U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/31/97 - 11/03/97 ** EVENT NUMBERS ** 33198 33199 33200 33201 33202 33203 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. AIR FORCE RADIOISOTOPE COMMIT. |NOTIFICATION DATE: 10/31/97 | | CITY: TYNDALL AIR FOR REGION: 2 |NOTIFICATION TIME: 09:25 [ET]| | COUNTY: STATE: FL |EVENT DATE: 10/06/97 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 15:00[EST]| | DOCKET: |LAST UPDATE DATE: 10/31/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PIERCE SKINNER RDO | | |DON COOL EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: HICKS |LAWRENCE YANDELL R4DO | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. AIR FORCE RADIOISOTOPE COMMITTEE REPORTED 5 MISSING COMPASSES THAT | | CONTAIN TRITIUM. | | | | THERE WERE 12 COMPASSES STORED IN WAREHOUSE #4 PENDING DISPOSAL. THEY WERE | | TRANSFERRED TO WAREHOUSE #5 PRIOR TO ARRANGEMENTS BEING COMPLETED TO | | TRANSFER THEM TO THE 88 ABW/EMB, RAD. MAT. RECYCLING CENTER, WRIGHT | | PATTERSON AIR FORCE BASE. IT WAS NOTED BY THE BASE ALTERNATE RADIATION | | SAFETY OFFICER (RSO) THAT 5 OF THE 12 COMPASSES WERE MISSING. | | | | AN INVESTIGATION BY THE BASE BIO ENVIRONMENTAL ENGINEER (BEE) AND SUPPLY | | PERSONNEL DETERMINED THAT THE COMPASSES BECAME MISSING WHILE TRANSPORTING | | THEM FROM WAREHOUSE #4 TO WAREHOUSE #5. FROM PHONE CONVERSATIONS WITH THE | | ALTERNATE RSO, HE IS OF THE OPINION THAT THE COMPASSES ARRIVED AT WAREHOUSE | | #5, WHICH MANY ORGANIZATIONS HAVE ACCESS TO, AND THAT THE COMPASSES WERE | | REMOVED BY SOMEONE WITH ACCESS TO THE WAREHOUSE. | | | | IN THE FUTURE ALL RADIOACTIVE MATERIAL KEPT IN WAREHOUSE #5 WILL BE KEPT IN | | A LOCKED 55 GALLON DRUM, WITH ACCESS ONLY BY THE BASE RSO. | | | | THE LICENSEE INFORMED NRC REGION 4. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33199 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/31/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:39 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/31/97 | +------------------------------------------------+EVENT TIME: 10:20[EST]| |NRC NOTIFIED BY: DENNIS LATZ |LAST UPDATE DATE: 10/31/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESSURE SUPPRESSION CAPABILITY DURING DESIGN BASE LOSS OF COOLANT ACCIDENT | | MAY BE REDUCED BELOW DESIGN BASIS. | | | | THERE IS A VALVE ALIGNMENT THAT COULD EXIST DURING PRIMARY CONTAINMENT | | PURGE THAT WOULD CREATE A SUPPRESSION POOL BYPASS PATH THAT WOULD REDUCE | | THE PRESSURE SUPPRESSION FUNCTION OF THE CONTAINMENT IF A FAILURE OF THE | | INBOARD ISOLATION VALVES WERE TO OCCUR. PRIMARY CONTAINMENT PURGE SUPPLY | | AND EXHAUST VALVES PROVIDE A PATH FOR FRESH AIR FLOW INTO AND OUT OF THE | | DRYWELL AND SUPPRESSION POOL. THE PURGE SUPPLY CONSISTS OF A SINGLE | | OUTBOARD VALVE SUPPLYING TWO INBOARD VALVES, ONE TO THE DRYWELL AND ONE TO | | THE SUPPRESSION