U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/21/96 - 08/22/96 ** EVENT NUMBERS ** 30902 30903 30904 30905 30906 30907 30908 30909 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30902 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 08/21/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 11:45 [ET]| |RX TYPE: [3] CE |EVENT DATE: 11/11/95 | +------------------------------------------------+EVENT TIME: 03:00[CDT]| |NRC NOTIFIED BY: DAVID MATTHEWS |LAST UPDATE DATE: 08/21/96 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTAINMENT SPRAY RECIRCULATION VALVE, FOUND PARTIALLY OPEN, WOULD | | POTENTIALLY RESULT IN EXCEEDING ALLOWABLE LEAKAGE RATE FROM ENGINEERED | | SAFETY FEATURES SYSTEMS. | | | | WHILE PERFORMING A SURVEILLANCE (ESFAS) TEST ON CONTAINMENT SPRAY SYSTEM | | (CSS) ISOLATION VALVE CS125A, A CSS RECIRCULATION VALVE TO THE REACTOR | | WATER STORAGE POOL (CSS118A) WAS FOUND TO BE OPEN APPROXIMATELY ONE AND ONE | | HALF TURNS. THE LICENSEE INITIALLY THOUGHT THIS WOULD NOT HAVE RESULTED IN | | A LEAKAGE RATE FROM THE ENGINEERED SAFETY FEATURES SYSTEMS, DURING ACCIDENT | | MITIGATION, OVER THE DESIGN LIMIT OF 8 GPM. HOWEVER, AFTER FURTHER | | ANALYSIS, THE LICENSEE DECIDED TODAY THEY WERE UNABLE TO SHOW THAT THIS 8 | | GPM LIMIT WOULD NOT HAVE BEEN EXCEEDED. | | | | THIS RCS LEAKAGE RATE IS LIMITED BY DESIGN BASIS RADIATION DOSE RATES IN | | THE CONTROL ROOM FOLLOWING A POSTULATED ACCIDENT. THE PARTIALLY OPEN VALVE | | WAS FOUND AS A RESULT OF A LOW (<181 FEET) LEVEL IN THE CONTAINMENT SPRAY | | RISER DURING THE SURVEILLANCE TEST. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30903 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 08/21/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/21/96 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: ACKERMAN |LAST UPDATE DATE: 08/21/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILLER 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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED GAP IN BORAFLEX SHEET GREATER THAN MAXIMUM SIZE ASSUMED | | IN CRITICALITY ANALYSIS | | | | WHILE REVIEWING NEUTRON ATTENUATION (BLACKNESS) TEST DATA FOR BORAFLEX | | SHEETS INSTALLED IN THE SPENT FUEL POOL, THE LICENSEE DISCOVERED A GAP OF | | AS MUCH AS NINE INCHES IN BORAFLEX MATERIAL LOCATED AT RACK LOCATION L2A9. | | THE SPENT FUEL POOL CRITICALITY ANALYSIS ASSUMES A MAXIMUM GAP OF FOUR | | INCHES. THE LICENSEE REPORTED THAT NO FUEL IS CURRENTLY BEING STORED AT | | THIS RACK LOCATION, OR IN ANY ADJACENT LOCATIONS. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30904 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/21/96 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 14:50 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/21/96 | +------------------------------------------------+EVENT TIME: 13:43[CDT]| |NRC NOTIFIED BY: MOSBY |LAST UPDATE DATE: 08/21/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SANBORN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOOSE LATCHES ON DOORS TO 4160 VAC CIRCUIT BREAKER CABINETS COULD HAVE | | CAUSED LOSS OF EQUIPMENT NEEDED TO MAINTAIN SAFE SHUTDOWN | | | | ON 8/9/96, THE LICENSEE IDENTIFIED LOOSE DOOR LATCHES ON SOME SAFETY | | RELATED 4160 VAC BREAKER CABINETS. THE LICENSEE REPORTED THAT THESE BREAKER | | CABINET DOORS COULD BE PULLED OPEN BY HAND, ALTHOUGH THE LATCHES WERE | | ENGAGED. THE LICENSEE HAS EVALUATED THIS CONDITION, AND HAS DETERMINED THAT | | THESE LOOSE LATCHES COULD HAVE AFFECTED EQUIPMENT NEEDED TO MAINTAIN THE | | UNIT IN A SAFE SHUTDOWN CONDITION. | | | | SPECIFICALLY THE FOLLOWING EQUIPMENT COULD HAVE BEEN AFFECTED: | | TRAIN A: COMPONENT COOLING WATER AND ESSENTIAL SERVICE WATER PUMPS | | TRAIN B: CENTRIFUGAL CHARGING, SAFETY INJECTION, CONTAINMENT SPRAY, AND | | RESIDUAL HEAT REMOVAL PUMPS. | | | | THE LICENSEE HAS REPAIRED THESE DOOR LATCHES, AND HAS DEVELOPED A | | PREVENTIVE MAINTENANCE PROCEDURE AND SCHEDULE TO PREVENT RECURRENCE OF THIS | | PROBLEM. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30905 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/21/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 16:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/21/96 | +------------------------------------------------+EVENT TIME: 14:15[EDT]| |NRC NOTIFIED BY: ROBERTSON |LAST UPDATE DATE: 08/21/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES 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 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR COMMON MODE FAILURE OF 28 VDC BATTERY CHARGERS DURING SEISMIC | | EVENT | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "DURING PREVENTIVE MAINTENANCE INSPECTIONS OF THE 28 VDC BATTERY CHARGERS, | | THE TECHNICIANS DISCOVERED THAT THE 230 VAC INPUT BREAKERS WERE | | EXPERIENCING FAILURES OF THE BREAKER TABS. THESE BREAKERS ARE MODEL | | ARR24HK150F3 FROM C&D BATTERIES (ELECTRA CORP). THE SPECIFIC PROBLEM WAS | | THAT THE CABLE CONNECTION TO THE BREAKER WAS BEING FLEXED BY OPENING THE | | PANEL DOOR WHEN MAINTENANCE WAS BEING PERFORMED. THE FLEXING OF THE BREAKER | | EVENTUALLY CRACKS AND BREAKS THE TABS ON THE LOAD SIDE OF THE BREAKER. THIS | | CRACKING COULD CAUSE A COMMON CONDITION TO EXIST WITH THE 28 VDC BATTERY | | CHARGERS THAT COULD LEAD TO THE POTENTIAL FAILURE OF THE 28 VDC SYSTEM | | FOLLOWING A SEISMIC EVENT WITH THE DESIGN BASIS ACCIDENT. ENGINEERING IS | | EVALUATING THE OPTIONS FOR THE RESOLUTION OF THIS ISSUE." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30906 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: VETERANS AFFAIRS MEDICAL CENTER |NOTIFICATION DATE: 08/21/96 | | CITY: INDIANAPOLIS REGION: 3 |NOTIFICATION TIME: 17:16 [ET]| | COUNTY: MARION STATE: IN |EVENT DATE: 07/29/96 | |LICENSE#: 13-00694-03 AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/21/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MILLER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: SHUMACHER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CUSTODIAN INADVERTENTLY DISPOSED OF APPROXIMATELY 500-600 æCi OF | | PHOSPHORUS-32. THE LOSS WAS NOT DISCOVERED UNTIL THE FOLLOWING DAY, WHEN | | THE COMPACTED WASTE WAS SENT TO THE LANDFILL. THE LICENSEE HAS ALREADY | | CONTACTED NRC REGION III (LAFRANZO) REGARDING THIS MATTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30907 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/21/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 23:45 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/21/96 | +------------------------------------------------+EVENT TIME: 22:43[EDT]| |NRC NOTIFIED BY: PIKE |LAST UPDATE DATE: 08/21/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BORES 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 +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) DECLARED INOPERABLE. ENTERED 14 DAY | | LIMITING CONDITION OF OPERATION FOR RCIC PER TECHNICAL SPECIFICATION 3.7.4. | | | | RCIC STEAM INBOARD CONTAINMENT ISOLATION VALVES CLOSED PER A RCIC | | CONTAINMENT ISOLATION SIGNAL. INITIAL INVESTIGATION