U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/26/94 - 04/28/94 ** EVENT NUMBERS ** 27021 27160 27161 27162 27163 27164 27165 27166 27167 27168 27169 27170 27171 27172 27173 27174 27175 27176 27177 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27021 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 03/30/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 19:26 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/30/94 | +------------------------------------------------+EVENT TIME: 17:41[CST]| |NRC NOTIFIED BY: EDAM |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH PRESSURE SWITCHES FOR THE RCIC RUPTURE DISC ISOLATION LOGIC FOUND TO | | BE OUT OF SPEC HIGH DURING PLANNED MAINTENANCE. | | | | WHILE PERFORMING PLANNED MAINTENANCE ON THE RCIC TURBINE EXHAUST HIGH | | PRESSURE PRESSURE SWITCHES (INITIATE AN ISOLATION IF THE RUPTURE DISC | | BLOWS), THE LICENSEE FOUND A PROBLEM WITH BOTH THE INBOARD ISOLATION VALVES | | LOGIC AND THE OUTBOARD ISOLATION VALVES LOGIC. FIRST, THE MAINTENANCE WAS | | PERFORMED ON THE INBOARD ISOLATION LOGIC, AND THE PRESSURE SWITCH WAS FOUND | | TO BE OUT OF SPEC HIGH. THE PRESSURE SWITCH WAS REPLACED, CALIBRATED AND | | RETURNED TO SERVICE. | | | | THEY THEN PROCEEDED TO THE PLANNED MAINTENANCE ON THE OUTBOARD LOGIC, AND | | THAT PRESSURE SWITCH WAS ALSO FOUND TO BE OUT OF SPEC HIGH. THAT PRESSURE | | SWITCH WAS ALSO REPLACED, CALIBRATED AND RETURNED TO SERVICE. THE PRESSURE | | SWITCHES ARE SUPPOSED TO BE SET TO PROVIDE AN ISOLATION BETWEEN 8.6 AND 10 | | PSIG, AND THE AS FOUND CONDITION FOR THE TWO ORIGINAL SWITCHES TRIPPED AT | | 12 AND 13.4 psig, RESPECTIVELY. BASED ON FINDING BOTH ISOLATION LOGICS OUT | | OF SPEC HIGH, THE EVENT IS CONSIDERED REPORTABLE. | | | | THE LICENSEE IS CURRENTLY IN DAY 2 OF A 14 DAY LCO FOR THE RCIC | | MAINTENANCE. ALL OTHER ECCSs ARE OPERABLE, HOWEVER, THEY ARE ALSO IN A 7 | | DAY LCO FOR PLANNED MAINTENANCE ON A PRESSURE SWITCH IN THE ATWS SYSTEM. | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | ***UPDATE FROM LICENSEE:ALLEN TO NRC:HUFFMAN AT 11:23 EST ON 3/31/94*** | | ANOTHER PRESSURE SWITCH (PS2420B) ON THE RCIC RUPTURE DISC ISOLATION LOGIC | | WAS FOUND OUT OF CALIBRATION. THE AS FOUND TRIP SETPOINTS OF THE ISOLATION | | AND ANNUNCIATOR SWITCHES FOR THE "B" TRAIN LOGIC WERE FOUND AT 12.6 AND | | 14.2 PSIG. THE SWITCH WILL BE REPLACED. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED. R4DO(SHEAR) INFORMED. | | | | * * * UPDATE 1245EDT 4/26/94 FROM LENNY SUEPER BY S.SANDIN * * * | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "ON MARCH 30, 1994, AT 1826 HOURS, THE DUANE ARNOLD ENERGY CENTER NOTIFIED | | THE NRC OF A REPORTABLE CONDITION BASED ON THREE OF THE FOUR REACTOR CORE | | ISOLATION COOLING (RCIC) TURBINE EXHAUST DIAPHRAGM PRESSURE SWITCHES | | (PS2420B, C, AND D) BEING FOUND OUT OF TOLERANCE JUST PRIOR TO THEIR | | REPLACEMENT. THREE PRESSURE SWITCHES EXCEEDED THEIR AS-FOUND LIMITS AS | | SPECIFIED IN THE SURVEILLANCE PROCEDURE AND THE NOMINAL SETPOINT IN | | TECHNICAL TABLE 3.2-A (LESS THAN OR EQUAL TO 10 PSIG). ALTHOUGH THE | | MAINTENANCE WAS COMPLETED AND THE RCIC SYSTEM WAS RETURNED TO SERVICE | | WITHIN THE ALLOWED OUT OF SERVICE TIME, PAST OPERABILITY OF THE PRESSURE | | SWITCHES WAS A CONCERN." | | | | "THE FOUR SWITCHES SENSE THE PRESSURE BETWEEN TWO RCIC TURBINE EXHAUST | | DIAPHRAGMS AND COMPROMISE A PAIR OF TWO-OUT-OF-TWO-ONCE LOGICS THAT | | INITIATE SIGNALS TO CLOSE THE RCIC INBOARD (M02400) AND OUTBOARD (M02401) | | STEAM SUPPLY ISOLATION VALVES. THESE VALVES ARE PRIMARY CONTAINMENT | | ISOLATION SYSTEM (PCIS) VALVES. IT WAS INITIALLY BELIEVED THAT THE FUNCTION | | OF THESE SWITCHES WAS TO PROVIDE SIGNALS TO CLOSE THE ISOLATION VALVES IN | | ORDER TO MAINTAIN THE PRIMARY CONTAINMENT BOUNDARY. PER NUREG-1022, ANY | | EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF A | | SAFETY FUNCTION THAT IS NEEDED TO CONTROL THE RELEASE OF RADIOACTIVE | | MATERIAL IS CONSIDERED A FOUR-HOUR REPORTABLE CONDITION. THEREFORE, THIS | | CONDITION WAS REPORTED WHEN THREE OF THE FOUR RCIC PRESSURE SWITCHES WERE | | FOUND DRIFTED OUT OF TOLERANCE." | | | | "DURING RESEARCH OF THE BASIS FOR THE SWITCH SETPOINTS, QUESTIONS ABOUT THE | | INTENDED DESIGN FUNCTIONS WERE IDENTIFIED. AN ENGINEERING