U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/21/97 - 05/22/97 ** EVENT NUMBERS ** 32248 32288 32295 32360 32364 32365 32366 32367 32368 32369 32370 32371 32372 32373 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32248 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 03:08[EDT]| |NRC NOTIFIED BY: GOETCHIUS |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOLCE RDO | |AESF 50.72(b)(2)(ii) ESF 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 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY INJECTION SIGNAL RECEIVED DUE TO STUCK OPEN MSSV DURING TESTING. | | | | WHILE TESTING THE MAIN STEAM SAFETY VALVES (MSSV) AS PART OF REFUELING | | OUTAGE ACTIVITIES, ONE MSSV STUCK OPEN, THEN SUBSEQUENTLY RESEATED, CAUSING | | A SAFETY INJECTION SIGNAL DUE TO STEAM GENERATOR DIFFERENTIAL PRESSURE. | | NEITHER REACTOR COOLANT SYSTEM (RCS) PRESSURE NOR TEMPERATURE DECREASED | | SIGNIFICANTLY DUE TO THE STUCK MSSV, AND NO INJECTION OF WATER TO THE RCS | | OCCURRED. (THIS IS AN INTERMEDIATE HEAD SAFETY INJECTION PLANT.) | | | | OPERATORS ENTERED EMERGENCY OPERATING PROCEDURE 'E0' IN RESPONSE TO THE | | EVENT. THE LICENSEE REPORTED THAT ALL SYSTEMS FUNCTIONED AS EXPECTED, | | EXCEPT THAT THE '25' FAN COOLER UNIT AND '23' AUXILIARY BOILER FEED PUMP | | DID NOT AUTOMATICALLY START IN RESPONSE TO THE ESFAS SIGNAL. THIS EQUIPMENT | | WAS MANUALLY STARTED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 0529 ON 05/01/97 BY GOETCHIUS ENTERED BY STRANSKY * * * | | | | THE LICENSEE HAS ENTERED TECHNICAL SPECIFICATION 3.0.3. THE '25' FAN COOLER | | UNIT HAS BEEN DECLARED INOPERABLE (BUT REMAINS AVAILABLE), AND THE | | EMERGENCY DIESEL GENERATOR FOR THE OTHER ESFAS TRAIN IS CURRENTLY OUT OF | | SERVICE FOR MAINTENANCE. THE LICENSEE HAS 30 HOURS TO EITHER DECLARE THE | | FAN COOLER UNIT OPERABLE OR TO REDUCE RCS TEMPERATURE TO <350øF IN ORDER TO | | COMPLY WITH THE TECHNICAL SPECIFICATION. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED. THE HOO NOTIFIED R1DO (DOLCE). | | | | * * * UPDATE AT 1527 ON 05/21/97 BY PHIL SANTINI ENTERED BY JOLLIFFE * * * | | | | AFTER THE ABOVE SAFETY INJECTION SIGNAL WAS RECEIVED ON 05/01/97, THE | | LICENSEE DISCOVERED THAT THE WATER LEVEL AND THE NITROGEN PRESSURE IN THE | | ISOLATION-VALVE-SEAL-WATER-INJECTION TANK WERE BOTH BELOW REQUIRED MINIMUM | | VALUES. THE TANK WATER LEVEL WAS AT 75% (MINIMUM LEVEL IS 82%) AND THE | | TANK NITROGEN PRESSURE WAS AT 38 PSIG (MINIMUM PRESSURE IS 52 PSIG). | | | | AFTER A SAFETY INJECTION SIGNAL IS RECEIVED, IT IS EXPECTED THAT TANK LEVEL | | WOULD DECREASE AND THE PLANT OPERATOR WOULD TAKE PROPER ACTION TO RESTORE | | THE TANK TO AN ACCEPTABLE CONDITION. | | | | ADDITIONAL LICENSEE REVIEW OF THE NITROGEN PRESSURE REGULATOR VENDOR MANUAL | | INDICATED THAT THE REGULATOR SHOULD NOT HAVE ALLOWED TANK PRESSURE TO | | DECREASE BELOW THE MINIMUM ACCEPTABLE PRESSURE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE AND DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE WILL SUBMIT A LICENSEE EVENT REPORT TO THE NRC REGARDING THIS | | EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO LAURIE PELUSO. