U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/11/95 - 10/12/95 ** EVENT NUMBERS ** 29439 29440 29441 29442 29443 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29439 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/11/95 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 11:50 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/11/95 | +------------------------------------------------+EVENT TIME: 11:15[EDT]| |NRC NOTIFIED BY: BARRY COLEMAN |LAST UPDATE DATE: 10/11/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE CONTAINMENT ISOLATION VALVES FOR THE DRYWELL FLOOR DRAIN SYSTEM FAILED | | A LOCAL LEAK RATE TEST (LLRT). | | | | THE VALVES ARE 2G11F003 AND 2G11FOO4. THESE VALVES ARE INTENDED TO SERVE | | AS ISOLATION FOR THE DRYWELL FLOOR DRAIN SYSTEM. THE VALVES SERVE TO | | ISOLATE THE PRIMARY CONTAINMENT FROM THE RAD WASTE BUILDING. THE VALVES | | ARE PHYSICALLY LOCATED IN THE SECONDARY CONTAINMENT. THE LINEUP OF THE | | SYSTEM IS SUCH THAT ANY LEAKAGE PAST THE VALVES GOES DIRECTLY FROM THE | | PRIMARY CONTAINMENT TO THE RAD WASTE BUILDING BYPASSING SECONDARY | | CONTAINMENT. THE COMBINED LEAKAGE RATE ACCEPTANCE CRITERIA FOR ALL SUCH | | PATHS IS 0.009 La. THE LEAKAGE RATE WITH BOTH VALVES SHUT EXCEEDED 0.009 | | La. | | | | THE LAST TIME THE VALVES WERE TESTED SATISFACTORILY WAS LAST REFUELING | | OUTAGE. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FAILURE OF THE | | VALVES. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29440 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/11/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:20 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/11/95 | +------------------------------------------------+EVENT TIME: 12:30[EDT]| |NRC NOTIFIED BY: ERIC DEMONCH |LAST UPDATE DATE: 10/11/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THIS EVENT REPRESENTS A VIOLATION OF OPERATING LICENSE SECTION 2.C. AND IS | | REPORTABLE UNDER SECTION 2.E. | | | | IT WAS DISCOVERED THAT 5 BATTERY-OPERATED EMERGENCY LIGHTING UNITS REQUIRED | | BY APPENDIX R OF 10 CFR PART 50, SECTION 3.J, WERE INOPERABLE FOR 2 TO 3 | | MONTHS WITH NO COMPENSATORY ACTION TAKEN. THE UNITS HAVE BEEN REPAIRED, | | AND THE PLANT IS IN FULL COMPLIANCE WITH APPENDIX R. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29441 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/11/95 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 17:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/11/95 | +------------------------------------------------+EVENT TIME: 13:30[PDT]| |NRC NOTIFIED BY: BILL RYAN |LAST UPDATE DATE: 10/11/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |DUNE 73.71(b)(1) UNAUTHORIZED ENTRY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A WESTINGHOUSE EMPLOYEE WAS GRANTED UNESCORTED ACCESS BASE ON INCOMPLETE | | INFORMATION FROM WESTINGHOUSE. | | | | ON 10/05/95, A WESTINGHOUSE EMPLOYEE SCREENED UNDER THE WESTINGHOUSE | | ELECTRIC CORPORATION ACCESS PROGRAM WAS APPROVED FOR TEMPORARY UNESCORTED | | ACCESS AT DIABLO CANYON. THE UNESCORTED ACCESS CLEARANCE WAS GRANTED BASED | | ON A CERTIFICATION LETTER FROM THE WESTINGHOUSE ACCESS AUTHORIZATION | | COORDINATOR. ON 10/11/95, WESTINGHOUSE ADVISED THE LICENSEE THAT THE | | INDIVIDUAL WAS NOT RECOMMENDED FOR UNESCORTED ACCESS BASED ON A SUBSEQUENT | | PSYCHOLOGICAL EVALUATION. THIS EVALUATION SHOULD HAVE BEEN COMPLETED BY | | WESTINGHOUSE PRIOR TO THE ACCESS RECOMMENDATION. ACCESS FOR THE INDIVIDUAL | | HAS BEEN SUSPENDED. THE WESTINGHOUSE EMPLOYEE PERFORMED GENERAL LABOR | | FUNCTIONS WHILE HOLDING UNESCORTED ACCESS. THE LICENSEE IS REVIEWING THE | | EMPLOYEE'S WORK AND WILL ADVISE THE NRC IF ANYTHING ADVERSE TO PLANT SAFETY | | IS IDENTIFIED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29442 