U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/08/94 - 07/11/94 ** EVENT NUMBERS ** 27390 27491 27498 27503 27505 27506 27507 27508 27509 27510 27511 27512 27513 27514 27515 27516 27517 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27390 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/13/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 14:27 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/10/94 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: JOE BURGIN |LAST UPDATE DATE: 07/08/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AS A RESULT OF DESIGN DOCUMENTATION REVIEWS RELATED TO THE AUXILIARY | | FEEDWATER SYSTEM, THE LICENSEE HAS DISCOVERED THAT THE CABLE SEPARATION | | REQUIREMENTS ARE NOT MET FOR THE AUXILIARY FEEDWATER FLOW INDICATION | | INSTRUMENTATION. THE SEPARATION BETWEEN TRAIN 1 AND TRAIN 2 IS LESS THAN | | 12 INCHES IN SOME AREAS WHICH IS LESS THAN CATEGORY 1 REQUIREMENTS. | | | | THE LICENSEE HAS INSTALLED TWO CHANNELS OF WIDE RANGE LEVEL INDICATION ON | | EACH STEAM GENERATOR. THEY ARE EVALUATING TO SEE IF THEY CAN TAKE CREDIT | | FOR THIS INSTRUMENTATION IN LIEU OF THE AUXILIARY FEEDWATER FLOW | | INDICATION. | | | | THE NRC RESIDENT INSPECTOR, STATE AND LOCAL OFFICIALS HAVE BEEN NOTIFIED. | | | | *** RETRACTION FROM BATES TO HUFFMAN AT 09:31 EDT ON 7/8/94 *** | | LICENSEE REVIEW OF THE ELECTRICAL SEPARATION REQUIREMENTS FOR THE AUXILIARY | | FEEDWATER FLOW RATE INDICATORS REVEALED THAT THESE INDICATORS WERE NOT | | REQUIRED TO BE CATEGORY 1. THE ACTUAL INSTALLATION REQUIREMENTS IN REG | | GUIDE 1.97, REV 2, WHICH IS PART OF THE MILLSTONE UNIT 2 DESIGN BASIS, CALL | | FOR THESE AUX FEEDWATER FLOW RATE INDICATORS TO BE TYPE D, CATEGORY 2. | | SINCE THE INSTALLED INDICATORS MEET CATEGORY 2 REQUIREMENTS, THE PLANT WAS | | NEVER OUTSIDE ITS DESIGN BASIS, AND THE CONDITION IS NOT REPORTABLE. | | | | THE NRC RESIDENT INSPECTOR AND R1DO(DURR) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27491 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 07/06/94 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 15:12 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/06/94 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: ALLISON |LAST UPDATE DATE: 07/09/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |SKINNER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CHAFFEE EO | | |CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | AN NOUE WAS DECLARED WHEN ACCESS TO THE RIVER WATER STRUCTURE WAS LIMITED | | DUE TO INCREASED LEVEL OF THE RIVER CAUSED BY RAINS ASSOCIATED WITH | | TROPICAL STORM ALBERTO. | | | | AN NOUE WAS DECLARED AT 1330CDT WHEN ACCESS TO THE RIVER WATER STRUCTURE | | BECAME LIMITED DUE TO AN INCREASE IN RIVER LEVEL. AT 1400CDT, RIVER LEVEL | | WAS MEASURED AT 115 FEET, 10 INCHES. THE INCREASE IN RIVER LEVEL IS | | ATTRIBUTED TO RAINS ASSOCIATED WITH TROPICAL STORM ALBERTO. NO PLANT | | EQUIPMENT HAS BEEN AFFECTED BY THE RAINS AND STANDING WATER ONSITE. BOTH | | UNITS ARE STABLE AT 100%. OFFSITE POWER IS STABLE AND ALL SAFETY EQUIPMENT | | (EXCEPT THE "B" CONTAINMENT SPRAY PUMP FOR A NORMAL SURVEILLANCE) REMAINS | | OPERABLE AND AVAILABLE. | | | | RAINS CONTINUE AT THIS TIME. THE RIVER IS EXPECTED TO CREST AT 120 FEET | | SOMETIME TOMORROW. THE RIVER WATER STRUCTURE REMAINS ACCESSIBLE BY BOAT. | | PERSONNEL ARE AT THE STRUCTURE AT THIS TIME AND IT WILL BE MANNED AS LONG | | AS POSSIBLE. THE LICENSEE WILL ENTER AN ALERT AT A RIVER LEVEL GREATER | | THAN 127 FEET. THERE ARE CURRENTLY NO PLANS TO REDUCE POWER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE ALABAMA RADIATION | | CONTROL DIVISION AND GEORGIA EMERGENCY MANAGEMENT AGENCY WERE NOTIFIED. | | | | *** UPDATE FROM JOHNSON TO HUFFMAN AT 0430 EDT ON 7/7/94 *** | | CURRENT RIVER WATER LEVEL IS 120 FEET AND STILL RISING SLOWLY. MORE RAIN IS | | ANTICIPATED IN THE AREA. NORMAL RIVER WATER LEVEL THIS TIME OF YEAR WOULD | | BE APPROXIMATELY 90 FEET. THE RIVER WATER PUMP HOUSE CONTAINS PUMPS WHICH | | PROVIDE MAKEUP WATER TO THE LICENSEE'S COOLING TOWERS AND EMERGENCY COOLING | | POND. THE PUMP HOUSE IS NORMALLY ACCESSIBLE BY FOOT BUT IS NOW SURROUNDED | | BY THE SWOLLEN RIVER WATERS AND CAN