U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/11/97 - dr.der ~02/12/97 ** EVENT NUMBERS ** 31592 31762 31763 31764 31765 31766 31767 31768 31769 31770 31771 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31592 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/14/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/14/97 | +------------------------------------------------+EVENT TIME: 10:00[EST]| |NRC NOTIFIED BY: DEPUYDT |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURGESS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CCW TRAIN INOPERABLE DUE TO SPACER MISSING FROM TORQUE SWITCH. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 1000 HOURS TODAY, WITH UNIT 2 AT 100 PERCENT RATED THERMAL POWER, IT | | WAS DETERMINED THAT THE 2-CMO-415, EAST COMPONENT COOLING WATER (CCW) | | SUPPLY TO THE MISCELLANEOUS HEADER, WAS INOPERABLE DUE TO A TORQUE SWITCH | | CONFIGURATION THAT COULD PREVENT THE VALVE FROM GOING FULL CLOSED. THE | | VALVE, PER THE DESIGN BASIS, IS DESIGNED TO BE MANUALLY CLOSED DURING | | POST-LOCA OPERATION AFTER RECIRCULATION HAS COMMENCED. DUE TO THE | | INOPERABLE 2-CMO-415, THE EAST CCW TRAIN WAS DECLARED INOPERABLE BY | | OPERATIONS, AND THE VALVE WAS CLOSED. CONSERVATIVELY, THE VALVE AND CCW | | TRAIN HAVE NOT BEEN ABLE TO PERFORM THEIR DESIGN FUNCTION SINCE SEPTEMBER | | 3, 1996, WHEN THE NEW TORQUE SWITCH WAS INSTALLED; THEREFORE, THIS EVENT IS | | BEING REPORTED UNDER 10 CFR 50.72(b)(1)(ii)(B) AS A CONDITION OUTSIDE THE | | DESIGN BASIS. | | | | THE NEW TORQUE SWITCH WAS INSTALLED IN SEPTEMBER 1996 AND SATISFACTORILY | | TESTED UNDER STATIC CONDITIONS PRIOR TO RETURN TO SERVICE. ON JANUARY 12, | | 1997, ANOTHER VALVE WITH THE IDENTICAL TORQUE SWITCH CONFIGURATION FAILED | | TO GO FULLY CLOSED. THE INVESTIGATION INTO THE FAILURE TODAY REVEALED THAT | | IT WAS DUE TO THE LACK OF A SPACER IN THE TORQUE SWITCH ASSEMBLY. THIS | | FAILURE WOULD ONLY AFFECT VALVE TRAVEL IN THE CLOSED DIRECTION. | | | | A SEARCH REVEALED THAT SEVEN OF THESE ASSEMBLIES WERE RECEIVED BY THE | | PLANT, FOUR OF WHICH HAVE BEEN INSTALLED. THE REMAINDER OF THE SHIPMENT | | LOT HAVE NOT BEEN INSTALLED AND HAVE BEEN VERIFIED TO LACK THE SPACER WHICH | | WOULD PREVENT THE FAILURE. TWO OF THE VALVES WHICH RECEIVED THE NEW | | SWITCHES ARE NON-SAFETY APPLICATIONS, AND THE THIRD, WHICH IS SAFETY | | RELATED, IS AN APPLICATION WHERE THE DIRECTION OF REQUIRED TRAVEL IS IN THE | | OPEN DIRECTION. THE FOURTH VALVE IS 2-CMO-415. AFTER DISCUSSION WITH | | ENGINEERING, IT WAS DETERMINED THAT ALTHOUGH THE VALVE ORIGINALLY TESTED | | SATISFACTORILY, THE VALVE SHOULD BE DECLARED INOPERABLE DUE TO THE TORQUE | | SWITCH CONFIGURATION, SINCE REASONABLE ASSURANCE DID NOT EXIST THAT THE | | VALVE COULD PERFORM ITS DESIGN FUNCTION. | | | | THE TECHNICAL SPECIFICATION ACTION STATEMENT FOR THE CCW SYSTEM HAS BEEN | | ENTERED, WHICH REQUIRES THAT THE INOPERABLE TRAIN BE RESTORED WITHIN 72 | | HOURS. CURRENT PLANS ARE TO RESTORE THE EAST CCW TRAIN TO OPERABLE STATUS | | BY TOMORROW MORNING, JANUARY 15, 1997." | | | | THE LICENSEE IS ALSO EVALUATING THE NEED FOR A 10 CFR PART 21 NOTIFICATION. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | *RETRACTION BY M. BETH DEPUYDT @ 1329 EST ON 02/11/97, TAKEN BY MACKINNON* | | | | DURING THE SUBSEQUENT INVESTIGATION AND EVALUATION OF THE ABOVE EVENT, IT | | WAS DISCOVERED THAT THE VALVE HAD BEEN TESTED UNDER DYNAMIC CONDITIONS | | DURING THE TIME THAT THE INCORRECTLY CONFIGURED TORQUE SWITCH WAS | | INSTALLED. EXAMINATION OF THIS SURVEILLANCE DATA BY ENGINEERING REVEALED | | THAT THE TESTING WAS ACTUALLY PERFORMED UNDER MORE SEVERE CONDITIONS THAN | | THE ACTUATOR WOULD EXPERIENCE UNDER ACCIDENT CONDITIONS. THIS INFORMATION, | | IN COMBINATION WITH INFORMATION FROM THE EPRI TOPICAL REPORT (TR-103224, | | BUTTERFLY VALVE MODEL DESCRIPTION REPORT), EFFECTIVELY PROVED THAT THE | | VALVE WOULD HAVE CLOSED UNDER DESIGN BASIS CONDITIONS AND WAS, THEREFORE, | | NEVER INOPERABLE. BASED ON THE EVALUATION PERFORMED BY ENGINEERING, THIS | | EVENT IS NOT REPORTABLE, AND IT IS BEING RETRACTED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS RETRACTION BY THE LICENSEE. | | THE R3DO (MARC DAPAS) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:36 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/10/97 | +------------------------------------------------+EVENT TIME: 21:30[CST]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SPDS DECLARED INOPERABLE BUT FUNCTIONAL FOR LONGER THAN 8 HOURS - | | | | THE LICENSEE REMOVED THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FROM | | SERVICE FOR LONGER THAN 8 HOURS TO PERFORM MAINTENANCE ON THE UN- | | INTERRUPTIBLE POWER SUPPLY FOR THE #1A BUS THAT POWERS THE SPDS. THE SPDS | | IN INOPERABLE BUT FUNCTIONAL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31763 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 07:25 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 03:50[EST]| |NRC NOTIFIED BY: RUSS KEARNEY |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 58 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HALF SCRAM CAUSED BY THE LOSS OF A BUS AND POWER REDUCTION REQUIRED DUE TO | | LOSS OF ISOPHASE BUS DUCT COOLING | | | | BUS "F1C" (A 480-VOLT FEED FOR VARIOUS PLANT LOADS INCLUDING A REACTOR | | PROTECTION SYSTEM MOTOR-GENERATOR SET) WAS LOST FOR UNKNOWN REASONS. THIS | | TRIGGERED A HALF SCRAM WHICH INITIATED CONTROL ROOM EMERGENCY | | RECIRCULATION, TRIPPED FUEL HANDLING BUILDING SUPPLY FANS, AND CAUSED | | BALANCE OF PLANT DIVISION 2 ISOLATIONS (REACTOR WATER CLEANUP, IN-BOARD | | RADIATION MONITOR SUCTION, SUPPRESSION POOL CLEANUP, ETC.). THE "A" TRAIN | | OF THE ISOPHASE BUS DUCT COOLING WAS LOST WHEN BUS "F1C" WAS LOST. THE "B" | | TRAIN OF THE ISOPHASE BUS DUCT COOLING SUBSEQUENTLY WAS LOST WHEN THE | | COOLING FAN TRIPPED ON HIGH STATOR TEMPERATURE. THE LOSS OF ISOPHASE BUS | | DUCT COOLING NECESSITATED A REDUCTION IN UNIT POWER. THE LICENSEE IS | | INVESTIGATING THE CAUSES FOR THE LOSS OF BUS "F1C" AND THE "B" TRAIN OF | | ISOPHASE BUS DUCT COOLING. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31764 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/11/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 10:00[EST]| |NRC NOTIFIED BY: TYRONE S. TONKINSON |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY 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 +------------------------------------------------------------------------------+ | PRESSURE BOUNDARY LEAKAGE DISCOVERED ON A REACTOR PRESSURE VESSEL | | INSTRUMENT NOZZLE. THE LEAK RATE IS LESS THAN 1 DROP/MIN. THE REACTOR | | VESSEL IS FLOODED UP FOR REFUELING. | | | | DURING INSERVICE INSPECTION PREPARATION ACTIVITIES ON UNIT 2, LEAKAGE (LESS | | THAN 1 DROP PER MINUTE) WAS OBSERVED FROM A 2-INCH INSTRUMENTATION NOZZLE | | PENETRATION. THIS INSTRUMENTATION NOZZLE SENDS REACTOR VESSEL WATER LEVEL | | AND PRESSURE SIGNALS TO THE REACTOR PROTECTION SYSTEM (RPS), 'C' LOOP OF | | LOW PRESSURE COOLANT INJECTION (LPCI), 'C' LOOP OF LOW PRESSURE CORE SPRAY | | (LPCS), AUTOMATIC DEPRESSURIZATION SYSTEM, NUCLEAR STEAM SUPPLY SHUTOFF | | SYSTEM, ETC. THE LEAKAGE IS FROM THE TOP OF INSTRUMENT NOZZLE N-12B. THE | | INSTRUMENT NOZZLE IS LOCATED AT PLANT ELEVATION 318' (APPROXIMATELY 13 FEET | | ABOVE THE TOP OF ACTIVE FUEL). THE OBSERVED LEAKAGE IS FROM THE REACTOR | | COOLANT SYSTEM PRESSURE BOUNDARY AND IS NOT ISOLABLE. NO DEFECTS ARE | | READILY OBSERVABLE ON THE SURFACE OF THE NOZZLE. NON-DESTRUCTIVE | | EXAMINATIONS WILL BE PERFORMED TO DETERMINE THE NATURE OF THE DEFECT. | | INSTRUMENTATION ASSOCIATED WITH THE NOZZLE'S INSTRUMENT LOOP HAS BEEN | | DECLARED INOPERABLE PENDING EVALUATION OF THE AS-FOUND CONDITION. SYSTEMS | | AFFECTED INCLUDE RPS, 'C' LOOP OF LPCI, AND 'C' LOOP OF LPCS. THE | | ASSOCIATED INSTRUMENTATION IS NOT SUPPORTING SAFETY-RELATED SYSTEMS | | CURRENTLY REQUIRED TO BE OPERABLE BY TECHNICAL SPECIFICATIONS. REACTOR | | COOLANT TEMPERATURE IS BEING MAINTAINED BELOW 120øF IN ACCORDANCE WITH THE | | ACTION STATEMENT OF TECHNICAL SPECIFICATION 3.4.8. THERE IS NO RELEASE OF | | RADIOACTIVE MATERIAL INVOLVED. SUFFICIENT SAFETY SYSTEMS ARE OPERABLE TO | | SATISFY TECHNICAL SPECIFICATION REQUIREMENTS. THE NOZZLE WILL BE REPAIRED | | BEFORE THE REFUELING OUTAGE IS OVER. