U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/20/96 - 08/21/96 ** EVENT NUMBERS ** 30896 30897 30898 30899 30900 30901 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30896 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/20/96 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 09:25 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 08/20/96 | +------------------------------------------------+EVENT TIME: 08:30[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 08/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LETDOWN STORAGE TANK (LDST) LEVEL INSTRUMENT CALIBRATION ERRORS COULD HAVE | | LED TO THE HIGH PRESSURE INJECTION (HPI) PUMP BECOMING HYDROGEN BOUND | | DURING AN EMERGENCY CORE COOLING SYSTEM (ECCS) ACTUATION. | | | | THE LICENSEE DISCOVERED THAT UNCERTAINTY IN THE CALIBRATION ACCURACY FOR | | THE LDST LEVEL INSTRUMENTS WAS LARGER THAN PREVIOUSLY ASSUMED. UNDER | | ACCIDENT CONDITIONS REQUIRING HIGH PRESSURE INJECTION TOO LOW OF A LEVEL IN | | THE LDST COULD CAUSE THE HYDROGEN COVER GAS FROM THE LDST TO BE DRAWN INTO | | THE HPI PUMPS. THIS COULD GAS BIND THE PUMPS RENDERING THEM INOPERABLE. | | | | THE LICENSEE DETERMINED THAT THE INSTRUMENTATION AS PRESENTLY CALIBRATED | | DOES NOT COMPROMISE ECCS OPERABILITY. HOWEVER, A REVIEW OF HISTORICAL | | RECORDS DETERMINED THAT IN THE PAST IN THREE INSTANCES ON UNIT 1, TWO | | INSTANCES ON UNIT 2, AND ONE INSTANCE ON UNIT 3, THE HPI PUMPS COULD HAVE | | BECOME HYDROGEN BOUND DURING AN ECCS ACTUATION. DUE TO THE DOUBT | | SURROUNDING PAST OPERABILITY OF THE HPI SYSTEM THE LICENSEE IS SUBMITTING | | THIS REPORT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30897 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/20/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 16:08 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/20/96 | +------------------------------------------------+EVENT TIME: 15:52[EDT]| |NRC NOTIFIED BY: MARTIN |LAST UPDATE DATE: 08/20/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED FOULING OF THE 'A' CONTAINMENT RECIRCULATION SPRAY | | SYSTEM (RSS) HEAT EXCHANGERS THAT COULD HAVE ADVERSELY AFFECTED | | PERFORMANCE. | | | | THE LICENSEE DISCOVERED MUSSELS AND ARCOR CHIPS IN THE FRONT OF THE 'A' RSS | | HEAT EXCHANGERS. (ARCOR IS A MATERIAL USED TO PROTECT SYSTEM PIPING.) THE | | LICENSEE HAS EVALUATED THE POTENTIAL FOR FOULING OF THE HEAT EXCHANGERS DUE | | TO THE ACCUMULATION OF THESE MATERIALS, AND HAS DETERMINED THAT SYSTEM | | PERFORMANCE COULD HAVE BEEN UNACCEPTABLY DEGRADED. THE 'B' TRAIN HEAT | | EXCHANGERS WERE ALSO INSPECTED, BUT NO FOULING WAS OBSERVED. THE LICENSEE | | BELIEVES THAT THE FOULING WAS A RESULT OF SYSTEM TESTING PERFORMED IN JULY | | IN WHICH TWO SERVICE WATER PUMPS WERE ALIGNED TO THE TRAIN AND FLOW WAS | | INCREASED TO MAXIMUM. THE LICENSEE HAS CLEANED THE HEAT EXCHANGERS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30898 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 08/20/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 08/20/96 | +------------------------------------------------+EVENT TIME: 14:43[EDT]| |NRC NOTIFIED BY: SENSENBACH |LAST UPDATE DATE: 08/20/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 100% POWER DUE TO CLOSURE OF 'B' MAIN FEED REG VALVE | | | | WITH THE UNIT OPERATING AT FULL POWER, THE 'B' MAIN FEEDWATER REGULATING | | VALVE FAILED CLOSED. THIS RESULTED IN AN AUTOMATIC REACTOR TRIP ON 'B' | | STEAM GENERATOR LOW LEVEL (2 OF 3 CHANNELS < 17%). ALL CONTROL RODS | | INSERTED FOLLOWING THE TRIP. THE MOTOR DRIVEN AND TURBINE DRIVEN AUXILIARY | | FEEDWATER PUMPS AUTOMATICALLY STARTED, AND ARE SUPPLYING WATER TO THE STEAM | | GENERATORS. NO PRIMARY OR SECONDARY RELIEF VALVES LIFTED. THE PLANT IS | | STABLE IN MODE 3. | | | | THE FEED REG VALVE FAILURE WAS CAUSED BY THE LOSS OF ELECTRICAL CONTINUITY | | IN A CIRCUIT IN THE I/P (CURRENT TO PNEUMATIC) CONVERTER WHICH OCCURRED | | WHEN A TERMINAL SCREW BACKED OUT. THE LICENSEE REPORTED THAT THE SOURCE | | RANGE DETECTORS WERE MANUALLY REINITIATED AFTER ONE INTERMEDIATE RANGE | | CHANNEL STABILIZED ABOVE THE REINITIATION SETPOINT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30899 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 08/20/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 18:14 [ET]| |RX TYPE: [3] CE |EVENT DATE: 07/26/96 | +------------------------------------------------+EVENT TIME: 