U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/11/97 - 07/14/97 ** EVENT NUMBERS ** 32608 32609 32610 32611 32612 32613 32614 32615 32616 32617 32618 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32608 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/11/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 03:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/11/97 | +------------------------------------------------+EVENT TIME: 03:00[EDT]| |NRC NOTIFIED BY: CROKE |LAST UPDATE DATE: 07/11/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ESELGROTH RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROMPT ALERT RADIO TRANSMITTER INOPERABLE FOR GREATER THAN ONE HOUR | | | | AT 0300 ON 07/11/97, THE LICENSEE WAS NOTIFIED THAT THE NOAA AMESVILLE | | TRANSMITTER BECAME INOPERABLE AT 0143. THE LICENSEE USES THIS TRANSMITTER | | TO NOTIFY THE PUBLIC OF EMERGENCY CONDITIONS AT THE PLANT. THE CONTRACTOR, | | JPS COMMUNICATIONS, IS CURRENTLY REPAIRING THE TRANSMITTER. | | | | THE LICENSEE PLANS TO CONTACT THE STATES OF VERMONT, NEW HAMPSHIRE, AND | | MASSACHUSETTS OF THIS CONDITION. THE LICENSEE ALSO PLANS TO INFORM THE NRC | | RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0838 ON 07/11/97, FROM MAY TAKEN BY STRANSKY * * * | | | | THE TRANSMITTER WAS REPAIRED AT 0815. | | | | THE NRC RESIDENT HAS BEEN INFORMED BY THE LICENSEE. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (ESELGROTH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 07/11/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 05:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/11/97 | +------------------------------------------------+EVENT TIME: 05:16[EDT]| |NRC NOTIFIED BY: DAMERON |LAST UPDATE DATE: 07/11/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |URYC RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO LOSS OF ONE REACTOR COOLANT PUMP | | | | AT 0516, THE '2D' REACTOR COOLANT PUMP TRIPPED DUE TO THE ACTUATION OF A | | GROUND FAULT RELAY. THIS CAUSED AN AUTOMATIC REACTOR TRIP/TURBINE TRIP DUE | | TO THE LOSS OF A REACTOR COOLANT PUMP. FOLLOWING THE TRIP, ALL CONTROL RODS | | INSERTED COMPLETELY, AND ALL SYSTEMS FUNCTIONED AS EXPECTED. THE AUXILIARY | | FEEDWATER SYSTEM AUTOMATICALLY STARTED DUE TO LOW-LOW STEAM GENERATOR WATER | | LEVEL. THE UNIT IS CURRENTLY STABLE IN HOT STANDBY. | | | | THE LICENSEE PLANS TO INVESTIGATE THE CAUSE OF THE GROUND FAULT RELAY | | ACTUATION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/11/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:24 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/10/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/11/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JEFF WRIGHT RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT MAURER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PADUCAH IS MAKING A 24-HOUR NON-CFR REPORT OF AN AUTOMATIC ACTUATION OF A | | "Q" SAFETY SYSTEM. | | | | THE LIQUID HANDLING CRANE HOIST BRAKE (WHICH IS "Q" CLASS SAFETY EQUIPMENT) | | AUTOMATICALLY ACTUATED WHEN THE HOIST MOTOR FOR THE LIQUID HANDLING CRANE | | (WHICH IS "Q" CLASS SAFETY EQUIPMENT) STOPPED FOR UNKNOWN REASONS. | | | | AT 1630 CDT ON 07/10/97, THE HOIST MOTOR ON THE C-360 BUILDING WEST CRANE | | FAILED WHILE MOVING HEELED