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31765 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 13:58[CST]| |NRC NOTIFIED BY: MATT ROBERT |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 97 POWER OPERATION | 97 POWER OPERATION | | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AFTER REVIEWING AN EVENT REPORT FROM ANOTHER PLANT ON SEISMIC QUALIFICATION | | OF RACKABLE BREAKERS, SEVERAL 480-VOLT AC RACKABLE BREAKERS WERE FOUND IN | | THE REMOVED POSITION INSTEAD OF BEING IN THE DISCONNECT POSITION. | | | | MANY 480-VOLT AC RACKABLE BREAKERS OF VARIOUS UNIT SUBSTATIONS WERE FOUND | | TO BE IN THE REMOVED POSITION INSTEAD OF BEING IN THE DISCONNECT POSITION. | | ALTHOUGH STILL IN THEIR CUBICLES, THE REMOVED POSITION IS NOT SEISMICALLY | | QUALIFIED. THIS INFORMATION WAS DISCOVERED TODAY (02/11/97) WHILE THE | | LICENSEE WAS REVIEWING A SUSQUEHANNA EVENT THAT OCCURRED ON 11/05/96. | | WITHOUT SEISMIC QUALIFICATION READILY AVAILABLE THE LICENSEE DECIDED TO | | MAKE THIS ONE-HOUR NOTIFICATION. | | | | THE LICENSEE THINKS THAT FOUR OF THE RACKABLE BREAKERS FOUND IN THE REMOVED | | POSITION INSTEAD OF BEING IN THE DISCONNECT POSITION WERE CLASS-1E | | BREAKERS. MOST OF THE BREAKERS FOUND IN THE REMOVED POSITION WERE SPARE | | BREAKERS. SPARE BREAKERS HAD BEEN LEFT IN THE REMOVED POSITION INSTEAD OF | | BEING PLACED IN THE DISCONNECT POSITION AFTER COMING OUT OF BUS OUTAGES. | | ALL STATION BREAKERS WERE WALKED DOWN. THOSE FOUND IN THE REMOVED POSITION | | WERE SECURED IN THE DISCONNECT POSITION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31766 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 15:12[CST]| |NRC NOTIFIED BY: R POWERS |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 +------------------------------------------------------------------------------+ | DISCOVERY OF CONTAINMENT PENETRATIONS THAT ARE SUSCEPTIBLE TO THERMALLY | | INDUCED OVERPRESSURIZATION FOLLOWING A LOCA (GENERIC LETTER 96-06 ISSUE) | | | | DURING GENERIC LETTER 96-06 REVIEW, THE LICENSEE IDENTIFIED 21 CONTAINMENT | | PENETRATIONS AS BEING POTENTIALLY SUSCEPTIBLE TO THERMALLY INDUCED | | OVERPRESSURIZATION FOLLOWING A LOSS OF COOLANT ACCIDENT. WHILE PERFORMING | | SUBSEQUENT ENGINEERING EVALUATIONS IN RESPONSE TO NRC GENERIC LETTER 96-06, | | IT WAS DETERMINED THAT 17 OF THE 21 CONTAINMENT PENETRATIONS ARE | | SUSCEPTIBLE TO THERMALLY INDUCED OVERPRESSURIZATION DURING A DESIGN BASIS | | LOSS OF COOLANT ACCIDENT SUCH THAT CODE ALLOWABLE STRESS LIMITS COULD BE | | EXCEEDED. THESE INCLUDED THE FOLLOWING PENETRATIONS: | | | | 1MC-046 CC CC SUPPLY | | 1MC-047 CC CC RETURN | | 1MC-050 MC MC MAKEUP CONDENSATE (MC) | | 1MC-052 FC FUEL POOL COOLING AND CLEANUP | | 1MC-053 FC FUEL POOL COOLING AND CLEANUP | | 1MC-056 FP FIRE PROTECTION | | 1MC-065 WX RADWASTE REPRO. AND DISPOSAL | | 1MC-069 RE CNMT. EQUIPMENT DRAINS RE | | 1MC-070 RF CNMT. FLOOR DRAINS RF | | 1MC-081 FP FIRE PROTECTION | | 1MC-082 FP FIRE PROTECTION | | 1MC-085 CY CYCLE CONDENSATE | | 1MC-088 CC CCW RETURN | | 1MC-103 WO WO CHILLER WATER SUPP. | | 1MC-104 WO WO CHILLER WATER RETURN | | 