17:57[CDT]| |NRC NOTIFIED BY: KULLMANN |LAST UPDATE DATE: 08/20/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SANBORN 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 COLD SHUTDOWN | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION SYSTEM ISOLATION VALVES LEAK EXCESSIVELY | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "THE CONTROL ROOM HVAC SYSTEM AT WATERFORD 3 IS DESIGNED TO MAINTAIN THE | | CONTROL ROOM IN A SAFE CONDITION FOLLOWING AN ACCIDENT AS REQUIRED BY | | GENERAL DESIGN CRITERION 19 OF APPENDIX A TO 10 CFR 50 AND AS SPECIFIED IN | | THE STANDARD REVIEW PLAN (SECTION 6.4). DURING TESTING OF THE CONTROL ROOM | | HVAC, IT WAS DETERMINED THAT THE CONTROL ROOM NORMAL VENTILATION ISOLATION | | VALVES (HVC-101, HVC 102) LEAK BY WHEN THE EMERGENCY FILTRATION SYSTEM IS | | IN SERVICE. PAST TESTING INVOLVED GIVING A CLOSE SIGNAL TO BOTH VALVES IN | | WHICH BOTH VALVES HAVE ALWAYS CLOSED. DURING THIS TESTING, WITH BOTH VALVES | | CLOSED, THE LEAKAGE WAS WITHIN ACCEPTABLE LIMITS. HOWEVER, WHEN THE VALVES | | WERE TESTED INDIVIDUALLY, THE IDENTIFIED LEAKAGE MAY HAVE ALLOWED AN | | UNACCEPTABLE AMOUNT OF UNFILTERED AIR INTO THE CONTROL ROOM ENVELOPE | | FOLLOWING A DESIGN BASIS ACCIDENT. A PRELIMINARY EVALUATION PERFORMED BY | | WATERFORD 3 PERSONNEL INDICATES THAT THE THYROID DOSE CRITERIA SPECIFIED IN | | THE STANDARD REVIEW PLAN MAY HAVE BEEN EXCEEDED BY APPROXIMATELY 5 REM | | FOLLOWING A DESIGN BASIS ACCIDENT. THE LINE CONTAINING HVC-101 AND HVC-102 | | HAS SUBSEQUENTLY BEEN ISOLATED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30900 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/20/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 19:54 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/20/96 | +------------------------------------------------+EVENT TIME: 18:08[EDT]| |NRC NOTIFIED BY: SAUER |LAST UPDATE DATE: 08/20/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES 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 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT FAN COOLERS MAY NOT RECEIVE SUFFICIENT SERVICE WATER FLOW | | | | THE FOLLOWING IS TEST OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "DURING A LICENSING BASIS REVIEW OF THE CONTAINMENT FAN COIL UNIT (CFCU) | | PERFORMANCE, ENGINEERING PERSONNEL DISCOVERED THAT BOTH OF THE SALEM UNITS | | HAD THE POTENTIAL TO OPERATE OUTSIDE THEIR DESIGN BASIS. THIS CONDITION | | RESULTED FROM FAILURE TO PROPERLY EVALUATE THE EFFECT OF THE MOTOR-OPERATED | | VALVE TIME RESPONSE FOR ISOLATION TO THE NONSAFETY-RELATED TURBINE LOADS. | | SPECIFICALLY, THE ISOLATION VALVES FOR THE TURBINE HEADER DO NOT START TO | | CLOSE UNTIL APPROXIMATELY THIRTY SECONDS INTO THE EMERGENCY LOADING | | SEQUENCE TO ACCOMMODATE WATER HAMMER CONCERNS. AS A RESULT OF THIS DELAY, | | THE SERVICE WATER SYSTEM MAY NOT HAVE PROVIDED ADEQUATE SERVICE WATER | | PRESSURE TO SUPPLY THE MINIMUM COOLING WATER FLOW FOR THE CONTAINMENT | | COOLING FUNCTION. THE TWO CONTAINMENT SPRAY PUMPS ALSO PROVIDE CONTAINMENT | | COOLING DURING DESIGN BASIS EVENTS. PRELIMINARY ANALYSIS HAD INDICATED THAT | | THE CFCU FLOW RATES WOULD BE SUPPORTED WITH THE TURBINE ISOLATION VALVES | | FULL OPENED. HOWEVER, THE MORE DETAILED ANALYSIS DETERMINED THAT THE HEAT | | TRANSFER RATES COULD CAUSE ADDITIONAL FLOW RESTRICTIONS IN THE TUBES AND | | DECREASE THE AVAILABLE FLOW THROUGH THE CFCUs." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30901 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/20/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 20:05 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/20/96 | +------------------------------------------------+EVENT TIME: 19:20[EDT]| |NRC NOTIFIED BY: DONG |LAST UPDATE DATE: 08/20/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED NEW YORK STATE REGARDING TRANSFORMER OIL LEAK ONSITE. | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION REGARDING THE LEAKAGE OF DIELECTRIC INSULATING OIL FROM THE | | OIL SUPPLY LINE AND LEADS FROM ALL PHASES OF FEEDER 33332 L & M (A CONED | | 138kV UNDERGROUND FEEDER ON NYPA PROPERTY). THE LEAKS ARE ABOVE GROUND AND | | THE LICENSEE ESTIMATES THE TOTAL LEAKAGE TO BE APPROXIMATELY 1 ml/MIN. THE | | LICENSEE CONSIDERS THE OIL TO BE PCB-FREE (GROUND SAMPLES HAVE BEEN TAKEN | | FOR ANALYSIS). THE LICENSEE HAS CONTAINED THE LEAK. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+