REVIEW CONCLUDED | | THAT THESE SWITCHES WERE DESIGNED TO DETECT A DEGRADED INNER DIAPHRAGM | | BOUNDARY BY MONITORING THE PRESSURE BETWEEN THE DIAPHRAGMS. IT SHOULD BE | | NOTED THAT THE INNER DIAPHRAGM IS EXPOSED TO THERMAL AND MECHANICAL | | STRESSES THAT CAN EVENTUALLY RESULT IN LEAKAGE. UPON DETECTING A DEGRADED | | OR LEAKING INNER DIAPHRAGM, THE PRESSURE SWITCHES INITIATE A SIGNAL SO AS | | TO CLOSE THE ISOLATION VALVES BEFORE THE OUTER DIAPHRAGM IS CHALLENGED TO | | PROVIDE PROTECTION TO PLANT PERSONNEL PRESENT IN THE ROOM AREA DURING A | | RCIC SYSTEM ROUTINE RUN. ALTHOUGH THE PRESSURE SWITCHES MAY ALSO DETECT THE | | INSTANTANEOUS RUPTURE OF BOTH DISKS, THAT IS NOT THEIR DESIGN FUNCTION | | (BOTH DIAPHRAGMS HAVE THE SAME DESIGN BURST PRESSURE)." | | | | "THE ENGINEERING REVIEW, WITH GE'S CONCURRENCE, CONCLUDED THAT THE INTENDED | | FUNCTION OF THESE SWITCHES IS TO PROVIDE AN EARLY WARNING SIGNAL OF A | | POTENTIALLY DEGRADED INNER DIAPHRAGM AND INITIATE A TURBINE TRIP ALTHOUGH | | THE SIGNAL IS SENT TO THE ISOLATION VALVE LOGIC. WITH THREE OF THE FOUR | | SWITCHES DRIFTED SLIGHTLY HIGHER THAN THEIR AS-FOUND LIMITS, THE EARLY | | INDICATION OF DEGRADED INNER DIAPHRAGM WOULD HAVE BEEN DELAYED. RCIC SYSTEM | | OPERABILITY WAS NOT AFFECTED BECAUSE THE SWITCHES DRIFTED IN THE DIRECTION | | (HIGH) WHICH ACTUALLY REDUCED THE PROBABILITY OF INADVERTENTLY ISOLATING | | THE RCIC SYSTEM WHEN IT IS NEEDED. THE STEAM LEAK DETECTION SYSTEM (SLDS) | | PROVIDES THE PRIMARY ISOLATION FUNCTION IN THE EVENT THAT BOTH DISKS | | RUPTURE. BASED ON THE CLARIFICATION OF THE INTENDED FUNCTION OF THESE | | PRESSURE SWITCHES, THE DAEC NO LONGER CONSIDERS THIS CONDITION REPORTABLE | | ACCORDING TO GUIDANCE GIVEN IN NUREG 1022." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(SHEAR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27160 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/26/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 08:41 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 05:04[EDT]| |NRC NOTIFIED BY: JOHN DEDOMENICO |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ 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 Y 2 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE "B" RPS BUS WAS MOMENTARILY DEENERGIZED CAUSING SEVERAL VALVES TO | | AUTOMATICALLY CLOSE. | | | | A GROUND FAULT TRIP ON A 480 VOLT MOTOR CONTROL CENTER CAUSED A LOSS OF | | POWER TO THE "B" RPS MG SET. THIS DEENERGIZED THE "B" RPS BUS CAUSING AN | | ISOLATION SIGNAL ON "B" AND "D" CHANNELS AND RESULTED IN 5 MAIN STEAM LINE | | DRAIN VALVES, A REACTOR WATER SAMPLE VALVE, AND A REACTOR WATER CLEANUP | | ISOLATION VALVE TO CLOSE. THE RPS BUS WAS REENERGIZED FROM ITS ALTERNATE | | POWER SUPPLY. THE ISOLATION SIGNALS WERE CLEARED AND THE AFFECTED SYSTEM | | ISOLATION VALVES WERE RESTORED TO THEIR NORMAL LINEUP. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE GROUND FAULT TRIP ON THE 480 | | VOLT MOTOR CONTROL CENTER. THE LICENSEE IS IN THE PROCESS OF A NORMAL | | POWER ASCENSION AND THEY ARE NOT CURRENTLY IN A TECH SPEC ACTION STATEMENT | | BECAUSE OF THE PROBLEM. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR AND LOWER ALLOWAYS CREEK | | TOWNSHIP OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 27161 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GENERAL TESTING & INSPECTION CO. |NOTIFICATION DATE: 04/26/94 | | CITY: WASHINGTONVILLE REGION: 3 |NOTIFICATION TIME: 09:40 [ET]| | COUNTY: STATE: OH |EVENT DATE: 04/26/94 | |LICENSE#: 34-09037-01 AGREEMENT: N |EVENT TIME: 09:40[EDT]| | DOCKET: |LAST UPDATE DATE: 04/26/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GARY SHEAR RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: GARY GWISDALLA | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BPE2 20.403(b)(1) PERS EXPOS > 5REM WB | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GENERAL TESTING & INSPECTION CO. WASHINGTONVILLE, OH | | | | | | OVEREXPOSURE EVENT | | | | CALL BACK NUMBERS: 304-372-8173 | | | | ESTIMATES OF PERSONNEL OVEREXPOSURE: 5650MREM | | | | DATE OF EXPOSURE: 2/15 -3/15 94 | | | | HOW WERE ESTIMATES OBTAINED: READING FILM BADGE | | | | -WERE PERSONNEL MONITORING DEVICES USED IN THE DETERMINATION: YES | | | | TYPES OF RADIATION : GAMMA | | | | | | GENERAL