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32288 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 00:13 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/06/97 | +------------------------------------------------+EVENT TIME: 23:00[CDT]| |NRC NOTIFIED BY: STEVE GORTON |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED INOPERABLE | | (BUT AVAILABLE) DUE TO A 250-VOLT DC MOTOR CONTROL CENTER UNDERVOLTAGE | | ALARM FOR UNKNOWN REASONS. (REFER TO EVENT #32295 FOR ADDITIONAL | | INFORMATION.) | | | | THE RCIC 250-VOLT DC MOTOR CONTROL CENTER UNDERVOLTAGE ALARM WAS RECEIVED | | IN THE CONTROL ROOM AT 2205 CDT. UPON INVESTIGATION, NO READILY APPARENT | | CAUSE WAS FOUND. WITH NO UNDERVOLTAGE ALARM AVAILABLE, FOUR 250-VOLT DC | | BREAKERS ARE AFFECTED. AS A RESULT, THE LICENSEE DECLARED THE RCIC SYSTEM | | INOPERABLE (BUT AVAILABLE) AT 2300 CDT, AND A 14-DAY LIMITING CONDITION FOR | | OPERATION WAS ENTERED. THE LICENSEE'S INVESTIGATION IS CURRENTLY ONGOING. | | ALL EMERGENCY CORE COOLING SYSTEMS ARE CURRENTLY OPERABLE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1824 ON 05/21/97 BY STEVE GROTON ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE DESIRES TO RETRACT THIS EVENT SINCE THE UNDERVOLTAGE ALARM WAS | | CAUSED BY A MALFUNCTIONING ALARM UNIT. NO UNDERVOLTAGE CONDITION EXISTED. | | THE RCIC SYSTEM WAS NEVER INOPERABLE. IN ADDITION, RCIC SYSTEM | | INOPERABILITIES ARE NOT REPORTABLE TO THE NRC SINCE NO SAFETY ANALYSIS | | TAKES CREDIT FOR RCIC SYSTEM OPERATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R3DO BRUCE JORGENSEN. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/07/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 23:41 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/07/97 | +------------------------------------------------+EVENT TIME: 22:00[CDT]| |NRC NOTIFIED BY: STEVE GORTON |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TOTAL LOSS OF REACTOR CORE ISOLATION COOLING (RCIC) 250-VOLT DC MOTOR | | CONTROL CENTER (MCC) UNDERVOLTAGE ALARM MONITORING RESULTING IN THE LOSS OF | | THE CAPABILITY TO MONITOR GROUP 5 PRIMARY CONTAINMENT ISOLATION VALVE POWER | | | | THIS EVENT IS SIMILAR TO AN EVENT THAT OCCURRED AT 2205 CDT ON MAY 6, 1997, | | WHICH INVOLVED A 14-DAY RCIC LIMITING CONDITION FOR OPERATION (LCO) DUE TO | | A 250-VOLT DC MCC UNDERVOLTAGE ALARM FOR UNKNOWN REASONS. (REFER TO EVENT | | #32288 FOR ADDITIONAL INFORMATION.) THE PREVIOUS EVENT INVOLVED THE LOSS | | OF HALF OF THE INDICATION, BUT OPERATORS STILL HAD THE ABILITY TO MONITOR | | THE CONTAINMENT FUNCTION. THE CAUSE OF THE PREVIOUS EVENT WAS BELIEVED TO | | BE A BAD RELAY IN THE LOCAL PANEL, AND THE LCO WAS EXITED AT 1525 CDT ON | | MAY 7, 1997. | | | | AT 2200 CDT ON MAY 7, 1995, THE SAME ALARM WAS RECEIVED IN THE CONTROL ROOM | | AGAIN, AND INVESTIGATION REVEALED THAT THE CAPABILITY TO MONITOR THE | | CONTAINMENT FUNCTION WAS LOST. TWO GROUP 5 PRIMARY CONTAINMENT ISOLATION | | VALVES (RCIC STEAM ISOLATION VALVES MO-2075 AND MO-2076) COULD NO LONGER BE | | MONITORED FOR UNDERVOLTAGE OR LOSS OF POWER. A LOSS OF POWER TO THE RCIC | | MCC COULD GO UNDETECTED RESULTING IN A FAILURE OF GROUP 5 VALVES TO CLOSE | | WHEN REQUIRED. AS A RESULT, THE LICENSEE DECLARED RCIC INOPERABLE AGAIN AT | | 2220 CDT, AND A 14-DAY LCO WAS RE-ENTERED. THE GROUP 5 ISOLATION VALVES | | HAVE BEEN MANUALLY CLOSED, AND THE LICENSEE'S INVESTIGATION IS ONGOING. | | (ALL EMERGENCY CORE COOLING SYSTEMS ARE CURRENTLY OPERABLE.