1MC-116 SC STANDBY LIQUID CONTROL | | | | THE LICENSEE PLANS TO FIX THESE PENETRATIONS BY EITHER DRILLING HOLES IN | | THE DISC OF THE VALVES, INSTALLING RELIEF VALVES, INSTALLING RUPTURE DISKS, | | OR ADDING EXPANSION TANKS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31767 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/11/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:42 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 17:35[EST]| |NRC NOTIFIED BY: R GREEN |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GENERIC LETTER 96-06 ISSUES (REFER TO SIMILAR EVENT #31770.) | | | | DURING REVIEW OF GENERIC LETTER 96-06, A CONCERN HAS BEEN RAISED FOR | | DOUBLE-VALVED VENT, DRAIN, AND TEST CONNECTIONS ON WATER FILLED SYSTEMS | | INSIDE PRIMARY CONTAINMENT. THE POTENTIAL EXISTS FOR WATER TRAPPED BETWEEN | | THE VALVES OR BETWEEN THE OUTBOARD VALVE AND THE PIPING CAP TO EXPAND DUE | | TO A TEMPERATURE INCREASE IN THE PRIMARY CONTAINMENT AS ANALYZED FOR THE | | DESIGN BASIS LOSS OF COOLANT ACCIDENT EVENT. A PRELIMINARY REVIEW | | INDICATES THAT DESIGN PRESSURE MAY BE EXCEEDED, BUT SYSTEM INTEGRITY WILL | | BE MAINTAINED IN THE PIPING SYSTEMS AS THE HIGHEST PRESSURE EXPECTED WOULD | | NOT CAUSE EQUIPMENT FAILURE. SYSTEMS ARE BEING MAINTAINED OPERABLE BASED | | ON THIS PRELIMINARY EVALUATION, BUT FURTHER ENGINEERING SUPPORTING ANALYSIS | | IS BEING REQUESTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31768 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:47 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/01/97 | +------------------------------------------------+EVENT TIME: 21:29[CST]| |NRC NOTIFIED BY: D KLOPSTEIN |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 44 POWER OPERATION | 44 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A FIRE WATCH SUPERVISOR REPORTED TO WORK WITHIN FIVE HOURS OF CONSUMING | | ALCOHOL. | | | | THE STATION SECURITY ADMINISTRATOR RECEIVED INFORMATION THAT A FIRE WATCH | | SUPERVISOR KNOWINGLY VIOLATED THE FITNESS-FOR-DUTY POLICY AT ZION STATION | | IN THAT THIS INDIVIDUAL CONSUMED ALCOHOL DURING THE FIVE-HOUR ABSTINENCE | | PERIOD PRIOR TO SHOWING UP TO WORK. | | | | THE FIRE WATCH SUPERVISOR'S ACCESS HAS BEEN PLACED ON TEMPORARY HOLD | | PENDING FURTHER INVESTIGATION. THE ACCESS FOR TWO ADDITIONAL SUPERVISORS | | ARE ON TEMPORARY HOLD PENDING FURTHER INVESTIGATION. | | | | THE FIRE WATCH SUPERVISOR ENTERED THE PROTECTED AREA ON 02/01/97, BUT | | PERFORMED NO SAFETY-RELATED TASKS. | | | | THE NRC REGION III OFFICE IS AWARE OF THIS EVENT. THE NRC RESIDENT | | INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31769 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: USDA |NOTIFICATION DATE: 02/11/97 | | CITY: LINCOLN REGION: 4 |NOTIFICATION TIME: 17:48 [ET]| | COUNTY: LANCASTER STATE: NE |EVENT DATE: 