BE REACHED ONLY VIA A PONTOON BOAT. | | PERSONNEL ARE STATIONED INSIDE THE PUMP HOUSE AND ARE MONITORING INLEAKAGE | | TO THAT STRUCTURE. SUMP PUMPS WITHIN THE BUILDING ARE CURRENTLY ABLE TO | | KEEP UP WITH THE INLEAKAGE. | | | | THE LICENSEE STATED THAT ACCESS TO AND FROM THE PLANT IS SATISFACTORY BUT | | THAT THE NATIONAL GUARD HAD BEEN STAGED AT KEY ROAD LOCATIONS TO ENSURE | | ADEQUATE EGRESS IF AN EVACUATION WERE NEEDED. LICENSEE MANAGEMENT PLANS TO | | EVALUATE CONTINUED FULL POWER OPERATIONS EARLY TODAY BASED ON THE WEATHER | | PREDICTIONS AT THAT TIME. | | | | R2DO(SKINNER) HAS BEEN NOTIFIED. | | | | HOO NOTE: THIS INFORMATION WAS OBTAINED DURING THE ROUTINE PLANT STATUS | | CALL AND WAS NOT PROVIDED AS A FORMAL UPDATE BY THE LICENSEE. | | | | * * * UPDATE 07/09/94 1029EDT FROM:VANDERBYE BY:SCARFO * * * | | THE NOUE WAS TERMINATED AT 0915CDT WHEN RIVER LEVEL DECREASED TO ALLOW | | NORMAL ACCESS TO THE RIVER WATER INTAKE STRUCTURE. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. STATE AND LOCAL AGENCIES WILL BE NOTIFIED. | | R2DO(SKINNER), EO(ROSSI), FEMA(SULLIVAN) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 27498 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BABCOCK & WILCOX CO. |NOTIFICATION DATE: 07/07/94 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 13:00 [ET]| |COMMENTS: HEU FABRICATION & SCRAP RECOVERY |EVENT DATE: 07/07/94 | | NAVAL REACTOR FUEL |EVENT TIME: 12:47[EDT]| | |LAST UPDATE DATE: 07/08/94 | | CITY: LYNCHBURG REGION: 2 +-----------------------------+ | COUNTY: CAMPBELL STATE: VA |PERSON ORGANIZATION| |LICENSE#: SNM-42 AGREEMENT: N |SKINNER RDO | | DOCKET: 07000027 |PAPERIELLO EO | +------------------------------------------------+ROY FEMA | |NRC NOTIFIED BY: COFFEY | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: UNUSUAL EVENT | | |10 CFR SECTION: | | | | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED - FIRE IN A METALLURGICAL LAB WITH A MINOR INJURY | | | | A METAL FIRE OCCURRED WHEN REPAIRS WERE BEING MADE TO A SAW. AN UNUSUAL | | EVENT WAS DECLARED AT 1247 EDT. THE FIRE BURNED FOR ONLY A SHORT TIME | | BEFORE BEING EXTINGUISHED. NO OUTSIDE ASSISTANCE WAS REQUESTED. ONE | | WORKER RECEIVED A MINOR BURN AND WAS TREATED ON SITE. THERE WAS NO RELEASE | | OF RADIOACTIVITY. NO INFORMATION WAS IMMEDIATELY AVAILABLE ABOUT THE | | SPREAD OF CONTAMINATION IN THE FIRE AREA. THE UNUSUAL EVENT WAS TERMINATED | | AT 1308 EDT. | | | | THE LICENSEE NOTIFIED CAMEL COUNTY, THE VIRGINIA DEPARTMENT OF EMERGENCY | | SERVICES AND THE NRC RESIDENT. THE LICENSEE IS PREPARING A PRESS RELEASE. | | | | * * * UPDATE FROM OLSEN AT 1234 EDT ON 7/8/94 TAKEN BY WEAVER * * * | | | | THE LICENSEE REPORTED THE EVENT UNDER 10 CFR 70.50 (24 HOUR NOTIFICATION). | | THE FOLLOWING ADDITIONAL INFORMATION WAS PROVIDED. | | | | "AT APPROXIMATELY 1230 , JULY 7, 1994, A FIRE OCCURRED IN THE BAY 7A | | METALLURGICAL LAB AT B&W'S NAVAL NUCLEAR FUEL DIVISION PLANT IN CAMPBELL | | COUNTY, VIRGINIA. TWO MAINTENANCE WORKERS WERE REPAIRING A SAW IN THE | | LABORATORY WHEN METAL FINES (CHIPS) AUTO IGNITED. THE MATERIAL CONTAINED | | ENRICHED URANIUM AND BECAME AIRBORNE. SIX PEOPLE WERE EXPOSED TO THE | | AIRBORNE MATERIAL. THEIR EXPOSURES ARE NOT KNOWN AT THIS TIME. AIR | | SAMPLING DATA HAS NOT BEEN FULLY EVALUATED AT THIS TIME. FIVE INDIVIDUALS | | WERE CONTAMINATED UP TO 1000 DPM. ONE INDIVIDUAL RECEIVED BURNS TO HIS | | RIGHT ARM, WAS TREATED AT THE SCENE, AND RETURNED TO WORK. THE LABORATORY | | IS BEING DECONTAMINATED. ACTIONS TO BE TAKEN TO PREVENT A RECURRENCE OF | | THIS TYPE OF EVENT WILL BE DETERMINED AT THE CONCLUSION OF THE | | INVESTIGATION. HOO NOTIFIED R2 RDO (SKINNER) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27503 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/07/94 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 16:53 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/07/94 | +------------------------------------------------+EVENT TIME: 16:13[EDT]| |NRC NOTIFIED BY: ROBERT MALONEY |LAST UPDATE DATE: 07/08/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ERNIE ROSSI EO | | |CHARLES SHULL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH FIRE SUPPRESSION