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1828 ON 05/21/97 BY STEVE GORTON ENTERED BY JOLLIFFE * * * | | THE LICENSEE DESIRES TO RETRACT THIS EVENT SINCE THE LOSS OF ALARM | | MONITORING DID NOT MAKE THE GROUP 5 ISOLATION VALVE INOPERABLE. THE | | GROUP 5 ISOLATION FUNCTION WAS NOT INOPERABLE. IN ADDITION, RCIC SYSTEM | | INOPERABILITIES ARE NOT REPORTABLE TO THE NRC SINCE NO SAFETY ANALYSIS | | TAKES CREDIT FOR RCIC SYSTEM OPERATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R3DO BRUCE JORGENSEN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32360 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 16:53 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 14:57[CDT]| |NRC NOTIFIED BY: JIM KURAS |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 90 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -MANUAL REACTOR TRIP FROM 90% POWER DUE TO STEAM LEAK IN TURBINE BUILDING- | | | | THE LICENSEE DISCOVERED A STEAM LEAK IN THE TURBINE BUILDING COMING FROM | | THE THIRD STAGE EXTRACTION STEAM ISOLATION VALVE (#AF-FV-58C) TO THE #7B | | MAIN FEEDWATER HEATER. THE LICENSEE SUSPECTS A BODY-TO-BONNET LEAK BASED | | ON A VISUAL INSPECTION. CONTROL ROOM OPERATORS REDUCED POWER FROM 100% TO | | 90% TO REDUCE THE LEAK. THE LICENSEE EVACUATED THE TURBINE BUILDING. | | | | AT 1457 (CDT), CONTROL ROOM OPERATORS MANUALLY TRIPPED THE PLANT FROM | | 90% POWER. ALL CONTROL RODS INSERTED COMPLETELY. THE MAIN TURBINE TRIPPED | | AND TERMINATED THE STEAM LEAK. THE AUXILIARY FEEDWATER SYSTEM ACTUATED, | | AS EXPECTED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. THE PLANT IS | | STABLE IN MODE 3 (HOT STANDBY). | | | | THE STEAM IN THE TURBINE BUILDING CAUSED INTERMITTENT 125 VDC NON-SAFETY | | RELATED BUS GROUND ALARMS. THERE DOES NOT APPEAR TO BE ANY EQUIPMENT | | DAMAGE AND NO PERSONNEL WERE INJURED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A PRESS | | RELEASE. | | | | * * * UPDATE AT 1502 ON 05/21/97 BY JENNIFER YUNK ENTERED BY JOLLIFFE * * * | | | | AT 1330 (CDT) ON 05/21/97, THE LICENSEE ISSUED A PRESS RELEASE REGARDING | | THIS EVENT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE | | OPERATIONS OFFICER NOTIFIED THE R4DO GARY SANBORN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 03:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 21:31[PDT]| |NRC NOTIFIED BY: PIERCE |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SUSPECTED BLOWN POTENTIAL TRANSFORMER CIRCUIT FUSE CAUSED EMERGENCY DIESEL | | GENERATOR (EDG) TO START. | | | | VITAL BUSES F, G, AND H ARE ENERGIZED AND OPERABLE. AUXILIARY POWER IS | | OPERABLE WITH STARTUP POWER AVAILABLE AND EMERGENCY DIESEL GENERATORS 1-1 | | AND 1-3 ARE OPERABLE. | | | | WHILE RESTORING STARTUP TRANSFORMER 1-2 AND NON-VITAL 4.16KV BUS E, AN | | INADVERTENT START OF EMERGENCY DIESEL GENERATOR 1-1 OCCURRED (THE EDG RAN | | UNLOADED FOR 10 TO 15 MINUTES BEFORE IT WAS SECURED). THE START WAS CAUSED | | BY ACTUATION OF DEVICE 27HHU (STARTUP TRANSFORMER FEEDER UNDERVOLTAGE | | RELAY) WHEN THE # 10 KNIFE SWITCH (TEST CUT OUT) WAS