U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/15/95 - 02/16/95 ** EVENT NUMBERS ** 28385 28386 28387 28388 28389 28390 28391 28392 28393 28394 28395 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28385 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 02/15/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 00:42 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 02/15/95 | +------------------------------------------------+EVENT TIME: 00:30[EST]| |NRC NOTIFIED BY: BRUCE DANIELSON |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGASTAT RELAYS FOUND TO EXCEED THEIR QUALIFIED LIFE | | | | MORE THAN ONE DOZEN AGASTAT RELAYS INSTALLED IN CATEGORY I EQUIPMENT HAVE | | BEEN FOUND WHICH HAVE EXCEEDED THEIR TEN YEAR QUALIFIED LIFE. THIS | | INFORMATION WAS DISCOVERED DURING A REVIEW OF VENDOR INFORMATION. THE | | NUMBER IS EXPECTED TO INCREASE AS THE REVIEW PROGRESSES. THE EARLIEST | | INSTALLATION DATE DISCOVERED TO THIS POINT IS 1980. | | | | THE LICENSEE IS EXPECTED TO BEGIN CORE RELOAD IN THREE DAYS. THE PLANT | | INDICATED THIS SCHEDULE MAY BE DELAYED BASED ON THIS EVENT. THE LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28386 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/15/95 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 00:58 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/14/95 | +------------------------------------------------+EVENT TIME: 21:12[EST]| |NRC NOTIFIED BY: TOM TUTTLE |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT LOSS OF 125 VDC POWER LEADS TO A MANUAL REACTOR SCRAM | | | | DIVISION I EMERGENCY 125 VDC POWER WAS MOMENTARILY LOST WHILE TRANSFERRING | | THE RESPECTIVE BATTERY CHARGERS. THE MOMENTARY LOSS OF DC CONTROL POWER | | CAUSED A TRIP OF BOTH REACTOR WATER RECIRCULATION PUMPS RESULTING IN | | NATURAL CIRCULATION CONDITIONS. A MANUAL REACTOR SCRAM WAS IMMEDIATELY | | PERFORMED PER PLANT OPERATING PROCEDURES. ALL CONTROL RODS INSERTED AND | | THE REACTOR IS SHUTDOWN. ALL SYSTEMS APPEAR TO HAVE FUNCTIONED AS | | EXPECTED, BUT INVESTIGATION CONTINUES. | | | | THE RECIRC PUMPS WERE RESTARTED IN SLOW SPEED. ESF ACTUATIONS OCCURRED FOR | | GROUP 8 & 9, PRIMARY CONTAINMENT OUTBOARD ISOLATION VALVE SIGNALS AND | | REACTOR BUILDING NORMAL VENTILATION ISOLATION DUE TO MOMENTARY LOSS OF | | DIVISION I DC POWER. THE REACTOR IS CURRENTLY STABLE IN HOT SHUTDOWN. | | RESTORATIONS ARE CONTINUING AND THE POST SCRAM REVIEW IS BEING PERFORMED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28387 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/15/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 01:21 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/14/95 | +------------------------------------------------+EVENT TIME: 23:12[EST]| |NRC NOTIFIED BY: GREG COLLINS |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION FOR UNKNOWN REASONS | | | | AT 2312 ON 2/14/95, WHILE UNIT 2 WAS IN A REFUEL OUTAGE, A 'B1' HALF SCRAM | | AND A GROUP 6C ISOLATION