U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/23/96 - 10/24/96 ** EVENT NUMBERS ** 31194 31195 31197 31198 31199 31200 31201 31202 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31194 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 10/22/96 | |UNIT: [1] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:05 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 10/22/96 | +------------------------------------------------+EVENT TIME: 10:45[EDT]| |NRC NOTIFIED BY: BRETT BOISMENU |LAST UPDATE DATE: 10/23/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAKE WELLING RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTRACTOR SUPERVISOR TESTED POSITIVE FOR ALCOHOL. | | | | A CONTRACTOR FULFILLING A SUPERVISORY POSITION ATTEMPTED TO ENTER THE | | PROTECTED AREA AND WAS DENIED ENTRY BY THE SECURITY GUARD BASED UPON ON | | SUSPICION OF AN ALCOHOL ODOR. A FOR CAUSE TEST WAS CONDUCTED AND RESULTED | | IN A POSITIVE ALCOHOL TEST. THE INDIVIDUAL'S ACCESS WAS TERMINATED. THE | | CONTRACTOR WAS NOT INVOLVED IN PLANT OPERATIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | | | | ***RETRACTION BY BRETT BOISMENN @ 1319EDT 10/23/96 TAKEN BY MACKINNON*** | | | | NINE MILE POINT WOULD LIKE TO RETRACT THIS NOTIFICATION. EVEN THOUGH THE | | INDIVIDUAL (WHO TESTED POSITIVE WAS A SUPERVISOR FOR HIS COMPANY) HE WAS | | NOT ASSIGNED TO ANY SUPERVISORY RESPONSIBILITIES WHILE HE WAS WORKING AT | | THE PLANT. THEREFORE, THE EVENT SHOULD NOT HAVE BEEN REPORTED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THE EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31195 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 10/22/96 | |UNIT: [1] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:05 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 10/21/96 | +------------------------------------------------+EVENT TIME: 21:00[EDT]| |NRC NOTIFIED BY: BRETT BOISMENU |LAST UPDATE DATE: 10/23/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAKE WELLING RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTRACTOR FULFILLING A SUPERVISORY POSITION TESTED POSITIVE FOR ALCOHOL. | | | | A CONTRACTOR FULFILLING A SUPERVISORY POSITION WAS FOR CAUSE TESTED BASED | | ON CREDIBLE INFORMATION AND TESTED POSITIVE FOR ALCOHOL. | | THE INDIVIDUAL'S ACCESS WAS TERMINATED. CONTRACTOR WAS NOT INVOLVED IN | | PLANT OPERATIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | | ***UPDATE BY BRETT BOISMENN @ 1319EDT 10/22/96 TAKEN BY MACKINNON*** | | THE EVENT TIME AND DATE FOR THIS EVENT WAS 2100 EDT ON 10/21/96. | | R1DO (BLAKE WELLING) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31197 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 10/23/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 11:55 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 10/23/96 | +------------------------------------------------+EVENT TIME: 11:15[EDT]| |NRC NOTIFIED BY: G. C. WITHROW |LAST UPDATE DATE: 10/23/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A REVISED CONTAINMENT