CYLINDER #UK-2009 FOLLOWING A CYLINDER VALVE | | CHANGE. AS PER THE CRANE DESIGN, THE HOIST BRAKES CLOSED AND SUSPENDED THE | | LOAD APPROXIMATELY SIX FEET OFF THE GROUND. AFTER THE CRANE WAS IDLE FOR | | APPROXIMATELY ONE HOUR, THE ABILITY TO RAISE AND LOWER THE HOIST WAS | | RESTORED. THE CYLINDER WAS LOWERED INTO A CYLINDER STORAGE CRADLE. THE | | CRANE WAS REMOVED FROM SERVICE PENDING AN ENGINEERING INVESTIGATION. | | | | THE LICENSEE CATEGORIZED THIS EVENT NOTIFICATION ACCORDING TO PROCEDURE | | UE2-RA-RE1030, CRITERIA J2. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY PADUCAH. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/11/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:46 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/11/97 | +------------------------------------------------+EVENT TIME: 11:45[CDT]| |NRC NOTIFIED BY: JAY HOUSTON |LAST UPDATE DATE: 07/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEFF WRIGHT 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TRUCK CARRYING RADIOACTIVE PERSONNEL CLOTHING WAS INVOLVED IN AN | | ACCIDENT. THIS REPORT WAS MADE DUE TO POTENTIAL MEDIA INTEREST. | | | | AT APPROXIMATELY 1145 CDT, A SHIPMENT OF RADIOACTIVE PERSONNEL PROTECTIVE | | CLOTHING LEFT LASALLE STATION. THE SHIPMENT WAS EN ROUTE TO PROFESSIONAL | | LAUNDRY MANAGEMENT, WHEN AN ACCIDENT OCCURRED BETWEEN THE TRUCK CARRYING | | THE CLOTHING AND A PRIVATELY OWNED VEHICLE. THE SHIPPING CONTAINERS WERE | | NOT DAMAGED OR BREACHED. THERE WAS NO ENVIRONMENTAL DAMAGE OR PERSONNEL | | INJURY AS A DIRECT RESULT OF THE RADIOACTIVE SHIPMENT. THIS NOTIFICATION IS | | BEING MADE IN ACCORDANCE WITH THE LICENSEE'S REPORTABILITY MANUAL SECTION | | SAF 4.1 (POSSIBLE MEDIA INTEREST). | | | | RADIATION PROTECTION PERSONNEL WERE DISPATCHED TO THE SCENE OF THE | | ACCIDENT. INSPECTION SHOWED THAT THE TRUCK CARRYING THE RADIOACTIVE | | CLOTHING HAD A DAMAGED PASSENGER SIDE MUD FLAP AND A CUT IN ONE OF ITS | | TIRES. DOSE RATES WERE VERIFIED AS BEING THE SAME AS BEFORE THE ACCIDENT. | | THE TRUCK TIRE WAS REPAIRED, AND THE TRUCK WAS RELEASED TO TAKE THE | | RADIOACTIVE PERSONNEL PROTECTIVE CLOTHING TO THE CLEANING FACILITY. | | | | A PRIVATELY OWNED VEHICLE WAS DAMAGED IN THE ACCIDENT, BUT THE DRIVER OF | | THE VEHICLE WAS NOT INJURED. THE DRIVER OF THE CAR WAS TAKEN TO THE LOCAL | | HOSPITAL FOR OBSERVATION. THE DRIVER OF THE TRUCK WAS NOT INJURED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32612 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ITT INDUSTRIES |NOTIFICATION DATE: 07/11/97 | | CITY: CITY OF INDUSTR REGION: 4 |NOTIFICATION TIME: 17:45 [ET]| | COUNTY: STATE: CA |EVENT DATE: 07/11/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[PDT]| | DOCKET: |LAST UPDATE DATE: 07/11/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JEFF WRIGHT (R3DO) RDO | | | | +------------------------------------------------+IAN BARNES (R4DO) RDO | |NRC NOTIFIED BY: TED HOLDREDGE |BRUNO URYC (R2DO) RDO | |HQ OPS OFFICER: JOHN MacKINNON |P. ESELGROTH (R1DO) RDO | +------------------------------------------------+VERN HODGE (RVIB) NRR | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WITHDRAWAL OF POTENTIAL 10 CFR PART 21 SAFETY CONCERN | | | | THE ORIGINAL 10 CFR PART 21 NOTIFICATION CAN BE FOUND IN EN 31570. HOWEVER, | | THE FINAL SUPPLEMENT TO THE ITT BARTON 10 CFR PART 21 NOTIFICATION IS | | PROVIDED IN DETAIL. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SUBMITTED BY ITT: | | | | "THIS NOTIFICATION IS PROVIDED AS SUPPLEMENTARY INFORMATION TO THE 10 CFR | | PART 21 NOTIFICATION FILED BY THE V. C. SUMMER NUCLEAR STATION (DOCKET | | NUMBER 50/395) IN THEIR LICENSING EVENT REPORT (LER) NUMBER 96-007, REV. 2, | | SUBMITTED TO THE U.S. NUCLEAR REGULATORY COMMISSION BY SOUTH CAROLINA | | ELECTRIC AND GAS LETTER NUMBER RC-97-0027 DATED JANUARY 30, 1997, AND ITT | | BARTON SUPPLEMENTARY INFORMATION ON THIS ISSUE DATED DECEMBER 13, 1996." | | | | "ITT BARTON SUPPLIES MODEL 763 AND 763A GAGE PRESSURE ELECTRONIC | | TRANSMITTERS TO THE COMMERCIAL NUCLEAR POWER INDUSTRY AS BASIC COMPONENTS | | FOR USE IN SAFETY-RELATED APPLICATIONS. WE PREVIOUSLY REPORTED (DECEMBER | | 13, 1996) A SITUATION INVOLVING SOLDERING INDUCED EMBRITTLEMENT OF STRAIN | | GAGE LEAD WIRES AS POSSIBLY REPRESENTING A POTENTIAL SIGNIFICANT SAFETY | | HAZARD." | | | | "THE WIRE EMBRITTLEMENT OCCURS DURING THE SOLDERING OF THE 10 STRAND #40AWG | | COPPER LEADS THAT CONNECT THE VARIABLE RESISTANCE STRAIN GAGES TO THE | | REMAINDER OF THE ELECTRONIC CIRCUIT. THIS EMBRITTLEMENT INVOLVES A | | METALLURGICAL REACTION BETWEEN THE COPPER WIRE AND THE TIN BASED SOLDER | | USED TO MAKE THE CONNECTIONS. WHILE A THIN LAYER OF THIS INTER-METALLIC | | COMPOUND IS NATURALLY PRODUCED DURING THE METALLURGICAL BONDING PROCESS, AS | | THE THICKNESS OF THE LAYER INCREASES, COPPER IS CONSUMED, AND THE | | MECHANICAL INTEGRITY OF THE JOINT IS REDUCED. THE DYNAMICS OF THE | | INTER-METALLIC MATERIAL GROWTH ARE INFLUENCED BY A NUMBER OF FACTORS WHICH | | INCLUDE THE AMOUNT OF TIN AND OTHER ELEMENTS IN THE SOLDER, THE SOLDERING | | TEMPERATURE, AND THE DURATION OF THE HEAT EXPOSURE." | | | | "ITT BARTON WAS INITIALLY CONCERNED THAT INSTRUMENTS WITH EXCESSIVE WIRE | | EMBRITTLEMENT MAY NOW BE IN USE FOR SAFETY-RELATED APPLICATIONS WHICH MAY | | FAIL WHEN SUBJECTED TO HIGH VIBRATIONAL STRESSES EXPERIENCED DURING NUCLEAR | | POWER PLANT DESIGN BASIS EVENTS. HOWEVER, AFTER VERY METICULOUS EVALUATION, | | WE HAVE CONVINCED OURSELVES THAT, EVEN UNDER THE WORST CREDIBLE SOLDERING | | CONDITIONS, THE STRENGTH OF THE STRAIN GAGE LEAD WIRES HAS A SAFETY FACTOR | | OF AT LEAST 200 TO 1 WHEN SEISMIC INDUCED LOADING CONSISTENT WITH OUR 12 g | | SEISMIC QUALIFICATION [IS] CONSIDERED. THIS FINDING IS CONSISTENT WITH THE | | RESULTS OF THE SEISMIC QUALIFICATION TESTING PERFORMED ON THESE TYPE[S] OF | | INSTRUMENTS BY BOTH ITT BARTON AND WESTINGHOUSE WHERE NOT ONE OF THE TEST | | SPECIMENS WAS FOUND TO HAVE STRAIN GAGE LEAD WIRE FAILURE." | | | | "AS A MATTER OF PRUDENCE, ITT BARTON IS IMPLEMENTING A DESIGN CHANGE THAT | | WILL SUBSTANTIALLY IMPROVE THE STRUCTURAL INTEGRITY OF THE SOLDERED WIRE | | JOIN AND LIMIT THE SUSCEPTIBILITY OF THE JOINT TO MECHANICAL FATIGUE THAT | | MIGHT BE INDUCED BY FIELD CALIBRATION PERSONNEL WHILE INSPECTING THE | | INTERNALS OF THE INSTRUMENT. BECAUSE THIS DESIGN CHANGE CANNOT BE | | RETROFITTED INTO EXISTING FIELD UNITS, ITT BARTON WILL ISSUE AN INDUSTRY | | ADVISORY LETTER TO OUR CUSTOMERS WARNING THEM OF THE SENSITIVITY OF THE | | WIRES TO MECHANICAL DAMAGE AND CAUTIONING THAT INSTRUMENT INSPECTIONS NOT | | INVOLVED PHYSICAL CONTACT WITH THE EXPOSED STRAIN GAGE LEAD WIRES." | | | | "BASED ON THIS RECENT EVALUATION (DOCUMENTED IN A FORMAL ENGINEERING REPORT | | AVAILABLE FOR AUDIT/REVIEW AT OUR FACILITIES), ITT BARTON IS PLEASED TO | | ANNOUNCE THAT OUR CONCERNS HAVE BEEN ALLEVIATED, AND WE FORMALLY WITHDRAW | | OUR NOTIFICATION OF THIS POTENTIAL 10 CFR [PART] 21 SAFETY CONCERN. ITT | | BARTON NOW CONSIDERS THIS ISSUE CLOSED." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32613 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 07/11/97 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 21:43 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/11/97 | +------------------------------------------------+EVENT TIME: 20:10[EDT]| |NRC NOTIFIED BY: G J RADISHOFSKI |LAST UPDATE DATE: 07/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR LOSS OF CONTROL STRUCTURE CHILLED WATER SYSTEM. | | | | WHILE PERFORMING TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION | | (LCO) 3.8.1.1 ACTION STATEMENTS d(1) AND d(2), THE LICENSEE DETERMINED THAT | | CONTROL STRUCTURE HEATING VENTILATION AND AIR CONDITIONING WOULD BE LOST IN | | THE EVENT THE 'A' DIESEL GENERATOR WAS REQUIRED TO SUPPLY EMERGENCY POWER. | | THE 'A' EMERGENCY DIESEL GENERATOR WAS DECLARED INOPERABLE DUE TO THE | | QUESTIONABLE POSITIONING OF A LOAD LIMIT ADJUSTMENT KNOB. THE 'B' CONTROL | | STRUCTURE CHILLER IS CURRENTLY OUT OF SERVICE FOR PLANNED MAINTENANCE, AND | | THE 'A' CHILLER IS SUPPLIED BY THE 'A' DIESEL GENERATOR DURING A LOSS OF | | OFFSITE POWER. IF THIS SITUATION WERE TO OCCUR, THERE WOULD BE A LOSS OF | | THE CONTROL STRUCTURE CHILLED WATER SYSTEM WHICH PROVIDES A SAFETY | | FUNCTION. | | | | PREPARATIONS ARE BEING MADE TO START THE 'A' DIESEL GENERATOR AND TO | | PERFORM A SURVEILLANCE RUN TO PROVE OPERABILITY. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * 0440 JULY 12, 1997, UPDATE BY TROCINE * * * | | | | DURING THE MORNING PLANT STATUS CALL, THE LICENSEE (KECK) STATED THAT THE | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION WAS EXITED AT 0030 | | ON JULY 12, 1997. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32614 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 07/11/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 23:00 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 07/11/97 | +------------------------------------------------+EVENT TIME: 19:35[CDT]| |NRC NOTIFIED BY: RANDY KNIGHT |LAST UPDATE DATE: 07/11/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE HIGH PRESSURE COOLANT INJECTION SYSTEM WAS DECLARED INOPERABLE DURING | | SURVEILLANCE TESTING. | | | | DURING SURVEILLANCE TESTING OF THE UNIT 2 HIGH PRESSURE COOLANT INJECTION | | SYSTEM, THE SYSTEM DID NOT FUNCTION AS EXPECTED WITH REGARD TO REVOLUTIONS | | PER MINUTE VERSUS DISCHARGE PRESSURE VERSUS FLOW. THIS CONSTITUTED AN | | UNSATISFACTORY PERFORMANCE OF THE SURVEILLANCE TEST, AND THE SYSTEM WAS | | DECLARED INOPERABLE. THIS PLACED UNIT 2 IN A 7-DAY LIMITING CONDITION OF | | OPERATION PER TECHNICAL SPECIFICATION 3.5.E(2). ALL OTHER EMERGENCY CORE | | COOLING SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF | | NEEDED. THE ELECTRICAL GRID IS ALSO STABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32615 