U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/13/96 - 12/16/96 ** EVENT NUMBERS ** 31354 31432 31445 31446 31447 31448 31449 31450 31451 31452 31453 31454 31455 31456 31457 31458 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31354 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 11/19/96 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 17:14 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/17/96 | +------------------------------------------------+EVENT TIME: 19:18[CST]| |NRC NOTIFIED BY: DAVID ERBE |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A SECURITY OFFICER DISCOVERED AN UNATTENDED PATROL VEHICLE WITH A WEAPON IN | | IT. AN INVENTORY REVEALED THAT ALL WEAPONS AND AMMUNITION WERE ACCOUNTED | | FOR. DISCUSSIONS WITH REGION 4 (SCHAEFER) LED THE LICENSEE TO MAKE THIS | | REPORT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. (REFER TO THE HOO LOG | | FOR ADDITIONAL INFORMATION.) | | | | * * * 1313 DECEMBER 13, 1996, UPDATE FROM JOHNSON RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. AFTER REVIEWING ALL | | AVAILABLE GUIDANCE, THE LICENSEE DETERMINED THAT THIS EVENT WAS LOGGABLE | | RATHER THAN ONE-HOUR REPORTABLE. THIS EVENT IS BEING LOGGED, AND THE | | LICENSEE DOES NOT INTEND TO ISSUE A FOLLOWUP WRITTEN REPORT. CORRECTIVE | | ACTION AND DISCIPLINARY ACTION HAVE BEEN TAKEN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND AN NRC REGIONAL | | SECURITY INSPECTOR (SCHAEFER). THE NRC OPERATIONS CENTER NOTIFIED THE R4DO | | (SANBORN). (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31432 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/11/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/10/96 | +------------------------------------------------+EVENT TIME: 21:08[CST]| |NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 12/14/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE MOTOR-OPERATED VALVES (MOV) MAY NOT BE CAPABLE OF OPENING AGAINST | | WORST CASE SYSTEM DIFFERENTIAL PRESSURE. | | | | DURING A REVIEW OF MOV CAPABILITY, THE LICENSEE DETERMINED THAT THREE | | DRYWELL SPRAY VALVES (3-1501-27B, 3-1501-28A, AND 3-1501-28B) MAY NOT BE | | ABLE TO OPEN AND/OR CLOSE AGAINST FULL PUMP SHUTOFF PRESSURE AND WORST CASE | | MOV PARAMETERS. MODIFICATIONS HAD BEEN PREVIOUSLY PREPARED FOR THESE | | VALVES FOR IMPLEMENTATION DURING THE REFUELING OUTAGE SCHEDULED FOR | | 04/26/97. THESE MODIFICATIONS MIGHT BE RESCHEDULED FOR THIS OUTAGE. | | | | THESE VALVES BECAME INOPERABLE AS A RESULT OF A CHANGE IN VALVE THRUST | | TESTING METHODOLOGY. THE UNIT 2 VALVES AND THE REMAINDER OF THE UNIT 3 | | VALVES HAVE SUFFICIENT OPERATING MARGIN USING THE ENHANCED METHODOLOGY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 12/14/96, @ 02:22 BY SLAGER TO GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. AFTER FURTHER REVIEW, THE LICENSEE | | HAS DETERMINED THAT THE SUBJECT VALVES WILL PERFORM THE REQUIRED SAFETY | | FUNCTIONS UNDER DESIGN BASIS CONDITIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. THE REGION 3 DUTY OFFICER | | (RING) WAS INFORMED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31445 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 12/13/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 04:19 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 02:35[EST]| |NRC NOTIFIED BY: JAMES HELM |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 11 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT TRIP WHILE SHUTTING DOWN DUE TO STEAM FLOW/FEED FLOW MISMATCH | | COINCIDENT WITH LOW STEAM GENERATOR LEVEL | | | | WHILE SHUTTING DOWN FOR