIDENT LONG-TERM COOLING. THE LICENSEE IS STILL INVESTIGATING HOW | | LONG THIS CONDITION HAS EXISTED, THE CAUSE, AND WHAT CORRECTIVE MEASURES TO | | TAKE PRIOR TO STARTUP. | | | | THE NRC RESIDENT INSPECTOR AND STATE HAVE BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30822 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 08/02/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: : [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/11/99 | +------------------------------------------------+EVENT TIME: 18:30[EDT]| |NRC NOTIFIED BY: |LAST UPDATE DATE: 08/01/96 | |HQ OPS OFFICER: +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | | | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 | 0 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | | | | | * * * * * PLEASE DISREGARD! THIS IS NOT AN EVENT NOTIFICATION. * * * * * | | | | | +------------------------------------------------------------------------------+