CLOSED. CAUSE OF THE | | RELAY ACTUATION DURING BUS RESTORATION IS SUSPECTED TO BE A BLOWN POTENTIAL | | TRANSFORMER CIRCUIT FUSE ASSOCIATED WITH VITAL BUS H STARTUP FEEDER. | | TECHNICAL MAINTENANCE DEPARTMENT IS INVESTIGATING TO DETERMINE THE EXACT | | CAUSE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32365 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 05:14 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 02:54[CDT]| |NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 1 STARTUP | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE. | | | | AT 0144 CDT WHILE OPERATING HPCI SYSTEM TO DEMONSTRATE OPERABILITY | | FOLLOWING REFUELING OUTAGE A HPCI TURBINE BEARING LOW PRESSURE ALARM WAS | | RECEIVED. THE HPCI TURBINE WAS TRIPPED IN ACCORDANCE WITH STATION OPERATING | | PROCEDURES. LOCAL OIL PRESSURE INDICATED 10 psig, THE ALARM SET POINT IS | | 5.5 psig. THE PRESSURE SWITCH WAS CAL CHECKED AND DETERMINED TO BE | | OPERATING CORRECTLY. AT 0254 CDT THE HPCI SYSTEM WAS DECLARED INOPERABLE. | | | | EARLIER IN THE SHIFT, AT 0014 CDT, THE REACTOR CORE ISOLATION COOLING | | SYSTEM WAS RUN AND DEMONSTRATED TO BE OPERABLE. BOTH LOW PRESSURE COOLANT | | INJECTION AND CORE SPRAY SUBSYSTEMS WERE VERIFIED TO BE OPERABLE. THE | | AUTOMATIC DEPRESSURIZATION SYSTEM LOGIC IS CURRENTLY BEING DEMONSTRATED TO | | BE OPERABLE. | | | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION LCO ACTION STATEMENT 3.5.4.C | | AFTER HPCI WAS DECLARED INOPERABLE. THIS ACTION STATEMENT REQUIRES AN | | ORDERLY SHUTDOWN TO BE INITIATED AND REACTOR PRESSURE TO BE REDUCED TO 150 | | psig OR LESS WITHIN 24 HOURS. THE LICENSEE IS CURRENTLY MAKING EFFORT TO | | CORRECT THIS CONDITION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32366 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNKNOWN |NOTIFICATION DATE: 05/21/97 | | CITY: TAFTVILLE REGION: 1 |NOTIFICATION TIME: 10:20 [ET]| | COUNTY: HARTFORD STATE: CT |EVENT DATE: 05/20/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 14:20[EDT]| | DOCKET: |LAST UPDATE DATE: 05/21/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAURIE PELUSO RDO | | |FRED COMBS (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: GARY MCCAHILL | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL WASTE CONTAINING IODINE-131 SET OFF INCINERATOR RADIATION ALARM. | | | | ON 05/20/97 AT 1420, A CALL WAS RECEIVED FROM ROB GALLAGHER AT THE LISBON | | INCINERATOR OWNED BY RILEY ENERGY SYSTEMS OF TAFTVILLE. A TRAVELING FLOOR | | TRUCK HAD SET OFF THE SCALE ALARM WITH A READING OF 20,000 CPM. A SURVEY | | PERFORMED BY PLANT PERSONNEL, USING LUDLUM MODEL 3 METER WITH A LUDLUM 44-2 | | SODIUM-IODIDE PROBE, FOUND 500,000 CPM ON THE PASSENGER SIDE OF THE | | TRAILER. THE INSTALLED SYSTEM HAS ONE DETECTOR MOUNTED ON THE DRIVERS SIDE. | | | | STATE OF CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION RADIATION | | CONTROL PHYSICISTS WERE DISPATCHED TO SURVEY THE TRUCK. A DOSE-RATE OF 1 | | MILLIREM/hr WAS FOUND ON THE PASSENGERS SIDE OF THE TRAILER# CP-41, ABOUT | | 25 FEET FROM THE REAR. THE DOSE-RATE IN THE CAB WAS THE SAME AS BACKGROUND. | | | | ROB GALLAGHER ALLOWED THE TRUCK TO BE DUMPED ON THE INCINERATORS TIPPING | | FLOOR. THREE BAGS OF