MAINTENANCE, THE REACTOR TRIPPED DUE TO A STEAM | | FLOW/FEED FLOW MISMATCH COINCIDENT WITH LOW STEAM GENERATOR LEVEL IN THE | | 'A' STEAM GENERATOR. ONE OF TWO CHANNELS OF 'A' STEAM GENERATOR LEVEL WAS | | LESS THAN 20% NARROW RANGE WITH ONE OF TWO CHANNELS OF 'A' STEAM FLOW | | GREATER THAN FEED FLOW. STEAM GENERATOR LEVEL CONTROL WAS IN MANUAL AT THE | | TIME OF THE TRIP. FOUR INDIVIDUAL CONTROL ROD POSITION INDICATIONS WERE | | BETWEEN 10 AND 32 STEPS FOLLOWING THE TRIP; HOWEVER, ALL ROD BOTTOM LIGHTS | | WERE LIT. EMERGENCY BORATION WAS INITIATED AS A SAFETY PRECAUTION. | | AUXILIARY FEEDWATER INITIATED DUE TO LOW-LOW STEAM GENERATOR LEVEL AND | | REACTOR COOLANT SYSTEM PRIMARY TEMPERATURE DECREASED TO 539øF PRIOR TO | | RECOVERY TO 546øF. DECAY HEAT REMOVAL IS VIA THE MAIN CONDENSER. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1212 DECEMBER 13, 1996, UPDATE FROM WEBSTER RECEIVED BY TROCINE * * * | | | | FOLLOWING THE TRIP, HOT ROD DROP TESTING WAS PERFORMED IN ACCORDANCE WITH | | PROCEDURE 2-OPT-RX-014. ROD DROP TIMES WERE SATISFACTORY FOR ALL 48 RODS, | | AND ALL RECOIL RESPONSES WERE WITHIN ACCEPTABLE LIMITS. THE LICENSEE PLANS | | TO FURTHER EVALUATE INDIVIDUAL ROD POSITION INDICATIONS P-6, D-4, M-4, AND | | F-6 DURING THIS MAINTENANCE OUTAGE AND PLANS TO TAKE CORRECTIVE ACTIONS AS | | REQUIRED. THE P-6 ROD BOTTOM LIGHT WAS NOTED NOT TO ILLUMINATE DURING THE | | TRIP WITH INDICATION AT 18 STEPS. THE ROD BOTTOM LIGHT DID ILLUMINATE | | AFTER REMOVAL AND RE-INSTALLATION OF THE BISTABLE CONNECTOR DURING THE HOT | | ROD DROP TESTING. THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (WERT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31446 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 12/13/96 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 05:57 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 01:36[CST]| |NRC NOTIFIED BY: TIM GOLDEN |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRIP OF A VALVE POWER SUPPLY CAUSED NUMEROUS CONTAINMENT ISOLATION VALVES | | TO CLOSE. | | | | BREAKER 336 ON UNIT 3'S INSTRUMENT AND CONTROLS PANEL 9-9 TRIPPED WHILE | | SETTING VALVE LIMITS ON 3-FSV-84-8D (DIVISION 2 CONTAINMENT ATMOSPHERE | | DILUTION). THE LOSS OF POWER OCCURRED WHILE A TEMPORARY POWER SUPPLY | | TRANSFORMER WAS BEING CONNECTED. THE LOSS OF POWER ALSO AFFECTED DRYWELL | | HYDROGEN AND OXYGEN ANALYZER ISOLATION VALVES 3-FSV-76-49, 50, 55, 56, 57, | | 58, 59, 60, 65, 66, 67, AND 68. ALL OF THESE VALVES ARE PRIMARY | | CONTAINMENT ISOLATION VALVES WHICH WENT TO THEIR CLOSED FAIL-SAFE POSITIONS | | UPON DE-ENERGIZATION. VALVE MAINTENANCE WAS SUSPENDED WHILE THE LICENSEE | | DETERMINES THE CAUSE FOR THE LOSS OF POWER. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31447 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 12/13/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:51 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 10:20[EST]| |NRC NOTIFIED BY: JOHN BALLETTA |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG EO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |AUSTIN FEMA | | |STUART RUBIN, 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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED WHEN VAPOR FROM A TOLUENE SPILL IN AN OFFICE IN THE | | PROTECTED AREA CAUSED PERSONNEL EVACUATION. | | | | APPROXIMATELY ONE GALLON OF TOLUENE WAS SPILLED ONTO THE FLOOR IN AN OFFICE | | LOCATED IN THE PROTECTED AREA. THE SUBSEQUENT RELEASE OF TOXIC VAPOR | | CAUSED THE EVACUATION OF THE AREA AND THE DECLARATION OF AN UNUSUAL EVENT. | | AS A PRECAUTION THE CONTROL