U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/15/96 - 10/16/96 ** EVENT NUMBERS ** 31029 31067 31150 31151 31152 31153 31154 31155 31156 31157 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31029 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/19/96 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 14:00 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/19/96 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: JEFF MOSHER |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM DECKER RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROCEDURAL DEFICIENCY WAS IDENTIFIED THAT COULD HAVE RESULTED IN THE DOSE | | TO THE CONTROL ROOM PERSONNEL EXCEEDING ACCIDENT ANALYSIS ASSUMPTIONS. | | | | ABNORMAL OPERATING PROCEDURE 30 (FUEL FAILURE DURING HANDLING) WAS | | DEFICIENT REGARDING ACTIONS REQUIRED TO MITIGATE THE CONSEQUENCES OF A FUEL | | HANDLING EVENT. THE PROCEDURE DID NOT INSTRUCT THE CONTROL ROOM OPERATORS | | TO MANUALLY ISOLATE THE CONTROL ROOM AND INITIATE BOTTLED AIR SUPPLY TO THE | | CONTROL ROOM. A TECHNICAL SPECIFICATION CHANGE WAS APPROVED ON 02/27/96, | | WHICH ALLOWED THE PERSONNEL AIR LOCK DOOR TO REMAIN OPEN AS LONG AS A | | DEDICATED PERSON WAS STATIONED AT THE DOOR TO CLOSE IT. THE FUEL HANDLING | | ACCIDENT ANALYSIS ASSOCIATED WITH THIS TECHNICAL SPECIFICATION CHANGE | | STATES THAT UPON A VERBAL NOTIFICATION OF A FUEL HANDLING ACCIDENT WITH A | | POTENTIAL RADIONUCLIDE RELEASE OR A HIGH RADIATION ALARM FROM A CONTAINMENT | | RADIATION MONITOR, THE CONTROL ROOM WILL BE MANUALLY ISOLATED AND THE | | CONTROL ROOM BOTTLED AIR SYSTEM INITIATED. THIS STATEMENT SHOULD HAVE BEEN | | INCORPORATED INTO ABNORMAL OPERATING PROCEDURE 30 BUT WAS NOT. THE | | LICENSEE WILL HAVE ABNORMAL OPERATING PROCEDURE 30 REVISED BEFORE UNIT 2 | | STARTS RELOADING FUEL. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1330 EDT 10/15/96, FROM PAGE KEMP BY S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS REPORT BASED ON THE FOLLOWING: | | | | ON SEPTEMBER 19, 1996, A FOUR-HOUR REPORT WAS MADE TO THE NRC OPERATIONS | | CENTER AT 1400 HOURS IN ACCORDANCE WITH 10CFR50.72(b)(2)(iii)(D). THE | | REPORT WAS MADE WHEN IT WAS DETERMINED THAT AN ASSUMPTION MADE BY THE FUEL | | HANDLING ACCIDENT (FHA) SAFETY ANALYSIS TO MANUALLY DUMP BOTTLED AIR TO THE | | CONTROL ROOM IN THE EVENT OF A FHA INSIDE CONTAINMENT WAS NOT INCLUDED IN | | THE FHA ABNORMAL PROCEDURE 0-AP-30. SUBSEQUENT REVIEWS OF PROCEDURE | | 0-AP-30 HAVE DETERMINED THAT THE PROCEDURE DID ENSURE THAT NECESSARY | | ACTIONS WERE TAKEN FOLLOWING A FHA IN THE CONTAINMENT TO TERMINATE ANY | | RELEASE AND PREVENT THE CONTROL ROOM OPERATORS FROM EXCEEDING GDC 19 | | LIMITS. THEREFORE, THE CRITERIA FOR A REPORT PER 10CFR50.72(b)(2)(iii)(D) | | WAS NOT MET AND THE FOUR HOUR REPORT IS BEING RETRACTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO(JULIAN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/27/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 00:08 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 21:35[EDT]| |NRC NOTIFIED BY: BECKER |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 PLANT HAD A CONTAINMENT PURGE SYSTEM ISOLATION SIGNAL DUE TO A | | HIGH-HIGH RADIATION SIGNAL FROM THE MANIPULATOR CRANE RAD MONITOR. | | | | THIS OCCURRED DURING THE REACTOR VESSEL HEAD SET EVOLUTION, WHEN THE VESSEL | | HEAD CAME CLOSE TO THE CRANE AND THE HIGH-HIGH SETPOINT (45MR/HR) WAS | | SENSED FOR APPROX. 20 SECONDS BY THE MANIPULATOR CRANE RAD MONITOR. THIS | | GENERATED THE CONTAINMENT PURGE ISOLATION SIGNAL. THE CONTAINMENT PURGE | | WAS RE-ESTABLISHED AT 21:51 WHEN THE REACTOR HEAD WAS BEING LOWERED ONTO | | THE GUIDE STUDS AND THE MANIPULATOR CRANE RAD MONITOR RETURNED TO 5MR/HR. | | THE RI WILL BE INFORMED. | | | | * * * 1330 EDT 10/15/96, FROM PAGE KEMP TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS REPORT BASED ON THE FOLLOWING: | | ON 09/27/96, A 4-HOUR REPORT WAS MADE TO THE NRC OPERATIONS CENTER AT 0008 | | IN ACCORDANCE WITH 10CFR50.72(b)(2)(ii). THE REPORT WAS MADE WHEN THE UNIT | | 2 CONTAINMENT PURGE AUTOMATICALLY ISOLATED ON A HIGH-HIGH RADIATION