HOUSEHOLD GARBAGE AND APPROXIMATELY 1 CUBIC FOOT OF | | LOOSE MATERIAL WERE SEGREGATED AND PLACED IN A YELLOW BAG. THE REST OF THE | | LOAD WAS SURVEYED AND RELEASED. | | | | THE DOSE-RATE ON THE BAG WAS 25 mrem/hr CONTACT, 3mrem/hr AT ONE FOOT AND | | 0.5 mrem/hr AT ONE METER. ISOTOPIC ANALYSIS IDENTIFIED THE RADIOACTIVE | | MATERIAL AS IODINE-131. THE BAG WAS PLACED IN THE TRUCK AND TAKEN BACK TO | | NEW HAVEN TRANSFER STATION. THE BAG WAS SEALED IN A 55 GALLON DRUM AND | | STORED IN A SECURE UNOCCUPIED AREA. RADIATION SURVEYS WILL BE TAKEN OF THE | | 55 GALLON DRUM IN ABOUT 80 DAYS. | | | | THE STATE OF CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION RADIATION | | CONTROL NOTIFIED NRC REGION 1 DAVE CHAWAGO OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/21/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 15:09 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 14:50[EDT]| |NRC NOTIFIED BY: TERRY RATHBURN |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | POTENTIAL UNAUTHORIZED ENTRY INTO AREAS CONTAINING VITAL EQUIPMENT. | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32368 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 15:22 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 12:30[CDT]| |NRC NOTIFIED BY: TODD MIELKE |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -CONTAINMENT HATCH DOORS PRESSURE EQUALIZING BALL VALVES HAVE TEFLON SEATS- | | | | AFTER REVIEWING AN INDUSTRY OPERATING EXPERIENCE LETTER REGARDING THE USE | | OF TEFLON MATERIALS IN CONTAINMENT HATCH DOOR SEALING COMPONENTS, THE | | LICENSEE DISCOVERED THAT THE PRESSURE EQUALIZING BALL VALVES FOR THE UNIT 1 | | AND 2 CONTAINMENT HATCH DOORS HAVE TEFLON SEATS. THESE BALL VALVE SEATS | | COULD RECEIVE HIGH RADIATION EXPOSURE IN POST-LOCA RADIATION FIELDS WHICH | | COULD IMPACT THEIR ABILITY TO PERFORM THEIR SAFETY FUNCTION (CONTAINMENT | | ISOLATION). THE LICENSEE DECLARED THE UPPER HATCH INNER DOOR AND THE | | LOWER HATCH INNER AND OUTER DOORS FOR BOTH UNITS INOPERABLE. LICENSEE | | PERSONNEL WILL REPLACE INADEQUATE COMPONENTS. | | | | LICENSEE PERSONNEL WILL PERFORM ADDITIONAL EVALUATIONS TO ENSURE THAT ALL | | HATCH COMPONENTS ARE CAPABLE OF FUNCTIONING IN THE POST-LOCA RADIATION | | FIELDS AND WILL REPLACE COMPONENTS FOUND TO BE LESS THAT ADEQUATE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 05/21/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 17:46 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 16:50[EDT]| |NRC NOTIFIED BY: DAVE CROOK |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS DECKER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 'C' SI PUMP INOP DUE TO CONTROL CABLES RUN IN 'A' SI PUMP CABLE TRAYS - | | | | ON 05/21/97, THE LICENSEE CONFIRMED THAT PORTIONS OF THE MANUAL AND | | AUTO-START CONTROL CABLES FOR THE 'C' SAFETY INJECTION PUMP ARE ROUTED IN | | THE SAME CABLE TRAY WITH THE AUTO-START CONTROL CABLE FOR THE 'A' SAFETY | | INJECTION PUMP AND FOR THE 'B' SAFETY INJECTION PUMP WHEN IT IS LINED UP | | FOR 'A' TRAIN OPERATION. | | | | AT 1650 ON 05/21/97, THE LICENSEE DETERMINED THAT THIS CONDITION IS | | REPORTABLE TO THE NRC AS A POTENTIAL CONDITION OUTSIDE THE DESIGN BASIS | | OF THE PLANT. | | | | DURING