TESTING AND INSPECTION COMPANY REPORTED A POSSIBLE OVEREXPOSURE TO | | A RADIOGRAPHER. HIS FILM BADGE FOR THE PERIOD 2/15 - 3/15 SHOWED AN | | EXPOSURE OF 5650mr. THE COMPANY THAT READ THE FILM BADGE (LANDOWER) TOLD | | THE LICENSEE THAT THE BADGE EXHIBITED NO VISIBLE FILTER PATTERN. THIS MAY | | MEAN THAT THE BADGE WAS NOT IN ITS HOLDER WHEN THE EXPOSURE WAS RECEIVED OR | | THAT THE BADGE IS FAULTY. | | | | THE LICENSEE QUESTIONS WHETHER THE WORKER ACTUALLY RECEIVED THE RECORDED | | EXPOSURE. THE LICENSEE'S DOUBT IS BASED ON THE IRREGULARITIES WITH THE | | BADGE AS WELL AS DISCUSSIONS WITH THE INDIVIDUAL INVOLVED. THE RATE ALARM | | METER CARRIED BY THE INDIVIDUAL NEVER ALARMED AND HIS DOSIMETER WAS NEVER | | OFF SCALE. IN ADDITION, THE INDIVIDUAL COULD NOT RECALL ANY EVENT WHICH | | WOULD HAVE ALLOWED HIM TO RECEIVE THIS HIGH OF A DOSE. ANOTHER INDIVIDUAL | | WHO HAD WORKED WITH THE POTENTIALLY OVEREXPOSED PERSON RECEIVED A DOSE OF | | 100mr IN THE SAME TIME PERIOD. THEY HAD WORKED TOGETHER ON ALL THE JOBS | | (FIVE) PERFORMED DURING THE PERIOD. | | | | A CONTACT NUMBER FOR THE FILM BADGE COMPANY IS 708-755-7000 | | | | | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27162 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 04/26/94 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 11:21 [ET]| |RX TYPE: [3] CE |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 08:11[CDT]| |NRC NOTIFIED BY: W. H. PENDERGRASS |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | A/R Y 70 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP SUBSEQUENT TO ACTUATION OF THE REACTOR POWER CUTBACK SYSTEM. | | | | THE FOLLOWING FAX WAS RECEIVED BY THE OPERATIONS CENTER: | | "DURING POWER ASCENSION TO THE 93% PLATEAU FOR STARTUP PHYSICS TESTING, A | | REACTOR POWER CUTBACK OCCURRED WHEN THE REACTOR POWER CUTBACK SYSTEM WAS | | PLACED INTO SERVICE AT 70% REACTOR POWER. CEA SUBGROUPS 5 & 6 WERE DROPPED | | BY THE REACTOR POWER CUTBACK SYSTEM, THE MAIN TURBINE SETBACK TO THE 200 | | MEGAWATT POSITION, THE STEAM BYPASS SYSTEM OPERATED TO QUICK OPEN VALVES | | AND THEN MODULATE. | | | | "SUBSEQUENT TO THE REACTOR POWER CUTBACK, WHILE THE PLANT WAS IN A | | TRANSIENT CONDITION AN AUTOMATIC REACTOR TRIP OCCURRED. BASED ON INITIAL | | INDICATIONS, WE (THE LICENSEE) BELIEVE THAT CORE PROTECTION CALCULATOR | | AUXILIARY TRIPS ON CHANNEL A & B DUE TO LOW PRESSURIZER PRESSURE OF 1860 | | PSIA CAUSED THE REACTOR TRIP. MINIMUM PRESSURIZER PRESSURE OBSERVED DURING | | THE EVENT WAS 1840 PSIA. | | | | "ALL SYSTEMS RESPONDED AS EXPECTED FOR THE REACTOR POWER CUTBACK AND | | REACTOR TRIP. THE PLANT IS STABLE IN MODE 3 AND RECOVERY ACTIONS ARE IN | | PROGRESS. INITIAL ESTIMATES FOR PLANT RECOVERY INDICATE THAT UNIT RESTART | | MAY COMMENCE BY MIDNIGHT." | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE CUTBACK ACTUATION. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/26/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 12:23 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 04:00[CDT]| |NRC NOTIFIED BY: RONALD MCGEE |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ISOLATION SIGNAL GENERATED DUE TO A VALVE NOT BEING | | FULLY CLOSED DURING MAINTENANCE. | | | | THE "A" RWCU PUMP WAS ISOLATED FOR MAINTENANCE. IT WAS LATER DETERMINED | | THAT DURING THE ISOLATION FOR THE MAINTENANCE THE DISCHARGE VALVE FOR THE | | RWCU PUMP WAS NOT FULLY CLOSED. WHEN THE VENT LINE ON THE PUMP WAS OPENED | | FLOW FROM THE RWCU SYSTEM CAME BACK THROUGH THE SLIGHTLY OPENED DISCHARGE | | VALVE AND CAUSED A PRIMARY CONTAINMENT ISOLATION SIGNAL. THE PRIMARY | | CONTAINMENT ISOLATION SIGNAL WAS CAUSED DUE TO EXCEEDING A FLOW OF 40 GPM. | | THE PRIMARY CONTAINMENT ISOLATION SIGNAL CAUSED THE ISOLATION VALVES IN THE | | RWCU SYSTEM TO CLOSE TERMINATING FLOW THROUGH THE SYSTEM. | | | | OPERATORS IN THE CONTROL ROOM HAD NOTICED AN INCREASE IN FLOW IN THE RWCU | | SYSTEM AND WERE IN THE PROCESS OF ATTEMPTING TO CONTACT THE OPERATOR THAT | | HAD OPENED THE VENT VALVE OF THE PROBLEM WHEN THE ISOLATION OCCURRED. THE | | VENT VALVE GOES TO A CLOSED RAD WASTE SYSTEM, SO THE OPERATOR THAT OPERATED | | THE VALVE COULD NOT SEE THE FLOW. | | | | THE MANUAL ISOLATION VALVE THAT DID NOT FULLY CLOSE WAS CAUSED BY A FAULTY | | REACH ROD OPERATOR. A