ROOM VENTILATION SYSTEM WAS PLACED INTO THE | | RECIRCULATION MODE OF OPERATION. A HAZMAT TEAM HAS CLEANED UP THE SPILL. | | THE LICENSEE EXPECTS TO TERMINATE THE UNUSUAL EVENT WHEN TOXIC VAPOR LEVELS | | RETURN TO SAFE VALUES AND WORK CAN BE RESUMED IN THE OFFICE. | | | | THE LICENSEE HAS NOTIFIED THE NEW YORK STATE WARNING POINT, THE FOUR | | SURROUNDING COUNTIES, AND THE NRC RESIDENT INSPECTOR. THE LICENSEE ALSO | | EXPECTS TO ISSUE A PRESS RELEASE. | | | | *** 1231 DECEMBER 13, 1996, UPDATE FROM BALLETTA RECEIVED BY S.SANDIN *** | | | | THE LICENSEE INDICATED THAT NEITHER THE DEPARTMENT OF TRANSPORTATION NOR | | THE COAST GUARD WILL BE NOTIFIED PER THE LICENSEE'S EMERGENCY PLAN. | | | | *** 1342 DECEMBER 13, 1996, UPDATE FROM BALLETTA RECEIVED BY TROCINE *** | | | | AIR MONITORING IS CURRENTLY ONGOING IN THE CENTRAL CONTROL ROOM AND | | OPERATING AREAS OF THE PLANT, AND MONITORING RESULTS HAVE INDICATED LESS | | THAN DETECTABLE CONCENTRATIONS OF TOLUENE. THE LICENSEE ALSO STATED THAT | | NO PREVIOUS ANALYSES IN THESE AREAS HAVE EVER MEASURED DETECTABLE | | CONCENTRATIONS OF TOLUENE. HOWEVER, THERE ARE STILL DETECTABLE | | CONCENTRATIONS OF TOLUENE IN THE OFFICE AREA WERE THE SPILL OCCURRED. THE | | OFFICE AREA IS CURRENTLY BEING MONITORED, AND THE LICENSEE PLANS TO REMAIN | | IN THE UNUSUAL EVENT UNTIL THE TOXIC VAPOR CONCENTRATIONS ARE SAFE FOR | | RE-ENTRY INTO THE AFFECTED OFFICE AREA. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND MADE ADDITIONAL | | NOTIFICATIONS TO THE DEPARTMENT OF ENVIRONMENTAL CONTROL, THE PUBLIC | | SERVICE COMMISSION, AND THE WEST CHESTER DEPARTMENT OF HEALTH. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (ROGGE) AND NRR EO (CHAFFEE). | | | | *** 1606 DECEMBER 13, 1996, UPDATE FROM BALLETTA RECEIVED BY TROCINE *** | | | | THE LICENSEE EXITED THE UNUSUAL EVENT AT 1530. WITHIN THE AFFECTED OFFICE | | BUILDING, THERE IS CURRENTLY ONLY ONE AREA OF APPROXIMATELY 100 SQUARE FEET | | WHICH REMAINS WITH ANY DETECTABLE TOLUENE CONCENTRATIONS, AND PERSONNEL | | ACCESS TO THIS AREA HAS BEEN RESTRICTED. | | | | THE LICENSEE NOTIFIED THE APPLICABLE STATE AND COUNTY AGENCIES AND PLANS TO | | NOTIFY THE NRC RESIDENT INSPECTOR. TWO PRESS RELEASES WERE ALSO ISSUED. | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (ROGGE), AEOD IRD (CONGEL), NRR | | EO (CHAFFEE), AND FEMA (RISHE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31448 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 12/13/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 12:43 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 09:13[EST]| |NRC NOTIFIED BY: MIKE WILLIAMS |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEN WERT 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED AN INVALID DIVISION I LOSS OF COOLANT ACCIDENT (LOCA) | | SIGNAL ATTRIBUTED TO PERSONNEL ERROR. | | | | AT 0913 ON 12/13/96, AN INVALID UNIT 1 DIVISION I LOCA SIGNAL WAS RECEIVED. | | THIS RESULTED IN THE FOLLOWING AUTOMATIC ACTIONS: | | | | - AUTOMATIC START OF DIESEL GENERATORS 1, 2, 3, AND 4; | | - AUTOMATIC START OF UNIT 1 CORE SPRAY PUMP 1A; | | - AUTOMATIC START OF UNIT 2 NUCLEAR SERVICE WATER PUMP 2A; | | - A UNIT 1 GROUP 10 DIVISION I ACTUATION (PNEUMATIC VALVES TO PRIMARY | | CONTAINMENT 1-RNA-SV-5261 AND 1-RNA-SV-5262 CLOSED.); AND | | - UNIT 1 1-SW-V106 (REACTOR BUILDING CLOSED COOLING WATER HEAT EXCHANGER | | SERVICE WATER INLET VALVE) CLOSED. | | | | THE INVALID LOCA SIGNAL WAS APPARENTLY DUE TO AN INSTRUMENTATION & CONTROL | | TECHNICIAN ATTEMPTING TO TAKE VOLTAGE READINGS WITH AN INSTRUMENT METER | | INCORRECTLY SET TO THE