02/07/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[CST]| | DOCKET: |LAST UPDATE DATE: 02/11/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LARRY YANDELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: HEARTY | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | URANIUM ACETATE (500 GRAMS) SPILLED IN THE BASEMENT OF A BUILDING RENTED BY | | THE USDA. | | | | THE STATE OF NEBRASKA DEPARTMENT OF HEALTH AND HUMAN SERVICES, PUBLIC | | HEALTH ASSESSMENT, RADIOACTIVE MATERIAL PROGRAM, REPORTED THE FOLLOWING | | EVENT. THIS EVENT IS DOCUMENTED IN STATE OF NEBRASKA ORIGINAL ITEM NUMBER | | NE-97-007. | | | | ON 02/07/97, A TRANSIENT ENTERED THE BASEMENT OF THE FACILITY AT 512 SOUTH | | 7th STREET IN LINCOLN, NEBRASKA, AND REMOVED THREE BOTTLES OF URANIUM | | ACETATE DIHYDRATE TO A STAIRWELL IN THE BUILDING. WHEN DISCOVERED, THE | | HAZMAT TEAM WAS CALLED, AND THE CHEMICALS WERE REMOVED TO LINCOLN/LANCASTER | | COUNTY STORAGE BUNKER. THE STATE WAS NOTIFIED OF THIS ON 02/10/97. ON | | 02/11/97, THE STATE WAS CALLED TO RESPOND TO THE SCENE SINCE A WORKER HAD | | DISCOVERED A FOURTH BOTTLE BROKEN ON THE FLOOR OF THE CAGED STORAGE AREA. | | THE MATERIAL DID NOT APPEAR TO HAVE SPREAD FROM THE AREA, AND IT WAS NOT AN | | AIRBORNE HAZARD. THE BUILDING OWNER WAS TOLD TO RESTRICT ACCESS AND | | CONTRACT FOR WASTE DISPOSAL SERVICES TO DECONTAMINATE THE AREA. RADIATION | | MONITORS USED BY THE STATE OF NEBRASKA RADIOACTIVE MATERIALS PERSONNEL DID | | NOT DETECT ANY ALPHA RADIATION OR ANY OTHER RADIATION WHEN THEY SURVEYED | | THE SPILLED URANIUM ACETATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31770 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/11/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:11 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 18:00[EST]| |NRC NOTIFIED BY: ALEJANDRO |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY 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 +------------------------------------------------------------------------------+ | GENERIC LETTER 96-06 ISSUES (REFER TO SIMILAR EVENT #31767.) | | | | DURING REVIEW OF GENERIC LETTER 96-06, A CONCERN HAS BEEN RAISED FOR DOUBLE | | VALVED VENT, DRAIN, AND TEST CONNECTIONS ON WATER FILLED SYSTEMS INSIDE THE | | PRIMARY CONTAINMENT. THE POTENTIAL EXISTS FOR WATER TRAPPED BETWEEN THE | | VALVES OR BETWEEN THE OUTBOARD VALVE AND THE PIPING CAP TO EXPAND DUE TO A | | TEMPERATURE INCREASE IN THE PRIMARY CONTAINMENT AS ANALYZED FOR THE DESIGN | | BASIS LOSS OF COOLANT ACCIDENT EVENT. AN OPERABILITY ANALYSIS INDICATES | | THAT DESIGN PRESSURE MAY BE EXCEEDED, BUT SYSTEM INTEGRITY WILL BE | | MAINTAINED IN THE PIPING SYSTEMS AS THE HIGHEST PRESSURE EXPECTED WOULD NOT | | CAUSE PIPING FAILURE. SYSTEMS ARE BEING MAINTAINED OPERABLE BASED ON THIS | | EVALUATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31771 