REACH ROD IS USED FOR THIS VALVE DUE TO ALARA | | CONSIDERATIONS. THE REACH ROD FOR THE VALVE WAS MECHANICALLY BOUND DUE TO | | A PROBLEM WITH THE POSITION INDICATOR. THEREFORE EVEN THOUGH THE POSITION | | INDICATION INDICATED CLOSED, THE VALVE ITSELF WAS STILL APPROXIMATELY 1/2 | | TURN OPEN. | | | | THERE WERE NO RADIOLOGICAL PROBLEMS CAUSED BY THIS EVENT. IN ADDITION | | THERE WERE NO REACTOR VESSEL LEVEL FLUCTUATIONS SEEN DUE TO THIS EVENT. | | CURRENTLY THE "A" RWCU IS ISOLATED FOR MAINTENANCE AND THE "B" RWCU PUMP IS | | IN SERVICE. | | | | THE LICENSEE'S REPORT WAS DELAYED BY ABOUT 4 HOURS. THE LICENSEE'S INITIAL | | DETERMINATION WAS THAT THE EVENT WAS NOT REPORTABLE BECAUSE IT WAS DUE TO | | AN EQUIPMENT MALFUNCTION. UPON FURTHER REVIEW THE LICENSEE HAS DETERMINED | | THAT THE EVENT IS REPORTABLE. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27164 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 04/26/94 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 13:39 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 11:47[CDT]| |NRC NOTIFIED BY: STEVE AUSTIN |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF AIR CONDITIONING FOR THE CLASS 1E SWITCHGEAR ROOMS WERE | | DECLARED INOPERABLE CAUSING THE LICENSEE TO ENTER TECH SPEC 3.0.3 FOR | | APPROXIMATELY 40 MINUTES. | | | | DURING THE PERFORMANCE OF A SURVEILLANCE PROCEDURE ON THE HALON SYSTEM FOR | | THE CLASS 1E SWITCHGEAR ROOMS (STNFP 402) THE FIRE DAMPERS FOR THE OPPOSITE | | TRAIN TRIPPED. THE SURVEILLANCE PROCEDURE WAS BEING PERFORMED ON THE "A" | | TRAIN AND THE AIR CONDITIONER FOR THAT TRAIN (SGK05A) HAD BEEN DECLARED | | INOPERABLE. WHEN THE FIRE DAMPERS IN THE "B" TRAIN CLOSED IT CAUSED THE | | "B" TRAIN AIR CONDITIONER TO ALSO BE DECLARED INOPERABLE. WITH BOTH AIR | | CONDITIONER TRAINS DECLARED INOPERABLE THE LICENSEE ENTERED TECH SPEC | | 3.0.3. | | | | THE "A" TRAIN AIR CONDITIONER FOR THE CLASS IE SWITCHGEAR ROOM WAS RETURNED | | TO SERVICE AT 12:34 (CT) AND TECH SPEC 3.0.3 WAS EXITED. THE "B" TRAIN | | REMAINS INOPERABLE AND THE LICENSEE IS INVESTIGATING THE PROBLEM. AT THIS | | TIME THE LICENSEE BELIEVES THAT THE CAUSE OF THE PROBLEM IS A CIRCUITRY | | PROBLEM AND NOT A PERSONNEL ERROR. THE LICENSEE IS IN A 72 HOUR | | ADMINISTRATIVE LCO BECAUSE THE "B" TRAIN REMAINS INOPERABLE. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27165 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 04/26/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 10:10[PDT]| |NRC NOTIFIED BY: JEANNE KITTLER |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |CHRIS GRIMES EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | M/R Y 50 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM FROM 50% POWER DUE TO APRM OSCILLATIONS. | | | | AT 08:30 (PDT) THE LICENSEE WAS AT 70% POWER AND EXPERIENCED A LOSS OF | | MOTOR CONTROL CENTER 3A DUE TO AN OVERLOAD WHEN STARTING A TURBINE BUILDING | | EXHAUST FAN. THE LOSS OF THE MOTOR CONTROL CENTER CAUSED A LOSS OF POWER TO | | THE LEVEL CONTROLLERS FOR THE FEEDWATER HEATERS. THE LOSS OF THE LEVEL | | CONTROLLERS CAUSED THE FEEDWATER HEATERS TO TRIP AND RESULTED IN A LOSS OF | | FEEDWATER HEATING. THE LICENSEE REDUCED POWER TO 50% PER THEIR ABNORMAL | | PROCEDURES BY REDUCING CORE FLOW DUE TO THE LOSS OF FEEDWATER HEATING. | | | | AT APPROXIMATELY 9:00 PDT THE PLANT WAS AT 50% POWER AND 55% CORE FLOW. AT | | APPROXIMATELY 10:10 PDT APRM READINGS WERE OBSERVED TO BE OSCILLATING | | APPROXIMATELY 10% PEAK TO PEAK AND THE PLANT WAS MANUALLY SCRAMMED. | | | | THE REACTOR IS CURRENTLY SHUTDOWN AND STABLE AND THE POST TRIP RESPONSE WAS | | NORMAL. ALL RODS FULLY INSERTED, AND NO SAFETY RELIEF VALVES LIFTED. ALL | | ELECTRICAL BUSSES TRANSFERRED AS EXPECTED AND DECAY HEAT IS BEING REMOVED | | BY BLEEDING STEAM TO THE MAIN CONDENSER. REACTOR VESSEL WATER LEVEL IS | | BEING MAINTAINED BY THE FEED PUMPS. ALL ECCS AND EDGs ARE OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE APRM OSCILLATIONS AND TO | | DETERMINE IF ANY OTHER REPORTABLE CONDITIONS EXIST. THE CAUSE OF MOTOR | | CONTROL CENTER 3A OVERLOADING WAS AN INADVERTENT ACCUMULATION OF LOADS ON | | THE BUS. THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | * * * UPDATE 14:50 4/26/94 FROM CONSERRIERE TAKEN BY SEBROSKY * * * | | THE LICENSEE HAS DETERMINED THAT THE CAUSE OF THE APRM OSCILLATIONS WAS THE | | LVDT ON THE REACTOR RECIRC "A" FLOW CONTROL VALVE. THIS RESULTED IN | | CHANGES IN DRIVE FLOW AND CHANGES IN CORE NEUTRONICS WITH THE RESULT BEING | | THE APPEARANCE OF INSTABILITY. IT HAS BEEN DETERMINED THAT THE CAUSE OF | | THE PROBLEM WAS NOT CORE INSTABILITY OR CORE OSCILLATIONS. | | | | THE LICENSEE'S UPPER PLANT MANAGEMENT WILL INFORM THE NRC REGION OF THE | | ABOVE INFORMATION. HOO NOTIFIED R4DO(CAIN) AND EO(CHAFFEE). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27166 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/26/94 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 14:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 08:34[PDT]| |NRC NOTIFIED BY: D.J. DYE |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN 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 +------------------------------------------------------------------------------+ | UNEXPECTED DIESEL GENERATOR START DUE TO SHORTED PHASE POTENTIAL LIGHT ON | | STARTUP FEEDER BREAKER. | | | | DURING NORMAL ROUNDS THE ELECTRICAL OPERATOR FOUND THE PHASE "C" POTENTIAL | | LIGHT ON BREAKER "52HG14", STARTUP FEEDER TO 4KV BUS "G" BURNED OUT. IN | | ATTEMPTING TO REPLACE THE BULB HE INADVERTENTLY SHORTED THE PHASE "C" | | SOCKET TO THE ADJACENT PHASE "B" SOCKET RESULTING IN THE PHASE "B" | | SECONDARY POTENTIAL FUSE BLOWING. THIS CAUSED THE DIESEL GENERATOR "1-2" | | CIRCUITRY TO SENSE STARTUP BUS UV AND STARTED THE DIESEL GENERATOR. SINCE | | NO 4KV BUS UV WAS SENSED, THE DIESEL GENERATOR DID NOT LOAD ONTO THE BUS." | | | | THE LICENSEE HAS SECURED THE DIESEL AND IS CONDUCTING AN INVESTIGATION INTO | | THE ROOT CAUSE. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27167 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 04/26/94 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/26/94 | +------------------------------------------------+EVENT TIME: 12:45[EDT]| |NRC NOTIFIED BY: KOZINSKY |LAST UPDATE DATE: 04/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 +------------------------------------------------------------------------------+ | POWER INADVERTENTLY REMOVED FROM HVAC PENETRATION DAMPERS DURING TAGOUT. | | | | "ON 3/1/94 AN EQUIPMENT TAGOUT WAS PERFORMED ON EQUIPMENT BEING DELETED | | UNDER A DESIGN CHANGE. THIS TAGOUT UNKNOWINGLY REMOVED POWER FROM TWO | | TRAINS OF PIPING PENETRATION SYSTEM DISCHARGE DAMPERS. THIS COULD HAVE | | PREVENTED THE FULFILLMENT OF THE PIPING PENETRATION HVAC SYSTEM FUNCTION | | NEEDED TO CONTROL THE RELEASE OF RADIOACTIVE MATERIAL. THIS CONDITION WAS | | DISCOVERED ON 4/24/94. POWER WAS PROMPTLY RESTORED TO THE DAMPERS. AN | | ENGINEERING EVALUATION WAS BEGUN TO DETERMINE THE IMPACT OF THIS CONDITION | | ON THE SYSTEM FUNCTION. PRELIMINARY DETERMINATION IS THAT THIS CONDITION | | COULD HAVE PREVENTED THE PIPING PENETRATION HVAC SYSTEM FROM MAINTAINING | | NEGATIVE PRESSURE IN SOME PIPING PENETRATION AREAS." | | | | THE DAMPERS INVOLVED RECEIVE 120VAC CONTROL POWER AND ARE IDENTIFIED AS | | "1PV2550B" (TRAIN "A") AND "1PV2551B" (TRAIN "B"). DURING THE PERIOD | | BETWEEN 3/1/94 AND 4/24/94 SURVEILLANCE TESTING WAS PERFORMED WHICH DID NOT | | REVEAL THE REMOVAL OF POWER. THE LICENSEE IS INVESTIGATING THE ROOT CAUSE. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27168 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 04:39 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 02:00[CDT]| |NRC NOTIFIED BY: HITZEL |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 7 DAY LCO ACTION STATEMENT DUE TO ONE TRAIN OF CORE | | SPRAY BEING DECLARED INOPERABLE. | | | | THIS OCCURRED WHILE THEY WERE PERFORMING SURVEILLANCE PROCEDURE | | 6.3.4.2(CORE SPRAY MOV OPERABILITY TEST) AND THE CORE SPRAY MIN FLOW | | VALVE(CORE SPRAY-MOV-5B) CLOSED ON AN AUTOMATIC SIGNAL AND REOPENED | | AUTOMATICALLY WHEN CORE SPRAY-MOV-26B(CORE SPRAY TEST LINE RECIRC VALVE) | | WAS OPENED. IT APPEARS THAT WHEN THEY STROKED THE "26B" VALVE, THEY GOT A | | FLOW SPIKE AND THAT CAUSED THE AUTO CLOSE SIGNAL FOR THE "5B" VALVE. THE | | CONDENSATE BOOSTER PUMP WAS ALREADY RUNNING PRIOR TO THE START OF THE | | SURVEILLANCE ON THIS LOOP. THEY ARE STILL INVESTIGATING THE CAUSE OF THE | | SPIKE. THE "B" CORE SPRAY LOOP