RESISTANCE SETTING. THIS RESULTED IN THE INVALID | | DIVISION I LOCA SIGNAL BEING TRANSMITTED. | | | | THE SAFETY SIGNIFICANCE OF THIS EVENT WAS MINIMAL. ALL SYSTEMS FUNCTIONED | | AS DESIGNED. ALL SYSTEMS HAVE BEEN RETURNED TO THEIR NORMAL STANDBY | | LINEUPS, AND ASSOCIATED WORK ACTIVITIES HAVE BEEN STOPPED PENDING FINAL | | INVESTIGATION RESULTS. NONE OF THE DIESEL GENERATORS TIED TO THEIR | | RESPECTIVE BUSES NOR WAS THERE ANY INJECTION TO THE VESSEL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31449 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 12/13/96 | | CITY: PITTSBURGH REGION: 1 |NOTIFICATION TIME: 14:22 [ET]| | COUNTY: STATE: PA |EVENT DATE: 12/13/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/13/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE, RVIB NRR | |NRC NOTIFIED BY: N. J. LIPARULO | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MOLDED CASE CIRCUIT BREAKERS WITH INCORRECTLY INSTALLED DC SHUNT TRIP UNITS | | AND MISSING SHUNT TRIP BARRIERS | | | | CALLAWAY IDENTIFIED A DEVIATION DURING TESTING OF 6 TYPE HFD3045 AND | | HFD3060 MOLDED CASE CIRCUIT BREAKERS WITH 125-VOLT DC SHUNT TRIP DEVICES | | SUPPLIED AS SAFETY-RELATED BY WESTINGHOUSE. THE SHUNT TRIP CIRCUITRY IS | | SPECIFIED TO BE EQUIPPED WITH A CUT-OFF SWITCH TO REMOVE THE SHUNT TRIP | | COIL FROM THE POWER SOURCE SUBSEQUENT TO TRIPPING THE BREAKER. THE COIL IS | | NOT DESIGNED FOR CONTINUOUS DUTY AND WOULD EVENTUALLY OPEN THE CIRCUIT IF | | IT REMAINED ENERGIZED. THE SHUNT TRIP COIL OF THE BREAKERS SUPPLIED TO | | CALLAWAY REMAINED CONNECTED TO THE POWER SOURCE AFTER THE BREAKER TRIPPED. | | IN ADDITION, DURING THE EVALUATION OF THE BREAKERS THAT WERE RETURNED FROM | | CALLAWAY, IT WAS DETERMINED THAT SHUNT TRIP BARRIERS WERE MISSING. THESE | | BARRIERS PROVIDE PROTECTION AGAINST DAMAGE DUE TO ARCING. THE VENDOR | | (CUTLER HAMMER) DETERMINED THAT 21 BREAKERS WITH EITHER AC OR DC SHUNT TRIP | | UNITS (INCLUDING THE 6 REFERENCED ABOVE) HAD BEEN SHIPPED ONLY TO THE | | CALLAWAY PLANT. SUBSEQUENT OPERABILITY OF THESE BREAKERS AFTER A TRIP HAS | | NOT YET BEEN DETERMINED BY CUTLER HAMMER. | | | | ALL SIX OF THE BREAKERS WITH INCORRECTLY INSTALLED DC SHUNT TRIP UNITS HAVE | | BEEN IDENTIFIED AND ARE IN THE PROCESS OF BEING RETURNED TO THE VENDOR. | | WESTINGHOUSE HAS ALSO BEEN INFORMED BY CALLAWAY THAT ONLY ONE BREAKER WITH | | A SUSPECT BARRIER IS IN SERVICE. CALLAWAY DOES NOT PLAN TO PLACE THE | | REMAINING FOURTEEN BREAKERS IN SERVICE UNTIL IT IS VERIFIED THAT THE SHUNT | | TRIP BARRIERS ARE INSTALLED. SINCE SUBSEQUENT OPERABILITY OF THE SHUNT | | TRIP UNITS WITH MISSING BARRIERS IS INDETERMINATE, CALLAWAY WILL BE ADVISED | | TO PERFORM A SURVEILLANCE TEST AFTER ANY BREAKER TRIP DEMAND UNTIL THE | | BREAKER CAN BE CORRECTED OR REPLACED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31450 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FARWELL & HENDRICKS |NOTIFICATION DATE: 12/13/96 | | CITY: CINCINATTI REGION: 3 |NOTIFICATION TIME: 15:08 [ET]| | COUNTY: STATE: OH |EVENT DATE: 12/13/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/13/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE, RVIB NRR | |NRC NOTIFIED BY: MARK D. McCLUNG | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR INCORRECT OPERATION (ARMATURE BINDING) OF SAFETY-RELATED | | GE-TYPE HGA RELAYS MANUFACTURED BETWEEN JANUARY 1989 AND JUNE 1991 BY GE | | ELECTRICAL DISTRIBUTION AND SUPPLIED BY GE NUCLEAR ENERGY | | | | FARWELL & HENDRICKS, INC., PROVIDED NOTIFICATION VIA FACSIMILE REGARDING | | INFORMATION RECEIVED FROM FLORIDA POWER & LIGHT