U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/30/96 - 01/31/96 ** EVENT NUMBERS ** 29903 29904 29905 29906 29907 29908 29909 29910 29911 29912 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29903 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/30/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 03:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 00:24[CST]| |NRC NOTIFIED BY: CARLSON |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FULL SCRAM SIGNAL ACTUATED THE ALTERNATE ROD INSERTION (ARI) SYSTEM. NO | | CONTROL ROD MOVEMENT BECAUSE THE RODS WERE ALREADY FULLY INSERTED. | | | | WHILE HANGING A CLEARANCE TAG FOR INVERTER BYS-INV01B DURING MAINTENANCE | | ACTIVITIES, POWER WAS LOST TO 120 VOLT INSTRUMENT BUS VBN-PNL01B1. THIS | | CAUSED THE LOSS OF SEVERAL CONTROL ROOM INDICATIONS AND ALARMS PLUS THE | | INITIATION OF THE ALTERNATE ROD INSERTION (ARI) SYSTEM. WHEN THE ARI SYSTEM | | INITIATED, IT CAUSED WATER TO FLOW INTO THE SCRAM DISCHARGE VOLUME (SDV) | | AND AS THE SDV FILLED, IT TRIPPED THE LEVEL TRANSMITTER ON THE SDV GIVING A | | DIVISION I REACTOR PROTECTION SYSTEM (RPS) SIGNAL. A DIVISION II RPS SIGNAL | | WAS ALREADY TRIPPED DUE TO ONGOING MAINTENANCE. THIS COMBINATION RESULTED | | IN A FULL RPS ACTUATION SIGNAL. THERE WAS NO CONTROL ROD MOVEMENT BECAUSE | | ALL RODS WERE ALREADY FULLY INSERTED INTO THE CORE. THE CLEARANCE WAS | | STOPPED AND THEN THEY BACKED OUT OF THE PROCEDURE. POWER WAS RESTORED TO | | THE INVERTED 14 MINUTES AFTER POWER HAD BEEN LOST TO THE INVERTER. THE | | SCRAM SIGNAL WAS RESET. SHUTDOWN COOLING REMAINED IN SERVICE DURING THIS | | EVENT. | | | | THE PROCEDURE FOR WORKING ON THE INVERTER HAD BEEN REVIEWED BY A SENIOR | | REACTOR OPERATOR PRIOR TO THE TIME WORK ON THE INVERTER HAD BEEN | | AUTHORIZED. THE SENIOR REACTOR OPERATOR MISSED THE STEP OF SUPPLYING | | ALTERNATE POWER TO THE INSTRUMENT BUS WHEN THE INVERTER WAS TAKEN OUT OF | | SERVICE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29904 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/30/96 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 05:32 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 03:37[CST]| |NRC NOTIFIED BY: R KOPECKY |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BRIAN GRIMES EO | | |BILL JOHNSON REG4 | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 80 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY TRIPPED DUE TO CIRCULATING WATER PUMPS CAVITATING. 5 RODS | | DID NOT FULLY INSERT WHEN THE REACTOR WAS MANUALLY TRIPPED. | | | | REACTOR POWER WAS INITIALLY AT 98%. CIRCULATING WATER BAY LEVEL STARTED | | DECREASING AFTER THE CIRCULATING WATER SCREEN ICED UP. LICENSEE WAS | | MANUALLY REDUCING REACTOR POWER WHEN THEY HAD TO MANUALLY TRIP THE PLANT | | FROM 80% POWER DUE TO THE CIRCULATING WATER PUMPS CAVITATING. FIVE RODS DID | | NOT FULLY INSERT INTO THE CORE (RODS F6, H2, H8, K6, & K10). ALL RODS WERE | | INITIALLY 231 STEPS OUT OF THE CORE. ROD F6 WAS 18 STEPS OUT, H2 WAS 12 | | STEPS OUT, H8 WAS 12 STEPS OUT, K6 WAS 6 STEPS OUT AND ROD K10 WAS 6 STEPS | | OUT (ONE STEP IS 5/8") BY DIGITAL ROD POSITION INDICATION. TWENTY MINUTES | | AFTER THE REACTOR WAS MANUALLY TRIPPED, INDIVIDUAL ROD POSITION INDICATION | | (IRPI) ROD BOTTOM LIGHTS FOR RODS F6, H8, & K10 ILLUMINATED. ROD H2 IRPI | | ROD BOTTOM LIGHT ILLUMINATED AT 0435 CST. ROD K6 IRPI ROD BOTTOM LIGHT | | ILLUMINATED AT 0457 CST. THE LICENSEE EMERGENCY BORATED THE REACTOR COOLANT | | SYSTEM WHEN THEY DISCOVERED THAT 5 RODS HAD NOT FULLY INSERTED INTO