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/11/95 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 22:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/11/95 | +------------------------------------------------+EVENT TIME: 17:15[PDT]| |NRC NOTIFIED BY: GARY ANDERSON |LAST UPDATE DATE: 10/11/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 RELEASE PATHWAY FROM CONTAINMENT TO THE ENVIRONMENT MAY HAVE EXISTED FOR | | 52.5 HOURS IN VIOLATION TO TECH SPEC 3.9.4. | | | | AT 07:00 PDT ON 10/04/95, THE LICENSEE OPENED STEAM GENERATOR SECONDARY MAN | | WAYS. AT 11:30 PDT ON 10/06/95, THE LAST FUEL ASSEMBLY WAS OFFLOADED TO | | THE FUEL HANDLING BUILDING. AT 17:15 PDT ON 10/11/95, THE LICENSEE | | CONFIRMED THAT THE UPSTREAM MAIN STEAM ISOLATION VALVES (MSIV) FOR LOOPS 1 | | AND 2 WERE NOT FULLY CLOSED. A RELEASE PATHWAY VIA THE OPEN MAN WAYS, THE | | OPEN MSIVs, AND THE OPEN STEAM LINE DRAIN VALVES, ETC., EXISTED IN | | VIOLATION OF TECH SPEC 3.9.4. THE LICENSEE WILL ASSURE CONTAINMENT | | INTEGRITY AND MSIV CLOSURE VIA MECHANICAL POSITION RESTRAINT (GAG) PRIOR TO | | REFUELING OPERATIONS DURING THE CURRENT REFUELING OUTAGE (1R7). | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29443 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 10/12/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 04:13 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 10/12/95 | +------------------------------------------------+EVENT TIME: 02:23[EDT]| |NRC NOTIFIED BY: ANDY BARBEE |LAST UPDATE DATE: 10/12/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 5 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP DURING TURBINE OVERSPEED TESTING DUE TO THE | | INADVERTENT MIS-POSITIONING OF A SWITCH | | | | WITH REACTOR POWER AT APPROXIMATELY 5.3%, OPERATORS WERE ROLLING THE | | TURBINE AT 1,800 RPM, AND PROCEDURE OPT-1075 (TURBINE OVERSPEED TRIP TEST - | | 18-MONTH INTERVAL MODES 1-2) WAS IN PROGRESS. STEP 15 OF THIS PROCEDURE | | DIRECTED OPERATORS TO PLACE THE 'OVERSPEED TRIP' KEY SWITCH IN THE | | 'OVERSPEED TEST PERMISSIVE' POSITION; HOWEVER, THE 'OVERSPEED TRIP' KEY | | SWITCH WAS INADVERTENTLY PLACED IN THE 'OPC TEST' POSITION. THE OPC | | (OVERSPEED PROTECTION CONTROLLER) CAUSED THE TURBINE GOVERNOR AND | | INTERCEPTOR VALVES TO CLOSE, AND TURBINE SPEED REDUCED TO 1,690 RPM. THE | | SWITCH MIS-POSITIONING WAS REALIZED BY THE BALANCE-OF-PLANT OPERATOR, AND | | THE DECISION WAS MADE TO RESTORE THE SWITCH TO THE 'IN SERVICE' POSITION. | | THE TURBINE IMMEDIATELY ATTEMPTED TO RETURN TO 1,800 RPM CAUSING AN | | INCREASE IN STEAM FLOW TO THE TURBINE. THE EXCESSIVE STEAM FLOW CAUSED | | STEAM GENERATOR LEVELS TO SWELL, AND PERMISSIVE P-14 (STEAM GENERATOR | | HIGH-HIGH LEVEL) WAS RECEIVED ON THE 'B' STEAM GENERATOR. SENSED TURBINE | | POWER INCREASED ABOVE 10% TURBINE LOAD WHICH REMOVED THE 'LOW POWER TRIPS | | BLOCKED P-7.' | | | | THE P-14 SIGNAL GENERATED A TURBINE TRIP WHICH IN TURN GENERATED A REACTOR | | TRIP SIGNAL. FEEDWATER ISOLATION, WHICH WAS ALSO INITIATED BY P-14, CLOSED | | ALL FEEDWATER ISOLATION VALVES AND PROVIDED A TRIP SIGNAL TO THE 'B' MAIN | | FEEDWATER PUMP. THE TRIP OF THE MAIN FEEDWATER PUMP (TRIP OF THE LAST | | RUNNING FEEDWATER PUMP) GENERATED AN AUXILIARY FEEDWATER START SIGNAL TO | | BOTH MOTOR-DRIVEN AUXILIARY FEEDWATER PUMPS. ALL RODS INSERTED ON THE | | REACTOR TRIP, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE PLANT WAS | | STABILIZED USING THE EMERGENCY OPERATING PROCEDURES. THE LICENSEE IS | | CURRENTLY UTILIZING NORMAL CHARGING FOR PRIMARY INVENTORY CONTROL, THE | | REACTOR COOLANT PUMPS FOR PRIMARY TRANSPORT CONTROL, MAIN FEEDWATER FOR | | STEAM GENERATOR INVENTORY CONTROL, AND THE CONDENSER FOR HEAT SINK CONTROL. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+