CO. APPLICABLE TO | | SAFETY-RELATED GE-TYPE HGA RELAYS. BASED UPON THIS INFORMATION, FARWELL & | | HENDRICKS DETERMINED THAT TWO UTILITIES HAVE BEEN PROVIDED WITH DEDICATED | | RELAYS THAT ARE AFFECTED. RELAYS PROVIDED TO NORTHEAST NUCLEAR ENERGY CO. | | UNDER NORTHEAST UTILITIES PURCHASE ORDER #878067 AND RELAYS PROVIDED TO NEW | | YORK POWER AUTHORITY UNDER PURCHASE ORDER #C92J1798 WERE MANUFACTURED | | DURING THE TIME FRAME INDICATED. FARWELL & HENDRICKS PLANS TO NOTIFY THOSE | | UTILITIES IN ACCORDANCE WITH THE RESPECTIVE PROCUREMENT DOCUMENTS. | | | | INFORMATION REGARDING THE POTENTIAL FOR INCORRECT OPERATION OF THESE RELAYS | | WAS SENT BY GE NUCLEAR ENERGY LOCATED IN SAN JOSE, CALIFORNIA TO THE | | FOLLOWING COMPANIES ON NOVEMBER 5, 1996: CAROLINA POWER & LIGHT CO.; DTE | | ENERGY; ENTERGY OPERATIONS, INC.; FLORIDA POWER & LIGHT CO.; NEBRASKA | | PUBLIC POWER DISTRICT; PECO ENERGY CO.; SOUTHERN NUCLEAR OPERATING CO.; | | TENNESSEE VALLEY AUTHORITY; AND VERMONT YANKEE NUCLEAR POWER CORP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31451 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/13/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:41 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 15:25[EST]| |NRC NOTIFIED BY: PETER FARSACI |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 +------------------------------------------------------------------------------+ | POTENTIAL FOR WATER TRAPPED BETWEEN ISOLATION VALVES TO HEAT UP AND CAUSE | | PRESSURE IN THE PIPE TO EXCEED ALLOWABLE LIMITS DURING SPECIFIC ACCIDENT | | CONDITIONS (THIS AFFECTS THE CORE SPRAY SYSTEM HIGH POINT VENT LINES AND | | THE POST-ACCIDENT SAMPLE SYSTEM LINE INSIDE CONTAINMENT.) | | | | BASED UPON RESULTS OF PRELIMINARY ENGINEERING EVALUATIONS OF CORE SPRAY | | SYSTEM HIGH POINT VENT LINES AND THE POST-ACCIDENT SAMPLE SYSTEM LINE | | INSIDE CONTAINMENT, IT WAS DETERMINED THAT THE PLANT WAS OPERATED OUTSIDE | | THE DESIGN BASIS. THE EVALUATION WAS BEING PERFORMED AS A RESULT OF NRC | | GENERIC LETTER 96-06. | | | | THE PRELIMINARY EVALUATION INDICATED THAT DURING A DESIGN BASIS LOSS OF | | COOLANT ACCIDENT, WATER IN THESE LINES THAT IS TRAPPED BETWEEN THE | | ISOLATION VALVES WOULD HEAT UP AND EXPAND, POTENTIALLY CAUSING PRESSURE IN | | THE PIPE TO EXCEED ALLOWABLE STRESSES. THE SYSTEMS ARE CURRENTLY OPERABLE | | BECAUSE THE LINES WERE PARTIALLY DRAINED. THIS ALLOWS A VOLUME FOR HEATED | | WATER TO EXPAND WHICH PREVENTS AN OVERPRESSURE CONDITION. THE LICENSEE | | PLANS TO UTILIZE ADMINISTRATIVE CONTROLS TO ASSURE THAT THIS EXPANSION | | SPACE REMAINS AVAILABLE UNTIL FINAL DISPOSITION OF THIS ISSUE. THIS REPORT | | NOTIFICATION MAY BE RESCINDED BASED UPON THE FINAL ENGINEERING EVALUATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31452 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/13/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:06 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 17:45[CST]| |NRC NOTIFIED BY: MARK DEUTSCHER |LAST UPDATE DATE: 12/13/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INADEQUATE SYSTEM LOGIC FUNCTIONAL TEST FOR THE CONTROL ROOM VENT ISOLATION | | SYSTEM | | | | DURING ENGINEERING EVALUATION OF THE SYSTEM LOGIC FUNCTIONAL TEST FOR THE | | CONTROL ROOM VENT ISOLATION SYSTEM, SYSTEM ENGINEERING PERSONNEL DETERMINED | | THAT THE LOGIC TESTS THAT ARE PERFORMED DO NOT ADEQUATELY TEST THE COMPLETE | | LOGIC CIRCUIT. AS A RESULT, THE LICENSEE DECLARED THE CONTROL ROOM VENT | | ISOLATION SYSTEM INOPERABLE DUE TO THE MISSED SURVEILLANCE. PER TECHNICAL | | SPECIFICATION REQUIREMENT 4.0.C, THE