CHAMBER. THE CONFIGURATION OF THE VALVES ALLOW A BYPASS | | PATH BETWEEN THE DRYWELL AND SUPPRESSION CHAMBER AIR SPACE. THIS BYPASS, | | BOTH INBOARD VALVES FAIL TO CLOSE, WOULD REDUCE THE PRESSURE SUPPRESSION | | EFFECT OF THE STEAM BEING DISCHARGED THROUGH THE WATER CONTAINED IN THE | | SUPPRESSION CHAMBER. | | | | ANALYSIS AT BROWNS FERRY HAS SHOWN THAT THE PEAK CONTAINMENT PRESSURE IN | | THE EVENT OF A DESIGN BASIS LOSS OF COOLANT COULD EXCEED THE CONTAINMENT | | DESIGN PRESSURE. FROM THIS EVIDENCE, IT IS LIKELY THAT A SIMILAR CONDITION | | WOULD OCCUR AT MILLSTONE 1. | | | | SYSTEM OPERATING INSTRUCTIONS WILL BE REVISED TO PROHIBIT SIMULTANEOUSLY | | PURGING THE DRYWELL AND SUPPRESSION CHAMBER UNLESS THE UNIT IS IN COLD | | SHUTDOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR, STATE AND LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33200 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/31/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:24 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/31/97 | +------------------------------------------------+EVENT TIME: 18:09[EST]| |NRC NOTIFIED BY: MIKE VASELY |LAST UPDATE DATE: 10/31/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INFORMATION CALL CONCERNING WESTINGHOUSE DB-50 CIRCUIT BREAKER PROBLEMS. | | THE LICENSEE HAS APPROXIMATELY 40 DB-50 CIRCUIT BREAKERS USED ON 480 VOLT | | SYSTEMS. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AS A RESULT OF CON EDISON'S ONGOING INVESTIGATION INTO THE PERFORMANCE OF | | WESTINGHOUSE MODEL DB-50 CIRCUIT BREAKERS, PRELIMINARY RESULTS OF TESTING | | AND INSPECTION HAVE REVEALED TWO ITEMS THAT ARE THE SUBJECT OF THIS REPORT. | | | | 1. CIRCUIT BREAKER TRIP BAR FORCES WERE MEASURED AND IT WAS FOUND THAT LOW | | FORCES (AS MEASURED ON THE TRIP BAR BETWEEN THE SHUNT TRIP AND THE DIRECT | | TRIP ACTUATOR) RESULT IN PREMATURE TRIPPING (TRIP FREE). THROUGH | | DISCUSSIONS WITH WESTINGHOUSE, A PREVIOUSLY UNKNOWN LIMITING CRITERIA FOR | | TRIP BAR FORCE IS A MINIMUM OF 0.9 POUNDS (14 OUNCES). THE PREVIOUSLY | | IDENTIFIED UPPER LIMIT IS 1.9 POUNDS (31 OUNCES). THIS FORCE IS MEASURED AT | | THE CENTER OF THE TRIP BAR AND IS THE FORCE REQUIRED TO RAISE THE TRIP BAR | | APPROXIMATELY 0.25". | | | | THE LOW TRIP FORCES WERE FOUND ON SOME BREAKERS WITHOUT MOLDED TRIP PADS | | (WEIGHTS) THAT HAD BEEN REMOVED WHEN BREAKERS WERE MODIFIED TO REPLACE THE | | ELECTRO-MECHANICAL TRIP UNITS WITH AMPTECTORS. THE MOLDED TRIP PADS (OR | | EQUIVALENT MATERIAL) WILL BE ADDED TO THE TRIP BAR SYMMETRICALLY TO | | INCREASE THE FORCE REQUIRED TO RAISE THE BAR ABOVE 0.9 POUNDS. | | | | 2. CIRCUIT BREAKER TRIP ROLLING ARM SPRING WAS FOUND IN CERTAIN CASES TO BE | | OVERWOUND. THIS SPRING, WHICH IS PART OF THE OPERATING MECHANISM, WHEN | | OVERWOUND CAN PROVIDE AN ADDITIONAL UNWANTED FORCE ON THE TRIP ROLLER ARM | | LINKAGE. THE PHYSICAL INDICATION OF THE ABNORMALITY WAS FIRST NOTED WHEN | | THE BREAKER CLOSING MECHANISM COULD BE MOVED DURING MANUAL CLOSURE EVEN | | WITH THE TRIP BAR RAISED. | | | | FROM OUR INVESTIGATION OF GOOD BREAKERS, THE SPRING FORCE SHOULD NOT EXCEED | | 1.1 POUNDS. | | | | THE ABOVE INFORMATION IS PRELIMINARY AND WILL BE SUPPLEMENTED OR MODIFIED | | AS NECESSARY WHEN THE INVESTIGATION IS COMPLETE." | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS CALL BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33201 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 10/31/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 19:46 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 10/31/97 | +------------------------------------------------+EVENT TIME: 16:40[EST]| |NRC NOTIFIED BY: TOM PAGLIA |LAST UPDATE DATE: 10/31/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING PLANT SAFEGUARD LOGIC TESTING A SAFETY INJECTION ACTUATION SIGNAL | | WAS RECEIVED. | | | | AT 1640 EST, WITH PROCEDURE PT-32.1 IN PROGRESS (PLANT SAFEGUARD LOGIC TEST | | "B" TRAIN), THE UNIT RECEIVED A SAFETY INJECTION SIGNAL FROM PRESSURIZER | | LOW PRESSURE AT 1750 psig. AT THE TIME OF THE EVENT, THE PRESSURIZER LOW | | PRESSURE LOGIC WAS BEING TESTED. THE PLANT IS IN A REFUELING OUTAGE WITH | | THE REFUELING CAVITY LEVEL AT > 23' AND FUEL MOVEMENT IS CURRENTLY ON HOLD. | | BOTH RESIDUAL HEAT REMOVAL PUMPS WERE RUNNING IN THE NORMAL SHUTDOWN | | COOLING MODE WITH AVERAGE CORE EXIT THERMOCOUPLE TEMPERATURE OF | | APPROXIMATELY 85øF. THE "B" DIESEL GENERATOR WAS REMOVED FROM SERVICE FOR | | MAINTENANCE. THE "A" COMPONENT COOLING WATER PUMP AND THE "B" AND "C" | | SERVICE WATER PUMPS WERE RUNNING TO SUPPORT RESIDUAL HEAT REMOVAL COOLING. | | MOST OTHER SAFEGUARD EQUIPMENT WAS NOT REQUIRED IN THIS MODE OF OPERATION, | | AND HAD BEEN REMOVED FROM SERVICE FOR OUTAGE MAINTENANCE. THE SAFETY | | INJECTION SIGNAL AND SEQUENCING WAS VERIFIED ON BOTH TRAINS. | | | | PLANT CONDITIONS REMAINED STABLE ON THE RESIDUAL HEAT REMOVAL AND THE | | SAFETY INJECTION SIGNAL WAS RESET AT 1641 EST. PROCEDURES E-0 (REACTOR TRIP | | & SAFETY INJECTION) AND ES-1.1 (RECOVERY) WERE USED FOR INFORMATION ONLY IN | | SECURING OR RESTARTING EQUIPMENT. THE CAUSE OF THE SAFETY INJECTION SIGNAL | | IS NOT KNOWN, AND IS CURRENTLY UNDER INVESTIGATION BY INSTRUMENT AND | | CONTROL TECHNICIANS. | | | | THE "A" DIESEL GENERATOR AND TWO STANDBY SERVICE WATER PUMPS STARTED ON THE | | SAFETY INJECTION SIGNAL AND THE "B" SPENT FUEL POOL PUMP TRIPPED (NO | | INCREASE IN SPENT FUEL POOL TEMPERATURE OCCURRED). ADDITIONALLY, SOME | | CONTAINMENT ISOLATION VALVES RECEIVED THE SAFETY INJECTION ACTUATION | | SIGNAL. NO WATER WAS INJECTED INTO THE REACTOR VESSEL. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 11/01/97 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 14:58 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 11/01/97 | +------------------------------------------------+EVENT TIME: 13:38[CST]| |NRC NOTIFIED BY: GADBOIS |LAST UPDATE DATE: 11/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON GARDNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 38 POWER OPERATION | 35 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN BECAUSE OF PRESSURE BOUNDARY | | LEAKAGE (ACTUAL LEAK RATE IS APPROXIMATELY 0.32gpm). | | | | THE LICENSEE REDUCED REACTOR POWER LAST NIGHT FROM 99% TO 38% IN ORDER TO | | MAKE A DRYWELL ENTRY TO INVESTIGATE THE CAUSE OF INCREASED DRYWELL SUMP | | LEVELS. A LEAK OF 0.32gpm WAS DISCOVERED TO BE COMING FROM A WELD ON A TAP | | OFF OF THE 'B' RECIRCULATION LOOP FLOW ELEMENT (3-261-9B) WHERE IT TIES | | INTO THE INSTRUMENT LINE ON THE RECIRCULATION LINE (THIS IS PRESSURE | | BOUNDARY LEAKAGE). THE REACTOR WILL BE SHUTDOWN TO MODE 3 (HOT SHUTDOWN) | | WITHIN THE NEXT 3 TO 4 HOURS, AND WILL THEN BE COOLED DOWN TO MODE 4 (COLD | | SHUTDOWN) SO THAT THE LEAK CAN BE REPAIRED. ALL EMERGENCY CORE COOLING | | SYSTEMS AND THE EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED. | | THE LICENSEE SAID THAT THE TOTAL UNIDENTIFIED LEAK RATE (WHICH IS 0.92gpm) | | HAS CHANGED VERY LITTLE IN THE LAST 2 WEEKS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33203 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/02/97 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:45 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/02/97 | +------------------------------------------------+EVENT TIME: 11:00[EST]| |NRC NOTIFIED BY: D FIELDS |LAST UPDATE DATE: 11/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BISTABLE SETPOINTS FOR THE RECIRCULATION ACTUATION SIGNAL WERE FOUND TO BE | | INCORRECTLY SET | | | | AN ENGINEERING CALCULATION DETERMINED THAT THE BISTABLE SETPOINT FOR THE | | RECIRCULATION ACTUATION SIGNAL IS IN ERROR IN A NON-CONSERVATIVE DIRECTION. | | THE SETPOINT SHOULD BE 4' ABOVE THE BOTTOM OF THE REFUELING WATER STORAGE | | TANK; HOWEVER, THE ACTUAL SETPOINT WAS FOUND TO BE 3' ABOVE THE BOTTOM OF | | THE TANK. THIS SETPOINT ERROR APPLIES TO ALL FOUR CHANNELS OF THE | | RECIRCULATION ACTUATION SIGNAL BISTABLES AND HAS EXISTED FOR AN | | INDETERMINATE LENGTH OF TIME. | | | | THE RECIRCULATION BISTABLE CHANNEL SETPOINTS WERE ADJUSTED USING INSTRUMENT | | AND CONTROL PROCEDURE # 11400052 (ENGINEER SAFEGUARDS ACTUATION SYSTEM | | CHANNEL FUNCTIONAL TEST). THIS PROCEDURE INSTRUCTED THE INSTRUMENT AND | | CONTROL TECHNICIANS TO ADJUST EACH CHANNEL SETPOINT TO 4.96 mA (3') INSTEAD | | OF TO 5.28 mA (4'). THE LICENSEE STATED THAT THE UNIT 2 BISTABLES FOR THE | | RECIRCULATION ACTUATION SIGNAL ARE SET CORRECTLY. THE LICENSEE IS CURRENTLY | | INVESTIGATING THIS PROBLEM. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+