U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/07/97 - 05/08/97 ** EVENT NUMBERS ** 32283 32286 32288 32289 32290 32291 32292 32293 32294 32295 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/06/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:37 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 13:25[EDT]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TRAPP RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAN COOLER UNIT VALVES AUTOMATICALLY REALIGNED TO INCIDENT MODE | | | | WHILE TESTING THE PLACEMENT OF A JUMPER ON THE INSTRUMENT AIR SYSTEM IN | | PREPARATION FOR PERFORMANCE OF A SURVEILLANCE TEST, VALVES FOR THE FIVE FAN | | COOLER UNITS AUTOMATICALLY SWAPPED INTO INCIDENT MODE. FOUR OF THE FAN | | COOLERS ARE CURRENTLY SHUT DOWN, AND THE SERVICE WATER SUPPLY TO ALL FAN | | COOLERS IS CLOSED OFF DUE TO THE OUTAGE. AFTER CONFIRMING THE CAUSE OF THE | | REALIGNMENT, TECHNICIANS RESUPPLIED INSTRUMENT AIR TO THE VALVES RETURNING | | THEM TO THEIR INITIAL POSITIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1536 ON 05/07/97, FROM CORNAX TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. BASED UPON REVIEW OF GUIDANCE | | CONTAINED IN NUREG-1022, THE LICENSEE HAS DETERMINED THAT THIS EVENT IS NOT | | REPORTABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (TRAPP). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32286 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/06/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 21:05 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 16:30[CDT]| |NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED | | |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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNISOLABLE LEAK FOUND ON REACTOR RECIRCULATION SYSTEM. | | | | DURING A DRYWELL ENTRY MADE TO IDENTIFY THE SOURCE OF LEAKAGE INSIDE THE | | CONTAINMENT, THE LICENSEE DISCOVERED A CRACKED WELD ON A VENT VALVE FOR THE | | 'B' REACTOR RECIRCULATION FLOW CONTROL VALVE (FCV). THE CRACK IS LOCATED | | AT THE POINT WHERE THE HIGH POINT VENT VALVE ATTACHES TO A PIECE OF 3/4" | | PIPING AT THE TOP OF THE FCV. THE LICENSEE CONSIDERS THIS LEAK TO BE | | UNISOLABLE DUE TO EXCESSIVE LEAKAGE PAST THE 20" DIAMETER ISOLATION VALVES | | FOR THE 'B' RECIRCULATION LOOP. THE LICENSEE REPORTED THAT TOTAL | | UNIDENTIFIED DRYWELL LEAKAGE IS CURRENTLY 2 GALLONS PER MINUTE (GPM). THE | | LICENSEE INTENDS TO REPAIR THE WELD BEFORE UNIT STARTUP. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * 1033 EDT MAY 7, 1997, UPDATE FROM DAWSON RECEIVED BY TROCINE * * * | | | | AT 0900 CDT ON MAY 7, 1997, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO | | THE PRIMARY SYSTEM LEAK RATE EXCEEDING THE TECHNICAL SPECIFICATION | | REQUIREMENTS BASED UPON THE VERIFICATION OF REACTOR COOLANT SYSTEM PRESSURE | | BOUNDARY LEAKAGE. THE TECHNICAL SPECIFICATION LIMIT IS ZERO PRESSURE | | BOUNDARY LEAKAGE, AND THE CURRENT