LICENSEE ENTERED THE 24-HOUR CLOCK FOR | | TAKING THE ACTION REQUIREMENTS OF TECHNICAL SPECIFICATION 3.2.A-1. SYSTEM | | ENGINEERING PERSONNEL ARE CURRENTLY WRITING A PROCEDURE TO TEST THE LOGIC. | | IF THE 24-HOUR TIME FRAME IS NOT MET, THE ACTION STATEMENT REQUIRES THE | | LICENSEE TO ISOLATE CONTROL ROOM VENTILATION AND PLACE IT IN THE | | RECIRCULATION MODE OF OPERATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31453 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 12/14/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 03:34 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/14/96 | +------------------------------------------------+EVENT TIME: 01:47[CST]| |NRC NOTIFIED BY: POWELL |LAST UPDATE DATE: 12/14/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEN WERT 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 1 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE MANUALLY TRIPPED THE REACTOR FROM <1% (3E-8 COUNTS) DUE TO | | POSSIBLE ROD CONTROL PROBLEMS DURING PHYSICS TESTING. | | | | AN URGENT FAILURE SIGNAL WAS RECEIVED ON ROD CONTROL, AND THIS BASICALLY | | LOCKED UP THE LICENSEE'S ABILITY TO MOVE RODS. THE LICENSEE HAD SEVERAL | | QUESTIONS AND CONCERNS ABOUT THE ROD CONTROL SYSTEM; SO AS A CONSERVATIVE | | MEASURE, THE REACTOR WAS MANUALLY TRIPPED IN ORDER TO TROUBLESHOOT THE ROD | | CONTROL PROBLEM. THE CAUSE WAS UNKNOWN AT TIME OF THIS REPORT, AND IT IS | | BEING INVESTIGATED. ALL RODS WERE FULLY INSERTED, NO SAFETY RELIEF VALVES | | LIFTED, AND NO EMERGENCY CORE COOLING SYSTEM INJECTIONS OCCURRED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31454 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/14/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/14/96 | +------------------------------------------------+EVENT TIME: 08:40[EST]| |NRC NOTIFIED BY: ROBERTSON |LAST UPDATE DATE: 12/14/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE COAST GUARD AND THE NEW JERSEY DEPARTMENT OF | | ENVIRONMENTAL PROTECTION OF OIL LEAKAGE ON SITE THAT WAS DISCHARGED TO THE | | DELAWARE RIVER. | | | | THIS OCCURRED WHEN A SECONDARY CONTAINING DEVICE UTILIZED TO CATCH OIL | | LEAKAGE FROM A PORTABLE DIESEL GENERATOR OVERFLOWED DUE TO EXCESSIVE | | RAINFALL. THIS CONDITION CAUSED A VISIBLE SHEEN OF OIL TO TRAVEL TO A | | STORM DRAIN WHICH ULTIMATELY DISCHARGED TO THE DELAWARE RIVER. IT IS | | ESTIMATED THAT THE QUANTITY OF OIL IS LESS THAN ONE GALLON. LEAKAGE TO THE | | STORM DRAIN HAS BEEN TERMINATED, AND THE AREA AROUND THE DIESEL IS BEING | | CLEANED. ALL OTHER SECONDARY CONTAINMENT DEVISES OUTSIDE ARE BEING | | CHECKED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31455 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 12/14/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 14:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/13/96 | +------------------------------------------------+EVENT TIME: 15:25[CST]| |NRC NOTIFIED BY: TIM BOWMAN |LAST UPDATE DATE: 12/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |NLTR LICENSEE 24 HR REPORT | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE TO MAINTAIN AN OPERABLE PERSONNEL AIRLOCK DOOR CLOSED AND LOCKED | | WHILE THE OTHER PERSONNEL AIRLOCK DOOR WAS INOPERABLE | | | | AT 0830 CST ON DECEMBER 14, 1996, IT WAS DISCOVERED THAT THE REQUIREMENT OF | | TECHNICAL SPECIFICATION 3.6.1.3, ACTION A.1, TO MAINTAIN THE OPERABLE | | PERSONNEL AIRLOCK DOOR CLOSED AND LOCKED WITH AN INOPERABLE PERSONNEL | | AIRLOCK DOOR HAD BEEN VIOLATED ON DECEMBER 13, 1996, BETWEEN 1525 CST AND | | 1553 CST. THE REACTOR CONTAINMENT BUILDING SIDE PERSONNEL