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 07/12/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/12/97 | +------------------------------------------------+EVENT TIME: 12:27[EDT]| |NRC NOTIFIED BY: IDDINGS |LAST UPDATE DATE: 07/12/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ICE CONDENSER LOWER INLET DOORS OPENED AS A RESULT OF THE UPPER CONTAINMENT | | AIRLOCK DOORS BEING OPENED. | | | | AT APPROXIMATELY 1227 EDT ON 07/12/97, REACTOR OPERATIONS RECEIVED CONTROL | | ROOM ANNUNCIATOR INDICATIONS THAT THE LOWER ICE CONDENSER DOORS WERE OPEN. | | PERSONNEL HAD OPENED THE UPPER CONTAINMENT AIRLOCK RESULTING IN AN INCREASE | | IN PRESSURE ACROSS THE LOWER ICE CONDENSER INLET DOORS. THIS IN TURN | | RESULTED IN THE LOWER INLET DOORS OPENING. THERE WERE NO INDICATIONS OF ANY | | LINE BREAKS IN CONTAINMENT. THE UNIT WAS IN MODE 5 (COLD SHUTDOWN) COOLING | | DOWN FOR MAINTENANCE ON THE "2D" REACTOR COOLANT PUMP. (REFER TO EVENT | | #32609 FOR ADDITIONAL INFORMATION.) | | | | THE ICE CONDENSER DOORS ARE ENGINEERED SAFETY FEATURES FOR CONTAINMENT. | | THERE WERE NO ADVERSE AFFECTS ON ANY PLANT SYSTEMS, STRUCTURES, AND | | COMPONENTS. THE PLANT CONDITIONS WERE UNAFFECTED BY THE OPENING OF THE | | LOWER ICE CONDENSER INLET DOORS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32616 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 07/13/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 13:24 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/13/97 | +------------------------------------------------+EVENT TIME: 11:58[EDT]| |NRC NOTIFIED BY: ALAN RABENOLD |LAST UPDATE DATE: 07/13/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEFF WRIGHT RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR PROTECTION SYSTEM (RPS) ELECTRICAL PROTECTION ASSEMBLY (EPA) | | BREAKER OPENED UNEXPECTEDLY ON RPS BUS 'B', RESULTING IN SEVERAL ENGINEERED | | SAFETY FEATURE ACTUATIONS. | | | | LOSS OF RPS BUS 'B' CAUSED A HALF SCRAM SIGNAL, INBOARD BALANCE-OF-PLANT | | ISOLATIONS, REACTOR WATER CLEANUP (RWCU) SYSTEM ISOLATION, RWCU PUMP TRIP, | | AND LOSS OF CONTAINMENT COOLING. SEVERAL RADIATION MONITORS WERE ALSO LOST | | DUE TO THE EPA BREAKER OPENING. | | | | THE PLANT IS STABLE AT 100%, AND ALL SYSTEMS FUNCTIONED AS DESIGNED. THE | | CAUSE OF THE EVENT IS UNDER INVESTIGATION. RPS BUS 'B' WILL NOT BE RESTORED | | TO SERVICE UNTIL THE EPA BREAKER IS REPAIRED. AFTER RPS BUS 'B' IS RESTORED | | TO SERVICE, THE HALF SCRAM AND THE ISOLATION SIGNALS WILL BE RESET. | | | | ALL EMERGENCY CORE COOLING SYSTEMS, EMERGENCY DIESEL GENERATORS, AND THE | | REACTOR CORE ISOLATION COOLING SYSTEM ARE FULLY OPERABLE IF NEEDED. THE | | LICENSEE ALSO STATED THAT THE ELECTRICAL GRID IS STABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32617 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: |NOTIFICATION DATE: 07/13/97 | | CITY: PACIFIC CITY REGION: 4 |NOTIFICATION TIME: 14:45 [ET]| | COUNTY: TILLAMOOK STATE: OR |EVENT DATE: 07/13/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 11:00[PDT]| | DOCKET: |LAST UPDATE DATE: 07/13/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |IAN BARNES RDO | | |DONALD COOL (NMSS) EO | +------------------------------------------------+FRANK CONGEL (AEOD) IRD | |NRC