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/11/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 20:06 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/11/97 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: BORCHERT |LAST UPDATE DATE: 02/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON BELLAMY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT DESIGN PRESSURE MAY BE CHALLENGED DURING HOT ZERO POWER | | OPERATION IF A MAIN STEAM LINE BREAK OCCURRED WITH BOTH MOTOR-DRIVEN | | AUXILIARY FEEDWATER PUMPS FEEDING THE STEAM GENERATORS. | | | | BASED ON DISCUSSIONS WITH THE MOTOR-DRIVEN AUXILIARY FEEDWATER (AFW) PUMP | | VENDOR DURING ATTEMPTS TO PROVIDE CLOSURE AND FINAL RESOLUTION OF ADVERSE | | CONDITION REPORT M2-97-0237, ENGINEERING PERSONNEL CONCLUDED THAT AFW FLOW | | RATES WOULD MOST LIKELY BE HIGHER THAN THE PUMP RUN-OUT FLOW RATE (>575 gpm | | PER PUMP) IDENTIFIED BY THE PUMP CURVE DUE TO THE REDUCED FLOW RESISTANCE | | FOLLOWING A MAIN STEAM LINE BREAK. (THE FSAR ANALYSIS DID NOT INCLUDE A | | SINGLE FAILURE THAT MAY CAUSE AFW CONTROL VALVES TO OPEN.) BASED ON THE | | INDETERMINATE FLOW WHICH IS BELIEVED TO BE SOME VALUE GREATER THAN THE | | PREVIOUSLY ASSUMED AFW PUMP RUN-OUT FLOW OF 575 gpm (1,150 gpm TOTAL), PEAK | | CONTAINMENT PRESSURE ACCEPTANCE CRITERIA OF 54 psig IS SUSPECTED TO BE | | CHALLENGED ALTHOUGH A PEAK PRESSURE VALUE FOR THE MAIN STEAM LINE BREAK | | EVENT IS CURRENTLY INDETERMINATE. CONTAINMENT SPRAY ACTUATION IS ASSUMED | | TO OCCUR. | | | | THE BIGGEST CHALLENGE TO PEAK CONTAINMENT PRESSURE MAY OCCUR DURING HOT | | ZERO POWER CONDITION WHERE TWO MOTOR-DRIVEN AUXILIARY FEEDWATER PUMPS ARE | | IN OPERATION WITH THEIR REGULATING VALVES FULLY OPEN. IF A MAIN STEAM LINE | | BREAK WERE TO OCCUR AT THIS TIME, THE AFW FLOW WOULD BE MAXIMIZED (>1,150 | | gpm) IMMEDIATELY SINCE BOTH FEEDWATER REGULATING VALVES ARE OPEN, AND THE | | AFW PUMPS ARE IN OPERATION. THE AFW PUMPS WOULD FEED THE FAULTED STEAM | | GENERATOR AT HIGHER FLOW RATES THAN WERE INITIALLY ASSUMED, AND THIS WOULD | | CAUSE CONTAINMENT PEAK PRESSURE TO INCREASE. THIS CONDITION CAN EXIST | | WITHOUT A SINGLE FAILURE. | | | | THE FOLLOWING CORRECTIVE ACTIONS ARE PLANNED TO BE TAKEN BY ENGINEERING: | | DETERMINE THE MAXIMUM AFW RUN-OUT FLOW RATE, PERFORM THE MAIN STEAM LINE | | BREAK ANALYSIS BASED ON THE ANTICIPATED RUN-OUT FLOW RATES OF THE AFW | | PUMPS, AND FORMALLY EVALUATE IF THE PEAK CONTAINMENT PRESSURE REACHED | | DURING THE SCENARIO IS BOUNDING AND IF THERE IS AN ACTUAL CHALLENGE TO THE | | ACCEPTANCE CRITERIA FOR PEAK CONTAINMENT PRESSURE. BASED ON THE CURRENT | | OPERATING MODE, THERE ARE NO OPERABILITY CONCERNS. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS EVENT NOTIFICATION. | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THE EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+