U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/29/94 - 08/30/94 ** EVENT NUMBERS ** 27672 27720 27721 27722 27723 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27672 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 08/15/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/12/94 | +------------------------------------------------+EVENT TIME: 12:00[CDT]| |NRC NOTIFIED BY: WAGNER |LAST UPDATE DATE: 08/29/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK RDO | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOST 10 MILLICURIE NICKEL-63 SOURCE. | | | | DURING THE PERFORMANCE OF THE SEMI-ANNUAL INVENTORY, A 10 MILLICURIE | | NICKEL-63 SOURCE (SERIAL #"27119") WAS DETERMINED TO BE MISSING FROM ITS | | EXPLOSIVE DETECTOR. THE LAST TIME THE WHEREABOUTS OF THE SOURCE WAS KNOWN | | WAS ON 08/12 AT NOON. A SEARCH HAS NOT FOUND THE MISSING SOURCE. NICKEL-63 | | IS REPORTED TO BE A BETA EMITTER. THE SOURCES ARE USUALLY KEPT IN A SAFE IN | | THE CALIBRATION FACILITY. INSTRUMENT/MAINTENANCE TECHNICIANS USE THIS TYPE | | OF SOURCE ON AN INFREQUENT BASIS (NOT REGULARLY USED). | | | | A SEARCH FOR THE SOURCE IS ONGOING. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | *** UPDATE DATE: 8/29/94 UPDATE TIME: 1441 ***FROM LICENSEE: D. POI | | BY STRANSKY*** LICENSEE FOUND SUPPORTING DOCUMENTATION TO VERIFY THAT THE | | SOURCE WAS PROPERLY DISPOSED. RI INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27720 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 08/29/94 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 09:44 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 08/29/94 | +------------------------------------------------+EVENT TIME: 07:32[EDT]| |NRC NOTIFIED BY: MARTIN MANTENFEL |LAST UPDATE DATE: 08/29/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |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 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM ON MAIN TRANSFORMER LOCKOUT AND MAIN GENERATOR LOCKOUT. CAUSE | | OF THE MAIN TRANSFORMER LOCKOUT IS UNDER INVESTIGATION. | | | | REACTOR SCRAMMED DUE TO A MAIN TRANSFORMER LOCKOUT WHICH CAUSED A MAIN | | GENERATOR LOCKOUT/ TURBINE TRIP. ALL CONTROL RODS FULLY INSERTED. THE UNIT | | RECEIVED GROUP 2 (SAMPLE VALVES) AND GROUP 6 (RWCU) ISOLATIONS, AS | | EXPECTED. PER THEIR SCRAM PROCEDURE LICENSEE SECURED TWO OF THEIR THREE | | OPERATING REACTOR FEEDWATER PUMPS ("B" & "C"). SHORTLY AFTER REACTOR | | FEEDWATER PUMPS "B" & "C" WERE SECURED THEIR ONLY OPERATING REACTOR | | FEEDWATER PUMP "A" TRIPPED ON LOW OIL PRESSURE (THIS IS UNDER | | INVESTIGATION). LICENSEE MANUALLY STARTED RCIC TO CONTROL REACTOR VESSEL | | WATER LEVEL. LOWEST REACTOR VESSEL WATER WAS +18" PER THEIR STRIP CHART | | RECORDER. REACTOR VESSEL WATER LEVEL IS NOW +30" (RCIC & HPCI GET AN | | AUTOMATIC START ON LOW LOW REACTOR VESSEL WATER LEVEL WHICH IS -49"). RCIC | | WAS OPERATED FOR APPROXIMATELY 5 MINUTES BEFORE IT WAS SECURED WHEN REACTOR | | FEEDWATER PUMP "B" WAS PLACED IN SERVICE. THREE SRVs OPENED DURING THE | | REACTOR SCRAM AND CLOSED (THEY WERE OPEN FOR A SHORT PERIOD OF TIME). | | TWO CLEAN AREA REACTOR BUILDING SUPPLY DAMPERS FAILED TO INDICATE FULLY | | CLOSED DURING THE UNIT TRIP (CONTROL ROOM HAD DUAL INDICATION OF THE | | DAMPERS). LICENSEE MANUALLY CLOSED AND THEN TAGGED OUT THE DAMPERS (DAMPERS | | WERE FOUND TO BE ABOUT 0.125" OPEN). LICENSEE IS INVESTIGATING WHY THESE | | DAMPERS DID NOT FULLY CLOSE. | | RESTART DATE IS UNKNOWN. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27721 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 08/29/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:59 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 08/29/94 | +------------------------------------------------+EVENT TIME: 09:53[CDT]| |NRC NOTIFIED BY: KOLB |LAST UPDATE DATE: 08/29/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARTIN FARBER 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 | A/R Y 98 POWER OPERATION | 92 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ROD "D-11" SCRAMMED IN WHEN A HALF-SCRAM WAS INSERTED FOR A SURVEILLANCE | | TEST PROCEDURE. | | | | QUAD CITIES 2 MADE A VOLUNTARY FOUR HOUR NOTIFICATION DUE TO A CONTROL ROD | | SCRAMMING IN WHILE PERFORMING "QCOS 200-3" (LOW AND LOW-LOW REACTOR WATER | | LEVEL