WAS THEN DECLARED INOPERABLE AND THEY | | ENTERED AN LCO ACTION STATEMENT. THIS 7 DAY LCO REQUIRES THAT THE OTHER | | CORE SPRAY, BOTH LPCI SUBSYSTEMS AND THE DIESELS BE VERIFIED OPERABLE AND | | THIS HAS BEEN DONE. THE FT CALHOUN RI WAS INFORMED. | | | | | | HOO NOTE: SEE SIMILAR EVENT #26723 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27169 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 14:00 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 12:14[CDT]| |NRC NOTIFIED BY: RANDY KING |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A REACTOR TRIP WITH THE UNPLANNED INSERTION OF ALL EIGHT | | SHUTDOWN BANK "A" CONTROL RODS DURING I&C TESTING. | | | | "DURING HOT ROD DROP TESTING PER RESP 3.1, FOLLOWING A REFUELING OUTAGE, A | | REACTOR TRIP SIGNAL WAS RECEIVED WITH SHUTDOWN BANK "A" 20 STEPS OFF THE | | BOTTOM. ALL OTHER RODS WERE AT THE BOTTOM OF THE CORE. THE TRIP SIGNAL WAS | | GENERATED DURING I&C TESTING IN ACCORDANCE WITH ICP 2.20 "REACTOR | | PROTECTION ANALOG TESTING". THE REACTOR TRIP SIGNAL WAS EXPECTED, HOWEVER, | | IT WAS NOT ANTICIPATED THAT THE RODS WOULD BE OFF THE BOTTOM AT THAT TIME." | | LICENSEE HAS ROOT CAUSE UNDER INVESTIGATION ALTHOUGH AT THIS TIME IT | | APPEARS TO BE A TEST COORDINATION PROBLEM. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27170 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 14:10[EDT]| |NRC NOTIFIED BY: RANDY HAIFLET |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 +------------------------------------------------------------------------------+ | UNIT EXPERIENCED AN 8 MINUTE LOSS OF SHUTDOWN COOLING AND OTHER VARIOUS ESF | | ACTUATIONS DUE TO DOWN SPIKING OF THE REACTOR WATER LEVEL INDICATION DURING | | CRD VENTING. | | | | "DURING SHUTDOWN CONDITIONS A ESF ACTUATION OCCURRED WHILE VENTING THE CRD | | SYSTEM PRIOR TO PLACING IT IN SERVICE. THE CRD SYSTEM CONNECTS TO OUR | | REFERENCE LEG KEEP FILL SYSTEM AND WHILE VENTING AT THIS LOCATION A WATER | | LEVEL SPIKE DOWNWARD TO APPROXIMATELY 9" OCCURRED. A GROUP 2, GROUP 3, | | GROUP 6 AND REACTOR BUILDING ISOLATION OCCURRED, AS PER DESIGN. ACTUAL RPV | | LEVEL REMAINED STABLE AT +34" NORMAL LEVEL. THE ISOLATIONS WERE RESET AND | | SHUTDOWN COOLING INITIATED." | | | | SHUTDOWN COOLING WAS IN OPERATION PRIOR TO THE GROUP 3 ISOLATION WITH RCS | | TEMP AT 135F AS MEASURED IN THE RWCU SYSTEM. DURING THE 8 MINUTES THAT | | COOLING WAS INTERRUPTED, RCS TEMPERATURE INCREASED BETWEEN 2 AND 3F. THE | | LICENSEE NOTED THAT BASED ON HIS KNOWLEDGE THIS HAD NOT OCCURRED DURING ANY | | PREVIOUS CRD VENTING OPERATION. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27171 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 15:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 14:38[EDT]| |NRC NOTIFIED BY: CHRIS REEVES |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN RDO | |ANTO 50.72(b)(1)(iii) TORNADO | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 50 POWER OPERATION | 50 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS ENTERED TS 3.0.3 DUE TO A TORNADO WARNING ISSUED FOR NORTHEAST | | HAMILTON COUNTY, TN. | | | | AT 1438EDT THE SITE ENTERED ABNORMAL OPERATING INSTRUCTION (AOI/8) DUE TO A | | TORNADO WARNING ISSUED BY NOAA FOR NORTHEAST HAMILTON COUNTY, TN. AT | | 1500EDT TS 3.0.3 WAS ENTERED DUE TO INOPERABILITY OF CONTROL ROOM | | VENTILATION PER AOI/8. THE LICENSEE RECEIVED NOTIFICATION THAT THE TORNADO | | WARNING HAD BEEN DOWNGRADED AT 1535EDT AND EXPECTS TO EXIT TS 3.0.3 | | SHORTLY. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #27101 FOR ADDITIONAL INFORMATION | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27172 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:44 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 14:11[EDT]| |NRC NOTIFIED BY: BRUCE SENSENBACH |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH 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 45 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT EXPERIENCED A REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL DUE TO | | THE FAILURE OF THE "A" MAIN FEEDWATER CONTROL VALVE. | | | | "WITH REACTOR POWER AT APPROXIMATELY 45% AND INCREASING AT 10% PER HOUR, | | THE POSITIONER FOR THE "A" MAIN FEEDWATER CONTROL VALVE FAILED. REACTOR | | TRIPPED ON 2 