LEAK RATE IS 0.36 GPM. | | | | THE UNIT IS CURRENTLY IN HOT SHUTDOWN FOLLOWING A REACTOR SCRAM DUE TO | | UNRELATED EVENTS. (REFER TO EVENT #32282 FOR ADDITIONAL INFORMATION.) AT | | THIS TIME, REACTOR COOLANT SYSTEM PRESSURE IS 25 PSIG, AND REACTOR COOLANT | | SYSTEM TEMPERATURE IS 260øF. | | | | THE LICENSEE PLANS TO TERMINATE THE UNUSUAL EVENT WHEN THE UNIT ENTERS COLD | | SHUTDOWN. THIS IS CURRENTLY EXPECTED TO OCCUR WITHIN THE NEXT FEW HOURS. | | AT THIS TIME, THE LICENSEE PLANS TO PERFORM A SIX TO SEVEN-DAY FORCED | | OUTAGE IN ORDER TO REPAIR THE LEAK. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. THE NRC OPERATIONS CENTER NOTIFIED THE R4DO (TAPIA), | | AEOD IRD (CONGEL), NRR EO (GOODWIN), AND FEMA (WRIGHT). | | | | * * * 1450 EDT MAY 7, 1997, UPDATE FROM DAWSON TO GOULD * * * | | | | THE NOTIFICATION OF UNUSUAL EVENT WAS TERMINATED AT 1344 CDT DUE TO THE | | PLANT ENTERING COLD SHUTDOWN. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R4DO (HARRELL), NRR EO (CHAFFEE), AND FEMA | | (WRIGHT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32288 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 00:13 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 23:00[CDT]| |NRC NOTIFIED BY: STEVE GORTON |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED INOPERABLE | | (BUT AVAILABLE) DUE TO A 250-VOLT DC MOTOR CONTROL CENTER UNDERVOLTAGE | | ALARM FOR UNKNOWN REASONS. (REFER TO EVENT #32295 FOR ADDITIONAL | | INFORMATION.) | | | | THE RCIC 250-VOLT DC MOTOR CONTROL CENTER UNDERVOLTAGE ALARM WAS RECEIVED | | IN THE CONTROL ROOM AT 2205 CDT. UPON INVESTIGATION, NO READILY APPARENT | | CAUSE WAS FOUND. WITH NO UNDERVOLTAGE ALARM AVAILABLE, FOUR 250-VOLT DC | | BREAKERS ARE AFFECTED. AS A RESULT, THE LICENSEE DECLARED THE RCIC SYSTEM | | INOPERABLE (BUT AVAILABLE) AT 2300 CDT, AND A 14-DAY LIMITING CONDITION FOR | | OPERATION WAS ENTERED. THE LICENSEE'S INVESTIGATION IS CURRENTLY ONGOING. | | ALL EMERGENCY CORE COOLING SYSTEMS ARE CURRENTLY OPERABLE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32289 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 03:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 22:48[CDT]| |NRC NOTIFIED BY: JOHN MYERS |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO AUTOMATIC SCRAMS WITH NO ROD MOTION; GROUP 2, 3, AND 6 ISOLATIONS; AND | | TEMPORARY LOSS OF SHUTDOWN COOLING DUE TO A FALSE INDICATION OF LOW WATER | | LEVEL | | | | AT 2248 CDT ON MAY 6, 1997, A FULL SCRAM AND GROUP 2 (SHUTDOWN COOLING AND | | DRYWELL), 3 (REACTOR WATER CLEANUP), AND 6 (SECONDARY CONTAINMENT AND | | STANDBY GAS TREATMENT) ISOLATIONS OCCURRED DUE TO AN APPARENT LOW WATER | | LEVEL SIGNAL. AT THE TIME, THE PLANT WAS SHUTDOWN FOR A REFUELING OUTAGE | | WHICH BEGAN ON MARCH 29, 1997 (39 DAYS AGO). THERE WAS NO CONTROL ROD | | MOVEMENT BECAUSE THE CONTROL RODS WERE ALREADY INSERTED. THE GROUP 2 | | ISOLATION RESULTED IN THE LOSS OF SHUTDOWN