PUMPS BEING DECLARED | | INOPERABLE. | | | | THE PLANT HAS TWO FIRE SUPPRESSION PUMPS. P-4 IS AN ELECTRIC DRIVEN PUMP | | AND P-5 IS A DIESEL DRIVEN PUMP. THE P-4 PUMP WAS TAKEN OUT OF SERVICE ON | | 6/30/94 TO REPAIR THE PUMP MOTOR. THE P-5 PUMP HAD A SURVEILLANCE | | PERFORMED ON IT TODAY. THE SURVEILLANCE PROCEDURE REQUIRED A MANUAL START | | OF THE FIRE PUMP. THE FIRST TIME A MANUAL START OF THE FIRE PUMP WAS | | ATTEMPTED IT FAILED, ON THE SECOND ATTEMPT THE PUMP STARTED AND THE | | LICENSEE LEFT THE PUMP RUNNING. THE LICENSEE CONSIDERED THE P-5 PUMP | | OPERABLE BECAUSE IT WAS RUNNING. | | | | TO ALLOW TROUBLESHOOTING OF THE P-5 FIRE PUMP THE LICENSEE HAD THE LOCAL | | FIRE DEPARTMENT SUPPLY A PUMPER. THE PUMPER WAS CONNECTED TO THE MAINE | | YANKEE FIRE SUPPRESSION SYSTEM AND A DEDICATED MAINE YANKEE OPERATOR WAS | | SUPPLIED TO CONTROL THE FIRE DEPARTMENT CONNECTION AND MAINTAIN THE SYSTEM | | PRESSURE. AFTER THIS WAS DONE P-5 WAS SHUTDOWN TO PERFORM TROUBLESHOOTING. | | WHEN P-5 WAS ATTEMPTED TO BE RESTARTED IT DID NOT START. THE LICENSEE | | DECLARED THE PUMP INOPERABLE AND ENTERED AN UNUSUAL EVENT. | | | | TECH SPEC 3.23.B.2 REQUIRES THE LICENSEE TO ESTABLISH A BACKUP FIRE | | SUPPRESSION SYSTEM WITHIN 24 HOURS (WHICH WAS ALREADY ESTABLISHED PRIOR TO | | STOPPING PUMP P-5) AND ALSO TO ISSUE VARIOUS REPORTS TO THE NRC. THE TECH | | SPEC DOES NOT REQUIRE THE LICENSEE TO SHUTDOWN. THE BASIS FOR TERMINATION | | OF THE UNUSUAL EVENT IS THE RESTORATION OF ONE OF THE TWO FIRE SUPPRESSION | | PUMPS. THE LICENSEE IS CURRENTLY TROUBLESHOOTING PUMP P-5 AND SUSPECTS | | THAT THE CAUSE OF THE PROBLEM IS LOW VOLTAGE IN THE STARTING CIRCUITRY FOR | | THE PUMP. THE LICENSEE IS UNSURE AT THIS TIME HOW LONG IT WILL TAKE TO | | MAKE REPAIRS. THE FIRE PUMPER THAT WAS BROUGHT ONSITE IS CURRENTLY RUNNING | | IN A RECIRC MODE TO SUPPLY THE FIRE SUPPRESSION HEADER. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND ALSO STATE AND LOCAL | | OFFICIALS. THE LICENSEE MAY ISSUE A PRESS RELEASE. | | | | * * * UPDATE 7/7/94 @ 20:08 FORM MALONEY TAKEN BY SEBROSKY * * * | | THE LICENSEE IS REQUIRED BY TECH SPEC 3.23.B REMEDIAL ACTION #2 TO NOTIFY | | THE NRC WITHIN 24 HOURS BY TELEPHONE OR TELEGRAPH OF ESTABLISHING A BACKUP | | FIRE SUPPRESSION SYSTEM. THEREFORE IN ADDITION TO INFORMING THE NRC OF THIS | | EVENT BECAUSE IT WAS AN UNUSUAL EVENT THE LICENSEE IS ALSO MAKING THIS | | REPORT IN ACCORDANCE WITH THEIR TECH SPECS. THE LICENSEE'S TECH SPECS ALSO | | REQUIRES THAT THE LICENSEE ISSUE A SPECIAL WRITTEN REPORT TO THE NRC WITHIN | | 14 DAYS OF THE EVENT. | | | | THE LICENSEE HAS STOPPED THE FIRE PUMPER THAT WAS BROUGHT ONSITE. THE | | LICENSEE DID THIS BECAUSE THERE ARE NO LOADS ON THE SYSTEM CURRENTLY. THE | | PUMPER IS STILL CONNECTED TO THE FIRE HEADER AND THE LICENSEE STILL HAS ONE | | DEDICATED MAINE YANKEE OPERATOR AND TWO INDIVIDUALS FROM THE FIRE | | DEPARTMENT ASSIGNED TO THE PUMPER. THE LICENSEE HAS ALSO ISSUED A 2 PAGE | | INTERIM DOCUMENT TO IMPLEMENT PROCEDURES TO MINIMIZE THE RISK OF A FIRE | | ONSITE UNTIL THE DIESEL DRIVEN PUMP (P-5) CAN BE PLACED BACK IN SERVICE. | | THE DOCUMENT INCLUDES STEPS SUCH AS NO SPARK PRODUCING OPERATIONS ALLOWED, | | NO USE OF FLAMMABLE LIQUIDS IN THE PLANT IS AUTHORIZED ETC... THE DOCUMENT | | ALSO INCLUDES PROCEDURES FOR USE OF THE TEMPORARY FIRE PUMPER. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. HOO NOTIFIED R1DO(DURR) | | AND EO(ROSSI). | | | | * * * UPDATE 7/8/94 @ 17:41 FROM MALONEY TAKEN BY SEBROSKY * * * | | THE UNUSUAL EVENT WAS TERMINATED AT 16:52 7/8/94 WHEN PUMP P-5 WAS RETURNED | | TO SERVICE. THE PROBLEM WITH P-5 WAS DISCOVERED TO BE IN THE WIRING FOR | | THE STARTING CIRCUIT, THE PROBLEM WAS REPAIRED, AND THE PUMP TESTED. THE | | BACKUP FIRE PUMP HAS BEEN RELEASED FROM THE SITE AT THIS TIME. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND STATE AND LOCAL | | OFFICIALS. THE LICENSEE WILL ALSO ISSUE A PRESS RELEASE. HOO NOTIFIED | | R1DO(DURR), EO(ROSSI) AND FEMA(SHULL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27505 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 3 |NOTIFICATION DATE: 07/08/94 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 11:04 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 07/08/94 | +------------------------------------------------+EVENT TIME: 09:18[CDT]| |NRC NOTIFIED BY: TOM SHARKEY |LAST UPDATE DATE: 07/08/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 94 POWER OPERATION | 94 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DELIBERATE ENTRY INTO TECH SPEC 3.0.3 TO REPAIR LEAKING RELIEF VALVE ON | | HIGH HEAD SAFETY INJECTION SYSTEM. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE REPORTING THIS EVENT: | | "RELIEF VALVE EM8852, LOCATED ON THE BORON INJECTION TANK(BIT), HAD | | DEVELOPED A LEAK. DURING TIMES WHEN THE CENTRIFUGAL PUMPS(CCP) ARE IN | | OPERATION, WATER LEAKS PAST THE SEAT OF EMHV8837A(B) OR EMHV8803A(B). THE | | WATER ENTERS THE BIT AND RELIEVES TO THE AUXILIARY BUILDING ATMOSPHERE | | THROUGH RELIEF VALVE EM8852. THIS LEAKAGE IS CONTRIBUTING TO REACTOR | | COOLANT SYSTEM (RCS) LEAKAGE. | | | | IN ORDER TO REPAIR THE LEAK, BOTH TRAINS OF THE HIGH HEAD SAFETY INJECTION | | (HHSIS) WERE REQUIRED TO BE RENDERED INOPERABLE. THE HHSIS IS A SUBSYSTEM | | OF THE EMERGENCY CORE COOLING SYSTEM (ECCS) REQUIRED BY TECHNICAL | | SPECIFICATION (T/S) 3.5.2. THE PLANNED MAINTENANCE WAS DISCUSSED WITH THE | | NRC RESIDENT INSPECTOR AND STAFF MEMBERS OF REGION III AND NRR. A SPECIAL | | PROCEDURE WAS DRAFTED AND REVIEWED BY THE ON-SITE REVIEW COMMITTEE. | | | | AT 0918 CDT, ON JULY 8, 1994, BOTH TRAINS OF HHSIS WERE RENDERED INOPERABLE | | AND T/S 3.0.3 WAS ENTERED. ....... | | | | ...... THE LEAK WAS REPAIRED. T/S 3.0.3. WAS EXITED AND T/S 3.5.2 LIMITING | | CONDITION FOR OPERATION WAS SATISFIED AND 0928 CDT ON JULY 8, 1994." | | END OF TEXT. | | | | THE BIT TANK RELIEF VALVE HAD A O.69 GPM LEAK. THE LICENSEE TOOK HIGH HEAD | | SAFETY INJECTION OUT OF SERVICE FOR 10 MINUTES TO REPAIR THE LEAK. THE LEAK | | MAINTENANCE WAS SUCCESSFUL AND THE SYSTEM HAS BEEN RESTORED TO ITS NORMAL | | CONFIGURATION. AN LER WILL BE ISSUED IN 30 DAYS PROVIDING ADDITIONAL | | DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27506 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/08/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:17 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/08/94 | +------------------------------------------------+EVENT TIME: 09:47[CDT]| |NRC NOTIFIED BY: KEVIN DORWICK |LAST UPDATE DATE: 07/08/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 58 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM DUE TO HIGH REACTOR WATER LEVEL. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "WHILE TUNING THE 1B TURBINE DRIVEN REACTOR FEED PUMP INPUT FROM THE | | REACTOR WATER LEVEL CONTROL SYSTEM, FEEDWATER CONTROL BECAME ERRATIC AND | | THE MAIN TURBINE TRIPPED ON HIGH REACTOR WATER LEVEL OF 55.5 INCHES NARROW | | RANGE. THE REACTOR AUTOMATICALLY SCRAMMED ON THE SUBSEQUENT CLOSURE OF THE | | TURBINE STOP VALVES AND CONTROL VALVES. FOLLOWING THE INITIAL SCRAM | | REACTOR WATER LEVEL SHRANK TO APPROXIMATELY 10 INCHES ON NARROW RANGE. | | | | ADDITIONALLY THE '1B' DIESEL GENERATOR WAS RUNNING LOADED AND PARALLEL TO | | THE GRID IN ACCORDANCE WITH SURVEILLANCE PROCEDURE LOS DG-M3. THE '1B' | | DIESEL GENERATOR EXPERIENCED AN INCREASE IN AMPS AND VARS WHEN THE UNIT | | CAME OFF LINE. AN INVESTIGATION WILL DETERMINE THE CAUSE OF THE | | MALFUNCTION IN THE FEEDWATER CONTROL SYSTEM AND AN INSPECTION OF THE '1B' | | DG WILL ENSURE PROPER OPERATION OF THE '1B' DIESEL GENERATOR. ALL ECCS | | REMAINED OPERABLE AND ALL LOADS TRANSFERRED AS REQUIRED. ALL OTHER | | EQUIPMENT AND PLANT SYSTEMS OPERATED AS DESIGNED. | | | | ADDITIONALLY AT 55.5 INCHES HPCS AND RCIC SYSTEM RECEIVED SIGNALS TO | | PREVENT INJECTION BUT WOULD HAVE AUTO INITIATED AT THEIR SETPOINTS OF -50 | | INCHES REACTOR WATER LEVEL" END OF TEXT. | | | | THE REACTOR WAS AT REDUCED POWER IN ORDER TO DO TESTING ON THE REACTOR | | WATER LEVEL CONTROL SYSTEM. THE REACTOR WATER LEVEL CONTROL SYSTEM HAD | | BEEN RECENTLY MODIFIED DURING THE LAST UNIT 1 REFUELING OUTAGE. THE PLANT | | EXPERIENCED A SCRAM ON 7/5/94 (SEE EVENT # 27482) COMING OUT OF THE | | REFUELING OUTAGE DUE TO A PROBLEM WITH THE REACTOR WATER LEVEL CONTROL | | SYSTEM. | | | | ALL RODS FULLY INSERTED