THE | | CORE. MAIN STEAM ISOLATION VALVES WERE FAST CLOSED DUE TO THE LOSS OF | | CIRCULATING WATER FLOW TO THE MAIN CONDENSER. DECAY HEAT IS BEING REMOVED | | VIA THE STEAM GENERATOR ATMOSPHERIC VALVES AND THE STEAM GENERATORS ARE | | BEING FED BY THE AUXILIARY FEEDWATER PUMPS (2 MOTOR AND 1 TURBINE). NONE OF | | THE STEAM GENERATORS HAVE LEAKING TUBES. REACTOR COOLANT SYSTEM IS BEING | | MAINTAINED AT A NO LOAD CONDITION OF 557øF. THE EMERGENCY CORE COOLING | | SYSTEM AND THE EDGs ARE FULLY OPERABLE IF NEEDED. THE CAUSE OF THE CONTROL | | RODS NOT GOING FULLY IN IS BEING INVESTIGATED. THE HEATER FOR THE | | CIRCULATING WATER SCREEN IS OPERATING PROPERLY. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | *** SEE EVENT # 29905 FOR CONTINUATION OF THE EVENT *** | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29905 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/30/96 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 10:00 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 08:46[CST]| |NRC NOTIFIED BY: D ONNEN |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |GENE BATES RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG EO | | |WRIGHT FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRAIN "A" ESSENTIAL SERVICE WATER SYSTEM DECLARED INOPERABLE. ENTERED | | UNUSUAL EVENT CLASSIFICATION PER STEP 1 & 2 OF THEIR ADMINISTRATIVE | | PROCEDURE. | | | | TRAIN "A" OF ESSENTIAL SERVICE WATER SYSTEM WAS DECLARED INOPERABLE WHEN | | ITS BAY LEVEL DROPPED TO TEN FEET BELOW THE LAKE LEVEL. TRAIN "B" OF | | ESSENTIAL SERVICE WATER SYSTEM IS OPERABLE AND ONE SERVICE WATER PUMP IS | | OPERABLE. TRAIN "A" OF ESSENTIAL SERVICE WATER SYSTEM WAS DECLARED | | INOPERABLE BECAUSE ICE BLOCKED ITS SCREEN AND WATER COULD NOT ENTER THE | | TRAIN "A" SERVICE WATER BAY. LICENSEE IS TRYING TO REMOVE ICE FROM THE | | TRAIN "A" ESSENTIAL SERVICE WATER SCREEN. EARLIER IN THE EVENT, LICENSEE | | LOST THEIR TURBINE AUXILIARY FEEDWATER PUMP WHEN IT PACKING BLEW OUT. THEY | | STILL HAVE TWO MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS OPERATING AND THEY | | ARE SUPPLYING WATER TO THEIR STEAM GENERATORS. REGION 4 ENTERED MONITORING | | PHASE OF NORMAL MODE OPERATION. ESSENTIAL SERVICE WATER SYSTEM SUPPLIES | | COOLING WATER TO THE EDGs, CCW HEAT EXCHANGERS, CCW PUMPS, ETC. EACH | | ESSENTIAL WATER TRAIN HAS ONE 100% CAPACITY PUMP. RESIDENT INSPECTOR WAS | | INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1352 EST BY KARSCH * * * | | | | AT 1330 EDT COMMISSIONERS ASSISTANTS BRIEFING NOTIFICATIONS (*INDICATES | | OFFICE DID NOT PARTICIPATE): AEOD(JORDAN), ERB(BARRETT), COMM | | JACKSON(JOHNSON), ROGERS(SORENSEN),EDO(*), EDO REGION(MITCHELL), | | EO(GOODWIN), PAO(BEECHER), CAO(*), SECY(BATES), STATE(DROGGITIS), | | IP(UPSHAW), BRIEFER(DYER), OTHERS(MARKSBERRY) | | *** SEE EVENT # 29904 FOR BACKGROUND INFORMATION *** | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29906 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 01/30/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: K.L.KOFRON |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | |VERN HODGE NRR | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED SOLDERING DEFECTS IN RELAYS USED IN EMERGENCY DIESEL | | GENERATORS (EDGs) AT BYRON AND BRAIDWOOD STATIONS. | | | | RELAYS MANUFACTURED BY THE AMERACE CORPORATION HAVE A COMMERCIAL GRADE | | ADD-ON BOARD WITH COMPONENTS TO SUPPRESS A COIL DEENERGIZATION TRANSIENT. | | THE LICENSEE DISCOVERED THAT THE SOLDER CONNECTION BETWEEN THE RELAY AND | | THIS ADD-ON