U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/09/96 - 10/10/96 ** EVENT NUMBERS ** 31048 31119 31120 31121 31122 31123 31124 31125 31126 31127 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31048 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 09/23/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 21:20 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/23/96 | +------------------------------------------------+EVENT TIME: 01:09[CDT]| |NRC NOTIFIED BY: PAUL NAUYALIS |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM TO INSERT IMMOVABLE CONTROL ROD DUE TO RC&IS FAILURE | | | | WITH THE UNIT IN COLD SHUTDOWN, CONTROL ROD 28-29 BECAME IMMOVABLE AT | | POSITION 28 DUE TO A LOCKUP OF THE ROD CONTROL AND INFORMATION SYSTEM | | (RC&IS). LICENSEE ATTEMPTS TO RESET THE RC&IS RESULTED IN A BLOWN FUSE IN | | THE POWER SUPPLY. OPERATORS MOVED THE MODE SELECTOR SWITCH FROM 'REFUEL' | | TO 'SHUTDOWN' IN ORDER TO INSERT A REACTOR SCRAM SIGNAL AND INSERT THE | | CONTROL ROD. FOLLOWING THE REACTOR SCRAM, THE CONTROL ROD MOVED FROM | | POSITION 28 TO POSITION 00 (FULLY INSERTED). NO OTHER CONTROL RODS WERE | | WITHDRAWN AT THE TIME OF THE EVENT. | | | | THE LICENSEE HAS DETERMINED THAT THE RC&IS LOCKUP WAS CAUSED BY SEVERAL | | TRANSPONDER CARDS THAT ARE NOT FUNCTIONING PROPERLY. ADDITIONALLY, THE | | LICENSEE BELIEVES THAT THE BLOWN FUSE MAY BE THE RESULT OF A FAULTY RESET | | SWITCH. THE LICENSEE DETERMINED THAT THIS EVENT WAS REPORTABLE AT 1755 CDT | | 9/23/96. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1222EDT 10/9/96 FROM PHILLIP SHORT TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "ON 9/23/96, A NOTIFICATION WAS MADE REGARDING AN ESF ACTUATION OF THE RPS | | SYSTEM. THIS EVENT HAS SINCE BEEN FURTHER EVALUATED BY THE CPS LICENSING | | DEPARTMENT AND FOUND NOT TO BE REPORTABLE. THIS NOTIFICATION IS BEING MADE | | TO RETRACT THE NOTIFICATION OF 9/23/96." | | | | THE LICENSEE FURNISHED A COPY OF THE LICENSING EVALUATION WHICH CONCLUDED | | "IN SUMMARY, ON THE BASIS THAT THE SEPTEMBER 23rd SCRAM WAS PRE-PLANNED AND | | AN EXPECTED RESULT OF PLACING THE MODE SWITCH IN THE SHUTDOWN POSITION, AND | | IN LIGHT OF THE FACT THAT PLANT CONDITIONS DID NOT REQUIRE A SCRAM EXCEPT | | FOR THE FACT THAT OPERATORS CHOSE TO UTILIZE THE MODE SWITCH SCRAM TO | | INSERT A CONTROL ROD WHILE TROUBLESHOOTING RC&IS, LICENSING CONCLUDES (AND | | CONCURS WITH OPERATIONS) THAT THE SCRAM DID NOT CONSTITUTE AN ESF ACTUATION | | REQUIRED TO BE REPORTED PURSUANT TO 10CFR50.72 OR 10CFR50.73." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(GARDNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31119 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 10/09/96 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 02:33 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/08/96 | +------------------------------------------------+EVENT TIME: 22:54[CDT]| |NRC NOTIFIED BY: CHAISSON |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 94 POWER OPERATION | 94 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DURING A | | QUARTERLY SURVEILLANCE TEST. | | | | DURING THE PERFORMANCE OF SURVEILLANCE TEST PROCEDURE 42A026-Q (STEAM LINE | | HIGH DELTA PRESSURE TEST) HPCI "B" LOGIC CAUSED HPCI CONTAINMENT OUTBOARD | | ISOLATION VALVE TO UNEXPECTEDLY CLOSE. ALL OTHER EMERGENCY CORE COOLING | | SYSTEMS AND THE REACTOR CORE ISOLATION COOLING SYSTEM WERE FULLY OPERABLE | | DURING THE TIME PERIOD HPCI WAS DECLARED INOPERABLE PER TECHNICAL | | SPECIFICATION 3.5.D.2 (14 DAYS TO RETURN HPCI TO SERVICE). AT 0059CDT | | 10/09/96 HPCI WAS DECLARED OPERABLE AND RETURNED TO SERVICE. PRELIMINARY | | INVESTIGATION INDICATES THAT OPERATOR ERROR CAUSED HPCI CONTAINMENT | | OUTBOARD ISOLATION VALVE TO CLOSE. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31120 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 10/09/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 08:04 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 05:21[EDT]| |NRC NOTIFIED BY: BRIAN BOOTH |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 | A N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING TRANSFER OF THE DIVISION 1 UPS TO ITS BACKUP POWER SUPPLY A VOLTAGE | | SURGE CAUSED A FULL SCRAM SIGNAL WITH NO ROD MOTION. | | | | DURING OUTAGE MAINTENANCE THE UNINTERRUPTIBLE POWER SUPPLY (UPS) FOR THE | | DIVISION 2 REACTOR PROTECTION SYSTEM (RPS) AND NUCLEAR STEAM SUPPLY SHUTOFF | | (NSSS) LOGIC WAS REMOVED FROM SERVICE FOR PLANNED MODIFICATION. | | CONCURRENTLY, A NON-INTRUSIVE INSPECTION AND TROUBLESHOOTING WAS IN | | PROGRESS ON THE DIVISION 1 UPS. THE INSPECTION IDENTIFIED A FAULT, AND | | SUBSEQUENT PERMISSION WAS GRANTED FROM THE CONTROL ROOM TO TRANSFER THE | | DIVISION 1 UPS TO ITS BACKUP POWER SOURCE. DURING THE TRANSFER, THE UPS | | MALFUNCTIONED AND CAUSED A VOLTAGE SURGE ON THE ASSOCIATED DOWNSTREAM | | LOADS. THE SAFETY RELATED DOWNSTREAM LOAD PROTECTORS (EPAs) TRIPPED ON AN | | OVERLOAD CONDITION AND DEENERGIZED THE DIVISION 1 RPS AND NSSS LOGIC. THE | | FULL SCRAM IS NOT REPORTABLE BECAUSE ALL THE RODS HAVE ALREADY INSERTED | | INTO THE CORE AND THE ROD CONTROL SYSTEM HAD BEEN REMOVED FROM SERVICE. | | HOWEVER, THIS NOTIFICATION IS BEING MADE BASED ON THE CONTAINMENT ISOLATION | | SIGNAL THAT WAS SENT TO VARIOUS VALVES WHICH MAY NOT HAVE BEEN PROPERLY | | REMOVED FROM SERVICE. A FOLLOWUP INVESTIGATION WILL DETERMINE WHICH | | CONTAINMENT VALVES REPOSITIONED, IF ANY, AND A NOTIFICATION RETRACTION MAY | | BE PURSUED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31121 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 10/09/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 11:12 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 09:50[EDT]| |NRC NOTIFIED BY: MCDOUGOUL |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |AL CHAFFEE EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |DENNY ROSS AEOD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 90 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON COMPLICATED REACTOR TRIP DURING REACTOR PROTECTION SYSTEM (RPS) | | SURVEILLANCE TESTING. | | | | AT 0950 TODAY, THE TURBINE DRIVEN MAIN FEEDWATER PUMP (P-2C) AND THE MAIN | | TURBINE/GENERATOR TRIPPED; COINCIDENT WITH AN AUTOMATIC RPS ACTUATION. RPS | | SURVEILLANCE ACTIVITIES WERE IN PROGRESS AT THE TIME OF THE TRIP AND ARE | | BEING REVIEWED AS A POSSIBLE CAUSE OF THE RPS ACTUATION. ALL RODS FULLY | | INSERTED INTO THE CORE. BOTH EMERGENCY FEEDWATER PUMPS AUTOMATICALLY | | STARTED ON LOW STEAM GENERATOR WATER LEVEL AND ONE OF THEIR TWO NON-SAFETY | | ELECTRIC DRIVEN FEEDWATER PUMPS AUTOMATICALLY STARTED ON LOW FEEDWATER | | HEADER PRESSURE (THE OTHER ELECTRIC FEEDWATER PUMP WAS TAGGED OUT). WHEN | | STEAM GENERATOR WATER LEVEL STABILIZED BOTH EMERGENCY FEEDWATER PUMPS WERE | | SECURED. STEAM GENERATOR WATER LEVEL IS BEING MAINTAINED BY THE ELECTRIC | | DRIVEN FEEDWATER PUMP. NO PRIMARY OR SECONDARY SIDE CODE SAFETY VALVES OR | | PORVs OPENED. REACTOR PLANT IS AT A Tave NO LOAD TEMPERATURE OF 532ø F. | | ONLY THE TURBINE DRIVEN FEEDWATER PUMP (P-2C) IS NEEDED TO MAINTAIN STEAM | | GENERATOR WATER LEVEL WHEN AT 90% POWER. THE TURBINE DRIVEN FEEDWATER PUMP | | TRIPS WHEN A REACTOR TRIP OCCURS. LICENSEE NOTIFIED THE STATE OF MAINE AND | | THE MAINE STATE POLICE OF THIS EVENT. MAINE YANKEE PLANS TO GENERATE A | | PRESS RELEASE CONCERNING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31122 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/09/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:48 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: SCOTT SPECHT |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE FOLLOWING FAILED | | MONTHLY SURVEILLANCE TEST. | | | | "WHILE PERFORMING HPCI MONTHLY VENT VERIFICATION SURVEILLANCE (QCOS2300.9), | | COULD NOT ESTABLISH WATER FLOW THROUGH VENT. CANNOT VERIFY HPCI SYSTEM | | FILLED AND VENTED. PER TECHNICAL SPECIFICATION 3.5.A.3, UNIT 2 IS IN A 14 | | DAY LIMITING CONDITION OF OPERATION. ALL REQUIREMENTS ARE MET FOR 14 DAY | | LCO." | | | | THE LICENSEE IS INVESTIGATING WHETHER MOV LEAKBY IS PREVENTING FILL OF THE | | PIPING AS OBSERVED AT THE HIGH POINT VENT. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31123 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/09/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 15:29 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 12:31[EDT]| |NRC NOTIFIED BY: STEPHEN DAVIS |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 +------------------------------------------------------------------------------+ | UNIT 3 EXPERIENCED AN UNEXPECTED AUTO-START OF AN AUXILIARY BOILER | | FEEDWATER PUMP DURING POST MAINTENANCE EDG TESTING. | | | | "AT 1231 HOURS ON OCTOBER 8, 1996, OPERATIONS NOTED THAT THE AUXILIARY | | BOILER FEEDWATER (ABFW) PUMP 32 STEAM SUPPLY LOW PRESSURE ALARM WAS ON AND | | THAT THE 32 ABFW PUMP WAS IN OPERATION. NO PLANT CONDITIONS REQUIRING | | OPERATION OF THE 32 ABFW WERE IDENTIFIED. TROUBLESHOOTING BY | | INSTRUMENTATION AND CONTROLS DETERMINED THAT RELAY BFPL, THE RELAY THAT | | INITIATES STARTUP OF THE 32 ABFW PUMP, WAS PICKED UP AND SEALED IN. OUR | | CORRECTIVE ACTION PROGRAM REQUIRES INVESTIGATION OF THE CAUSE OF THIS | | EVENT. NO IMMEDIATE CORRECTIVE ACTION WAS REQUIRED. THE 32 ABFW PUMP WAS | | SHUTDOWN AND DID NOT RESTART. THE 32 ABFW PUMP WAS NOT DECLARED | | INOPERABLE. IT SHOULD BE NOTED THAT 32 EMERGENCY DIESEL GENERATOR HAD JUST | | BEEN TIED TO THE 480V BUS 6A FOR TESTING AT THE TIME OF 32 ABFW PUMP | | AUTO-START." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1650EDT 10/9/96 FROM THOMAS McKEE BY S.SANDIN * * * | | | | THE LICENSEE IS CORRECTING THIS REPORT TO SHOW THAT THE STEAM SUPPLY LOW | | PRESSURE ALARM CLEARED RATHER THAN "WAS ON". | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31124 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/09/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 13:55[CDT]| |NRC NOTIFIED BY: DENNIS MORRIS |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 49 POWER OPERATION | 49 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO BOTH UNITS RWST ACCESS HATCHES. | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31125 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 10/09/96 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 17:32 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 16:20[EDT]| |NRC NOTIFIED BY: JOHN EATON |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED DURING A PROCEDURAL REVIEW THAT A CONDITION EXISTED | | WHICH COULD POTENTIALLY RESULT IN AN UNINTENTIONAL MONITORED RAD RELEASE | | COMPROMISING CONTAINMENT INTEGRITY. | | | | "FP&L DETERMINED THAT DURING THE LINEUP FOR THE POST ACCIDENT HYDROGEN | | MONITORS (PAHM) FOLLOWING A VALID ESF ACTUATION, A SINGLE ACTIVE FAILURE | | COULD RENDER THE POST ACCIDENT HYDROGEN MONITOR SYSTEM AND THE POST | | ACCIDENT CONTAINMENT VENTILATION SYSTEM INOPERABLE. IF A SINGLE ACTIVE | | FAILURE OF ONE OF THE CONTAINMENT HYDROGEN SAMPLE SUCTION VALVES OCCURRED, | | PROCEDURAL GUIDANCE EXISTED TO ALLOW CROSS-TYING THE PAHM AND PAC VENT | | SYSTEMS. THIS WOULD RESULT IN POTENTIALLY OVER PRESSURIZING THE PAC VENT | | FILTER SYSTEM RESULTING IN AN UNINTENTIONAL MONITORED RELEASE AND | | COMPROMISING CONTAINMENT INTEGRITY. THE PROCEDURE'S HAVE BEEN REVISED TO | | ELIMINATE THE ALTERNATE CROSS-TIE OPTION AND THAT PROCEDURE IS IN THE | | CONTROL ROOM." | | | | THIS CONDITION HAS EXISTED FOR SOMETIME. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31126 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 10/09/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:20 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: BILL NEVELOS |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A CRACK IN THE SERVICE WATER SUPPLY LINE TO THE SPENT FUEL | | POOL HEAT EXCHANGER. | | | | "DURING A ROUTINE INSERVICE INSPECTION, AN APPROXIMATE 30 INCH CRACK WAS | | DISCOVERED ON THE SERVICE WATER SUPPLY LINE TO THE SPENT FUEL POOL HEAT | | EXCHANGER." | | | | THE LICENSEE HAS STATIONED A 24 HOUR WATCH IN THE VICINITY OF THE CRACK AND | | IS IN THE PROCESS OF INSTALLING A CAMERA MONITORING SYSTEM. ADDITIONALLY, | | FIRE HOSES ARE BEING STRUNG TO PROVIDE ALTERNATE COOLING SHOULD THIS | | PORTION OF PIPE NEED TO BE ISOLATED. THERE IS NO INDICATION OF WEEPAGE | | FROM THE LONGITUDINAL CRACK. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31127 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/09/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 20:10 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 20:07[EDT]| |NRC NOTIFIED BY: JOE RUTTAR |LAST UPDATE DATE: 10/09/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 DETERMINED THAT A LOSS OF INSTRUMENT AIR TO THE TURBINE DRIVEN | | AUXILIARY FEEDWATER PUMP (TDAFW) MAIN STEAM SUPPLY VALVES WOULD ALSO RESULT | | IN A LOSS OF CONTAINMENT ISOLATION. | | | | "LOSS OF INSTRUMENT AIR TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP MAIN | | STEAM SUPPLY VALVES CAUSES THESE VALVES TO FAIL OPEN. THESE VALVES CANNOT | | THEN PERFORM THEIR CONTAINMENT ISOLATION FUNCTION. CORRECTIVE ACTIONS ARE | | UNKNOWN AT THIS TIME." | | | | THE LICENSEE WILL INFORM STATE OFFICIALS AND HAS INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+