ON THE SCRAM, AND NO RELIEF VALVES LIFTED. THE | | DECAY HEAT RATE IS LOW DUE TO THE UNIT'S RECENT POWER HISTORY, THEREFORE | | THE LICENSEE DOES NOT HAVE TO BLEED STEAM TO MAINTAIN TEMPERATURE/PRESSURE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27507 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: R & R INTERNATIONAL INC |NOTIFICATION DATE: 07/08/94 | | CITY: MADISON REGION: 3 |NOTIFICATION TIME: 14:26 [ET]| | COUNTY: STATE: OH |EVENT DATE: 07/08/94 | |LICENSE#: 3420292-02 AGREEMENT: N |EVENT TIME: 08:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/08/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | |DR. CARL PAPERIELLO EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LARRY BLASIO | | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A MOISTURE DENSITY GAGE OWNED BY R & R INTERNATIONAL INC WAS DISCOVERED TO | | BE MISSING AT A CONSTRUCTION SITE IN MADISON OHIO. | | | | THE MOISTURE DENSITY GAGE IS A CPN MODEL MC-3 GAGE. IT CONTAINS A 7 | | MILLICURIE OF CESIUM 137 AND A 50 MILLICURIE OF AMERICIUM 241. THE GAGE | | WAS SECURED INSIDE A LOCKED BOX, INSIDE A LOCKED TRAILER, INSIDE A LOCKED | | FENCE THE NIGHT OF 7/7/94. ON THE MORNING OF 7/8/94 IT WAS DISCOVERED THAT | | 4 TRAILERS ON THE CONSTRUCTION SITE HAD BEEN BROKEN INTO AND VARIOUS THINGS | | HAD BEEN STOLEN INCLUDING THE BOX CONTAINING THE MOISTURE DENSITY GAGE. THE | | LICENSEE HAS INFORMED THE MADISON POLICE DEPARTMENT OF THE THEFT AND PLANS | | TO ISSUE A PRESS RELEASE IN CONJUNCTION WITH THE POLICE DEPARTMENT IN AN | | ATTEMPT TO RECOVER THE GAGE. | | | | THE LICENSEE HAS DISCUSSED THIS PROBLEM WITH REGION III (GIBBONS) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27508 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/08/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 16:32 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/08/94 | +------------------------------------------------+EVENT TIME: 13:55[EDT]| |NRC NOTIFIED BY: DENNIS MOONEY |LAST UPDATE DATE: 07/08/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR BLOWDOWN ISOLATED DUE TO "CROSS TALK" BETWEEN RADIATION | | MONITORS. | | | | THE LICENSEE WAS IN THE PROCESS OF DISCHARGING A WASTE GAS DECAY TANK AND | | DUE TO "CROSS TALK" BETWEEN RADIATION MONITORS THE STEAM GENERATOR BLOWDOWN | | SYSTEM ISOLATED. THE "CROSS TALK" PROBLEM IS A PROBLEM THAT HAS OCCURRED | | IN THE PAST. THE RADIATION MONITORS INVOLVED WERE A RADIATION MONITOR IN | | THE WASTE GAS SYSTEM, THE STEAM GENERATOR BLOWDOWN RADIATION MONITOR AND/OR | | THE STEAM JET AIR EJECTOR RADIATION MONITOR. | | | | WHEN THE DISCHARGE OF THE WASTE GAS DECAY TANK STARTED THE RADIATION | | MONITOR IN THAT SYSTEM INCREASED AS EXPECTED. THE INCREASE IN THIS MONITOR | | CAUSED EITHER THE STEAM JET AIR EJECTOR RADIATION MONITOR OR THE STEAM | | GENERATOR BLOWDOWN MONITOR TO SPIKE AND CAUSE THE ISOLATION OF TWO VALVES | | (2MS220A & 2MS220B) IN THE STEAM GENERATOR BLOWDOWN SYSTEM. THE LICENSEE | | VERIFIED THAT THERE WAS NOT A VALID HIGH RADIATION MONITORING SIGNAL | | ASSOCIATED WITH THE STEAM GENERATOR BLOWDOWN SYSTEM, RESET THE ISOLATION | | SIGNAL, AND RETURNED THE STEAM GENERATOR BLOWDOWN SYSTEM TO NORMAL | | OPERATION. | | | | THE LICENSEE IS INVESTIGATING THE "CROSS TALK" PROBLEM. THE LICENSEE | | CONSIDERS ALL THE RADIATION MONITORS INVOLVED OPERABLE AT THIS TIME. THE | | LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND STATE AND LOCAL OFFICIALS | | IN ACCORDANCE WITH THEIR PROCEDURES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27509 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/08/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 21:48 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/08/94 | +------------------------------------------------+EVENT TIME: 21:05[EDT]| |NRC NOTIFIED BY: DENNIS MOONEY |LAST UPDATE DATE: 07/08/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UPON SECURING THE DISCHARGE OF THE WASTE GAS DECAY TANK THE LICENSEE | | EXPERIENCED THE SAME PROBLEM REPORTED IN EVENT 27508 (i.e DUE TO "CROSS | | TALK" BETWEEN RADIATION MONITORS STEAM GENERATOR BLOWDOWN WAS ISOLATED) | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE "CROSS TALK". THE