OCCURRED. THE SIGNAL WENT AWAY IMMEDIATELY AND | | THE HALF SCRAM WAS RESET. "THE GROUP 6C ISOLATION CAN BE RESET." NO MAIN | | CONTROL ROOM TESTING WAS IN PROGRESS THAT COULD HAVE CAUSED THIS. HOWEVER, | | AN IN SERVICE INSPECTION WAS IN PROGRESS ON AN INSTRUMENT RACK IN THE | | PLANT. THE INDIVIDUAL WAS ASKED IF HE TOUCHED OR BUMPED ANYTHING. HE | | REPLIED NEGATIVELY. INVESTIGATION CONTINUES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28388 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 02/15/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 09:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/14/95 | +------------------------------------------------+EVENT TIME: 12:01[CST]| |NRC NOTIFIED BY: TORREZ |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURDICK RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED UNOPENED CAN OF BEER IN VITAL AREA. | | | | THE LICENSEE DISCOVERED AN UNOPENED CAN OF BEER IN A REFRIGERATOR LOCATED | | ON THE 642' ELEVATION OF THE TURBINE BUILDING. THE OWNER IS UNKNOWN, BUT | | THE LICENSEE IS INVESTIGATING. THE LICENSEE STATED THAT THE REFRIGERATOR | | IS COMMONLY USED BY ALL SHIFTS, AND THAT THE UNIT IS IN A REFUELING OUTAGE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28389 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/15/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 11:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/15/95 | +------------------------------------------------+EVENT TIME: 10:58[EST]| |NRC NOTIFIED BY: BRADLEY |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CASTO RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DENNIG EO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL |BERNICE FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 | 0 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO TRANSPORTATION OF POTENTIALLY CONTAMINATED | | INJURED MAN TO LOCAL MEDICAL FACILITY. | | | | AT 1058 EST, AN UNUSUAL EVENT WAS DECLARED DUE TO THE TRANSPORTATION OF A | | POTENTIALLY CONTAMINATED INJURED INDIVIDUAL TO THE PIEDMONT MEDICAL CENTER. | | THE INDIVIDUAL HAD FALLEN APPROXIMATELY 20 FEET FROM A LADDER IN THE | | CONTAINMENT AND WAS COMPLAINING OF BACK INJURIES. THE LICENSEE PLACED THE | | INDIVIDUAL ON A BACKBOARD, AND THEN PROCEEDED TO REMOVE AS MUCH OF THE | | INDIVIDUAL'S ANTI-CONTAMINATION CLOTHING AS POSSIBLE BEFORE TRANSPORT. THE | | UNUSUAL EVENT WAS TERMINATED AT 1118 EST WHEN THE INDIVIDUAL ARRIVED AT THE | | MEDICAL CENTER. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28390 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 02/15/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 13:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/01/95 | +------------------------------------------------+EVENT TIME: 11:00[EST]| |NRC NOTIFIED BY: DEVEREUX TOWER |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SEAL PLATE WAS DISCOVERED TO BE MISSING ON 2/1/95 THAT COULD HAVE | | AFFECTED THE ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL | | EQUIPMENT IN THE AREA. | | | | THE LICENSEE DID NOT RECOGNIZE AT THE TIME, THAT THE CONDITION WAS | | POTENTIALLY OUTSIDE THE DESIGN BASIS. FURTHER EVALUATION PROVED THAT IT | | WAS NOT. THE LICENSEE IS MAKING THIS NOTIFICATION AND RETRACTING IT AT THE | | SAME TIME. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON FEBRUARY 1, 1995 DURING AN INSPECTION TO ADDRESS ELEVATED CONCRETE | | TEMPERATURES IN A TRENCH WHERE TWO STEAM GENERATOR (S/G) BLOWDOWN LINES ARE | | ROUTED ON UNIT 1, IT WAS NOTICED THAT A SEAL PLATE WAS MISSING. THE S/G | | BLOWDOWN SYSTEM NORMALLY OPERATES AT 540F WITH A DESIGN PRESSURE OF | | 1200PSIA. AT THE TIME OF DISCOVERY THE SYSTEM WAS ISOLATED FOR OTHER | | MAINTENANCE. | | | | THE PURPOSE OF THE SEAL PLATE IS TO DEFLECT THE STEAM ON A POSTULATED HIGH | | ENERGY LINE BREAK THAT WAS ASSUMED TO OCCUR AT THE TERMINAL END LOCATED IN | | THE AUXILIARY BUILDING. WITHOUT THE SEAL PLATE INSTALLED, THE | | ENVIRONMENTAL QUALIFICATIONS OF SAFETY RELATED ELECTRICAL EQUIPMENT IN THE | | AREA COULD BE RENDERED INVALID. THIS SITUATION, BASED ON AVAILABLE | | INFORMATION, WAS POTENTIALLY OUTSIDE THE CURRENT DESIGN BASIS, BUT WAS NOT | | RECOGNIZED AS SUCH AT THAT TIME. | | | | THE IMMEDIATE CORRECTIVE ACTION WAS TO INSTALL THE SEAL PLATE PRIOR TO | | UNISOLATING THE S/G BLOWDOWN LINES. | | | | SUBSEQUENT REVIEW AND ANALYSIS HAS SHOWN THAT THE POSTULATED LINE BREAK | | WOULD MORE REALISTICALLY OCCUR AT A LOCATION FURTHER DOWN THE PIPE LOCATED | | IN THE TURBINE BUILDING. THIS IS DUE TO THE FACT THAT THE LINE IS | | SEISMICALLY SUPPORTED AND RESTRAINED FOR PIPE FAILURE PAST THE SEAL PLATE | | LOCATION, WELL INTO THE TURBINE BUILDING. WITH THE BREAK OCCURRING AT A | | PLACE WHERE THE PIPE IS NO LONGER SUPPORTED AND RESTRAINED, THERE IS NO | | ADVERSE ENVIRONMENTAL AFFECT ON SAFETY RELATED SYSTEMS. | | | | BASED ON THIS ANALYSIS IT HAS BEEN DETERMINED THAT THE PLANT IS WITHIN THE | | DESIGN BASIS WITHOUT THE SEAL PLATE THEREFORE THIS 10CFR50.72 NOTIFICATION | | IS BEING RETRACTED. | | | | THIS COMMUNICATION IS BOTH A 10CFR50.72 NOTIFICATION AN A RETRACTION OF THE | | NOTIFICATION." END OF TEXT. | | | | UNIT 2 HAS A DIFFERENT DESIGN, THEREFORE THE SAME CONDITION DOES NOT EXIST | | IN THAT UNIT. THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28391 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/15/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:58 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/15/95 | +------------------------------------------------+EVENT TIME: 15:40[EST]| |NRC NOTIFIED BY: RICHARD DONOVAN |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRAINING RECORDS DO NOT DEMONSTRATE THAT CONTROL ROOM OPERATORS RECEIVED | | TRAINING ON USING A SELF CONTAINED BREATHING APPARATUS (SCBA). | | | | TO ASSURE CONTROL ROOM HABITABILITY THE LICENSEE REQUIRES THAT OPERATORS BE | | TRAINED ON HOW TO USE AN SCBA. TRAINING RECORDS FROM 1992 TO JUNE OF 