OUT OF 3 17% LEVEL ON THE "A" STEAM GENERATOR. MOTOR DRIVEN | | AUXILIARY FEEDWATER PUMPS STARTED AUTOMATICALLY ON THE REACTOR TRIP. | | PRESSURIZER LEVEL DECREASED TO 13%, RCS PRESSURE DECREASED TO 2043 PSIG AND | | THEN RETURNED TO NORMAL NO LOAD VALUES OF 20% AND 2235 PSIG. ALL SYSTEMS | | OPERATED AS REQUIRED WITH NO OTHER PROBLEMS. THE PLANT IS CURRENTLY AT HOT | | SHUTDOWN WHICH IS 2235 PSIG, 543F. WE ARE MAINTAINING TEMPERATURE USING THE | | ATMOSPHERIC RELIEF VALVES. PLANT TECHNICAL STAFF IS DETERMINING THE COURSE | | OF ACTION. STARTUP DATE AND TIME HAS NOT YET BEEN DETERMINED." | | | | LICENSEE IS USING ATMOSPHERIC RELIEFS TO CONTROL PLANT TEMPERATURE DUE TO | | LOW DECAY HEAT. THERE IS NO KNOWN STEAM GENERATOR TUBE LEAKAGE. STEAM | | GENERATOR LEVEL IS CURRENTLY 40% NARROW RANGE USING AFW PUMPS. ALL CONTROL | | RODS FULLY INSERTED WITH A NORMAL TRANSFER TO OFFSITE POWER. LICENSEE IS | | CURRENTLY TROUBLESHOOTING THE PROBLEM WITH THE "A" MAIN FEEDWATER CONTROL | | VALVE. PRIOR TO THE TRIP IT HAD STARTED TO GO CLOSED THEN STOPPED IN AN | | INTERMEDIATE POSITION. WHEN OPERATORS ATTEMPTED TO REPOSITION THE VALVE IT | | WOULD NOT MOVE IN EITHER DIRECTION. THE LICENSEE WAS UNABLE TO REDUCE POWER | | PRIOR TO RECEIVING THE AUTOMATIC TRIP. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR WHO IS ON HIS WAY TO THE SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27173 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 17:29 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 15:54[EDT]| |NRC NOTIFIED BY: GEORGE WILLIAMS |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOSTART OF STANDBY GAS TREATMENT SYSTEM DUE TO ADVERSE WEATHER | | CONDITIONS. | | | | "ON WEDNESDAY, APRIL 27, 1994, AT 1554, THE REFUEL FLOOR HVAC ISOLATED DUE | | TO A LOW REFUEL DIFFERENTIAL PRESSURE CONDITION. A GROUP VI A&B NSSSS | | ISOLATION SIGNAL WAS RECEIVED ON BOTH UNITS DUE TO THE LOW REFUEL | | DIFFERENTIAL PRESSURE CONDITION. THE LOW DIFFERENTIAL PRESSURE CONDITION | | EXISTED AS A RESULT OF A HIGH WIND STORM. THE STANDBY GAS TREATMENT SYSTEM | | OPERATED PER DESIGN AND DREW THE REFUEL FLOOR DIFFERENTIAL PRESSURE | | NEGATIVE (>-.25" H2O). NORMAL REFUEL FLOOR HVAC WAS RESTORED AT 1704 AND | | ALL ISOLATION SIGNALS WERE RESET." | | | | THE GROUP VI A&B NSSSS ISOLATION SIGNAL REPOSITIONS THE SUPPRESSION POOL | | AND DRYWELL SUPPLY AND EXHAUST VALVES CLOSED, HOWEVER, THESE VALVES WERE | | ALREADY CLOSED FOR CURRENT PLANT CONDITIONS. THE NITROGEN BLOCK VALVES USED | | FOR MAKEUP NITROGEN DID CLOSE AND HAVE BEEN REOPENED. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27174 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 18:10 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 14:38[PDT]| |NRC NOTIFIED BY: WILLIAM RALSTON |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | 3 | N Y 98 POWER OPERATION | 98 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT ACTUATION OF SAN CLEMENTE EMERGENCY SIREN #11 DURING TESTING. | | | | DURING QUARTERLY "GROWL" TESTING OF THE EMERGENCY SIRENS, TECHNICIANS | | INADVERTENTLY ACTUATED THE SOUTH SAN CLEMENTE EMERGENCY SIREN #11 FOR | | APPROXIMATELY 18 SECONDS. THIS SIREN HAS BEEN REMOVED FROM SERVICE. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27175 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 21:40 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 18:47[EDT]| |NRC NOTIFIED BY: RICHARD MASSA |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A POTENTIAL CONDITION WHICH COULD RESULT IN OVERLOADING | | OF THE EMERGENCY DIESEL GENERATOR (EDG) DURING A DESIGN BASIS ACCIDENT. | | | | "UNDER ACCIDENT CONDITIONS (DESIGN BASIS ACCIDENT: LOCA, LOP, 1 EDG | | OPERATING) THE IN SERVICE EMERGENCY DIESEL GENERATOR WOULD EXCEED ITS LOAD | | RATING IF EMERGENCY OPERATING PROCEDURE MANUAL ACTIONS ARE PERFORMED AND | | THE ENGINEERED SAFETY SYSTEM PUMPS ARE ALL OPERATING AT RUNOUT CONDITIONS." | | | | "THE CONTINUOUS LOAD RATING FOR THE EDG IS 2500KW, IT'S 2 HR RATING IS | | 2750KW, AND OPERATION BETWEEN 2750KW AND 3125KW IS LIMITED TO < 30 MINUTES. | | THE TOTAL ELECTRICAL LOAD ON THE OPERATING EDG WOULD EXCEED 2750 KW WHEN A | | SECOND BATTERY CHARGER IS PLACED IN SERVICE FOLLOWING FUNCTIONAL RECOVERY | | PROCEDURE (EOP-9) GUIDANCE." | | | | "IT