INVESTIGATION OF THIS POTENTIAL ISSUE, BUT PRIOR TO CONFIRMING | | THAT THIS CONDITION EXISTED, PLANT OPERATORS REMOVED THE 'C' SAFETY | | INJECTION PUMP FROM SERVICE BY RACKING THE BREAKER OUT AND REMOVING THE | | CONTROL POWER FUSES AND DECLARED THE 'C' SAFETY INJECTION PUMP INOPERABLE. | | THE 'A' SAFETY INJECTION PUMP IS LINED UP FOR 'A' TRAIN OPERATIONS AND THE | | 'B' SAFETY INJECTION PUMP IS LINED UP FOR 'B' TRAIN OPERATIONS. | | | | THERE IS NO ROBINSON TECH SPEC LCO ACTION STATEMENT FOR THE INOPERABLE | | 'C' SAFETY INJECTION PUMP. | | | | THIS CONDITION HAS APPARENTLY EXISTED SINCE INITIAL PLANT STARTUP. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS AND WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32370 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 17:37[EDT]| |NRC NOTIFIED BY: JIM BROOKS |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 +------------------------------------------------------------------------------+ | - NON-SAFETY RELATED EDG SW PRESSURE REGULATORS SHOULD BE SAFETY RELATED - | | | | DURING A DESIGN REVIEW OF THE EMERGENCY DIESEL GENERATOR (EDG) SERVICE | | WATER (SW) SYSTEM, THE LICENSEE IDENTIFIED THAT THE PRESSURE REGULATORS | | ASSOCIATED WITH SW FLOW THROUGH THE EDG HEAT LOADS ARE CLASSIFIED AS | | NON-NUCLEAR SAFETY RELATED. THE LICENSEE BELIEVES THAT THE PRESSURE | | REGULATORS AND COMPONENTS ASSOCIATED WITH THE EDGs (#DG-1A & B) SW SUPPLY | | FLOW CONTROL VALVES (#FCV-104-28A & B) AND ASSOCIATED FLOW CONTROLLERS | | (#FC-104-28A & B) SHOULD BE CLASSIFIED AS NUCLEAR SAFETY RELATED. | | | | THE LICENSEE HAS A HIGH DEGREE OF CONFIDENCE THAT THE PRESSURE REGULATORS | | WILL PERFORM THEIR INTENDED FUNCTION BASED ON PAST PERFORMANCE AND TESTING | | OF SIMILAR PRESSURE REGULATORS. THESE TYPES OF PRESSURE REGULATORS HAVE | | HISTORICALLY FUNCTIONED RELIABLY; ARE PERIODICALLY SURVEILLED (THEIR | | FILTERS ARE REPLACED); AND HAVE UNDERGONE RECENT TESTING IN SUPPORT OF | | COMMERCIAL GRADE DEDICATION. THE LICENSEE HAS INCLUDED THE PRESSURE | | REGULATORS, FLOW CONTROL VALVES, AND FLOW CONTROLLERS IN THE PLANT OPERATOR | | ROUNDS. AS SUCH, IT IS HIGHLY PROBABLE THAT THE REGULATED PRESSURE TO THE | | FLOW CONTROLLERS AND VALVE POSITIONERS WILL BE WITHIN DESIGN PARAMETERS AND | | THE FLOW CONTROL VALVES WILL PERFORM THEIR SAFETY FUNCTION AND THAT THE | | FAILURE OF THE PRESSURE REGULATORS IS UNLIKELY. THE LICENSEE HAS A HIGH | | DEGREE OF CONFIDENCE THAT THE FLOW CONTROL VALVES WILL PERFORM THEIR SAFETY | | FUNCTIONS WHICH IS TO OPEN/MODULATE WHEN THE EDGs START. PAST MONTHLY | | SURVEILLANCE ACTIVITIES CONFIRM THAT THE COOLING FUNCTION HAS BEEN | | PERFORMING AS REQUIRED AND THEREFORE THE PRESSURE REGULATORS HAVE | | FUNCTIONED PROPERLY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32371 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 20:12 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 17:10[EDT]| |NRC NOTIFIED BY: JOHN HUFF |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 +------------------------------------------------------------------------------+ | - ONE #3 STEAM GENERATOR TUBE WOULD NOT MEET REG GUIDE 1.121 REQUIREMENTS - | | | | RESULTS OF #3 STEAM GENERATOR IN-SITU HYDRO TESTING HAVE