ANALYSIS INDICATES THAT ANALYSIS OF THE FINAL SAFETY | | ANALYSIS REPORT UNDERESTIMATED PLANT RESPONSE TO A LARGE STEAM LINE BREAK. | | | | A REVISED CONTAINMENT ANALYSIS INDICATES THAT THE ANALYSIS OF THE FINAL | | SAFETY ANALYSIS REPORT FIGURE 3.4 (PAGE 3.11-8) UNDERESTIMATED PLANT | | RESPONSE TO LARGE STEAM LINE BREAKS. BIG ROCK POINT WAS NOT MADE AWARE OF | | THE DISCREPANCY DISCOVERED BY NUS/PALISADES IN 1990 AND CORRECTED FOR | | PALISADES AT THAT TIME. DURING CONVERSION OF CONTEMPT CODE (CONTAINMENT | | ANALYSIS COMPUTER CODE) FROM A MAINFRAME TO A PERSONAL COMPUTER VERSION, AN | | ERROR WAS DISCOVERED WHICH INVOLVED SPRAY SUPERHEAT EFFICIENCY. THIS MAY | | RESULT IN A ~ 65øF UNDERESTIMATION OF THE ELECTRICAL EQUIPMENT | | QUALIFICATION PROFILE CURVE. INITIAL THERMAL RESPONSE REVIEW INDICATES THAT | | ELECTRICAL EQUIPMENT QUALIFICATION COMPONENT HAVING LOWER THAN A 325øF | | QUALIFICATION WILL NOT EXPERIENCE A TEMPERATURE RISE DURING POSTULATED | | ACCIDENTS THAT WILL EXCEED THEIR QUALIFICATION. THUS SOME COMPONENTS ARE | | CONSIDERED NONCONFORMING BUT OPERABLE UNTIL FINALIZATION OF ANALYSIS CAN BE | | COMPLETE. THE PLANT WILL BE SHUTDOWN WITHIN THE NEXT 24 HOURS AND WILL | | REMAIN SHUTDOWN UNTIL A REVISED ANALYSIS IS COMPLETED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST JOHN REGIONAL MEDICAL CENTER |NOTIFICATION DATE: 10/23/96 | | CITY: JOPLIN REGION: 3 |NOTIFICATION TIME: 12:25 [ET]| | COUNTY: JASPER STATE: MO |EVENT DATE: 10/23/96 | |LICENSE#: 24-01090-03 AGREEMENT: N |EVENT TIME: 08:30[CDT]| | DOCKET: |LAST UPDATE DATE: 10/23/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRUCE JORGENSEN RDO | | |FRD COMBS (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: J. FISCHER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PATIENT RECEIVED RADIATION DOSE TO THE WRONG AREA AFTER THE PATIENTS | | IRIDIUM RIBBON BECAME DISLODGED. | | | | AT 1415 CDT ON 01/22/96, A TERMINAL PATIENT RECEIVED AN ENDOBRONCHIAL | | IRIDIUM IMPLANT TO RELIEVE PAIN FROM A TUMOR LOCATED IN THE PATIENTS | | BRONCHIAL PASSAGE WAY. A CATHETER WAS PLACED IN THE PATIENTS NOSE AND THE | | IRIDIUM RIBBON WAS INSERTED THROUGH THE CATHETER TO THE BRONCHIAL | | PASSAGEWAY (THE IRIDIUM RIBBON WAS PLACED NEAR THE SITE OF THE TUMOR). AT | | APPROXIMATELY 0100 CDT 10/23/96 THE PATIENT HAD A VIOLENT COUGHING SPELL. | | AT 0830 CDT A DOCTOR MAKING HIS ROUNDS DISCOVERED THAT THE IRIDIUM RIBBON | | WAS NOT LOCATED IN THE BRONCHIAL PASSAGEWAY ANY MORE BUT WAS LOCATED IN THE | | PATIENTS NASAL PASSAGE. THE DOCTOR HAD THE IRIDIUM RIBBON REMOVED AND | | ALERTED THE RADIATION STAFF OF THE DISPLACED IRIDIUM RIBBON. THE PATIENT | | INFORMED THE DOCTOR OF THE VIOLENT COUGHING SPELL AT 0100 CDT AND THAT THE | | NURSES WERE NOT NOTIFIED OF THE DISLODGED IRIDIUM RIBBON. | | THE CALCULATED DOSE THE PATIENT RECEIVED TO THE NASAL PASSAGE IS 363 TO | | 762cGy. THE CALCULATED DOSE THE PATIENT RECEIVED TO THE LENS OF THE EYE IS | | 111cGy. BASED UPON THE CONDITION OF THE PATIENT THE PATIENT WILL RECEIVE NO | | ADVERSE REACTION FROM THE IRIDIUM RIBBON BEING IN ITS IMPROPER POSITION FOR | | 7.5 HOURS. | | | | THE DOCTOR INFORMED THE PATIENT OF THE ABOVE INFORMATION AND INFORMED THE | | PATIENTS DOCTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31199 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/23/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/23/96 | +------------------------------------------------+EVENT TIME: 13:35[CDT]| |NRC NOTIFIED BY: DENNIS HIGINBOTHAM |LAST UPDATE DATE: 10/23/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ROLLUP FIRE DOOR FAILED TO CLOSE DURING TEST | | | | DURING THE PERFORMANCE OF TEST PROCEDURE SPP-96-033 TO VERIFY THE | | FUNCTIONALITY OF THE DIVISION 12 ESF SWITCHGEAR ROOM ROLLUP FIRE DOOR, THE | | DOOR FAILED TO CLOSE AS REQUIRED. SEE SIMILAR EVENT REPORTED BY THE | | LICENSEE TO THE NRC OPERATION CENTER ON 09/24/96 @ 1832EDT (SEE EVENT # | | 31054). FIRE WATCHES WERE ALREADY ESTABLISHED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | ***UPDATE @ 1557EDT 10/23/96, BY D. HIGINBOTHAM TAKEN BY MACKINNON*** | | | | DIVISION 11 ESF SWITCHGEAR ROOM ROLLUP FIRE DOOR FAILED TO CLOSE AS | | REQUIRED. AIR PRESSURE FROM THE HVAC SYSTEM PREVENTS THE ROLLUP DOORS FROM | | CLOSING. LICENSEE IS SUSPENDING THE TESTING OF THE ROLLUP DOORS. WILL TRY | | TO REPORT ALL FUTURE ESF SWITCHGEAR ROOM ROLLUP DOORS THAT FAIL TO CLOSE AS | | ONE EVENT. R3DO (JORGENSEN) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31200 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 10/23/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 17:17 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 10/23/96 | +------------------------------------------------+EVENT TIME: 14:42[CDT]| |NRC NOTIFIED BY: HARRINGTON |LAST UPDATE DATE: 10/23/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 +------------------------------------------------------------------------------+ | A FAILURE OF A SINGLE CONTAINMENT ISOLATION VALVE COULD PLACE THE PLANT IN | | AN UNANALYZED CONDITION. | | | | THE LICENSEE HAS CONCLUDED THAT THE POTENTIAL EXISTS FOR THE PLANT BEING IN | | AN UNANALYZED CONDITION IN THE EVENT OF A FAILURE OF A SINGLE CONTAINMENT | | ISOLATION VALVE. | | | | DUE TO SYSTEM PIPING INTERCONNECTIONS BETWEEN THE RESIDUAL HEAT REMOVAL | | SYSTEM AND THE CHEMICAL VOLUME AND CONTROL (CVCS) LETDOWN SYSTEM, THE | | POTENTIAL EXISTS TO PUMP CONTAINMENT SUMP WATER INTO THE CVCS WHEN IN THE | | POST LOSS OF COOLANT ACCIDENT (LOCA) CONTAINMENT SUMP RECIRCULATION MODE. | | THIS CAN OCCUR IF THE CONTAINMENT SUMP ISOLATION VALVE, LD-6, FAILS TO | | CLOSE DURING A LOCA. | | | | THE CONCERN IS THAT POST ACCIDENT RADIATION LEVELS MAY EXCEED THE ANALYZED | | CONDITIONS TO PERMIT PERSONNEL ACCESS IN THE AUXILIARY BUILDING TO PERFORM | | REQUIRED ACTIONS. LICENSEE WILL MOST LIKELY IMPLEMENT ADMINISTRATIVE | | CONTROLS TO PRECLUDE THIS CONDITION. | | | | THE RESIDENT INSPECTOR WAS INFORMED OF THIS EVEN BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31201 