ANALOG TRIP SYSTEM CALIBRATION SURVEILLANCE). THE ROD SCRAMMED IN TO | | "00" WHEN A "B" CHANNEL HALF-SCRAM WAS INSERTED FOR THE SURVEILLANCE. THE | | CONTROL ROD WAS TAKEN OUT OF SERVICE PER QC PROCEDURE. INVESTIGATION IS IN | | PROCESS TO DETERMINE THE CAUSE OF THE SCRAMMED ROD. THIS NOTIFICATION MAY | | BE RETRACTED UPON FURTHER CLARIFICATION OF THE REPORTABILITY MANUAL. | | | | THE SURVEILLANCE HAD ALREADY BEEN COMPLETED WITHOUT ANY PROBLEMS FOR THE | | "A" CHANNEL. THE ROD THAT SCRAMMED WAS THE "D-11" ROD, ABOUT THREE RODS IN | | FROM THE PERIPHERY, AND CAUSED THE DROP IN POWER LEVEL. THERE WERE NO | | OTHER DIFFICULTIES ASSOCIATED WITH THE EVENT. THE LICENSEE NOTIFIED THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27722 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/29/94 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 16:54 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/29/94 | +------------------------------------------------+EVENT TIME: 13:30[EDT]| |NRC NOTIFIED BY: DIGNAM |LAST UPDATE DATE: 08/29/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |COSTELLO RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL LOSS OF SAFE S/D CAPABILITY DUE TO EXCESSIVE TEMPERATURES IN | | CONTROL ROOM FOLLOWING DESIGN BASIS EARTHQUAKE. | | | | MAINTENANCE ON THE SUPPORTS FOR THE 31 CCR AIR CONDITIONING UNIT REVEALED | | THE SUPPORTS TO BE INOPERABLE DUE TO HEAVY CORROSION AND LOSS OF MATERIAL. | | THE SUPPORTS FOR THE 32 CCR AIR CONDITIONING UNIT ARE SUSPECTED OF BEING IN | | A SIMILAR CONDITION AND ARE UNDER EVALUATION. | | | | SHOULD A DESIGN BASIS EARTHQUAKE CAUSE THE FAILURE OF THE SUPPORTS FOR THE | | 31 CCR AIR CONDITIONING UNIT, THE UNIT WOULD BE RENDERED INOPERABLE AND | | COULD POTENTIALLY DEGRADE THE OPERATION OF THE 32 CCR A/C UNIT BY DAMAGING | | THE VENTILATION SYSTEM DUCT WORK. UNDER THESE CONDITIONS THE POTENTIAL | | EXISTS FOR THE AMBIENT CONTROL ROOM TEMPERATURE TO EXCEED THE DESIGN LIMIT | | OF 120øF. | | | | IMMEDIATE CORRECTIVE ACTIONS BEING UNDERTAKEN ARE TO PLACE WOODEN | | BLOCKS/BOARDS UNDER BOTH A/C UNITS TO SUPPORT THEM SHOULD THEIR REGULAR | | SUPPORTS FAIL. LONG-TERM CORRECTIVE ACTIONS WILL BE TO FULLY EVALUATE THE | | SUPPORTS FOR THE 32 A/C UNIT AND TO REPAIR OR REPLACE THE SUPPORTS FOR BOTH | | UNITS AS NEEDED. RI HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27723 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 08/29/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 19:50 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/29/94 | +------------------------------------------------+EVENT TIME: 14:53[CDT]| |NRC NOTIFIED BY: HITZEL |LAST UPDATE DATE: 08/29/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MURRAY 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC SYSTEM DESIGN DEFICIENCY IDENTIFIED DURING REVIEW TO SUPPORT PLANT | | DESIGN BASIS RECONSTITUTION. | | | | DURING A REVIEW OF SURVEILLANCE REQUIREMENTS ASSOCIATED WITH THE RCIC | | SYSTEM, THE REVIEWER NOTED THAT THE RESET FUNCTION FOR RCIC-MOV-M014, THE | | RCIC TURBINE TRIP AND THROTTLE VALVE, WAS POWERED BY AN AC, NOT DC MOTOR. | | IN THE EVENT OF A RCIC SYSTEM TRIP, THE TRIP MECHANISM MUST BE RESET. THE | | AC MOTOR IS DESIGNED TO PERFORMED THIS RESET FUNCTION AUTOMATICALLY. | | ADDITIONALLY, THE VALVE CAN BE RESET FROM THE CONTROL ROOM BY DEPRESSING | | THE TURBINE TRIP AND THROTTLE VALVE RESET BUTTON. HOWEVER, IN THE EVENT | | THAT AC POWER IS NOT AVAILABLE, AUTOMATIC AND REMOTE RESET WOULD NOT BE | | POSSIBLE. LOCAL OPERATOR ACTION WOULD BE REQUIRED. | | | | RCIC IS DESIGNED TO FUNCTION TO PROVIDE RESIDUAL HEAT REMOVAL IN THE EVENT | | OF A STATION BLACKOUT (SBO) IN WHICH ALL OFFSITE AND ONSITE AC POWER IS | | LOST FOR A PERIOD OF UP TO 4 HOURS. ADDITIONALLY, THE SYSTEM IS DESIGNED | | TO CYCLE AUTOMATICALLY IN THE SHORT TERM (4 TO 6 HOURS). THE DESIGN BASIS | | OF THE RCIC SYSTEM IS THAT IT SHOULD BE INDEPENDENT OF AC POWER AND SHALL | | DEPEND ONLY ON DC POWER FOR SHORT TERM OPERATION. | | | | TO RESOLVE THE APPARENT DESIGN DEFICIENCY, LICENSEE IS GOING TO INSTALL A | | DC MOTOR IN PLACE OF THE AC MOTOR. THIS ACTION WILL BE COMPLETED PRIOR TO | | RESUMING POWER OPERATION. THE RI HAS BEEN INFORMED. | +------------------------------------------------------------------------------+