U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/27/97 - 03/28/97 ** EVENT NUMBERS ** 32026 32027 32028 32029 32030 32031 32032 32033 32034 32035 32036 32037 32038 32039 32040 32041 32042 32043 32044 32045 32046 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32026 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/27/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/26/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:36[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/27/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MATT C. MAURER | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HIGH PRESSURE FIRE WATER SYSTEM IN BUILDING C-331 WAS DECLARED | | INOPERABLE. | | | | THE FOLLOWING WAS RECEIVED VIA FACSIMILE: | | | | "DURING A WALKDOWN OF THE C-331 BUILDING HIGH PRESSURE FIRE WATER (HPFW) | | SPRINKLER SYSTEMS, A BRANCH LINE WAS DISCOVERED MISSING ON HPFW #17 AT | | COLUMN EE-16 THROUGH FF-16 ON THE CELL FLOOR. THE MISSING BRANCH LINE | | PROVIDES FIRE PROTECTION FOR AN OPEN AREA UNDER THE UNIT BYPASS. THE | | MISSING BRANCH LINE SHOULD CONTAIN THREE SPRINKLER HEADS. THIS DEFICIENCY | | WAS IDENTIFIED DURING AN NRC FIRE PROTECTION INSPECTION. THIS SPRINKLER | | SYSTEM WAS DECLARED INOPERABLE AT 1126 HOURS ON 3/26/97 AND AN HOURLY FIRE | | PATROL WAS INITIATED AS REQUIRED BY TSR 2.4.4.5." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENTS #31841, 31850, 31972, 31977, 32002 AND 32012 FOR | | OTHER FIRE PROTECTION REPORTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32027 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 01:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/26/97 | +------------------------------------------------+EVENT TIME: 21:47[CST]| |NRC NOTIFIED BY: JOHN MILLIFF |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 WAS MANUALLY TRIPPED FROM 100% POWER DURING A FEEDWATER TRANSIENT. | | | | THE FOLLOWING IS A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "MANUAL REACTOR TRIP WAS INITIATED DUE TO A LOW STEAM GENERATOR LEVEL ON | | 'B' STEAM GENERATOR APPROACHING THE AUTOMATIC TRIP SETPOINT OF 33%. ACTUAL | | STEAM GENERATOR LEVEL IN 'B' STEAM GENERATOR WAS INDICATED AT 36% AND | | DECREASING AT THE TIME OF THE MANUAL REACTOR TRIP. CAUSE OF THE MAIN | | FEEDWATER PERTURBATION IS UNDER INVESTIGATION. ALL SAFETY SYSTEMS | | FUNCTIONED PROPERLY WITH NO DISCREPANCIES. ALL CONTROL RODS INSERTED | | FULLY." | | | | THE NORMAL STEAM GENERATOR OPERATING LEVEL AT 100% POWER IS 58.6% OF NARROW | | RANGE. DURING THE FEEDWATER TRANSIENT, OPERATORS UNSUCCESSFULLY ATTEMPTED | | TO RECOVER 'B' STEAM GENERATOR LEVEL USING MANUAL CONTROL OF THE 'B' MAIN | | FEEDWATER REG VALVE ALTHOUGH THE DEMANDED POSITION INDICATED 100%. ALL 3 | | TURBINE DRIVEN MAIN FEEDWATER PUMPS WERE IN SERVICE. FOLLOWING THE TRIP, | | STEAM GENERATOR LEVELS DECREASED TO APPROXIMATELY 40% WIDE RANGE RESULTING | | IN THE ACTUATION OF ALL 3 MOTOR DRIVEN AND THE STEAM DRIVEN AUXILIARY | | FEEDWATER PUMPS AS EXPECTED. MAIN FEEDWATER HAS SINCE BEEN RESTORED TO | | SERVICE AND THE AFW SYSTEM SHUTDOWN AND RETURNED TO STANDBY. NO PRIMARY OR | | SECONDARY RELIEF LIFTED. THE STEAM DUMPS TO THE MAIN CONDENSER ARE IN USE | | TO REMOVE DECAY HEAT. OFFSITE POWER REMAINED AVAILABLE WITH THE UNIT'S | | EMERGENCY DIESEL GENERATORS OPERABLE AND IN STANDBY. UNIT 1 WAS UNAFFECTED | | AND REMAINS AT 100% POWER. | | | | THE LICENSEE ESTIMATES A UNIT 2 RESTART SOMETIME TODAY FOLLOWING COMPLETION | | OF THE POST TRIP REVIEW AND ROOT CAUSE INVESTIGATION. THE LICENSEE DOES NOT | | INTEND TO ISSUE A PRESS RELEASE OR MAKE ANY OFFSITE NOTIFICATIONS. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32028 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 09:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRISON 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION | | REGARDING CONCENTRATION OF SOLIDS IN EFFLUENT IN EXCESS OF STATE LIMIT. | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION (DEC) REGARDING EXCESSIVE CONCENTRATIONS OF SUSPENDED SOLIDS | | IN OUTFALL FROM STORM DRAINS. THE LICENSEE REPORTED THAT SAMPLES TAKEN FROM | | THE WEST STORM SEWER AND WEST DRAINAGE OUTFALL CONTAINED 63 ppm AND 77 ppm | | OF SUSPENDED SOLIDS. THE DEC LIMIT IS 50 ppm. THE LICENSEE SPECULATED THAT | | THE HIGH CONCENTRATION IS DUE TO SAND AND OTHER MATERIALS (USED IN THE | | PARKING LOT DURING WINTER MONTHS) BEING WASHED INTO THE STORM DRAINS. THE | | NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32029 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 11:30[EST]| |NRC NOTIFIED BY: VASEY |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANKSBURY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CRACKING DISCOVERED IN FLOODUP TUBES USED TO PROTECT CABLES FROM MOISTURE | | INTRUSION. | | | | THE FOLLOWING IS TEXT FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON MARCH 27, 1997 AT 1130 WITH UNIT 1 SHUTDOWN FOR A REFUELING OUTAGE, IT | | WAS DETERMINED THAT THE COOK NUCLEAR PLANT, UNIT 1 WAS IN A CONDITION THAT | | SIGNIFICANTLY DEGRADED PLANT SAFETY BECAUSE OF CRACKS FOUND IN FLOODUP | | TUBES WHICH PROTECT ELECTRICAL CABLES FROM MOISTURE INTRUSION DURING A LOSS | | OF COOLANT ACCIDENT. | | | | THE ELECTRICAL PENETRATIONS FOR THE CONTAINMENT ARE LOCATED BELOW THE | | CALCULATED CONTAINMENT FLOODUP LEVEL FOLLOWING A LOSS OF COOLANT ACCIDENT. | | BECAUSE SAFETY RELATED CABLES HAVE NOT BEEN QUALIFIED FOR SUBMERGENCE IN | | WATER, THEY ARE ENCLOSED IN STAINLESS STEEL TUBES WHICH PROVIDE A BARRIER | | BETWEEN THE CABLE AND THE WATER IN CONTAINMENT. | | | | THE UNIT 1 FLOODUP TUBES WERE BEING EXAMINED FOR MOISTURE INTRUSION DURING | | ITS CURRENT REFUELING OUTAGE. DURING THIS EXAMINATION, NINE FLOODUP TUBES | | WERE FOUND TO HAVE CRACKS. AN EVALUATION OF THE IMPACT ON SAFETY RELATED | | EQUIPMENT WAS INITIATED. THE EVALUATION'S CONCLUSION IS THAT SEVERAL SAFETY | | RELATED COMPONENTS WERE ADVERSELY IMPACTED BY THE CONDITION. THESE | | COMPONENTS ARE: | | 1-BLP-132 STEAM GENERATOR NUMBER THREE NARROW RANGE LEVEL | | TRANSMITTER | | 1-BLP-142 STEAM GENERATOR NUMBER FOUR NARROW RANGE LEVEL | | TRANSMITTER | | 1-NSO-021 REACTOR COOLANT SYSTEM POST-ACCIDENT VENT SOLENOID | | VALVE | | 1-22-NRV-153 PRESSURIZER PRESSURE RELIEF VALVE NRV-153 CLOSE LIMIT | | SWITCH | | 1-IMO-316 EAST RHR AND NORTH SAFETY INJECTION TO REACTOR COOLANT | | LOOP NUMBERS 1 AND 4 COLD LEG SHUTOFF VALVE | | 1-NTR-140 REACTOR COOLANT LOOP NUMBER 4 HOT LEG WIDE RANGE | | TEMPERATURE RECORDER THERMAL SENSOR | | 1-NTR-240 REACTOR COOLANT LOOP NUMBER 4 COLD LEG WIDE RANGE | | TEMPERATURE RECORDER THERMAL SENSOR | | 1-HR-1 HYDROGEN RECOMBINER | | 1-NMO-153 PRESSURIZER RELIEF VALVE NRV-153 UPSTREAM SHUTOFF VALVE | | 1-VMO-102 CONTAINMENT HYDROGEN SKIMMER VENTILATION FAN HV-CEQ-2 | | SUCTION SHUTOFF VALVE | | 1-IMO-315 EAST RHR AND NORTH SAFETY INJECTION TO REACTOR COOLANT | | LOOP NUMBERS 1 AND 4 HOT LEG SHUTOFF VALVE | | 1-IMO-325 WEST RHR AND SOUTH SAFETY INJECTION TO REACTOR COOLANT | | LOOP NUMBERS 2 AND 3 HOT LEG SHUTOFF VALVE | | 1-NMO-151 PRESSURIZER RELIEF VALVE NRV-151 UPSTREAM SHUTOFF VALVE | | | | IN ALL CASES, THE CRACK IN THE TUBE PROVIDES A PATHWAY FOR WATER TO ENTER | | THE TUBE, AND, ANY QUALIFICATION DATA FOR THE IMMERSED CABLES, CONTINUED | | OPERATION OF THE ASSOCIATED EQUIPMENT CANNOT BE GUARANTEED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | [HOO NOTE: SEE RELATED EN 32005] | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32030 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:30 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 08:28[CST]| |NRC NOTIFIED BY: GREEN |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STETKA 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 92 POWER OPERATION | 92 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF SECONDARY CONTAINMENT WHEN BOTH INNER AND OUTER REACTOR BUILDING | | DOORS WERE OPENED SIMULTANEOUSLY. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "TODAY FROM 8:28:29 TO 8:35:56 SECONDARY CONTAINMENT APPEARS TO HAVE BEEN | | BREACHED WHEN BOTH THE INNER AND OUTER REACTOR BUILDING DOORS WERE | | INADVERTENTLY OPENED AT THE SAME TIME. THE DOORS APPEAR TO HAVE BEEN BOTH | | OPENED SEVERAL TIMES DURING THIS TIME FRAME. PRIOR TO THIS INCIDENT A | | REACTOR BUILDING HIGH PRESSURE ALARM WAS RECEIVED AT 0823. THIS CONDITION | | WAS CAUSED BY THE PERFORMANCE OF AN INSTRUMENT AND CONTROL CALIBRATION | | PROCEDURE. THE INSTRUMENT AND CONTROL TECHNICIANS PERFORMING THE PROCEDURE | | WERE INSTRUCTED TO BACK OUT OF THE PROCEDURE AND THE REACTOR BUILDING HIGH | | PRESSURE ALARM WAS CLEARED AT 0832. A PROCEDURE CHANGE IS BEING GENERATED | | TO PREVENT THIS CONDITION FROM OCCURRING AGAIN. THE SHIFT TECHNICAL ADVISOR | | WAS DISPATCHED TO THE REACTOR BUILDING ENTRANCE TO DETERMINE THE STATUS OF | | THE AIRLOCK DOORS. THE DOORS WERE CLOSED AND AN INDIVIDUAL WAS STATIONED AT | | THE DOORS TO ENSURE THAT BOTH DOORS WERE NOT OPENED AT THE SAME TIME AGAIN. | | THE CAUSE OF BOTH DOORS OPENING AT THE SAME TIME APPEARS TO BE PERSONNEL | | ERROR." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | [HOO NOTE: SEE RELATED EN 32022.] | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32031 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 13:13 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 09:07[PST]| |NRC NOTIFIED BY: ARBUCKLE |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARNES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | M/R Y 97 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DUE TO ENTRY INTO INSTABILITY REGION 'A' OF THE | | POWER/FLOW MAP. | | | | WHILE PERFORMING A TEST OF THE REACTOR RECIRCULATION PUMP ADJUSTABLE SPEED | | DRIVES, THE RECIRCULATION PUMPS RAN BACK TO 15 Hz, CAUSING THE UNIT TO | | ENTER INSTABILITY REGION 'A' OF THE POWER/FLOW MAP. OPERATORS MANUALLY | | SCRAMMED THE REACTOR UPON RECOGNITION OF THE CONDITION. ALL CONTROL RODS | | INSERTED FOLLOWING THE SCRAM, AND ALL SYSTEMS FUNCTIONED AS EXPECTED. | | | | OPERATORS HAD TRIPPED ONE FEEDWATER PUMP IN ORDER TO TEST THE AUTOMATIC | | RECIRCULATION PUMP RUNBACK TO 27 Hz. HOWEVER, DURING THE ENSUING TRANSIENT, | | REACTOR VESSEL TOP-TO-BOTTOM DIFFERENTIAL TEMPERATURE INCREASED, CAUSING | | THE PUMPS TO AUTOMATICALLY RUN BACK TO 15 Hz. THE LICENSEE STATED THAT NO | | POWER OSCILLATIONS WERE OBSERVED BEFORE THE SCRAM. | | | | DUE TO A LACK OF NEED FOR ELECTRICAL POWER, THE LICENSEE INTENDS TO REMAIN | | SHUTDOWN UNTIL THE COMMENCEMENT OF THE REFUELING OUTAGE, SCHEDULED TO BEGIN | | ON 3/28/97. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1608 FROM ARBUCKLE TAKEN BY BAILEY * * * | | | | THE LICENSEE UPDATED THIS NOTIFICATION TO REFLECT A 1 HOUR REPORTABILITY | | CRITERION FOR INITIATION OF A PLANT SHUTDOWN REQUIRED BY TECHNICAL | | SPECIFICATION LCO A/S 3.4.1. THE LICENSEE NOTIFIED THE NRC RESIDENT | | INSPECTOR OF THIS UPDATE. THE HOO NOTIFIED R4DO (TOM STETKA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32032 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 14:45 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 13:20[CST]| |NRC NOTIFIED BY: M ROSSEAU |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ED GOODWIN EO | | |RALPH HERSKO FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNDETERMINED AMOUNT OF FUEL OIL SPILLED INTO LAKE MICHIGAN. | | | | PER EPIP 1.2 CATEGORY 13 (CONDITION THAT WARRANTS STATE AND LOCAL OFFICIAL | | AWARENESS) AN UNUSUAL EVENT WAS DECLARED. | | | | FUEL OIL OVERFLOWED THE HEATING BOILER DAY TANK WHILE IT WAS BEING FILLED. | | AN UNDETERMINED AMOUNT OF FUEL OIL DRAINED INTO LAKE MICHIGAN. DURING THE | | FILLING OF THE HEATING BOILER DAY TANK EITHER THE FILL VALVE OR THE LEVEL | | CONTROL SYSTEM FAILED WHICH CAUSED THE DAY TANK TO OVERFLOW. THE BOILER | | HEATING DAY TANK OVERFLOWS TO THE ROOF OF THE TURBINE BUILDING WHICH THEN | | DRAINS THROUGH THE TURBINE BUILDING ROOF DRAINAGE SYSTEM TO A STORM DRAIN | | WHICH DRAINS TO LAKE MICHIGAN. THE HEATING BOILER DAY TANK IS LOCATED IN | | THE TURBINE BUILDING. A MAJORITY OF THE SPILLED FUEL OIL HAS BEEN CONTAINED | | AND NO FIRE WATCHES ARE REQUIRED. BOOMS HAVE BEEN PLACED IN LAKE MICHIGAN | | TO CONTAIN THE FUEL OIL SPILL. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS THAT FUEL OIL HAD ENTERED | | LAKE MICHIGAN. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1816 ON 3/27/97 FROM ROSSEAU TAKEN BY BAILEY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 1645 CST AFTER THE SPILL (TOTAL OF 20 | | GALLONS) WAS CLEANED UP BY A HAZMAT TEAM. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. THE NOTIFIED R3DO (LANKSBURY), NRR EO (MARSH), AND | | FEMA (SWEETSER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32033 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GENERAL ATOMICS, SAN DIEGO, CA |NOTIFICATION DATE: 03/27/97 | | CITY: SAN DIEGO REGION: 4 |NOTIFICATION TIME: 15:00 [ET]| | COUNTY: STATE: CA |EVENT DATE: 01/30/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[PST]| | DOCKET: |LAST UPDATE DATE: 03/27/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEANNE HARRISON, R1 RDO | | | | +------------------------------------------------+DAVID VERRELLI, R2 RDO | |NRC NOTIFIED BY: SHIRLEY SMITH |ROGER LANKSBURY, R3 RDO | |HQ OPS OFFICER: DICK JOLLIFFE |TOM STETKA, R4 RDO | +------------------------------------------------+VERN HODGE NRR | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 10CFR21 REPORT ON GENERAL ATOMICS RADIATION MONITOR MAINTENANCE TESTS - | | | | SORRENTO ELECTRONICS, INC (SE), AN AFFILIATE OF GENERAL ATOMICS, DETERMINED | | THAT THE OPERATIONS AND MAINTENANCE MANUAL FOR RADIATION MONITOR #RM-23A | | (CONTROL AND DISPLAY MODULE PART NUMBER #03575300-001) MAY NOT ADEQUATELY | | DEFINE THE REQUIREMENTS FOR PERFORMING PERIODIC SURVEILLANCE TESTS OF | | CERTAIN SAFETY RELATED APPLICATIONS. SE IS RECOMMENDING THAT ADDITIONAL | | DIAGNOSTIC TESTS BE RUN AS PART OF NORMAL MAINTENANCE ACTIVITIES IN ORDER | | TO IDENTIFY HARDWARE FAILURES WHICH MAY NOT BE DETECTED DURING NORMAL | | OPERATIONS. SE IS REVISING THEIR OPERATIONS AND MAINTENANCE MANUAL TO | | REFLECT THIS CHANGE. | | | | GENERAL ATOMICS IS NOTIFYING THE FOLLOWING NUCLEAR CUSTOMERS: | | BEAVER VALLEY, BRUCE, CHINSHAN, DRESDEN 2 & 3, HOPE CREEK, INDIAN POINT 3, | | KORI, KUOSHENG, MILLSTONE 2, OCONEE, SEQUOYAH, SOUTH TEXAS, | | TURKEY POINT 3 & 4, AND ZION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32034 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 03/27/97 | |UNIT: [ ] [4] [ ] STATE: FL |NOTIFICATION TIME: 15:24 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 14:40[EST]| |NRC NOTIFIED BY: JIM HICKEY |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - HIGH HEAD SAFETY INJECTION PUMP LEAK GREATER THAN VALUE ASSUMED IN FSAR - | | | | AT 1440 ON 03/27/97, DURING MAINTENANCE ACTIVITIES ON THE #4A HIGH HEAD | | SAFETY INJECTION PUMP TO REDUCE PUMP CASING FLANGE LEAKAGE, THE LEAK | | INCREASED TO 9 TO 10 GALLONS PER HOUR. LICENSEE ENGINEERING PERSONNEL | | DETERMINED THAT THIS LEAK RATE IS IN EXCESS OF CONSERVATIVE ASSUMPTIONS | | FOR EMERGENCY CORE COOLING SYSTEM RECIRCULATION LOOP LEAKAGE. THESE | | ASSUMPTIONS ARE USED IN THE CALCULATION FOR ASSURING THAT THE LEAKAGE IS | | LIMITED TO THAT WHICH WOULD MEET 10CFR100 LIMITS. | | | | THE AMOUNT OF LEAKAGE WAS LARGER THAN THAT ASSUMED IN THE FSAR AND COULD | | EXCEED GDC-19 DOSE CRITERIA AND IS THEREFORE CONSIDERED OUTSIDE THE PLANT | | DESIGN BASIS. | | | | TECH SPEC LCO A/S 3.5.2.E REQUIRES THE LICENSEE TO RESTORE THE INOPERABLE | | PUMP TO OPERABLE STATUS WITHIN 72 HOURS OR PLACE UNIT 4 IN AT LEAST HOT | | STANDBY MODE WITHIN 6 HOURS AND HOT SHUTDOWN MODE WITHIN THE FOLLOWING | | 6 HOURS. | | | | THE LICENSEE HAS ISOLATED THE PUMP AND PLANS TO REPAIR THE PUMP WITHIN | | 72 HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32035 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 15:59 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 15:35[EST]| |NRC NOTIFIED BY: ANDY WISNIEWSKI |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 +------------------------------------------------------------------------------+ | - FIRE PROTECTION LIGHTING CABLE RUN IN BOTH DIVISION I & II CABLE TRAYS - | | | | AT 1535 ON 03/27/97, CONTROL ROOM PERSONNEL WERE INFORMED BY ENGINEERING | | DEPARTMENT PERSONNEL THAT THE FEEDER CABLE FOR LIGHTING PANEL #LP-1SR | | (APPENDIX R LIGHTS ON THE REFUEL FLOOR) WAS ROUTED THROUGH BOTH DIVISION I | | AND DIVISION II CABLE TRAYS. A SINGLE FAILURE IN THIS CABLE COULD RENDER | | BOTH DIVISIONS INOPERABLE. THIS CONFIGURATION IS CONTRARY TO DIVISIONAL | | SEPARATION CRITERIA AS STATED IN VERMONT YANKEES SPECIFICATION AND PLACES | | THE PLANT OUTSIDE ITS DESIGN BASIS. | | | | THE LICENSEE HAS TAGGED THE FEEDER BREAKER TO LP-1SR OPEN, IS INSPECTING | | OTHER PANELS FOR SIMILAR CONDITIONS, AND IS DETERMINING LONG TERM | | CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32036 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 15:47[PST]| |NRC NOTIFIED BY: J. ARBUCKLE |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VALID REACTOR LOW LEVEL SCRAM SIGNAL DURING MAIN STEAM RELIEF VALVE TESTING | | | | DURING A MAIN STEAM RELIEF VALVE SURVEILLANCE, RELIEF VALVE CYCLING WAS | | USED TO ACHIEVE A DESIRED MAIN STEAM PRESSURE BAND. FOLLOWING RELIEF VALVE | | CLOSURE, REACTOR VESSEL LEVEL SHRANK BELOW THE SCRAM SETPOINT OF 13 INCHES. | | THE REACTOR VESSEL WATER LEVEL HAS BEEN RECOVERED TO THE NORMAL OPERATING | | BAND. AT THE TIME OF THE EVENT, ALL CONTROL RODS WERE ALREADY FULLY | | INSERTED INTO THE CORE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32037 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 13:55[CST]| |NRC NOTIFIED BY: R. COTE (COOPER CORP) |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY, R3 RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |LEANNE HARRISON, R1 RDO | | |TOM STETKA, R4 RDO | | |VERN HODGE NRR | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 NOTIFICATION BY VENDOR. COOPER-BESSEMER EMERGENCY DIESELS | | | | ON JANUARY 27, 1997 COMMONWEALTH EDISON COMPANY IDENTIFIED A SIGNIFICANT | | DROP IN CRANKCASE LUBE OIL LEVEL IN ONE OF THE COOPER-BESSEMER EMERGENCY | | DIESEL GENERATORS. SUBSEQUENT INVESTIGATION REVEALED THAT A CRACK HAD | | DEVELOPED IN THE CYLINDER LINER WALL ALLOWING JACKET WATER TO ENTER THE | | COMBUSTION CHAMBER. THIS RESULTED IN A FAILED PISTON. UPON REVIEW OF THE | | FAILED PISTON IT WAS NOTED THAT THE PISTON CROWN THICKNESS IN THE AREA OF | | FAILURE WAS BELOW DRAWING SPECIFICATIONS. | | | | THIS IS THE ONLY KNOWN FAILURE OF SUBJECT LINER. THIS LINER DESIGN IS IN | | USE ON "EARLY" KSV ENGINES IN USE AT THE ZION STATION AND AT THE COOPER | | NUCLEAR STATION. FAILURE OF THE PISTON WAS A DIRECT RESULT OF THE LINER | | FAILURE. FINITE ELEMENT ANALYSIS IS BEING CONDUCTED BY COOPER-BESSEMER TO | | DETERMINE ACCEPTABLE MINIMUM THICKNESS FOR THE PISTON CROWN SECTION. THIS | | PISTON EVALUATION COULD AFFECT THE FOLLOWING KSV USERS: PALO VERDE, | | BRAIDWOOD, BYRON, ZION, WATERFORD III, SOUTH TEXAS, COOPER, NINE MILE POINT | | 2, AND SUSQUEHANNA. IT IS EXPECTED THIS EVALUATION WILL BE COMPLETED | | BEFORE MAY 28, 1997. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32038 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/27/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:39 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/27/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:55[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/27/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: K. SISLER | | |HQ OPS OFFICER: HENRY BAILEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - POSSIBLE COMPROMISE OF CLASSIFIED INFORMATION - | | | | ON 3/27/97 AT 1530 HOURS, THE SITE CLASSIFICATION OFFICER DISCOVERED | | CLASSIFIED INFORMATION IN AN UNCLASSIFIED DOCUMENT. THE DOCUMENT WAS IN AN | | UNCLASSIFIED COMPUTER SYSTEM AND WAS A LEGACY ISSUE. THE DOCUMENT WAS | | SECURED AND THE SECURITY INVESTIGATION IS ONGOING. THE POTENTIAL EXISTS | | THAT A COMPROMISE OCCURRED WITH AN UNCLEARED EMPLOYEE ON SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32039 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/27/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:43 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/27/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:30[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/27/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: L. BOSHELL | | |HQ OPS OFFICER: HENRY BAILEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECTION OF HIGH PRESSURE FIRE WATER SYSTEM PIPING INOPERABLE | | | | DURING A WALKDOWN OF THE C-331 BUILDING HIGH PRESSURE FIRE WATER (HPFW) | | SPRINKLER SYSTEMS, A BRANCH PIPE WAS DISCOVERED NOT CONNECTED TO THE MAIN | | HEADER BETWEEN COLUMN LINE V-33 AND W-33. THIS LINE SERVICES THE EXHAUST | | DUCTWORK FOR FAN EE-3A. THE DUCTWORK EXHAUSTS AIR FROM THE PROCESS MOTORS | | ON THE BUILDING SECOND FLOOR. | | | | THE SPRINKLER SYSTEM WAS DECLARED INOPERABLE AT 10:21 ON 3/12/97 AND AN | | HOURLY FIRE PATROL WAS INITIATED AS REQUIRED BY TSR 2.4.4.5. THIS CONDITION | | WAS ORIGINALLY DETERMINED NOT TO BE REPORTABLE. ENGINEERING DETERMINED ON | | 3/27/97 THAT THE CONDITION WAS REPORTABLE UNDER 10 CFR 76.120.c.2.i. THE | | FINAL REPORT WILL ADDRESS THE LENGTH OF TIME THIS CONDITION HAS EXISTED. | | THE CERTIFICATE HOLDER NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 32040 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MILLSTONE 1, 2, 3 |NOTIFICATION DATE: 03/27/97 | | CITY: WATERFORD REGION: 1 |NOTIFICATION TIME: 17:05 [ET]| | COUNTY: STATE: CT |EVENT DATE: 03/27/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 16:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/27/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LEANNE HARRISON RDO | | |HOLONICH (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM BAUER | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | |ELOS 39.77(b) THEFT/LOSS OF RAD MAT | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOSS OF RADIOACTIVE MATERIAL FROM A TRUCK ENROUTE TO MILLSTONE - | | | | MILLSTONE RENTED AN EQUA-FLEX VESSEL #93-46 AND ASSOCIATED PIPING AND | | VALVES FROM THE BARNWELL WASTE MANAGEMENT FACILITY IN BARNWELL, SC, | | OPERATED BY CHEM-NUCLEAR SYSTEMS, INC TO PROCESS LIQUID RAD WASTE. THIS | | RADIOACTIVE ASSEMBLY WAS TRUCKED FROM BARNWELL, SC, TO MILLSTONE VIA SC, | | NC, VA, MD, DE, NJ, AND CT. THE TRUCK WAS PLACARDED RADIOACTIVE MATERIAL, | | SURFACE CONTAMINATED OBJECT 7, UN-2913, CHRIS CODE: RAM. | | | | THE TRUCK DRIVER FOR THE CARRIER, TRI-STATE TRUCKING COMPANY, STOPPED AT A | | REST STOP 18 MILES NORTH OF THE NJ/DE BORDER AT EXIT 18A ON I-295 NEAR | | PAULSBORO, NJ, WHERE HE OBSERVED A VALVE MISSING FROM THE ASSEMBLY. | | | | UPON ARRIVAL AT MILLSTONE, THE LICENSEE RECEIPT INSPECTED THE ASSEMBLY AND | | DETERMINED THAT A 2 INCH BALL VALVE WAS MISSING FROM THE ASSEMBLY. THE | | HOLE IN THE PIPE WHERE THE VALVE WAS LOCATED MEASURED 32 MR/HR ON CONTACT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, CT DEPARTMENT OF | | TRANSPORTATION, AND LOCAL OFFICIALS. | | | | NRC REGION 1 NOTIFIED DOT, EPA, DE STATE POLICE, NJ DEP, MD DEP, AND THE | | USCG NATIONAL RESPONSE CENTER. | | | | THE USCG NATIONAL RESPONSE CENTER NOTIFIED THE CENTERS FOR DISEASE | | CONTROL, PA EMERGENCY MANAGEMENT AGENCY, DE EMERGENCY MANAGEMENT AGENCY, | | DE DEPARTMENT OF NATIONAL RESOURCES AND ENVIRONMENTAL CONTROL, NJ DEP, | | EPA REGION II, EPA OFFICE OF AIR AND RADIATION, NOAA REGION II, DOE, AND | | THE NRC OPERATION CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32041 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: RIVERSIDE COUNTY FIRE DEPT |NOTIFICATION DATE: 03/27/97 | | CITY: LAKE ELSINORE REGION: 4 |NOTIFICATION TIME: 17:26 [ET]| | COUNTY: STATE: CA |EVENT DATE: 03/27/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 13:30[PST]| | DOCKET: |LAST UPDATE DATE: 03/27/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: CHECKAN, NAT RES CTR | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CITIZEN