COOLING. REACTOR WATER | | TEMPERATURE AT THE TIME OF THE EVENT WAS 104øF WITH A CONSERVATIVE | | ESTIMATED TIME TO BOILING OF 7 HOURS PER THE LOSS OF SHUTDOWN COOLING | | PROCEDURE. THE REACTOR VESSEL WAS RE-ASSEMBLED WITH THE HEAD INSTALLED AND | | TENSIONED. WATER LEVEL AT THE TIME OF THE EVENT WAS APPROXIMATELY 185 | | INCHES (BETWEEN THE MAIN STEAM LINES AND THE VESSEL FLANGE). | | | | THE SCRAM INSTRUMENTS WERE RETURNED TO SERVICE AT 0041 CDT ON MAY 7, 1997, | | AND THE GROUP 2 ISOLATION WAS RESET AT 0109 CDT. REACTOR WATER TEMPERATURE | | WAS 123øF AT THE TIME SHUTDOWN COOLING WAS RESTORED TO SERVICE INDICATING A | | HEATUP RATE OF 6øF PER HOUR. | | | | THE LICENSEE BELIEVES THAT THE LOW WATER LEVEL SIGNAL WAS THE APPARENT | | RESULT OF AIR INTRODUCED INTO THE LEVEL INSTRUMENT VARIABLE LEG BY THE AIR | | LOADING ON THE FLOODUP INSTRUMENT. THE AIR LOADING ALLOWS INSTALLED LEVEL | | INDICATION TO BE USED FOR FLOODUP FOR REFUELING. AT THE TIME OF THE EVENT, | | INSTRUMENTATION AND CONTROL (I&C) PERSONNEL WERE BACKFILLING THE REFERENCE | | LEG AS PART OF THE PROCESS OF REMOVING THE AIR LOADING DURING DRAIN DOWN OF | | THE REACTOR VESSEL. THE PROCESS USED FOR THE BACKFILLING ALLOWED AIR TO BE | | DISPERSED THROUGH THE LEVEL INSTRUMENTS RESULTING IN A FALSE INDICATION OF | | LOW LEVEL. I&C PERSONNEL HAVE FLUSHED THE INSTRUMENT LEGS TO REMOVE THE | | ENTRAINED AIR AND RESTORE THE INSTRUMENTS TO SERVICE. DURING THIS FLUSHING | | PROCESS, A SECOND REACTOR SCRAM OCCURRED AT 0051 CDT ON MAY 7, 1997 (PRIOR | | TO THE RESTORATION OF SHUTDOWN COOLING). | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32290 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 11:50 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 17:10[EDT]| |NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEW HAMPSHIRE PUBLIC UTILITIES COMMISSION OF A | | PERSONNEL INJURY. | | | | THE INJURY OCCURRED AT APPROXIMATELY 1700 WHEN 2 MECHANICS WERE CARRYING A | | 120-POUND STEEL BEAM 20 FEET IN THE UNIT 2 CONTAINMENT BUILDING. (UNIT 2 | | IS A NON-OPERATING FACILITY THAT WAS ABANDONED IN PLACE DURING CONSTRUCTION | | A NUMBER OF YEARS AGO.) ONE MECHANIC WAS WALKING BACKWARD WITH ONE END OF | | THE BEAM. THE INDIVIDUAL CAUGHT HIS FOOT ON A 4X6 ON THE FLOOR AND FELL | | RESULTING IN A BROKEN ANKLE. THE INDIVIDUAL WAS TRANSPORTED TO EXETER | | HOSPITAL BY A SITE AMBULANCE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32291 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:12 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/07/97 | +------------------------------------------------+EVENT TIME: 09:22[CDT]| |NRC NOTIFIED BY: CROW |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC START OF A DIESEL GENERATOR DURING A SURVEILLANCE | | | | THIS OCCURRED WHILE PERFORMING THE TEST SET-UP SECTION FOR SURVEILLANCE | | PROCEDURE 6.1DG.302, UNDERVOLTAGE LOGIC FUNCTIONAL, LOAD SHEDDING, AND | | SEQUENTIAL LOADING TEST (DIV 1). AT THIS TIME, TEMPORARY TEST JACKS WERE | | BEING INSTALLED ON TERMINALS 1 AND 4 ON THE "DG-REL-DG1" (4MX4) RELAY TO | | ALLOW JUMPER INSTALLATION. WHEN INSTALLING THE TEMPORARY TEST JACK ON | | TERMINAL NUMBER 1, CONTACT WAS ALSO MADE WITH THE ADJACENT NUMBER 2 | | TERMINAL. THE CAUSE IS BEING INVESTIGATED. COMPLETING THIS CONTACT MADE | | UP THE NORMAL START LOGIC WHICH RESULTED IN A SLOW START OF THE NUMBER 1 | | DIESEL GENERATOR, WHICH DID NOT LOAD. WHEN IT WAS VERIFIED THAT IT WAS NOT | | A VALID INITIATION SIGNAL, THE SURVEILLANCE PROCEDURE WAS SUSPENDED, AND | | THE DIESEL GENERATOR WAS SECURED AT 0938 CDT. ALL LOGIC FUNCTIONED AS | | EXPECTED, AND THE CRITICAL BUS WHICH REMAINED ENERGIZED BY THE START-UP | | TRANSFORMER WAS NOT AFFECTED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32292 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 18:07 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/07/97 | +------------------------------------------------+EVENT TIME: 15:36[CDT]| |NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFICATION OF STATE REGARDING UNEXPECTED EFFLUENT DISCHARGE BYPASS | | | | THE LICENSEE NOTIFIED THE LOUISIANA DIVISION OF ENVIRONMENTAL QUALITY | | REGARDING AN UNANTICIPATED EFFLUENT DISCHARGE BYPASS OF APPROXIMATELY | | 10,000 GALLONS OF WATER FROM THE CIRCULATING WATER SYSTEM. A COOLING TOWER | | BASIN OVERFLOWED WHEN BLOWDOWN WAS SECURED. THIS CAUSED A RELEASE OF 10,000 | | GALLONS OF WATER OVER A 10 MINUTE PERIOD. THE WATER WILL EVENTUALLY ENTER | | THE MISSISSIPPI RIVER VIA OUTFALL #006. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32293 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 19:44 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/07/97 | +------------------------------------------------+EVENT TIME: 16:20[CDT]| |NRC NOTIFIED BY: SCHRADER |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KROPP RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SOME MOVs POTENTIALLY AFFECTED BY APPENDIX R HOT SHORTS IN CONTROL ROOM | | | | THE LICENSEE'S PRELIMINARY REVIEW OF 10 CFR PART 50, APPENDIX R, "SMART" | | HOT SHORTS, DISCUSSED IN NRC INFORMATION NOTICE 92-18, HAS IDENTIFIED 23 | | MOTOR-OPERATED VALVES (MOV) THAT COULD BE AFFECTED. THESE MOVs ARE | | ASSOCIATED WITH THE AUXILIARY FEEDWATER, COMPONENT COOLING WATER, MAIN | | STEAM, SAFETY INJECTION, AND SERVICE WATER SYSTEMS. THESE VALVES COULD BE | | SUSCEPTIBLE TO DAMAGE DUE TO A FIRE IN THE MAIN CONTROL BOARD. THE LICENSEE | | PLANS TO ADDRESS THIS DESIGN ISSUE BEFORE STARTUP. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32294 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 23:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/07/97 | +------------------------------------------------+EVENT TIME: 21:36[EDT]| |NRC NOTIFIED BY: REEVES |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRISTENSEN 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 | A N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP SIGNAL WITHOUT ROD MOTION DURING TESTING | | | | AN AUTOMATIC REACTOR TRIP SIGNAL OCCURRED DUE TO "GENERAL WARNING" ALARMS | | ON BOTH THE 'A' AND 'B' CHANNELS OF THE SOLID STATE PROTECTION SYSTEM | | (SSPS) DURING REACTOR TRIP BREAKER TESTING. THE LICENSEE REPORTED THAT ALL | | CONTROL RODS WERE ALREADY INSERTED AND THAT THE ROD CONTROL MOTOR/GENERATOR | | SET OUTPUT BREAKERS WERE OPEN AT THE TIME OF THE EVENT. THE LICENSEE STATED | | THAT A GENERAL WARNING ALARM OCCURRED ON THE 'A' CHANNEL OF THE SSPS WHEN | | THE LOGIC TEST SELECTOR SWITCH WAS MOVED FROM THE "OFF" POSITION, AND A | | SECOND CONCURRENT ALARM OCCURRED ON THE 'B' CHANNEL WHEN THE 'B' REACTOR | | TRIP BYPASS BREAKER WAS CLOSED. THE AUTOMATIC REACTOR TRIP SIGNAL WAS | | APPROPRIATE FOR THIS CONDITION, BUT WAS NOT ANTICIPATED BY THE PROCEDURE. | | | | THE LICENSEE IS INVESTIGATING WHY THE TEST PROCEDURE DID NOT RECOGNIZE THE | | EXPECTED SSPS RESPONSE TO THE PROCEDURAL STEPS. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 23:41 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/07/97 | +------------------------------------------------+EVENT TIME: 22:00[CDT]| |NRC NOTIFIED BY: STEVE GORTON |LAST UPDATE DATE: 05/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TOTAL LOSS OF REACTOR CORE ISOLATION COOLING (RCIC) 250-VOLT DC MOTOR | | CONTROL CENTER (MCC) UNDERVOLTAGE ALARM MONITORING RESULTING IN THE LOSS OF | | THE CAPABILITY TO MONITOR GROUP 5 PRIMARY CONTAINMENT ISOLATION VALVE POWER | | | | THIS EVENT IS SIMILAR TO AN EVENT THAT OCCURRED AT 2205 CDT ON MAY 6, 1997, | | WHICH INVOLVED A 14-DAY RCIC LIMITING CONDITION FOR OPERATION (LCO) DUE TO | | A 250-VOLT DC MCC UNDERVOLTAGE ALARM FOR UNKNOWN REASONS. (REFER TO EVENT | | #32288 FOR ADDITIONAL INFORMATION.) THE PREVIOUS EVENT INVOLVED THE LOSS | | OF HALF OF THE INDICATION, BUT OPERATORS STILL HAD THE ABILITY TO MONITOR | | THE CONTAINMENT FUNCTION. THE CAUSE OF THE PREVIOUS EVENT WAS BELIEVED TO | | BE A BAD RELAY IN THE LOCAL PANEL, AND THE LCO WAS EXITED AT 1525 CDT ON | | MAY 7, 1997. | | | | AT 2200 CDT ON MAY 7, 1995, THE SAME ALARM WAS RECEIVED IN THE CONTROL ROOM | | AGAIN, AND INVESTIGATION REVEALED THAT THE CAPABILITY TO MONITOR THE | | CONTAINMENT FUNCTION WAS LOST. TWO GROUP 5 PRIMARY CONTAINMENT ISOLATION | | VALVES (RCIC STEAM ISOLATION VALVES MO-2075 AND MO-2076) COULD NO LONGER BE | | MONITORED FOR UNDERVOLTAGE OR LOSS OF POWER. A LOSS OF POWER TO THE RCIC | | MCC COULD GO UNDETECTED RESULTING IN A FAILURE OF GROUP 5 VALVES TO CLOSE | | WHEN REQUIRED. AS A RESULT, THE LICENSEE DECLARED RCIC INOPERABLE AGAIN AT | | 2220 CDT, AND A 14-DAY LCO WAS RE-ENTERED. THE GROUP 5 ISOLATION VALVES | | HAVE BEEN MANUALLY CLOSED, AND THE LICENSEE'S INVESTIGATION IS ONGOING. | | (ALL EMERGENCY CORE COOLING SYSTEMS ARE CURRENTLY OPERABLE.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+