U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/25/94 - 05/26/94 ** EVENT NUMBERS ** 27184 27258 27295 27296 27298 27299 27300 27301 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/29/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 02:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/29/94 | +------------------------------------------------+EVENT TIME: 00:46[EDT]| |NRC NOTIFIED BY: VARGA |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 +------------------------------------------------------------------------------+ | THE PLANT HAD AN ESF ACTUATION WHEN THEY RECEIVED AN AUTO START OF THE #11 | | MOTOR DRIVEN AUX FEEDWATER PUMP. | | | | THIS OCCURRED WHILE THEY WERE BREAKING CONDENSER VACUUM AND BOTH S/G FEED | | PUMPS RECEIVED A FIRST OUT TRIP SIGNAL WHEN VACUUM WAS REDUCED TO 0 PSIG. | | THIS FIRST OUT TRIP SIGNAL AUTOMATICALLY SENDS A START SIGNAL TO THE MOTOR | | DRIVEN AUX FEED PUMPS. THE # 11 AUX FEED PUMP HAD BEEN TEMPORARILY | | RELEASED FOR TESTING ON THE DAY SHIFT(4/28/94) AND HAD NOT BEEN RETAGGED | | FOR SHIFT SUPERVISOR. SINCE THIS PUMP HAD NOT BEEN RETAGGED, IT STARTED ON | | THE AUTO START SIGNAL. THE PUMP WAS SECURED WITHIN 5 MINS. THE RI WAS | | INFORMED AND LAC TOWNSHIP WAS NOTIFIED. | | | | * * * UPDATE 05/25/94 1155EDT FROM:KAFANTARIS BY:SCARFO * * * | | THE LICENSEE IS RETRACTING THIS EVENT ON THE BASIS OF THE SEPTEMBER, 1992, | | REVISION OF 10CFR50.72 & 50.73 (CRITERIA 2-AN ACTUATION THAT IS INVALID AND | | OCCURS AFTER THE SAFETY FUNCTION HAS BEEN COMPLETED) AND NUREG-1022. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R1DO(ANDERSON) NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/16/94 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 06:12 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/16/94 | +------------------------------------------------+EVENT TIME: 04:23[EDT]| |NRC NOTIFIED BY: C.N. SWENSON |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED A RHR HIGH PRESSURE ISOLATION DURING FLUSHING DUE TO | | POSSIBLE OUT OF CALIBRATION PRESSURE SWITCHES. | | | | "WITH REACTOR PRESSURE APPROXIMATELY 33 PSIG THE RHR SHUTDOWN COOLING | | PIPING WAS BEING FLUSHED IN PREPARATION FOR RHR SHUTDOWN COOLING MODE. | | REACTOR LEVEL WAS RAISED TO +40 INCHES PER PROCEDURE TO ACCOMMODATE THE | | FLUSH. FOLLOWING THE FIRST FLUSH THE REACTOR LEVEL CONTROLLER OVERSHOT TO | | APPROXIMATELY +50 INCHES. THE COMBINATION OF REACTOR DOME PRESSURE AND THE | | WATER LEG PRESSURE CAUSED BY THE HIGH REACTOR LEVEL CAUSED THE SHUTDOWN | | COOLING HIGH PRESSURE ISOLATION SIGNAL TO ACTUATE. THE ISOLATION WENT TO | | COMPLETION AS EXPECTED. HOWEVER, THE ISOLATION WAS NOT EXPECTED AND THE | | POTENTIAL WAS NOT ADDRESSED IN THE OPERATING PROCEDURE. INVESTIGATION IS | | CONTINUING INTO POSSIBLE PROCEDURE ENHANCEMENT OR POSSIBLE OVERLY | | CONSERVATIVE OR OUT OF CALIBRATION PRESSURE SWITCHES." | | | | THE LICENSEE IS REVIEWING CALIBRATION SHEETS TO VERIFY THAT NORMAL +23 | | INCHES STATIC HEAD IS INCLUDED IN THE PRESSURE SWITCH SETPOINT OF 60.5 | | PSIG. WITH +50 INCHES STATIC HEAD AND A DOME PRESSURE OF 33 PSIG THE | | LICENSEE ESTIMATES THAT THE COMBINED PRESSURE SEEN BY THE HIGH PRESSURE | | SWITCH IS 57.5 PSIG. CURRENT INFORMATION SUGGESTS THAT A PRESSURE SWITCH IS | | OUT OF CALIBRATION. THE LICENSEE NOTED THAT THE LEVEL OVERSHOOT TO +50 | | INCHES HAD NOT BEEN EXPERIENCED IN THE PAST AND ATTRIBUTED THE CAUSE TO | | SLUGGISH CONTROLLER RESPONSE. THE LEVEL CONTROLLER SETPOINT WAS READJUSTED | | TO +33 INCHES WHICH RESULTED IN A LEVEL OVERSHOOT OF +40 INCHES AND THE RHR | | FLUSHES COMPLETED. CURRENTLY RHR LOOP "A" WITH PUMP "C" IS IN SERVICE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE BY FOSS AT 1102 EDT ON 5/25/94 TAKEN BY WEAVER * * * | | THE LICENSEE HAS WITHDRAWN THIS EVENT BASED ON THEIR REVIEW OF THE FSAR. | | THEY HAVE CONCLUDED THIS IS NOT AN ESF ACTUATION. THE RESIDENT INSPECTOR | | HAS BEEN INFORMED. THE RI RDO (ANDERSON) WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/25/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 13:14[CDT]| |NRC NOTIFIED BY: DAVE KUSER |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNING EO | |NLCO TECH SPEC LCO A/S |BOB CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH EMERGENCY DIESEL GENERATORS BEING | | DECLARED INOPERABLE. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON MAY 25, 1994 AT 1:14 PM A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED | | WHEN BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE | | SURVEILLANCE TEST CONDUCTED EACH REFUELING OUTAGE NOT VERIFYING THE LOAD | | SHEDDING OF ALL LOADS ON THE CRITICAL 480 VOLT BUS. PROPER LOAD SHEDDING | | OF ALL 4160 VOLT LOADS IS VERIFIED DURING THE SEQUENTIAL LOADING TEST. THE | | PRINCIPAL 480 VOLT LOADS NOT VERIFIED TO BE SHED INCLUDE STATION AIR | | COMPRESSORS AND THE CRD PUMPS. THESE COMPONENTS ARE TRANSFERRED TO ANOTHER | | BUS DURING THE SURVEILLANCE TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE | | CRITICAL 480 VOLT BUS ARE SMALL. | | | | IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS IN SECTION 3.5.F.2, | | A LOAD REDUCTION TO 25 PERCENT POWER WAS INITIATED. AN ENGINEERING | | EVALUATION OF THE CONDITION IS ONGOING. A FOLLOW-UP NOTIFICATION WILL BE | | MADE WHEN SUCH INFORMATION IS AVAILABLE." END OF TEXT. | | | | THE LICENSEE IS REDUCING POWER AT 100 MW(e) PER HOUR. THE LICENSEE | | CONSIDERS THE EDGS AVAILABLE. ALL ECCS AND RCIC ARE OPERABLE. THE WEATHER | | IN THE AREA IS CALM WITH NO FORECAST OF RAIN. THE PROBLEM WAS DISCOVERED | | DURING REVIEW OF UNDERVOLTAGE TESTING. THE LAST REFUELING OUTAGE ENDED IN | | JULY OF 1993. THE LICENSEE IS INVESTIGATING CORRECTIVE ACTIONS AND IS | | PURSUING ENFORCEMENT DISCRETION WITH THE NRC TO STOP THE POWER DESCENSION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS INFORMED LOCAL AND | | STATE OFFICIALS IN ACCORDANCE WITH THEIR EMERGENCY PLAN. | | | | * * * UPDATE 5/25/94 @ 22:40 FROM CAUL TAKEN BY SEBROSKY * * * | | THE REACTOR IS CURRENTLY AT 24% POWER AND THE LICENSEE PLANS TO SCRAM THE | | THE PLANT AT 22:00 CT PER THEIR NORMAL SHUTDOWN PROCEDURES. THE SHUTDOWN | | IS BEING DONE DUE TO BOTH EDGS BEING DECLARED INOPERABLE. THE LICENSEE | | WILL EXIT THE UNUSUAL EVENT WHEN THE PLANT REACHES COLD SHUTDOWN | | CONDITIONS. COLD SHUTDOWN IS EXPECTED TO BE REACHED SOMETIME TOMORROW | | MORNING. THE LICENSEE HAS BEEN IN CONTACT WITH REGION 4 OFFICIALS | | CONCERNING THE SHUTDOWN AND HAS INFORMED THE RESIDENT INSPECTOR. | | | | HOO NOTIFIED R4DO(POWERS) AND EO(). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27296 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/25/94 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 14:56 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 14:55[EDT]| |NRC NOTIFIED BY: KELLY |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 | 0 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A DEFECT WAS IDENTIFIED IN AN AIR OPERATED VALVE ACTUATOR FOR A COPES | | VULCAN VALVE FOLLOWING AN UNSUCCESSFUL ATTEMPT TO INSTALL THE ACTUATOR ON | | POWER OPERATED RELIEF VALVE (PORV) "RC-PCV-456" ON FEBRUARY 4, 1994. A | | NONCONFORMANCE IN THE SPRING ADJUSTING NUT WAS IDENTIFIED WHILE | | INVESTIGATING THE NONCONFORMANCE IN THE YOKE THAT HAD PREVENTED | | INSTALLATION. THE VALVE ACTUATOR WITH THE DEFECT WAS DELIVERED BUT NEVER | | INSTALLED. | | | | THE NONCONFORMANCE IDENTIFIED IN THE SPRING ADJUSTING NUT WAS UNACCEPTABLE | | THREADS. ALL THREADS WERE FOUND STRESSED OR LOADED (DAMAGED) TO THE POINT | | WHERE THE THREAD DIMENSIONS WERE EITHER IMPOSSIBLE TO MEASURE OR WERE NOT | | WITHIN SPECIFIED MANUFACTURER DRAWING TOLERANCES. | | | | THE CAUSE OF THE NONCONFORMANCE ON THE SPRING ADJUSTING NUT HAS NOT BEEN | | FIRMLY ESTABLISHED. ACTION WILL BE TAKEN TO TEST THE SPRING ADJUSTING NUT | | TO SUBSTANTIATE REPORTABILITY, TO REVIEW EXISTING MAINTENANCE PROCEDURES | | AND COPES VULCAN INSTRUCTION MANUALS TO IDENTIFY REQUIRED REVISIONS AND TO | | INSPECT THE EXISTING WAREHOUSE STOCK OF COPES VULCAN PARTS FOR | | DEFICIENCIES. COPES VULCAN HAD PREVIOUSLY TAKEN ACTION TO REDUCE UNDERCUT | | SCREW THREADS. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/25/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:03 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 17:50[EDT]| |NRC NOTIFIED BY: RICHARD BONNER |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 +------------------------------------------------------------------------------+ | AC RELAYS WERE DISCOVERED IN THE DC STARTING CIRCUIT FOR THE TWO MOTOR | | DRIVEN AUXILIARY FEEDWATER PUMPS. | | | | THE LICENSEE DISCOVERED DURING A DESIGN REVIEW THAT THE AUTOMATIC STARTING | | CIRCUIT FOR THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS HAD AC RELAYS IN IT. | | THE STARTING CIRCUIT IS A DC CIRCUIT. THE RELAYS ARE NORMALLY ENERGIZED | | AND WHEN THEY ARE DEENERGIZED THEY INITIATE AUXILIARY FEEDWATER. THE AC | | RELAYS WERE INSTALLED AS PART OF A POST TMI BACKFIT AND HAVE BEEN IN THE | | SYSTEM FOR SEVERAL YEARS. | | | | THE POTENTIAL PROBLEM WITH THE AC RELAYS IN THE DC STARTING CIRCUITRY IS AN | | INADVERTENT START OF THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS. THE | | TURBINE DRIVEN AUXILIARY FEEDWATER PUMP IS NOT AFFECTED BY THE PROBLEM | | BECAUSE IT DOES NOT HAVE AN AUTOMATIC START FEATURE. THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE PROBLEM AND WILL CORRECT THE PROBLEM PRIOR | | TO CHANGING MODES. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS ALSO INFORMED | | STATE AND LOCAL AUTHORITIES OF THE PROBLEM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27299 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/25/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 18:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 15:50[CDT]| |NRC NOTIFIED BY: TOM BEUDIN |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNDERVOLTAGE RELAYS ON TRAIN 'A' AND TRAIN 'B' SAFEGUARDS BUSSES WERE FOUND | | TO BE OUT OF CALIBRATION. | | | | WHILE PERFORMING SURVEILLANCE TESTING ON THE 6.9KV AND 480V SAFEGUARDS | | TRAIN 'A' BUSSES IT WAS DISCOVERED THAT 14 OUT OF 15 UNDERVOLTAGE RELAYS | | WERE OUT OF CALIBRATION. A SAMPLE OF TRAIN 'B' UNDERVOLTAGE RELAYS WAS THEN | | PERFORMED AND IT WAS DETERMINED THAT 2 OUT OF 4 RELAYS WERE OUT OF | | CALIBRATION. ALL OF THE RELAYS WERE CALIBRATED AT ABOUT THE SAME TIME BY | | THE SAME INDIVIDUAL. THE LAST TIME THE SURVEILLANCE TEST WAS SUCCESSFULLY | | PERFORMED WAS IN 1992. THE TRAIN 'A' RELAYS HAVE BEEN RECALIBRATED AND THE | | LICENSEE PLANS ON RECALIBRATING THE TRAIN 'B' RELAYS TOMMORROW. | | | | THE LICENSEE IS STILL INVESTIGATING THE PROBLEM. AT THIS TIME THE LICENSEE | | BELIEVES THE PROBLEM IS CONFINED TO UNIT 2 BECAUSE OF THE SEPARATION OF | | CALIBRATION TIME AND BECAUSE OF THE RESULTS OF THE LAST THREE SURVEILLANCE | | TESTS ON UNIT 1. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27300 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/25/94 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 19:36 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 19:10[EDT]| |NRC NOTIFIED BY: JOE MONOGHAN |LAST UPDATE DATE: 05/25/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 18 OFFSITE EMERGENCY SIRENS LOST POWER DUE TO A RECENT THUNDERSTORM PASSING | | THROUGH THE AREA. THE LICENSEE'S PROCEDURES REQUIRE A NOTIFICATION BE MADE | | TO THE NRC IF MORE THAN 17 EMERGENCY SIRENS ARE INOPERABLE. THE LICENSEE | | WILL MONITOR RESTORATION OF POWER TO THE EMERGENCY SIRENS TO ENSURE THAT | | THEY ARE RETURNED TO SERVICE IN A TIMELY MANNER. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27301 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 05/26/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 05:09 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 00:40[CDT]| |NRC NOTIFIED BY: MATT POHL |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION FOR A ONE GALLON HYDRAZINE SPILL | | | | AT 0040 CDT A SECURITY GUARD REPORTED A STRONG AMMONIA ODOR IN THE VICINITY | | OF THE SECONDARY CHEMISTRY AMERZINE (I.E. HYDRAZINE) STORAGE TOTES. AN | | OPERATOR WAS DISPATCHED AND DISCOVERED THE AMERZINE SPILL. FURTHER | | INVESTIGATION REVEALED A LOOSE SWAGE-LOCK FITTING ON THE SUCTION OF THE | | AMERZINE TRANSFER PUMP. | | | | THE SPILLED LIQUID IS ISOLATED BY A BERM AND ROPED OFF TO PREVENT PERSONNEL | | ENTRY INTO THE AREA. THE SPILL WILL BE CLEANED UP WHEN HAZMAT PERSONNEL | | ARRIVE IN THE MORNING. NO PLANT EQUIPMENT OTHER THAN THE STORAGE TOTES ARE | | INACCESSIBLE BECAUSE OF THIS SPILL. NOTIFICATION WILL BE MADE TO THE | | NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY DURING NORMAL BUSINESS HOURS | | TODAY. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+