CONTAMINATED WHEN HE PICKED UP A TUBE CONTAINING STRONTIUM-90 - | | | | DON REYNOLDS, RIVERSIDE COUNTY FIRE DEPARTMENT, LAKE ELSINORE, CA, | | REPORTED TO THE USCG NATIONAL RESPONSE CENTER THAT A PRIVATE CITIZEN | | FOUND A TUBE CONTAINING STRONTIUM-90 (CHRIS CODE: NCC) ALONG SIDE A ROAD. | | THE INDIVIDUAL PICKED THE TUBE UP, PLACED IT IN HIS PICKUP TRUCK, AND | | TOOK IT TO THE LOCAL FIRE STATION IN LAKE ELSINORE, CA. THE INDIVIDUAL | | AND THE BED OF HIS TRUCK WERE CONTAMINATED. | | | | MR REYNOLDS NOTIFIED ARIZONA DEPT OF ENVIRONMENTAL QUALITY, ARIZONA | | EMERGENCY RESPONSE COMMISSION, DOE, EPA REGION IX, EPA OFFICE OF AIR AND | | RADIATION, DOI, NOAA REGION IX, AND THE CENTERS FOR DISEASE CONTROL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32042 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 17:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 15:47[CST]| |NRC NOTIFIED BY: ROYCE BROWN |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 +------------------------------------------------------------------------------+ | -LICENSEE MADE AN OFFSITE NOTIFICATION TO A STATE AGENCY | | | | A PLANT EMPLOYEE ATOP A RIDE-ON LAWN MOWER SLID INTO PUMPING BAY OF THE | | COLORADO RIVER. THE UNINJURED EMPLOYEE WAS RESCUED FROM THE BAY. THE | | LICENSEE IS RETRIEVING THE MOWER, HAS CONTAINED THE OIL AND GAS THAT | | HAS LEAKED FROM THE MOWER, AND IS CLEANING UP THE SPILL. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE TEXAS GENERAL LAND | | OFFICE, THE TEXAS NATIONAL RESOURCE CONSERVATION COMMISSION, AND THE EPA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32043 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 03/27/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 22:26 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 21:05[CST]| |NRC NOTIFIED BY: RON RUSTICK |LAST UPDATE DATE: 03/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LICENSEE DETERMINED THAT PLANT WAS OUTSIDE ITS DESIGN BASIS IN 1996 - | | | | ON 02/27/96, DURING A REVIEW OF THE APPENDIX R HIGH/LOW PRESSURE INTERFACE | | ON THE REACTOR WATER CLEANUP (RWCU) SYSTEM, THE LICENSEE DETERMINED THAT | | THE APPENDIX R SAFE SHUTDOWN REPORT INDICATED THAT THE RWCU SYSTEM REQUIRED | | ISOLATION DURING A DESIGN BASIS FIRE. NO PROCEDURAL STEPS HAD BEEN IN | | PLACE TO IMPLEMENT RWCU SYSTEM ISOLATIONS. THIS ISSUE WAS RESOLVED | | SATISFACTORILY THROUGH A REVISION TO OPERATING REACTOR INVENTORY LOSS | | WITHIN THE BOUNDS OF THE SAFE SHUTDOWN ANALYSIS. THIS PROCEDURE REVISION | | WAS COMPLETE ON 05/28/96. | | | | AT 2105 (CST) ON 03/27/97, THE LICENSEE DETERMINED THAT THIS CONDITION HAD | | PLACED THE PLANT OUTSIDE ITS DESIGN BASIS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/28/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:04 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/27/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:25[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/28/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UF6 RELEASE DETECTION AND ISOLATION SAFETY SYSTEM DECLARED INOPERABLE | | DURING SURVEILLANCE TESTING. | | | | THE FOLLOWING TEXT IS FROM A FAX SUBMITTED BY THE LICENSEE: | | | | "AT 0325CST ON 3/27/97, DURING TSR SURVEILLANCE TESTING OF THE UF6 RELEASE | | DETECTION AND ISOLATION SAFETY SYSTEM ON THE C-310 WEST NORMETEX PUMP, THE | | SAFETY SYSTEM FOR THE OPERATING EAST NORMETEX PUMP WAS DETERMINED TO BE | | INOPERABLE. AT 0410CST, THE EAST NORMETEX PUMP WAS PLACED IN MODE 3 | | (STANDBY) AS REQUIRED BY THE TSR. AT 2200CST, PLANT PERSONNEL PERMITTED | | PERFORMANCE OF THE SURVEILLANCE TEST BASED ON THE EXISTENCE OF TWO | | INDEPENDENT INSTRUMENT CHANNELS, EITHER OF WHICH IS CAPABLE OF PROVIDING | | THE PROTECTIVE FUNCTION. THE SURVEILLANCE TESTS THE ABILITY OF THE | | DETECTION AND ISOLATION SAFETY SYSTEM TO PERFORM THEIR INTENDED SAFETY | | FUNCTIONS. EACH OF THE TWO INSTRUMENT CHANNELS IS TESTED INDEPENDENTLY AND | | IS INOPERABLE DURING TESTING. PERSONNEL PERFORMING THE SURVEILLANCE, USING | | AN