AIRLOCK DOOR HAD | | BEEN DECLARED OPERABLE AT 1321 CST ON DECEMBER 13, 1996, FOLLOWING | | REPLACEMENT OF THE AIRLOCK SIDE SEAL OF THE REACTOR BUILDING SIDE PERSONNEL | | AIRLOCK DOOR. EACH PERSONNEL AIRLOCK DOOR HAS TWO SEALS (ONE ON THE | | AIRLOCK SIDE AND ONE ON THE BUILDING SIDE). THE MECHANICAL AUXILIARY | | BUILDING SIDE DOOR OF THE PERSONNEL AIRLOCK HAD BEEN CLOSED AND LOCKED TO | | COMPLY WITH TECHNICAL SPECIFICATION 3.6.1.3, ACTION A.1, WHILE THE REACTOR | | CONTAINMENT BUILDING SIDE PERSONNEL AIRLOCK DOOR WAS INOPERABLE. AT 1525 | | CST ON DECEMBER 13, 1996, THE MECHANICAL AUXILIARY BUILDING SIDE PERSONNEL | | AIRLOCK DOOR WAS UNLOCKED AND OPENED TO ALLOW REMOVAL OF EQUIPMENT FROM THE | | REACTOR CONTAINMENT BUILDING. AT 1553 CST ON DECEMBER 13, 1996, THE | | REACTOR CONTAINMENT BUILDING SIDE PERSONNEL AIRLOCK DOOR SEALS FAILED A | | PERIODIC LOCAL LEAK RATE TEST THAT VERIFIES THE INTEGRITY OF THE DOOR | | SEALS. THE REACTOR CONTAINMENT BUILDING SIDE DOOR WAS DECLARED INOPERABLE | | AT 1553 CST, AND THE MECHANICAL AUXILIARY BUILDING SIDE DOOR WAS CLOSED AND | | LOCKED TO COMPLY WITH TECHNICAL SPECIFICATION 3.6.1.3, ACTION A.1. | | | | THE REACTOR CONTAINMENT BUILDING SIDE PERSONNEL AIRLOCK DOOR WAS | | TECHNICALLY INOPERABLE FROM 1321 TO 1553 CST ON DECEMBER 13, 1996. THE | | UNLOCKING AND OPENING OF THE MECHANICAL AUXILIARY BUILDING PERSONNEL | | AIRLOCK DOOR AT 1525 CST ON DECEMBER 13, 1996, VIOLATED TECHNICAL | | SPECIFICATION 3.6.1.3, ACTION A.1. THIS INCIDENT IS A VIOLATION OF | | OPERATING LICENSE NPF-76, SECTION 2.G. | | | | THE LOCAL LEAK RATE TEST FOR THE REACTOR CONTAINMENT BUILDING SIDE | | PERSONNEL AIRLOCK DOOR SEALS HAD NOT BEEN PERFORMED PRIOR TO DECLARING THE | | COMPONENT OPERABLE. HOWEVER, THE REACTOR CONTAINMENT SIDE SEAL OF THE | | REACTOR CONTAINMENT BUILDING PERSONNEL AIRLOCK DOOR HAD NOT BEEN SUBJECTED | | TO MAINTENANCE, AND IT HAD PASSED LOCAL LEAK RATE TESTING PERFORMED ON | | DECEMBER 9, 1996. THEREFORE, AT LEAST ONE SEAL ON THE REACTOR CONTAINMENT | | BUILDING SIDE WAS FUNCTIONAL BETWEEN 1525 CST AND 1553 CST ON DECEMBER 13, | | 1996. THE AIRLOCK SIDE SEAL WAS REPAIRED, PASSED OPERABILITY TESTING, AND | | IS EXPECTED TO BE DECLARED OPERABLE WITHIN ONE HOUR OF THIS EVENT | | NOTIFICATION. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31456 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 12/15/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 01:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/15/96 | +------------------------------------------------+EVENT TIME: 00:59[EST]| |NRC NOTIFIED BY: KLEVORN |LAST UPDATE DATE: 12/15/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 33 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR WAS MANUALLY SCRAMMED FROM 33% POWER DUE TO ELECTROHYDRAULIC | | CONTROL (EHC) FLUID LEAK INDICATIONS. | | | | THIS OCCURRED WHILE THE PLANT WAS INCREASING POWER FOLLOWING A REFUELING | | OUTAGE. A MANUAL SCRAM WAS INSERTED BY OPERATORS AFTER THEY HAD RECEIVED A | | REPORT OF AN EHC FLUID LEAK (<100 GALLONS). ALL RODS FULLY INSERTED, AND | | NO EMERGENCY CORE COOLING SYSTEMS ACTUATED. AT THE TIME OF THIS REPORT, | | THE LICENSEE WAS NOT SURE IF ANY SAFETY RELIEF VALVES HAD LIFTED. THE | | CAUSE OF THE EHC LEAKAGE IS UNKNOWN AND WILL BE INVESTIGATED. ALL SYSTEMS | | APPEAR TO HAVE FUNCTIONED AS DESIGNED. THE MAIN STEAM ISOLATION VALVES ARE | | OPEN, AND THEY ARE CONTROLLING STEAM LOADS TO CONTROL REACTOR PRESSURE. A | | REACTOR FEEDWATER PUMP IS BEING USED TO CONTROL REACTOR LEVEL, AND THE HEAT | | SINK IS THE CONDENSER. AT THIS TIME, THE LICENSEE