U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/12/96 - 08/13/96 ** EVENT NUMBERS ** 30761 30867 30868 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/17/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 20:18 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/17/96 | +------------------------------------------------+EVENT TIME: 20:18[EDT]| |NRC NOTIFIED BY: BONNER |LAST UPDATE DATE: 08/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOLCE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR PROTECTION ANALYSIS MAY HAVE BEEN NONCONSERVATIVE. | | | | THE LICENSEE'S PRELIMINARY EVALUATION INDICATES THAT THE ANALYSIS FOR AN | | UNCONTROLLED CONTROL ROD BANK WITHDRAWAL FROM A SUBCRITICAL OR LOW POWER | | CONDITION MAY HAVE BEEN NONCONSERVATIVE. THE REACTOR PROTECTION SYSTEM | | STARTUP RATE TRIP, WHICH HAS SINCE BEEN REMOVED, MAY HAVE PLACED THE UNIT | | OUTSIDE OF ITS DESIGN BASIS. (THE CURRENT ANALYSIS DOES NOT REQUIRE A | | STARTUP RATE TRIP.) THE LICENSEE WILL CONTINUE TO EVALUATE THIS CONDITION. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 2055 EDT 08/12/96, FROM J.BERGEN TO S.SANDIN * * * | | | | THE LICENSEE IS CONTINUING ITS EVALUATION. IN 1978, THE LICENSEE REMOVED | | THE STARTUP RATE TRIP. AT THE TIME, COMBUSTION ENGINEERING WAS THE FUEL | | VENDOR AND PERFORMED THE SAFETY ANALYSIS. SUBSEQUENTLY, THE LICENSEE | | CONTRACTED WITH WESTINGHOUSE TO SUPPLY FUEL AND PERFORM THE SAFETY ANALYSES | | FOR ABOUT FOUR TO SIX CYCLES. SIEMENS REPLACED WESTINGHOUSE IN CYCLE 10 | | AND PERFORMED THE SAFETY ANALYSES UP TO AND INCLUDING THE CURRENT CYCLE | | (CYCLE 13). WHEN THE LICENSEE CONTACTED SIEMENS, SIEMENS EXPRESSED A | | CONCERN FOR THE ANALYSES PERFORMED IN CYCLES 10 THROUGH 13. SPECIFICALLY, | | THIS CONCERN WAS THAT THE CORE PEAKING FACTORS FOR OTHER ANALYSES WERE NOT | | BOUNDED WITH THE STARTUP RATE TRIP REMOVED. THE LICENSEE FOLLOWED UP BY | | CONTACTING WESTINGHOUSE; HOWEVER, WESTINGHOUSE HAS NOT YET REPLIED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (CARUSO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30867 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/12/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:30 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/12/96 | +------------------------------------------------+EVENT TIME: 10:05[EDT]| |NRC NOTIFIED BY: ED GOETCHIUS |LAST UPDATE DATE: 08/12/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SPECIAL REPORT - FIRE PROTECTION SYSTEM INOPERABLE FOR THE DURATION OF | | VALVE OPERABILITY TESTING | | | | PURSUANT TO THE REQUIREMENTS OF TECHNICAL SPECIFICATION 3.13.A.3.B.i., THE | | LICENSEE IS PROVIDING THIS NOTIFICATION TO REPORT A CONDITION WHERE THE | | HIGH PRESSURE FIRE PROTECTION SYSTEM WAS NOT ALIGNED IN ITS NORMAL | | OPERATING CONFIGURATION DUE TO THE ANNUAL SURVEILLANCE TESTING OF THE | | HEADER INTERCONNECT VALVE. THE VALVE IS A NORMALLY OPEN, MANUAL, GATE | | VALVE THAT CONNECTS THE TWO HIGH PRESSURE HEADERS. THE TEST PERFORMED WAS | | A STROKE TEST WHICH CAUSED ISOLATION OF ONE OF THE HIGH PRESSURE HEADERS | | FOR APPROXIMATELY 20 MINUTES. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30868 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 08/12/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 23:45 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 08/12/96 | +------------------------------------------------+EVENT TIME: 20:50[EDT]| |NRC NOTIFIED BY: DAVID CORLETT |LAST UPDATE DATE: 08/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OPERATOR ERROR RESULTING IN THE UNINTENTIONAL AUTOMATIC CLOSING OF THREE | | STEAM LINE DRAIN ISOLATION VALVES | | | | AN OPERATOR ERROR OCCURRED DURING THE PERFORMANCE OF ENGINEERED SAFETY | | FEATURE SLAVE RELAY TESTING WITH THE UNIT OPERATING AT 100% REACTOR POWER. | | THE OPERATOR INTENDED TO ACTUATE THE CONTAINMENT VENTILATION ISOLATION TEST | | SIGNAL BUT MISTAKENLY ACTUATED THE MAIN STEAM ISOLATION TEST SIGNAL | | INSTEAD. THIS RESULTED IN THE UNINTENTIONAL AUTOMATIC CLOSING OF THREE | | STEAM LINE DRAIN ISOLATION VALVES. PLANT OPERATION WAS NOT AFFECTED. ALL | | COMPONENTS ACTUATED PROPERLY IN RESPONSE TO THE SIGNAL RECEIVED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+