IS UNLIKELY THAT THE 30 MINUTE RUN TIME ABOVE 2750KW WOULD BE EXCEEDED | | FOR THE FOLLOWING REASONS: | | | | 1. DURING THE DBA IT IS ONLY APPROXIMATELY 32 MINUTES TO THE INITIATION OF | | RECIRCULATION ACTUATION SIGNAL (RAS) WHICH TRIPS THE OPERATING LOW PRESSURE | | SAFETY INJECTION PUMP. REMOVING THIS LOAD FROM THE EDG WOULD ELIMINATE THE | | POSSIBILITY OF EDG OVERLOAD. THUS THE MANUAL ACTION OF PLACING THE BATTERY | | CHARGER IN SERVICE WOULD HAVE TO BE COMPLETED WITHIN THE FIRST 2 MINUTES OF | | THE EVENT TO CHALLENGE THE 30 MINUTE RUN TIME LIMIT. | | | | 2. IT IS PROBABLE THAT THE CONTROL ROOM OPERATORS OR AUXILIARY OPERATORS | | WOULD MONITOR EDG LOADING UNDER THESE CONDITIONS AND TAKE ACTION TO LIMIT | | LOAD." | | | | "HOWEVER, AT THIS TIME DUE TO ONLY HAVING ANALYSIS FOR SMALL AND LARGE | | BREAK LOCAs WE ARE NOT CERTAIN OF THE MAXIMUM TIME TO RAS FOR INTERMEDIATE | | SIZE LOCAs, SO IT MAY BE MORE LIKELY THAN DESCRIBED IN (1) ABOVE THAT THIS | | CONDITION COULD OCCUR." | | | | THIS CONDITION WAS DISCOVERED DURING AN ENGINEERING DESIGN REVIEW ANALYSIS. | | CORRECTIVE ACTIONS WILL INCLUDE REVISIONS TO APPLICABLE EOPs. THE MAXIMUM | | LOADING UNDER THE ABOVE CONDITIONS WOULD BE 2786KW FOR EDG "11" AND 2802KW | | FOR EDG "12". THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27176 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 20:28 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 18:30[EDT]| |NRC NOTIFIED BY: JOHN ROSENBERGER |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 | | 2 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY RESPONSE FACILITY COMPUTER SYSTEM DECLARED INOPERABLE DUE TO | | MULTIPLEXER (MUX) FAILURE IN UPDATING SPDS BAR FOR UNIT 2 CORE HEAT | | REMOVAL. | | | | "CORE HEAT REMOVAL TOP LEVEL SAFETY PARAMETER DISPLAY SYSTEM (SPDS) BAR ON | | UNIT 2 IS INOPERABLE DUE TO A FAILED MUX, WHICH AFFECTS POINTS INPUTTING TO | | THE SPDS BAR. WITH ONE OR MORE SPDS TOP LEVEL BARS INOPERABLE, THE ERF | | COMPUTER SYSTEM IS CONSIDERED UNAVAILABLE AND IS REPORTABLE WITHIN 1 HOUR. | | CURRENTLY TROUBLESHOOTING AND ATTEMPTING TO REPAIR. FURTHER UPDATES" | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | | | ***UPDATE AT 02:26 @ 4/28/94 BY WEBSTER TO GOULD*** THE LICENSEE REPORTED | | THAT THEY REPLACED A POWER SUPPLY ON THE FAILED MULTIPLEXER AND IT WAS | | RETURNED TO SERVICE AT 2:15. THE RI WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27177 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 3 |NOTIFICATION DATE: 04/27/94 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 21:17 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/27/94 | +------------------------------------------------+EVENT TIME: 19:26[CDT]| |NRC NOTIFIED BY: DICK NIEL |LAST UPDATE DATE: 04/27/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT ENTERED TS 3.0.3 FOR 1 MINUTE AFTER DECLARING 2 OF 4 ACCUMULATORS | | INOPERABLE AFTER RECEIVING AN ACCUMULATOR HIGH PRESSURE ALARM. | | | | "AT 1925 HOURS ON 4/27/94, THE "B" ACCUMULATOR HIGH PRESSURE ALARM | | ANNUNCIATED. THE REACTOR OPERATOR WENT TO GET THE PROCEDURE TO VENT | | PRESSURE FROM THE ACCUMULATOR TO RETURN PRESSURE TO ITS NORMAL VALUE. AT | | 1926 HOURS THE "C" ACCUMULATOR HIGH PRESSURE ALARM ANNUNCIATED. THEREFORE, | | TECH 3.0.3 WAS ENTERED AT 1926 HOURS. AT 1927 HOURS THE HIGH PRESSURE ALARM | | WAS CLEARED ON THE "C" ACCUMULATOR THROUGH VENTING BY THE REACTOR OPERATOR. | | AT THIS TIME TECH SPEC 3.0.3 WAS EXITED. AT 1928 HOURS THE "B" ACCUMULATOR | | HIGH PRESSURE ALARM WAS CLEARED THROUGH VENTING BY THE REACTOR OPERATOR AND | | AT THIS TIME ALL ACCUMULATORS WERE RETURNED TO THEIR NORMAL PRESSURE | | VALUES. WE WERE, THEREFORE, IN TECH SPEC 3.0.3 FOR 1 MINUTE FROM 1926 HOURS | | TO 1927 HOURS." | | | | PRESSURE IS CONTROLLED IN THE FOUR ACCUMULATORS BETWEEN 602 AND 648 PSIG | | WITH THE HIGH PRESSURE ALARM SETPOINT BISTABLE AT 643.67 PSIG. THE LICENSEE | | SPECULATED THAT THE PRESSURE INCREASE MAY BE DUE TO A 6F TEMPERATURE | | INCREASE SINCE MIDNIGHT LAST NIGHT IN CONTAINMENT AS A RESULT OF HAVING ONE | | TRAIN OF ESW OUT-OF-SERVICE TO THE CONTAINMENT COOLERS. WITH ONE | | ACCUMULATOR INOPERABLE THE UNIT MOMENTARILY ENTERED THE 1 HOUR TECH SPEC | | A/S 3.5.1. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+