DETERMINED THAT | | ONE TUBE WOULD NOT MEET REG GUIDE 1.121 REQUIREMENTS OF WITHSTANDING THREE | | TIMES NORMAL OPERATING DIFFERENTIAL PRESSURE. THE TUBE FAILED AT 3100 PSID | | WHICH IS BELOW THE REG GUIDE 1.121 THREE TIMES NORMAL OPERATING | | DIFFERENTIAL PRESSURE LIMIT OF 5330 PSID. THIS STEAM GENERATOR HAS BEEN | | PREVIOUSLY REPORTED AND CLASSIFIED AS CATEGORY C-3 AND 100% OF THE TUBES | | ARE BEING INSPECTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32372 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 05/21/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 20:38 [ET]| |RX TYPE: [3] CE |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 02:45[CDT]| |NRC NOTIFIED BY: ROY PRADOS |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -RADIOACTIVE WATER SPILLED FROM THE SPENT FUEL POOL TO THE PROTECTED AREA- | | | | AT 0245 (CDT), RADIOACTIVE WATER SPILLAGE FROM THE SPENT FUEL POOL FLOWED | | UNDER THE FUEL HANDLING BUILDING (FHB) RAILROAD BAY DOORS TO THE PLANT | | PROTECTED AREA. SOME OF THE WATER THAT ESCAPED THE FHB ENTERED THE STORM | | DRAIN SYSTEM. THE AFFECTED PORTIONS OF THE STORM DRAIN SYSTEM WERE | | ISOLATED. SOME LOW LEVEL RADIOACTIVE WATER WAS DETECTED OUTSIDE THE PLANT | | PROTECTED AREA IN A DEAD-ENDED PORTION OF THE STORM DRAIN SYSTEM BETWEEN | | THE FHB AND THE ADMINISTRATION BUILDING. THE ACTIVITY WAS IDENTIFIED AS | | 1.2E-6 æCi/ml OF CO-58, WHICH IS BELOW THE EFFLUENT CONCENTRATION LIMIT | | SET IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2. | | | | REMEDIAL ACTIONS, WHICH ARE IN PROGRESS, INCLUDE PUMPING THE RADIOACTIVE | | WATER FROM THE AFFECTED PORTIONS OF THE STORM DRAIN SYSTEM TO COLLECTION | | TANKS. ALSO, CONTAMINATED SOIL AND ASPHALT ARE BEING COLLECTED AND TREATED | | AS LOW LEVEL RADIOACTIVE WASTE. | | | | THE AMOUNT OF RADIOACTIVE WATER SPILLAGE IS UNKNOWN. | | | | SINCE THE RADIOACTIVE WATER WAS CONTAINED ON SITE WITHIN THE STORM DRAIN | | SYSTEM, THERE IS NO EFFECT ON THE HEALTH AND SAFETY OF THE PUBLIC. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32373 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/22/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:04 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/22/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRUCE JORGENSEN RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT MAURER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |HHHH OFFSITE NOTIFICATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION MADE DUE TO A PCB SPILL | | | | A PCB-FILLED CAPACITOR WAS FOUND TO HAVE FAILED AND LEAKED PCB OIL INSIDE | | THE C-333 (PROCESS BUILDING) UNIT 3 CELL 1 B-SUBSTATION CAPACITOR CABINET. | | AN ESTIMATED 2 GALLONS OF PCB FLUID SPILLED INTO THE CABINET AND ONTO THE | | CONCRETE FLOOR. THE AREA WAS FLAGGED OFF AND POSTED AS A PCB SPILL SITE. A | | POST-CLEANUP VERIFICATION GRID WAS COMPLETED AND CHEMICAL OPERATIONS | | NOTIFIED OF THE DECONTAMINATION REQUIRED. PGDP ENVIRONMENTAL PERSONNEL WERE | | NOTIFIED. NOTIFICATIONS HAVE BEEN COMPLETED TO THE KENTUCKY DEPARTMENT OF | | ENVIRONMENTAL PROTECTION, ENVIRONMENTAL PROTECTION AGENCY REGION IV, AND | | THE NATIONAL RESPONSE CENTER. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+