SIGNAL | | FROM THE MANIPULATOR CRANE RADIATION MONITOR AS THE REACTOR VESSEL HEAD WAS | | PASSED NEAR THE MONITOR AS IT WAS BEING INSTALLED. ACCORDING TO NUREG 1022 | | VALID SIGNALS ARE THOSE SIGNALS THAT ARE INITIATED IN RESPONSE TO ACTUAL | | PLANT CONDITIONS OR PARAMETERS SATISFYING THE REQUIREMENTS FOR ESF | | INITIATION. FOR THE CONTAINMENT VENTILATION ISOLATION TO RECEIVE A VALID | | ESF SIGNAL, A FUEL HANDLING ACCIDENT INSIDE CONTAINMENT WOULD HAVE TO | | OCCUR. SINCE A FUEL HANDLING ACCIDENT DID NOT OCCUR, THE SIGNAL HAS BEEN | | DETERMINED TO BE INVALID AND DOES NOT MEET THE CRITERIA FOR A REPORT PER | | 10CFR50.72(b)(2)(ii). THE 4-HOUR REPORT IS BEING RETRACTED. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO(JULIAN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31150 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 10/15/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 02:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 01:36[EDT]| |NRC NOTIFIED BY: McGUINESS |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |POTTER RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED OFFSITE TO HOSPITAL | | | | WHILE PERFORMING A CONTAINMENT INSPECTION, AN INDIVIDUAL FELL DOWN AN | | INSTALLED PLANT LADDER IN THE LOWER CONTAINMENT. THE INDIVIDUAL WAS | | IMMOBILIZED AND TRANSPORTED TO THE LOCAL HOSPITAL. HOWEVER, DUE TO THE | | NEED FOR IMMOBILIZATION, A PORTION OF THE INDIVIDUAL'S BODY COULD NOT BE | | CHECKED DURING THE PRE-TRANSPORT WHOLE BODY SURVEY. THOSE PORTIONS OF THE | | INDIVIDUAL'S BODY WHICH WERE SURVEYED SHOWED NO SIGNS OF CONTAMINATION, AND | | THE LICENSEE DOES NOT EXPECT TO FIND CONTAMINATION ON OTHER PARTS OF THE | | INDIVIDUAL. THE SURVEY WILL BE COMPLETED UPON ARRIVAL AT THE HOSPITAL. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE 0346 FROM McGUINESS TAKEN BY STRANSKY * * * | | | | THE SURVEY OF THE INDIVIDUAL WAS COMPLETED, AND NO CONTAMINATION WAS FOUND. | | NOTIFIED R2DO (POTTER). | | | | * * * UPDATE AT 1716 ON 10/15/96, BY PACE TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE THE INDIVIDUAL WAS NOT | | CONTAMINATED. THEREFORE, THE EVENT DOES NOT MEET THE REPORTING CRITERIA OF | | 10 CFR 50.72. THE NRC RESIDENT WILL BE INFORMED OF THIS RETRACTION. THE | | HOO NOTIFIED THE R2DO (JULIAN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/15/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 00:20[CDT]| |NRC NOTIFIED BY: HALVERSON |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEACH 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 +------------------------------------------------------------------------------+ | FEEDWATER ISOLATION VALVES FAIL LOCAL LEAK RATE TEST | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "THE CONTAINMENT ISOLATION VALVES ON THE 'B' FEEDWATER LINE DID NOT MEET | | LOCAL LEAK RATE TESTING REQUIREMENTS FROM 10 CFR 50, APPENDIX J, AND | | TECHNICAL SPECIFICATION 3.6.1.3, 'PRIMARY CONTAINMENT ISOLATION VALVES.' | | THE LEAK RATE OF EACH VALVE WAS BEYOND THE LIMITS OF THE LLRT TEST | | EQUIPMENT. THE VALVES AFFECTED ARE THE 1B21F010B (REACTOR FEEDWATER HEADER | | CHECK VALVE) AND 1B21F032B (FEEDWATER CONTAINMENT ISOLATION CHECK VALVE)." | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31152 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 10/15/96 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 11:16 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: NEAL |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAMS 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO INDIVIDUALS TESTED POSITIVE DURING DRUG TESTING. | | | | A NON-LICENSED UTILITY SUPERVISOR TESTED POSITIVE FOR ILLEGAL DRUG USAGE. | | A CONTRACT WAREHOUSE SUPERVISOR TESTED POSITIVE FOR ALCOHOL USAGE. BOTH | | INDIVIDUALS HAVE BEEN DENIED ACCESS TO THE SITE. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31153 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/15/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:53 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 09:05[EDT]| |NRC NOTIFIED BY: SANJEEV |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 +------------------------------------------------------------------------------+ | ESF ACTUATION - EMERGENCY EQUIPMENT COOLING WATER (EECW) RECEIVED A START | | SIGNAL ON LOW REACTOR BUILDING CLOSED COOLING WATER (RBCCW) PRESSURE | | | | A LOW RBCCW PRESSURE SIGNAL CAUSED TWO EECW VALVES TO SHUT. THE LOW RBCCW | | PRESSURE WAS CAUSED BY OPENING A VALVE IN THE RBCCW SYSTEM TOO RAPIDLY. THE | | EECW PUMP HAD BEEN PREVIOUSLY STARTED TO SUPPORT A FILL AND VENT OF THE | | EECW SYSTEM. THE EECW SYSTEM HAS BEEN RESET, AND THE FILL AND VENT | | CONTINUES. RBCCW IS OPERATING NORMALLY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31154 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY |NOTIFICATION DATE: 10/15/96 | | CITY: LAWTON REGION: 4 |NOTIFICATION TIME: 15:35 [ET]| | COUNTY: STATE: OK |EVENT DATE: 10/15/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 10/15/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES CAIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MAJOR STEPHENS | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN EXIT SIGN CONTAINING 25 CURIES OF TRITIUM WAS DISCOVERED TO BE MISSING. | | THE SIGN WAS LOCATED IN THE VISITING OFFICER QUARTERS BUILDING AT FT. SILL | | IN LAWTON, OK. | | | | SEE HOO LOG FOR CALLER'S TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31155 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 10/15/96 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 19:09 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 09:53[PDT]| |NRC NOTIFIED BY: JOHNSON |LAST UPDATE DATE: 10/15/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTRACTOR FOREMAN TESTED POSITIVE FOR A CONTROLLED SUBSTANCE DURING A | | RANDOM DRUG TEST. THE INDIVIDUAL'S SITE ACCESS HAS BEEN INACTIVATED. THE | | WORK HISTORY OF THIS INDIVIDUAL IS BEING REVIEWED. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. THE DETAILS OF THIS REPORT ARE | | CONTAINED IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31156 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 10/16/96 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 01:21 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 23:11[EDT]| |NRC NOTIFIED BY: DOUG CREMER |LAST UPDATE DATE: 10/16/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS 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 | A/R Y 70 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO REACTOR SCRAM FROM 70% POWER DUE TO AUTO MAIN TURBINE TRIP - | | | | WITH UNIT 2 AT 98% POWER WITH NO TESTING OR MAINTENANCE ACTIVITIES IN | | PROGRESS, UNIT 2 RECEIVED A MAIN GENERATOR STATOR CURRENT UNBALANCE ALARM. | | CONTROL ROOM OPERATORS REDUCED REACTOR POWER. | | | | AT 70% POWER, THE MAIN TURBINE AUTO TRIPPED WHICH CAUSED THE REACTOR TO | | AUTO SCRAM AND PRIMARY CONTAINMENT ISOLATION SIGNALS FOR GROUP 2 (DRYWELL | | SUMP VALVES) AND GROUP 3 (REACTOR BUILDING VENTILATION SYSTEM) TO ACTUATE. | | ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. | | | | UNIT 2 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE MAIN TURBINE TRIP AND PLANS | | TO RESTART UNIT 2 UPON COMPLETION OF THE INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: THIS EVENT IS SIMILAR TO EVENT REPORT #31104 ON 10/06/96. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31157 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 10/16/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 01:22 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/15/96 | +------------------------------------------------+EVENT TIME: 23:35[EDT]| |NRC NOTIFIED BY: JOHN SLATTERY |LAST UPDATE DATE: 10/16/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 82 POWER OPERATION | 82 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SAFETY PARAMETER DISPLAY SYSTEM MULTIPLEXER FAILED FOR UNKNOWN REASONS - | | | | AT 2335 ON 10/15/96, THE UNIT 2 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) | | MULTIPLEXER FAILED FOR UNKNOWN REASONS. THIS AFFECTED THE DISPLAY OF | | REACTOR POWER AND CORE EXIT THERMOCOUPLES ON THE SPDS TOP LEVEL DISPLAY. | | | | THE LICENSEE IS REPAIRING THE MULTIPLEXER. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+