INDICATED THAT A FAULT | | OCCURRED IN THE INBOARD ISOLATION LOGIC DRAWER WHICH GENERATED A FALSE HIGH | | TEMPERATURE ISOLATION SIGNAL. LICENSEE DECLARED RCIC INOPERABLE PER | | TECHNICAL SPECIFICATION 3.7.4. ALL OTHER EMERGENCY CORE COOLING SYSTEMS ARE | | FULLY OPERABLE. LOWER ALLOWAYS CREEK TOWNSHIP WAS NOTIFIED OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30908 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/22/96 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 04:02 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/22/96 | +------------------------------------------------+EVENT TIME: 00:42[CDT]| |NRC NOTIFIED BY: BILL MATHER |LAST UPDATE DATE: 08/22/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | # 22 DIESEL COOLING WATER SAFEGUARDS PUMP AUTOSTARTED | | | | DURING A SURVEILLANCE TEST FOR # 12 DIESEL COOLING WATER SAFEGUARDS PUMP, # | | 12 & # 21 COOLING WATER PUMPS WERE RUNNING SUPPLYING LOOP "A" & "B" COOLING | | WATER HEADERS. THE CONTROL ROOM OPERATOR NOTICED THAT A STEP IN THE | | SURVEILLANCE TEST PROCEDURE HAD BEEN MISSED WHICH REQUIRED A VALVE TO BE | | CLOSED TO ISOLATE "A" & "B" COOLING WATER HEADERS PRIOR TO STARTING # 12 | | DIESEL PUMP. AFTER DISCUSSING THE MISSED STEP WITH CONTROL ROOM SUPERVISOR, | | THEY DECIDED TO CLOSE THE HEADER ISOLATION VALVE. WHEN THE ISOLATION VALVE | | CLOSED "B" HEADER PRESSURE DROPPED BELOW THE SETPOINT FOR # 22 DIESEL | | COOLING WATER PUMP AND IT AUTOSTARTED. THE PUMP HAS BEEN SECURED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30909 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/22/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:55 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/22/96 | +------------------------------------------------+EVENT TIME: 03:57[EDT]| |NRC NOTIFIED BY: MANSELL |LAST UPDATE DATE: 08/22/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BOB 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 20 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP ON HIGH STEAM GENERATOR WATER LEVEL. | | | | STEAM GENERATORS #21, #22, & #24 WATER LEVEL CONTROL SYSTEMS HAD BEEN | | SUCCESSFULLY TRANSFERRED FROM MANUAL CONTROL TO AUTOMATIC CONTROL AND A | | REACTOR OPERATOR WAS IN THE PROCESS OF TRANSFERRING STEAM GENERATOR # 23 | | WATER LEVEL CONTROL SYSTEM FROM MANUAL CONTROL TO AUTOMATIC CONTROL. DURING | | THE TRANSFER OF STEAM GENERATOR # 23 WATER LEVEL CONTROL SYSTEM FROM MANUAL | | TO AUTOMATIC CONTROL STEAM GENERATOR # 23 WATER LEVEL INCREASED TO 73% (ON | | NARROW RANGE INDICATION). THIS CAUSED A TURBINE TRIP/REACTOR TRIP SIGNAL ON | | HIGH STEAM GENERATOR WATER LEVEL. ALL RODS FULLY INSERTED INTO THE CORE. | | BOTH MOTOR DRIVEN AND THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS | | AUTOMATICALLY STARTED ON LOW STEAM GENERATOR WATER LEVEL (8% ON NARROW | | RANGE). THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP HAS BEEN SECURED AND | | STEAM GENERATOR WATER LEVEL IS BEING MAINTAINED BY THE MOTOR DRIVEN | | AUXILIARY FEEDWATER PUMPS. NO PORVs OR CODE SAFETY VALVES ON THE PRIMARY OR | | THE SECONDARY SIDE OF THE PLANT OPENED. LICENSEE IS CURRENTLY INVESTIGATING | | WHY STEAM GENERATOR # 23 WATER LEVEL INCREASED TO 73%. REACTOR COOLANT | | TEMPERATURE IS SLOWLY INCREASING TO Tave NO LOAD TEMPERATURE OF 547ø F | | (CURRENT REACTOR COOLANT TEMPERATURE IS 540ø F). STEAM DUMP BYPASS CONTROL | | SYSTEM IS OPERATING PROPERLY. PLANT STARTUP WILL BE GREATER THAN 24 HOURS | | FROM THE TIME OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+