DOES NOT KNOW THE VOLUME | | OF EHC FLUID THAT DISCHARGED TO THE PLANT FLOOR DRAINS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31457 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 12/15/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 04:38 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/15/96 | +------------------------------------------------+EVENT TIME: 02:19[CST]| |NRC NOTIFIED BY: JACOBSON |LAST UPDATE DATE: 12/15/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |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 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENTRY INTO A 14-DAY TECHNICAL SPECIFICATION LIMITING CONDITION FOR | | OPERATION (LCO) ACTION STATEMENT DUE TO ISOLATION OF THE REACTOR CORE | | ISOLATION COOLING (RCIC) TURBINE STEAM SUPPLY | | | | THIS OCCURRED WHILE INSTRUMENTATION & CONTROL TECHNICIANS WERE PERFORMING | | RESIDUAL HEAT REMOVAL (RHR) AREA HIGH TEMPERATURE CALIBRATIONS. DURING | | THIS TEST, A STEP REQUIRING TWO LEADS BE LIFTED WAS PERFORMED INCORRECTLY | | WHEN ONLY ONE LEAD WAS LIFTED. THIS RESULTED IN THE CLOSURE OF THE RCIC | | TURBINE STEAM SUPPLY VALVE WHEN RHR WAS RETURNED FROM BYPASS TO NORMAL. | | WITH RCIC INOPERABLE, THE PLANT ENTERED A 14-DAY LCO WHICH REQUIRES | | IMMEDIATE OPERABILITY VERIFICATION OF HIGH PRESSURE CORE SPRAY (HPCS) | | SYSTEM AND THE RETURN OF RCIC TO SERVICE WITHIN 14 DAYS. HPCS WAS VERIFIED | | TO BE OPERABLE, AND RCIC WAS RETURNED TO SERVICE WITHIN 56 MINUTES. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31458 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 12/15/96 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 23:40 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/15/96 | +------------------------------------------------+EVENT TIME: 22:24[CST]| |NRC NOTIFIED BY: SHANE FERGUSON |LAST UPDATE DATE: 12/15/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A DEATH AND TWO MISSING INDIVIDUALS IN THE | | LICENSEE'S OWNER CONTROLLED AREA | | | | WOLF CREEK LAKE IS LOCATED OUTSIDE THE SITE'S PROTECTED AREA BUT INSIDE THE | | LICENSEE'S OWNER CONTROLLED AREA. THE LICENSEE CURRENTLY ALLOWS THE PUBLIC | | TO UTILIZE WOLF CREEK LAKE, WHICH SUPPLIES THE UNIT'S COOLING WATER, FOR | | RECREATION; AND MEMBERS OF THE PUBLIC ARE REQUIRED TO CHECK IN AND OUT AT | | THE FISHING ACCESS FACILITY BOTH BEFORE AND AFTER USE OF THE LAKE. | | | | APPARENTLY, THREE INDIVIDUALS WITH A FISHING BOAT HAD CHECKED IN TODAY BUT | | DID NOT CHECK OUT AT SUNDOWN. A TRUCK AND BOAT TRAILER ALSO REMAINED IN | | THE PARKING LOT. THE LICENSEE INITIATED A SEARCH OF THE LAKE, AND FOUND | | DEBRIS FROM A BOAT AND A BODY FLOATING IN THE LAKE AT 2224 CST. THE DEBRIS | | WAS SPREAD OUT OVER A DISTANCE OF GREATER THAN 100 YARDS ALONG THE SHORE | | LINE. THE INDIVIDUAL WAS WEARING A LIFE JACKET AND IS BELIEVED TO HAVE | | DIED FROM EXPOSURE. AT THE TIME OF THIS NOTIFICATION, THE REMAINING TWO | | INDIVIDUALS AND THE BOAT HAD YET NOT BEEN FOUND. THE LICENSEE BELIEVES | | THAT THE BOAT MAY HAVE CAPSIZED BECAUSE IT WAS VERY WINDY EARLIER TODAY. | | THE CURRENT WATER TEMPERATURE IS 44øF, AND THE CURRENT AIR TEMPERATURE IS | | 29øF. THE LICENSEE IS CONTINUING ITS SEARCH FOR THE MISSING INDIVIDUALS. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND THE COUNTY, AND | | THE COUNTY IS ASSISTING THE LICENSEE WITH THE SEARCH. THE LICENSEE ALSO | | PLANS TO NOTIFY THE STATE AND TO ISSUE A PRESS RELEASE. THE R4DO (HOWELL) | | PLANS TO NOTIFY THE REGION 4 PUBLIC AFFAIRS OFFICE. | +------------------------------------------------------------------------------+