BOARD IS DEFECTIVE. THE FAILURE OF THIS RELAY COULD CAUSE THE | | EDG TO FAIL TO START. THE LICENSEE HAS REPAIRED THE DEFECTIVE SOLDER | | JOINTS AND REINSTALLED THE RELAYS. DEFECTIVE RELAYS COULD BE INSTALLED AT | | OTHER NUCLEAR PLANTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29907 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 01/30/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 15:04 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 13:30[CST]| |NRC NOTIFIED BY: JOHN NEUBECKER |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POSSIBLE GENERIC PROBLEM WITH TONE ALERT RADIOS. | | | | AFTER SEVERAL INSTANCES OF FAILURE OF THE TONE ALERT RADIOS THE LICENSEE | | PROVIDES, THEY DID FURTHER TESTING AND DISCOVERED THAT THE RADIOS DO NOT | | ALWAYS ACTIVATE ON AN EIGHT SECOND TONE. THE FCC RECENTLY SHORTENED THE | | TONE DURATION FROM 20 SECONDS TO 8 SECONDS. THE RADIO'S MANUFACTURER | | STATED THAT THE RADIOS ARE NOT RELIABLY ACTIVATED BY THE NEW, SHORTER, 8 | | SECOND TONE. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR, LOCAL | | EMERGENCY PLANNING AGENCIES, AND HAS NOTIFIED THE MISSOURI EMERGENCY | | MANAGEMENT AGENCY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29908 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 01/30/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 18:23 [ET]| |RX TYPE: [3] CE |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 14:30[CST]| |NRC NOTIFIED BY: TOM TULLOS |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL LOG POWER CHANNEL'S LOW LEVEL TRIP, INTENDED TO PREVENT INADVERTENT | | CRITICALITY, WERE FOUND TO BE SET TOO LOW. | | | | THE LICENSEE DISCOVERED THAT THE LOGARITHMIC POWER CHANNEL "A" SIGNAL WAS | | READING APPROXIMATELY 5% BELOW ACTUAL LOG POWER (NON-CONSERVATIVE). IT WAS | | THEN DETERMINED THAT THE "B,C,AND D" CHANNEL'S SIGNALS WERE ALSO READING | | LOW FROM APPROXIMATELY 3% TO 5%. THESE CHANNELS PROVIDE A PLANT TRIP | | SAFETY FUNCTION AT 0.257% POWER IN AN UNPLANNED CRITICALITY DURING STARTUP | | CONDITIONS OCCURS. THE LICENSEE DETERMINED THAT THESE LOWERED SETPOINTS | | RESULTED FROM NOT PERIODICALLY ADJUSTING THE BIAS OF THE DETECTORS. | | | | TWO TECH SPECS ARE AFFECTED BY THIS CONDITION. TECH SPEC 3.3.3.5, "REMOTE | | SHUTDOWN INSTRUMENTATION" REQUIRES RESTORATION OF AT LEAST TWO CHANNELS. | | TECH SPEC 3.3.1, "REACTOR PROTECTIVE INSTRUMENTATION" DOES NOT APPLY IN | | MODE 1. | | | | THE LICENSEE HAS DETERMINED THAT THE TECH SPEC ANALYTICAL LIMIT FOR THE SET | | POINT MAY HAVE BEEN EXCEEDED DURING THE PLANT START UP IN OCTOBER, 1995. | | THE LICENSEE IS INVESTIGATING TO DETERMINE IF SAFETY LIMITS WERE EXCEEDED. | | THE LICENSEE IS CURRENTLY RESTORING THE INOPERABLE LOG POWER CHANNELS, AND | | WILL DETERMINE APPROPRIATE LONG TERM FOLLOW UP. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29909 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/30/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:30 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 18:00[EST]| |NRC NOTIFIED BY: RICHARD SWEENEY |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT A LOSS OF COOLANT ACCIDENT (LOCA) CONCURRENT | | WITH A LOSS OF OFF-SITE POWER (LOOP), AND A FAILURE OF THE "B" TRAIN OF DC | | POWER WILL RESULT IN EXCESSIVE SERVICE WATER (SW) FLOW. THE SW SYSTEM IS | | DESIGNED TO PROVIDE FLOW TO TWO REACTOR BUILDING FAN COOLERS. IN THIS | | SCENARIO ALL THREE FAN COOLERS WOULD BE PROVIDED FLOW. THE LICENSEE'S | | INTERIM CORRECTIVE ACTION IS TO ISOLATE ONE FAN COOLER IF THESE EVENTS | | OCCUR. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29910 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/30/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 18:14[CST]| |NRC NOTIFIED BY: CURT BASNER |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 Y 1 STARTUP | 1 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT TRIP OF MAIN FEEDWATER PUMPS (MFP) AND A MAIN FEED ISOLATION | | VALVE (MFIV) DUE TO HIGH STEAM GENERATOR LEVEL. | | | | THE LICENSEE WAS PERFORMING A "RETURN TO SERVICE RUN" ON THE "2B" AUX FEED | | PUMP TO CHECK FLOW INSTRUMENTATION. THE LEVEL IN THE "2A" STEAM GENERATOR | | INCREASED TO 70% NARROW RANGE CAUSING A P14 ACTUATION. THIS ACTUATION | | SIGNAL CAUSED A MFP TRIP, A MFIV CLOSURE AND WOULD HAVE TRIPPED THE MAIN | | TURBINE HAD IT BEEN ON LINE. NORMAL LEVEL WAS RESTORED IN THE STEAM | | GENERATOR BY STEAMING TO THE MAIN CONDENSER VIA BYPASS VALVES. THE | | LICENSEE WILL RESTART THE MAIN FEEDWATER PUMPS AND CONTINUE THEIR START UP. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29911 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/30/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 23:35 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/30/96 | +------------------------------------------------+EVENT TIME: 21:27[CST]| |NRC NOTIFIED BY: BRAD WILLIAMS |LAST UPDATE DATE: 01/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE AS A | | RESULT OF FAILURE OF A MANUAL INITIATION TEST. | | | | THE LICENSEE WAS PERFORMING SURVEILLANCE TEST "QCOS-2300-13" (HPCI SYSTEM | | MANUAL INITIATION TEST) WHEN THE HPCI AUX OIL PUMP BEGAN CYCLING BETWEEN | | AUTO TRIP AND RUN. THE HPCI SYSTEM WAS SECURED NORMALLY AND | | TROUBLESHOOTING COMMENCED. THE LICENSEE DOES NOT HAVE ANY FURTHER | | INFORMATION REGARDING THE ROOT CAUSE AT THIS TIME. WITH THE HPCI SYSTEM | | INOPERABLE, THE PLANT IS IN A 14 DAY TECH SPEC LCO (RCIC SYSTEM IS | | OPERABLE). THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29912 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/31/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 04:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/31/96 | +------------------------------------------------+EVENT TIME: 03:20[EST]| |NRC NOTIFIED BY: JESSIE PIKE |LAST UPDATE DATE: 01/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF EMERGENCY ASSESSMENT CAPABILITY FOR THE EMERGENCY DIESEL GENERATORS | | AND THE SERVICE WATER SYSTEM | | | | AT 0024, THE UNIT EXPERIENCED A LOSS OF POWER TO SEVERAL OPTICAL ISOLATOR | | CABINETS (A 1E/NON-1E INTERFACE BOUNDARY). AT 0320, TROUBLESHOOTING | | EFFORTS BY LICENSEE PERSONNEL INDICATED THAT CONTROL ROOM ANNUNCIATION AND | | ALARM FUNCTIONS FROM 1E SAFETY-RELATED EQUIPMENT WERE AFFECTED. THIS COULD | | IMPAIR ASSESSMENT CAPABILITY RELATED TO THIS EQUIPMENT. NORMAL INDICATIONS | | AND CONTROLS FOR THE 1E SAFETY-RELATED EQUIPMENT WERE NOT AFFECTED. | | EXAMPLES OF EQUIPMENT AFFECTED INCLUDE THE EMERGENCY DIESEL GENERATOR AND | | SERVICE WATER SYSTEM ALARMS IN THE MAIN CONTROL ROOM. LOCAL ALARMS WERE | | NOT AFFECTED, AND PERSONNEL HAVE BEEN STATIONED NEAR THE AFFECTED | | EQUIPMENT. THE UNIT IS NOT IN A TECHNICAL SPECIFICATION LIMITING CONDITION | | FOR OPERATION AT THIS TIME. | | | | THE LICENSEE IS CONTINUING ITS TROUBLESHOOTING EFFORTS TO DETERMINE WHY | | POWER WAS LOST TO THE OPTICAL ISOLATOR CABINETS. THE LICENSEE IS ALSO | | ESTABLISHING A RESTORATION PLAN TO RESTORE THE OPTICAL ISOLATOR CABINETS TO | | SERVICE. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+