SIGNAL | | HAS BEEN RESET AND STEAM GENERATOR BLOWDOWN SYSTEM HAS BEEN RETURNED TO | | NORMAL OPERATION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND STATE AND LOCAL | | OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27510 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/09/94 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 09:48 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/09/94 | +------------------------------------------------+EVENT TIME: 08:50[EDT]| |NRC NOTIFIED BY: WILLOUGHBY |LAST UPDATE DATE: 07/09/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO AN AREA BOUNDARY. IMMEDIATE | | COMPENSATORY ACTIONS WERE TAKEN UPON DISCOVERY. SEE HOO LOG FOR DETAILS. | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27511 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 07/09/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 18:01 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/09/94 | +------------------------------------------------+EVENT TIME: 15:50[CDT]| |NRC NOTIFIED BY: DAVID SCHUSSLER |LAST UPDATE DATE: 07/09/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF THE STANDBY GAS TREATMENT TRAINS WERE DECLARED INOPERABLE | | DUE TO THE DISCOVERY THAT THEY WERE UNABLE TO MEET THEIR TECH SPEC REQUIRED | | FLOW RATES. | | | | THE PROBLEM WAS IDENTIFIED DURING A ROUTINE MONTHLY SURVEILLANCE. THE TECH | | SPEC REQUIRED FLOW RATE IS 3600 SCFM PER TRAIN. THE TRAIN 'A' VALUE | | OBTAINED DURING THE SURVEILLANCE WAS 34OO SCFM WHILE TRAIN 'B' WAS 3460 | | SCFM. THE LICENSEE HAS ENTERED TECH SPEC 3.7.B.2 WHICH REQUIRES THE PLANT | | TO BE IN HOT SHUTDOWN WITHIN 12 HOURS IF THE PROBLEM IS NOT FIXED. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE PROBLEM AND IS ALSO | | REVIEWING THE BASIS FOR 3600 SCFM LIMIT. THE RESIDENT INSPECTOR HAS BEEN | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27512 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/09/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/09/94 | +------------------------------------------------+EVENT TIME: 18:35[EDT]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 07/10/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE LOST A RADIO TRANSMITTER THAT WOULD INFORM THE PUBLIC IN THE | | EVENT OF A PROBLEM AT THE PLANT. | | | | THE CAUSE OF THE LOSS OF THE RADIO TRANSMITTER IS BEING INVESTIGATED AT | | THIS TIME. THE LICENSEE SUSPECTS THE CAUSE OF THE PROBLEM MAY BE DUE TO | | LIGHTENING IN THE AREA. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR AND OFFICIALS OF THE STATE | | OF MASSACHUSETTS, VERMONT, AND NEW HAMPSHIRE. | | | | * * * UPDATE 07/10/94 0115EDT FROM:CROKE BY:SCARFO * * * | | THE RADIO TRANSMITTER WAS RETURNED TO SERVICE AT 0107EDT. STATE AND LOCAL | | AGENCIES WILL BE NOTIFIED. R1DO(DURR) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27513 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 07/09/94 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 22:08 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/09/94 | +------------------------------------------------+EVENT TIME: 21:10[EDT]| |NRC NOTIFIED BY: DOUG MASON |LAST UPDATE DATE: 07/09/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 87 POWER OPERATION | 87 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO LESS THAN A 1 GALLON OIL SPILL FROM A DAM | | DOWNSTREAM OF THE SITE. | | | | THE LICENSEE NOTIFIED THE NATIONAL RESPONSE CENTER AND THE VIRGINIA | | DEPARTMENT OF EMERGENCY SERVICES OF A SPILL OF LESS THAN 1 GALLON OF OIL. | | THE SPILL WAS CAUSED BY A STORM THAT WENT THREW THE AREA AND BLEW A WASTE | | OIL BUCKET INTO THE DOWNSTREAM RIVER SPILLWAY AT THE HYDRO FACILITY. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27514 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 07/10/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 01:16 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 07/10/94 | +------------------------------------------------+EVENT TIME: 01:00[EDT]| |NRC NOTIFIED BY: DEMONCH |LAST UPDATE DATE: 07/10/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DURR RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 85 POWER OPERATION | 85 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TECHNICAL-SPECIFICATION REQUIRED SHUTDOWN WAS INITIATED WHEN FAILED RELAY | | CAUSED THE DRYWELL LEAK DETECTION SYSTEM TO BE INOPERABLE. | | | | THE "HIGH-HIGH DRYWELL SUMP LEVEL" RELAY IN CABINET "1M175" FAILED CAUSING | | A CONTROL POWER FUSE TO FAIL AND A LOSS OF POWER TO THE DRYWELL SUMP | | INTEGRATOR AND DRYWELL LEVEL SWITCHES IN THE SUMP. THE DRYWELL LEAK RATE | | DETECTION SYSTEM WAS DECLARED INOPERABLE AND TECHNICAL SPECIFICATION (T/S) | | ACTION STATEMENT 3.3.D.4 WAS ENTERED. A T/S-REQUIRED SHUTDOWN WAS | | INITIATED FROM 85% POWER AS A CONSEQUENCE OF THE ACTION STATEMENT. | | | | THE FAILED RELAY IS BEING REMOVED AND POWER IS BEING RESTORED TO THE | | DRYWELL SUMP INTEGRATOR (THE BACKUP SYSTEM TO THE DRYWELL LEAK RATE | | DETECTION SYSTEM). WHEN THE INTEGRATOR IS RETURNED TO SERVICE OR THE | | DRYWELL LEVEL RECORDER RETURNS TO SCALE (OFF SCALE LOW DUE TO THE | | ASSOCIATED AUTO-START OF BOTH DRYWELL SUMP PUMPS ON THE LOSS OF THE RELAY), | | THE T/S-REQUIRED SHUTDOWN WILL BE TERMINATED. THE LICENSEE ANTICIPATES | | COMPLETION OF REPAIRS WITHIN ONE HOUR. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. A PRESS RELEASE IS ANTICIPATED. | | | | * * * UPDATE 07/10/94 0322EDT FROM:DEMONCH BY:SCARFO * * * | | THE T/S-REQUIRED SHUTDOWN WAS TERMINATED AT 0315 AT 79% WHEN THE FAILED | | RELAY WAS "JUMPERED-OUT" AND CONTROL POWER WAS RESTORED TO THE DRYWELL SUMP | | INTEGRATOR. THE DRYWELL LEAK RATE DETECTION SYSTEM WAS DECLARED OPERABLE, | | AS WELL. THE BACKUP DRYWELL LEVEL RECORDER HAS ALSO RETURNED TO SCALE. THE | | RELAY REMAINS OUT-OF-SERVICE WITH THE ASSOCIATED HIGH-HIGH SUMP LEVEL ALARM | | AND AUTOMATIC PUMP-START. THE RELAY WILL BE REPLACED AND THE ALARM | | RESTORED TO SERVICE AT SOME UNSPECIFIED TIME. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. R1DO(DURR) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27515 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 07/10/94 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/10/94 | +------------------------------------------------+EVENT TIME: 13:55[EDT]| |NRC NOTIFIED BY: JACK BRISSON |LAST UPDATE DATE: 07/10/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 56 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM 56% POWER DUE TO A LOSS OF FEEDWATER. | | | | WITH UNIT 2 AT 100 % AND ATTEMPTING TO IMPROVE A HIGH THRUST BEARING | | TEMPERATURE PROBLEM ON THE '2A' FEEDWATER PUMP TEMPERATURE BEGAN INCREASING | | TO 210 DEGREES F. THE PUMP WAS MANUALLY TRIPPED AND A TURBINE RUNBACK | | AUTOMATICALLY INITIATED. THE UNIT WAS BEING STABILIZED AT APPROXIMATELY | | 56% POWER AND THE DIGITAL FEEDWATER CONTROL SYSTEM WAS ATTEMPTING TO | | CONTROL STEAM GENERATOR LEVELS. LEVEL CONTINUED TO GO HIGH ON 2 STEAM | | GENERATORS (STEAM GENERATORS 'A' AND 'C'). LEVEL CONTROL WAS THEN TAKEN TO | | MANUAL IN AN ATTEMPT TO RESTORE THE LEVEL IN THE STEAM GENERATORS. THE 'C' | | STEAM GENERATOR LEVEL REACHED THE HIGH HIGH LEVEL SETPOINT, HOWEVER, AND | | THIS CAUSED AN ISOLATION OF THE FEEDWATER SYSTEM AND A TURBINE TRIP. THE | | OPERATORS THEN MANUALLY TRIPPED THE REACTOR IN ACCORDANCE WITH THEIR | | PROCEDURES. | | | | ALL RODS FULLY INSERTED ON THE TRIP. NO PRIMARY RELIEF VALVES OR PORVS | | LIFTED, A SECONDARY ATMOSPHERIC DUMP VALVE AND POSSIBLY ONE SECONDARY PORV | | VALVE DID LIFT AND RESEAT. THE AUXILIARY FEEDWATER SYSTEM AUTOSTARTED AS | | EXPECTED AND IS CURRENTLY MAINTAINING STEAM GENERATOR WATER LEVELS. THE | | MAIN CONDENSER IS AVAILABLE AS A HEAT SINK. ALL ELECTRICAL BUSSES | | TRANSFERRED AS EXPECTED AND ALL ECCS AND EMERGENCY DIESEL GENERATORS ARE | | OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE HIGH THRUST BEARING | | TEMPERATURE ON THE '2A' FEED PUMP AND ALSO THE RESPONSE OF THE DIGITAL | | FEEDWATER CONTROL SYSTEM. IN ADDITION THE LICENSEE IS INVESTIGATING THE | | AUTOMATIC TURBINE RUNBACK. THE LICENSEE IS NOT SURE AT THIS TIME IF THE | | RUNBACK WAS TO THE PROPER POWER. THE AUTOMATIC RUNBACK IS SUPPOSED TO | | REDUCE POWER TO 65% POWER. THE OPERATORS BELIEVED THE RUNBACK REDUCED | | POWER TO AROUND 70% POWER. IN RESPONSE TO THIS THE LICENSEE HAD TAKEN | | MANUAL CONTROL OF THE TURBINE AND WAS IN THE PROCESS OF REDUCING POWER WHEN | | THE AUTOMATIC FEEDWATER ISOLATION OCCURRED DUE TO A HIGH HIGH STEAM | | GENERATOR LEVEL. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27516 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 07/11/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 00:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/10/94 | +------------------------------------------------+EVENT TIME: 22:01[CDT]| |NRC NOTIFIED BY: MANKIN |LAST UPDATE DATE: 07/11/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A MANUAL REACTOR SCRAM WAS INITIATED IN RESPONSE TO A LARGE ELECTRO | | -HYDRAULIC CONTROL (EHC) SYSTEM FLUID LEAK. | | | | IN RESPONSE TO AN EHC FLUID LOW LEVEL ALARM AND CONFIRMED A SIGNIFICANT EHC | | FLUID LEAK, OPERATORS INITIATED A MANUAL REACTOR SCRAM. ALL RODS FULLY | | INSERTED ON THE SCRAM. A TURBINE TRIP OCCURRED ON REVERSE GENERATOR POWER, | | AS EXPECTED. REACTOR WATER LEVEL "SHRUNK" TO 160 INCHES, BELOW THE LOW | | LEVEL REACTOR SCRAM/GROUP ISOLATION SETPOINT OF 170 INCHES. A GROUP 2 | | (DRYWELL SUMP VALVES) ISOLATION, GROUP 3 (PRIMARY AND SECONDARY | | CONTAINMENT) ISOLATION, GROUP 4 (SHUTDOWN COOLING) ISOLATION, AND GROUP 5 | | (REACTOR WATER CLEANUP) ISOLATION OCCURRED. AFTER REACTOR WATER LEVEL | | RECOVERED ABOVE 170 INCHES, OPERATORS CLEARED THE ISOLATIONS AND RESET THE | | SYSTEMS. A RECIRCULATION SYSTEM RUNBACK TO 20% OF MAXIMUM RECIRCULATION | | FLOW OCCURRED ON THE DECREASE IN FEED FLOW, AS EXPECTED. NO SAFETY/RELIEF | | VALVES LIFTED DURING THE SCRAM. NO OTHER ESF OR ECCS ACTUATIONS OCCURRED. | | ALL ELECTRICAL LOADS TRANSFERRED PROPERLY TO OFFSITE POWER. | | | | BYPASS VALVES WERE UTILIZED INITIALLY TO DISSIPATE DECAY HEAT, HOWEVER, | | OPERATORS OPENED STEAM LINE DRAIN VALVES TO PROCEED WITH THE COOLDOWN, | | CLOSED THE BYPASS VALVES, AND SECURED THE EHC SYSTEM. | | | | CURRENTLY, THE UNIT IS STABLE IN HOT SHUTDOWN. THE MAIN FEEDWATER SYSTEM | | IS FEEDING THE VESSEL AND STEAM LINE DRAINS ARE BEING UTILIZED TO DISSIPATE | | DECAY HEAT. OFFSITE POWER IS SUPPLYING ALL ELECTRICAL LOADS AND ALL | | EMERGENCY DIESEL GENERATORS ARE OPERABLE. | | | | THE CAUSE OF THE EHC LEAK IN UNDER INVESTIGATION AT THIS TIME. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27517 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 07/11/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 00:51 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 07/11/94 | +------------------------------------------------+EVENT TIME: 00:01[EDT]| |NRC NOTIFIED BY: ALEJANDRO |LAST UPDATE DATE: 07/11/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 85 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN AUTOMATIC REACTOR SCRAM OCCURRED FOR UNKNOWN REASONS. | | | | WHILE INCREASING TO 100% POWER, AN AUTOMATIC REACTOR SCRAM OCCURRED FOR | | UNKNOWN REASONS. ALL RODS FULLY INSERTED AND AN AUTOMATIC TURBINE TRIP | | OCCURRED ON THE REACTOR SCRAM, AS EXPECTED. REACTOR WATER LEVEL "SHRUNK" | | TO 25 INCHES, WELL BELOW THE LOW-LEVEL REACTOR SCRAM SETPOINT OF 53 INCHES. | | ONLY ONE OF TWO FEEDWATER COOLANT INJECTION (FWCI) PUMPS ACTUATED ON THE | | TURBINE TRIP. ALL OTHER PLANT SYSTEMS RESPONDED AS EXPECTED. | | | | CURRENTLY, THE UNIT IS STABLE IN HOT SHUTDOWN. THE MAIN FEED SYSTEM IS | | SUPPLYING THE VESSEL AND DECAY HEAT IS BEING DISSIPATED TO THE CONDENSER | | VIA BYPASS VALVES. OFFSITE POWER IS SUPPLYING ELECTRICAL LOADS AND ALL | | EMERGENCY DIESEL GENERATORS ARE OPERABLE. | | | | AN INVESTIGATION IS UNDERWAY TO DETERMINED THE CAUSE OF THE SCRAM AND THE | | REASON FOR THE DEFICIENT FWCI PUMP RESPONSE. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | | | | * * * UPDATE 07/11/94 0310EDT FROM:ALEJANDRO BY:SCARFO * * * | | A POST-TRIP ANALYSIS HAS DETERMINED THAT A FAILURE OF THE ELECTRONIC | | PRESSURE REGULATOR (EPR) CAUSED TURBINE CONTROL VALVES TO CLOSE, A REACTOR | | COOLANT SYSTEM (RCS) PRESSURE SPIKE, AND AN ASSOCIATED AVERAGE POWER RANGE | | MONITOR (APRM) HIGH (FLOW-BIASED) SCRAM SIGNAL. APRMs REGISTERED A HIGH | | POWER MEASUREMENT OF 107% PRIOR TO THE SCRAM. AN INVESTIGATION INTO THE | | FAILED COMPONENT OF THE EPR IS ONGOING. | +------------------------------------------------------------------------------+