1994 | | DO NOT SHOW THAT THIS TRAINING WAS COMPLETED. THE OPERATORS PRESENTLY ON | | SHIFT ARE ALL QUALIFIED IN THE USE OF AN SCBA. THERE ARE SOME OPERATORS | | THAT HAVE QUESTIONABLE TRAINING RECORDS AND THESE OPERATORS WILL BE | | EVALUATED AND MAY BE TAKEN OFF THE WATCH BILL. THE LICENSEE HAS AN | | ADEQUATE NUMBER OF OPERATORS WITH WELL DOCUMENTED TRAINING RECORDS TO | | ADEQUATELY STAFF ALL SHIFTS. THE LICENSEE IS CONTINUING TO INVESTIGATE THE | | PROBLEM AND CORRECTIVE ACTIONS. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND STATE OFFICIALS OF THE | | PROBLEM. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28392 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ITT FLUID TECHNOLOGY CORPORATION |NOTIFICATION DATE: 02/15/95 | | CITY: CITY OF INDUSTR REGION: 4 |NOTIFICATION TIME: 16:43 [ET]| | COUNTY: STATE: CA |EVENT DATE: 02/15/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 16:43[PST]| | DOCKET: |LAST UPDATE DATE: 02/15/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: CHARLES PERRY | | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ITT FLUID TECHNOLOGY CORPORATION OF CITY OF INDUSTRY, CALIFORNIA, IS | | UPDATING A PREVIOUS 10CFR PART 21 REPORT THAT DEALT WITH A PROBLEM | | CONCERNING DIFFERENTIAL PRESSURE INDICATING SWITCHES. | | | | THE PROBLEM CONCERNS SEISMIC TEST DATA THAT REVEALED THAT SWITCH CONTACT | | CHATTER MAY DEVELOP IN MODEL 288A AND 289A INDICATING SWITCHES DURING | | SEISMIC EVENTS AND ITT ISSUED A PRELIMINARY PART 21 REPORT ON THIS PROBLEM | | (SEE EVENT #28267). ITT BARTON HAS COMPLETED TESTING AT WYLE LABORATORIES | | IN NORCO, CA WHICH HAS CONFIRMED THAT THESE PRODUCTS MAY DEMONSTRATE SWITCH | | CONTACT CHATTER NOT IDENTIFIED DURING PREVIOUS NUCLEAR QUALIFICATION | | EFFORTS ASSOCIATED WITH THESE DEVICES. | | | | THE FINAL PART 21 REPORT SUPPLIES KNOWN SWITCH PERFORMANCE CHARACTERISTICS | | FOR VARIOUS SEISMIC LOADINGS WHICH WILL ALLOW THE INSTRUMENT USERS TO | | EVALUATE THEIR SPECIFIC INSTALLATIONS FOR SAFETY IMPLICATIONS. THE FINAL | | PART 21 ALSO CONTAINS A LIST OF CUSTOMERS WHO HAVE PURCHASED THESE | | INDICATING SWITCHES WITHIN THE PAST 10 YEARS. THE LIST OF CUSTOMERS | | APPEARS TO CONTAIN MOST OF THE UTILITIES WITH NUCLEAR POWER PLANTS. | | | | THIS REPORT AND THE PART 21 WERE FAXED TO WALTER HAASS OF NRR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28393 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/15/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 17:37 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/15/95 | +------------------------------------------------+EVENT TIME: 16:02[EST]| |NRC NOTIFIED BY: ALFRED FROBRICH |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING PERFORMANCE OF A TEST TO VERIFY ADEQUATE COOLING FLOW TO THE #31 | | SAFETY INJECTION (SI) PUMP LUBE OIL COOLER IT WAS DETERMINED THAT THE PLANT | | MAY HAVE A CONDITION THAT COULD AFFECT PLANT SAFETY. | | | | THE TEST BEING PERFORMED WAS ENG-566 "EXISTING SAFETY INJECTION