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/23/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 18:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/23/96 | +------------------------------------------------+EVENT TIME: 17:07[EDT]| |NRC NOTIFIED BY: CHARLES MEYER |LAST UPDATE DATE: 10/23/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 64 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP ON LOW CONDENSER VACUUM | | | | WHILE REMOVING THE CLEARANCE FROM UNIT 2 "B" MAIN FEEDWATER PUMP, THE | | TURBINE CASING WAS OVER PRESSURIZED CAUSING THE CASING RUPTURE DISC TO | | ACTUATE. "B" MAIN FEEDWATER PUMP HAD BEEN OUT OF SERVICE TO INVESTIGATE A | | VIBRATION PROBLEM ASSOCIATED WITH ITS TURBINE. | | | | THE OPENING OF THE RUPTURE DISC ON THE CASING OF THE "B" MAIN FEEDWATER | | PUMP TURBINE CASING CAUSED A LOSS OF MAIN CONDENSER VACUUM WHICH LED TO A | | TURBINE TRIP. THE TURBINE TRIP ACTUATED THE REACTOR TRIP. ALL RODS FULLY | | INSERTED INTO THE CORE. THE STEAM DUMPS WERE USED TO DUMP STEAM INTO THE | | CONDENSER UNTIL CONDENSER VACUUM WAS LOST. STEAM GENERATOR ATMOSPHERIC | | VALVES ARE BEING USED AT THE PRESENT TIME TO MAINTAIN THE PLANT AT A Tave | | NO LOAD TEMPERATURE OF 557øF. NONE OF THE STEAM GENERATOR TUBES HAVE ANY | | PRIMARY TO SECONDARY SYSTEM LEAKS. | | | | BOTH MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS AUTOMATICALLY ACTUATED ON LOW | | STEAM GENERATOR WATER LEVEL. STEAM GENERATOR WATER LEVEL IS CURRENTLY BEING | | MAINTAINED BY THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS. ALL EMERGENCY | | CORE COOLING SYSTEMS AND THEIR EMERGENCY DIESEL GENERATORS ARE FULLY | | OPERABLE IF NEEDED. | | | | LICENSEE THINKS THAT MAIN FEEDWATER PUMP TURBINE CASING OVER PRESSURIZED | | DUE TO EITHER THE MAIN FEEDWATER PUMP TURBINE STOP AND CONTROL VALVES | | LEAKING BY, OR THE ABOVE SEAT DRAIN VALVES FOR THE MAIN FEEDWATER PUMP | | TURBINE STOP AND CONTROL VALVES LEAKING BY. | | | | PRESENTLY THE LICENSEE IS TRYING TO PLUG THE MAIN FEEDWATER PUMP TURBINE | | CASING SO THEY CAN RESTORE MAIN CONDENSER VACUUM. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 10/24/96 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 05:00 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 03:19[EDT]| |NRC NOTIFIED BY: MICHAEL BECKER |LAST UPDATE DATE: 10/24/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP - REACTOR TRIP | | | | AT 0319 ON 10/24/96, UNIT ONE TRIPPED WHEN THE GENERATOR OUTPUT BREAKER | | OPENED DUE TO "GENERATOR NEGATIVE PHASE SEQUENCE". ALL SYSTEMS OPERATED AS | | DESIGNED. ALL THREE AFW PUMPS STARTED ON STEAM GENERATOR LOW LEVEL. STEAM | | GENERATOR LEVEL HAS BEEN RECOVERED AND THE STEAM GENERATORS ARE NOW BEING | | FED BY MAIN FEEDWATER. ALL RODS FULLY INSERTED. STEAM IS BEING DUMPED AS | | NECESSARY TO THE MAIN CONDENSER TO REMOVE DECAY HEAT. | | | | NO OBVIOUS GENERATOR PROBLEM EXISTED TO CAUSE THE GENERATOR TRIP AND THE | | CAUSE OF THE TRIP IS UNDER INVESTIGATION. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+