NOTIFIED BY: LT LECATO/CHEN |MARTHA DIBBLEE (OR) MGR | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER WAS NOTIFIED THAT A BLACK 55-GALLON DRUM | | MARKED "RADIOACTIVE MATERIAL" WAS FOUND AT McPHILIPS BEACH, OREGON. | | | | A 55-GALLON DRUM WAS DISCOVERED AT McPHILIPS BEACH, LOCATED 0.75 MILES | | NORTH OF CAPE COWANDA, OREGON, AND LOCATED NEAR PACIFIC CITY, OREGON. THE | | 55-GALLON DRUM HAS A "RADIOACTIVE MATERIAL" SIGN AND "HDZ 32" WRITTEN ON | | IT. | | | | THE HEADQUARTERS OPERATIONS OFFICER CONTACTED THE MANAGER OF THE MATERIALS | | PROGRAM FOR THE STATE OF OREGON. A STATE REPRESENTATIVE (DIBBLEE) STATED | | THAT A HAZMAT TEAM HAD BEEN DISPATCHED FROM ASTORIA, OREGON, TO McPHILIPS | | BEACH AT 1253 PDT AND THAT IT WOULD TAKE THE HAZMAT TEAM ABOUT TWO HOURS TO | | ARRIVE AT THE SCENE. THE STATE REPRESENTATIVE ALSO STATED THAT THE DRUM HAD | | A TEXACO LOGO ON IT. | | | | THE STATE OF OREGON EMERGENCY RESPONSE SYSTEM NUMBER FOR THIS EVENT IS | | OR-97-1818. THE NATIONAL RESPONSE NUMBER FOR THIS EVENT IS 394874. (REFER | | TO THE HOO LOG BOOK FOR APPLICABLE NAMES AND TELEPHONE NUMBERS.) | | | | *** 1622 EDT 07/13/97, UPDATE FROM MARTHA DIBBLEE TAKEN BY MACKINNON *** | | | | MARTHA DIBBLEE, MANAGER FOR THE STATE OF OREGON MATERIALS PROGRAM, WAS | | NOTIFIED THAT A POLICE OFFICER DISPATCHED TO THE SCENE OF THE 55-GALLON | | DRUM DISCOVERED THAT THE DRUM DID NOT HAVE THE WORDS/MARKINGS FOR | | RADIOACTIVE MATERIAL WRITTEN ON IT. THE HAZMAT TEAM PLANS TO INSPECT THE | | 55-GALLON DRUM FOR HAZARDOUS MATERIALS. | | | | THE R4DO (IAN BARNES), NMSS EO (FRED COMBS), AND AEOD IRD (FRANK CONGEL) | | WERE NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32618 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/13/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 21:36 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/13/97 | +------------------------------------------------+EVENT TIME: 17:18[CDT]| |NRC NOTIFIED BY: R TANDERUP |LAST UPDATE DATE: 07/13/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ONE OF TWO REACTOR PROTECTION SYSTEM (RPS) ELECTRICAL PROTECTION ASSEMBLY | | (EPA) BREAKERS OPENED UNEXPECTEDLY ON RPS BUS 'A', RESULTING IN SEVERAL | | ENGINEERED SAFETY FEATURE ACTUATIONS. | | | | COOPER STATION LOST THE 'A' RPS BUS DUE TO THE '1A2' EPA UNEXPECTEDLY | | OPENING. THE LOSS OF THE 'A' RPS BUS CAUSED A HALF SCRAM SIGNAL, CHANNEL | | 'A' GROUP 1 (ONE STEAMLINE DRAIN VALVE CLOSED) TRIP, 'A' GROUP 2 (PRIMARY | | CONTAINMENT ISOLATION - SEVERAL VALVES ISOLATED) TRIP, 'A' GROUP 7 (ONE | | REACTOR WATER SAMPLE LINE VALVE CLOSED) TRIP, 'A' AND 'B' GROUP 3 (REACTOR | | WATER CLEANUP) TRIPS, AND 'A' AND 'B' GROUP 6 (SECONDARY CONTAINMENT | | ISOLATIONS AND SOME PRIMARY CONTAINMENT VENT AND PURGE VALVES ISOLATED) | | TRIPS. | | | | THE 'A' RPS BUS WAS TRANSFERRED TO ITS ALTERNATE POWER SUPPLY AND THE ABOVE | | MENTIONED ISOLATIONS ARE BEING RESTORED TO THEIR NORMAL LINEUPS. THE CAUSE | | OF THE '1A2' EPA BREAKER TRIPPING OPEN IS BEING INVESTIGATED. | | | | ALL EMERGENCY CORE COOLING SYSTEMS, EMERGENCY DIESEL GENERATORS, AND THE | | REACTOR CORE ISOLATION COOLING SYSTEM ARE FULLY OPERABLE, IF NEEDED. THE | | LICENSEE ALSO STATED THAT THE ELECTRICAL GRID IS STABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+