COMPONENT | | COOLING WATER (SICCW) PUMP 31 FLOW TEST WITHOUT COMPONENT COOLING WATER". | | THE PLANT HAS 3 SAFETY INJECTION PUMPS THAT HAVE A SHAFT DRIVEN SICCW PUMP | | COMING OFF EACH OF THE SI PUMPS. THE SICCW PUMPS PROVIDE COOLING TO THE SI | | PUMP SEALS AND SI LUBE OIL COOLERS IN THE EVENT CCW IS LOST. | | | | THE #31 SICCW PUMP PROVIDED APPROXIMATELY 3.5 GPM COOLING FLOW TO THE LUBE | | OIL COOLER DURING THE TEST WHICH DOES MEET THE PLANT DESIGN SPECIFICATION | | OF 4 GPM. THE #31 SICCW PUMP IS CONSIDERED THE WORST CASE CONFIGURATION | | PUMP, HOWEVER THE REMAINING 2 PUMPS COULD HAVE BEEN IN THE SAME CONDITION. | | THE SI PUMPS ARE PART OF THE SI HIGH HEAD SYSTEM AND THE #31 SICCW PUMP IS | | OF ORIGINAL PLANT DESIGN. THE PLANT IS IN COLD SHUTDOWN AND IN THIS MODE OF | | OPERATION THE CONDITION HAS NO AFFECT ON SAFETY AND THE UNIT IS NOT IN ANY | | LIMITING CONDITION OF OPERATION (LCO) BECAUSE OF THE PROBLEM. PRIOR TO | | RETURNING THE PUMPS TO OPERABLE STATUS THE LICENSEE WILL IMPLEMENT A DESIGN | | CHANGE THAT WILL PROVIDE THE REQUIRED FLOW. | | | | THIS WAS THE FIRST TIME THIS TEST WAS PERFORMED ON THIS PUMP. THE OTHER 2 | | SI PUMPS HAVE BEEN RECENTLY REPLACED AND THE SAME TEST WAS PERFORMED ON | | THESE PUMPS. ONE OR THE PUMP'S SICCW FLOW WAS ADEQUATE AND THE OTHER | | PUMP'S FLOW IS CURRENTLY BEING EVALUATED. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28394 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/15/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:27 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/15/95 | +------------------------------------------------+EVENT TIME: 17:20[EST]| |NRC NOTIFIED BY: PHIL SANTINI |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE EXPERIENCED A TEST FAILURE DURING PTR14 "SAFETY INJECTION (SI) | | SYSTEM ELECTRICAL LOAD TEST". | | | | DURING PERFORMANCE OF THIS TEST THE MANUAL SAFETY INJECTION RELAY "SIM-2" | | MALFUNCTIONED IN ONE TRAIN OF MANUAL SAFETY INJECTION RESULTING IN SEVERAL | | COMPONENTS NOT RESPONDING AS EXPECTED. AUTOMATIC SI WAS NOT AFFECTED BY THE | | MALFUNCTIONING RELAY. THE EQUIPMENT AFFECTED WERE THE "21" AND "22" | | CONTAINMENT SPRAY PUMPS, AND THE "22" AUXILIARY COMPONENT COOLING WATER | | PUMP WHICH DID NOT ACTUATE. TRAIN "B" OF MANUAL SAFETY INJECTION AND TRAIN | | "B" OF CONTAINMENT ISOLATION PHASE "A" ALSO DID NOT ACTUATE. | | | | THE CORRECTIVE ACTION IS TO REPLACE RELAY SIM-2, AND REPEAT THE APPLICABLE | | PORTION OF TEST PTR14. THE LAST TIME THIS TEST WAS SUCCESSFULLY PERFORMED | | WAS THE LAST REFUELING OUTAGE. NO EQUIPMENT IS INOPERABLE BECAUSE OF THE | | FAILURE OF THIS TEST. ALL EMERGENCY CORE COOLING SYSTEMS ARE OPERABLE. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28395 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 02/15/95 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 22:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/15/95 | +------------------------------------------------+EVENT TIME: 21:26[EST]| |NRC NOTIFIED BY: ROBERT HAYES |LAST UPDATE DATE: 02/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JACK ROE EO | | |STINEDURF 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH EMERGENCY DIESEL GENERATORS (EDG) FOR | | UNIT 2 BEING INOPERABLE. | | | | THE LICENSEE HAD REMOVED THE 2AA EDG FROM SERVICE AND DECLARED IT | | INOPERABLE TO PERFORM ROUTINE MAINTENANCE AND MONTHLY SURVEILLANCE TESTING | | ON THE EDG. THE LICENSEE'S TECHNICAL SPECIFICATIONS REQUIRE THAT WITH ONE | | EDG INOPERABLE THE OTHER THREE EDGS AT THE SITE MUST BE DEMONSTRATED | | OPERABLE. TO DEMONSTRATE THE EDGS OPERABLE THEY ARE RUN FOR 5 MINUTES AT | | NORMAL SPEED (900 RPM) AFTER WHICH TIME THEY ARE GIVEN A "NORMAL" SHUTDOWN | | SIGNAL. THE NORMAL SHUTDOWN FOR THE EDG RUNS THE EDG AT A REDUCED SPEED | | (400 RPM) FOR 10 MINUTES AND THEN STOPS THE EDG. AFTER THE NORMAL SHUTDOWN | | IS COMPLETED THE EDG IS READY FOR ANY SUBSEQUENT AUTOMATIC START SIGNAL. | | | | THE 1AA EDG AND THE 1BB EDG WENT THROUGH THE NORMAL SHUTDOWN CYCLE WITHOUT | | A PROBLEM. THE 2BB EDG DID NOT STOP AFTER THE 10 MINUTE RUN AT REDUCED | | SPEEDS AS EXPECTED. THE LICENSEE WAS IN THE PROCESS OF INVESTIGATING WHY | | THE EDG DID NOT STOP WHEN THEY RECEIVED A LOW LUBE OIL LEVEL ALARM FOR THIS | | EDG. BASED ON THIS ALARM AND THE FACT THAT THE EDG WAS NOT GOING THROUGH A | | 'NORMAL' SHUTDOWN SEQUENCE OPERATORS IN THE CONTROL 'EMERGENCY STOPPED' THE | | EDG. WHEN THE EDG HAS BEEN 'EMERGENCY STOPPED' IT WILL NOT RESTART ON A | | SUBSEQUENT AUTOMATIC START SIGNAL. THEREFORE THE LICENSEE DECLARED THIS | | EDG INOPERABLE AND WITH BOTH EDGS INOPERABLE ON THE SAME UNIT THE LICENSEE | | DECLARED AN UNUSUAL EVENT FOR BOTH UNITS. | | | | THE LICENSEE EXITED THE UNUSUAL EVENT AT 22:20 WHEN THE 2BB EDG WAS | | RETURNED TO OPERABLE STATUS. AN OPERATOR VERIFIED LOCALLY THAT THE 2BB EDG | | LUBE OIL LEVEL IS WITHIN ITS REQUIRED LIMITS. THE LUBE OIL LEVEL WAS ALSO | | COMPARED WITH THE OTHER EDGS. ALL OF EDG'S LUBE OIL LEVELS ARE WITHIN THE | | SAME RANGE. THEREFORE THE LICENSEE HAS CONCLUDED THAT THE LOW LUBE OIL | | LEVEL ANNUNCIATOR IS INCORRECT. THE LOW LUBE OIL LEVEL ALARM SWITCH IS A | | NON TECH SPEC REQUIRED SWITCH AND IS NOT NECESSARY FOR THE OPERABILITY OF | | THE DIESEL. THE OPERATORS RESET THE EMERGENCY STOP SIGNAL, RETURNED THE | | EDG TO NORMAL STANDBY STATUS AND DECLARED THE 2BB EDG OPERABLE AT 22:20. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE PROBLEM WITH THE NORMAL | | SHUTDOWN OF THE 2BB EDG. NORMAL OFFSITE POWER IS AVAILABLE, HOWEVER, THERE | | ARE THUNDERSTORMS IN THE AREA AND THE LICENSEE HAS HAD INDICATION OF | | LIGHTENING STRIKES ON THE GRID. THE LICENSEE IS IN THE PROCESS OF | | RETURNING THE 2AA EDG TO SERVICE, WHICH WILL TAKE SEVERAL HOURS. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND STATE AND LOCAL | | OFFICIALS IN ACCORDANCE WITH THEIR EMERGENCY PLAN. | +------------------------------------------------------------------------------+