IN-HAND PROCEDURE, DID NOT REALIZE THAT THE TSR LCO CANNOT BE MET IF ONE | | OF THE TWO CHANNELS IS INOPERABLE FOR MORE THAN ONE HOUR. A LATER REVIEW | | BY ENGINEERING DETERMINED THAT BOTH INSTRUMENT CHANNELS MUST BE OPERABLE TO | | COMPLY WITH THE TSR. THE INOPERABLE CONDITION WAS CORRECTED AND THE UF6 | | RELEASE DETECTION AND ISOLATION SYSTEM WAS SUBSEQUENTLY DECLARED OPERABLE | | AND THE PUMP WAS RETURNED TO MODE 2 (WITHDRAWAL)." | | | | THE 'A' INSTRUMENT CHANNEL, REMOVED FROM SERVICE AT 2200CST ON 3/26/97 FOR | | TESTING, WAS NOT RESTORED UNTIL 0447CST ON 3/27/97. THIS EXCEEDED THE 1 | | HOUR ALLOWED PER TSR LCO, THUS, RENDERING THE ASSOCIATED SAFETY EQUIPMENT | | INOPERABLE. TESTING OF THE 'B' INSTRUMENT CHANNEL HAS NOT BEEN PERFORMED. | | THE LICENSEE HAS LONG TERM CORRECTIVE ACTIONS UNDER REVIEW, HOWEVER, | | BELIEVES THAT THE 1 HOUR CURRENTLY ALLOWED IS SUFFICIENT FOR TESTING. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32045 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/28/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 05:14 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/27/97 | +------------------------------------------------+EVENT TIME: 04:30[CST]| |NRC NOTIFIED BY: JOHN MILLIFF |LAST UPDATE DATE: 03/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ADDITIONAL DEBRIS IDENTIFIED IN CONTAINMENT DURING A TS REQUIRED | | CONTAINMENT CLOSEOUT INSPECTION. | | | | THE FOLLOWING TEXT WAS RECEIVED VIA FAX FROM THE LICENSEE: | | | | "THIS IS A SUPPLEMENTAL NOTIFICATION TO EVENT #31842. THIS CONDITION | | APPLIES TO UNIT 2 ONLY. UNIT 2 IS CURRENTLY IN MODE 2. ON MARCH 27, 1997, | | WHILE PERFORMING A WALKDOWN IN THE REACTOR CONTAINMENT BUILDING, SOME | | LAGGING WAS FOUND REMOVED AND UNSECURED INSIDE THE REGENERATIVE HEAT | | EXCHANGER ROOM. IT IS BELIEVED THAT THIS LAGGING HAD BEEN THERE SINCE THE | | LAST UNIT 2 REFUELING OUTAGE, FEBRUARY 24, 1997. A WALKDOWN OF ALL | | ACCESSIBLE AREAS HAS BEEN PERFORMED BY A TEAM CONSISTING OF FIVE MANAGERS. | | AN ENGINEERING REVIEW OF THE LOOSE LAGGING CONCLUDED THAT THIS DEBRIS WOULD | | NOT POSSIBLY REACH OR IMPACT THE CONTAINMENT SUMPS. THE LOOSE LAGGING WAS | | LOCATED IN A ROOM WHICH IS ALWAYS LOCKED CLOSED DUE TO RADIOLOGICAL | | CONDITIONS. A PREVIOUS NOTIFICATION (NRC EVENT #31842) WAS RECENTLY MADE | | ON FEBRUARY 24, 1997 WHICH DOCUMENTED AN INCIDENT WHERE SOME LOOSE DEBRIS | | WAS DISCOVERED FOLLOWING THE COMPLETION OF THE TECHNICAL SPECIFICATION | | REQUIRED CONTAINMENT INSPECTION FOR LOOSE DEBRIS FOLLOWING THE REFUELING | | OUTAGE. THIS LAGGING IS BELIEVED TO HAVE BEEN OVERLOOKED DURING THE | | PREVIOUS CONTAINMENT CLOSEOUT INSPECTION. THIS CONDITION IS BEING REPORTED | | AS A FAILURE TO FULLY MEET THE SURVEILLANCE REQUIREMENTS OF THE TECHNICAL | | SPECIFICATIONS REGARDING CONTAINMENT CLEANLINESS. AS SUCH, THIS CONDITION | | IS BEING REPORTED AS A VIOLATION OF THE PLANT OPERATING LICENSE NPF 80 (2G) | | SECTION 2.C(2) (24 HOUR REPORT)." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32046 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/28/97 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 05:18 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/28/97 | +------------------------------------------------+EVENT TIME: 03:19[CST]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 03/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO SECURITY COMPUTER SYSTEM FAILURE. | | | | AT 0319CST THE LOCK AND ALARM COMPUTER FAILED. THIS RESULTED IN THE TOTAL | | FAILURE OF THE ALARM SYSTEM AND A PARTIAL LOSS OF THE LOCKING SYSTEM. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN IN THE REQUIRED TIME. THE | | COMPUTER HAS NOT BEEN RESTORED AS OF THE TIME OF THE REPORT. THE LICENSEE | | IS CONDUCTING AN INVESTIGATION TO DETERMINE ROOT CAUSE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: A SIMILAR REPORT WAS RECEIVED 2/25/96 AND LATER RETRACTED. SEE | | EVENT #30024. | +------------------------------------------------------------------------------+