U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/02/95 - 05/03/95 ** EVENT NUMBERS ** 28749 28750 28751 28752 28753 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28749 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 05/02/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 14:53 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/02/95 | +------------------------------------------------+EVENT TIME: 13:30[EDT]| |NRC NOTIFIED BY: MCDOUGAL |LAST UPDATE DATE: 05/02/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | AN ENGINEERING EVALUATION DETERMINED THAT RECIRCULATION ACTUATION SIGNAL | | (RAS) SUCTION VALVES MAY BE BOUND DURING A LOCA PREVENTING THE WATER SOURCE | | SWAPOVER PRIOR TO RECIRCULATION PHASE OF COOLANT INJECTION. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "ENGINEERING HAS EVALUATED A POTENTIAL HYDRAULIC BINDING PROBLEM ON TWO | | MOTOR OPERATED VALVES (HSI-M-54 & HSI-M-55). DURING A LOCA THE AMBIENT | | TEMPERATURE IN THE CONTAINMENT SPRAY BUILDING HAS BEEN CALCULATED TO HEAT | | UP APPROXIMATELY 30 DEGREES FAHRENHEIT. THE RAS SUCTION VALVES ARE | | DESIGNED SUCH THAT WATER WILL PROBABLY BE PRESENT BETWEEN THE BONNET AND | | THE DISC. AN INCREASE OF ONLY 3 DEGREES IN THE WATER TEMPERATURE IS | | NECESSARY TO INCREASE THE PRESSURE, IN THIS VALVE AREA BELOW THE BONNET, | | SUCH THAT THE MOTOR OPERATOR WILL NOT BE CAPABLE OF OPENING THE VALVE WHEN | | A RAS IS ACTUATED. | | | | THE PLANT IS PRESENTLY SHUTDOWN WITH THE REACTOR DEFUELED. THE VALVES ARE | | CONSIDERED OPERABLE DURING REFUELING SHUTDOWN CONDITIONS BUT MUST BE | | CORRECTED PRIOR TO PLANT STARTUP, BASED ON THE ENGINEERING EVALUATION. | | | | THIS EVENT IS REPORTABLE PER 10CFR50.72(b)(2)(i). THE RESIDENT NRC | | INSPECTOR WILL BE INFORMED OF THIS NOTIFICATION." END OF TEXT. | | | | THE RAS SWITCHES THE WATER SOURCE DURING A LOCA FROM THE REFUELING WATER | | STORAGE TANK TO THE CONTAINMENT SUMP AT THE INITIATION OF RECIRCULATION | | PHASE OF THE LOCA. A CORRECTIVE ACTION HAS NOT BEEN DETERMINED AT THIS | | TIME, HOWEVER, ANY SUCH CORRECTIVE ACTION WILL BE IMPLEMENTED PRIOR TO | | RESTART. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28750 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/02/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:20 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/02/95 | +------------------------------------------------+EVENT TIME: 16:10[EDT]| |NRC NOTIFIED BY: WOOKEY |LAST UPDATE DATE: 05/02/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 2 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A GROUP ONE ISOLATION (MAIN STEAM ISOLATION VALVES - MSIVs) OCCURRED ON | | HIGH-STEAM FLOW DUE TO THE ACTUATION OF THE STEAM BYPASS VALVE SYSTEM. | | | | AFTER RESETTING THE TURBINE VACUUM TRIP, A GROUP ONE (MSIVs) OCCURRED. NO | | REACTOR PROTECTION SYSTEM (RPS) ACTUATION SIGNAL WAS ISSUED DUE TO THE | | POWER LEVEL OF THE UNIT AT THE TIME OF THE ISOLATION. THE HIGHEST PRESSURE | | IN THE REACTOR COOLANT SYSTEM WAS 1012 PSIG, WELL BELOW THE SCRAM SETPOINT | | OF 1055 PSIG AND THE RELIEF VALVE SETPOINT OF 1080 PSIG. NO OTHER | | ENGINEERED SAFETY FEATURES OR RPS ACTUATION SIGNALS OCCURRED. | | | | THE CAUSE OF THE MSIV CLOSURE IS BELIEVED TO BE THE FOLLOWING: AFTER THE | | TURBINE VACUUM TRIP WAS RESET, THE BYPASS VALVE SYSTEM WAS RE-ENABLED. WITH | | THE MANUAL PRESSURE REGULATOR SET AT 940 PSIG AND REACTOR PRESSURE AT 970 | | PSIG, ALL NINE BYPASS VALVES OPENED AND A HIGH STEAM FLOW CONDITION | | OCCURRED. THIS RESULTED IN STEAM FLOW GREATER THAN 40%, THE HIGH-STEAM | | FLOW MSIV CLOSURE SETPOINT BELOW 15% REACTOR POWER. THE LICENSEE ASSERTS | | THAT A RESET OF THE TURBINE VACUUM TRIP IS NOT A USUAL EVOLUTION DURING | | STARTUP. THE MANUAL PRESSURE REGULATOR SETTING IS ALSO BEING INVESTIGATED. | | | | THE VERMONT DEPARTMENT OF PUBLIC SERVICE WAS NOTIFIED BY THE LICENSEE. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28751 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/02/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:49 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/02/95 | +------------------------------------------------+EVENT TIME: 17:22[EDT]| |NRC NOTIFIED BY: WOOKEY |LAST UPDATE DATE: 05/02/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 2 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED INOPERABLE | | WHEN THE OUTBOARD STEAM SUPPLY ISOLATION VALVE FAILED TO OPERATE AS | | EXPECTED. | | | | THE RCIC SYSTEM WAS DECLARED INOPERABLE WHEN POSITION INDICATION AT THE | | ALTERNATE SHUTDOWN CONTROL PANEL OF THE RCIC OUTBOARD STEAM SUPPLY | | ISOLATION VALVE WAS LOST DURING A SURVEILLANCE TEST OF THE ISOLATION | | SYSTEM. TECHNICAL SPECIFICATION ACTION STATEMENT 3.7.2 WAS ENTERED AND | | FULFILLED WHEN THE INBOARD ISOLATION VALVE WAS CLOSED. THE CAUSE OF THE | | INDICATION FAILURE IS BELIEVED TO BE LOW THERMAL OVERLOAD SETTINGS IN THE | | VALVE OPERATOR CIRCUITRY. REPAIRS OF THE CIRCUITRY ARE UNDERWAY. | | | | CURRENTLY, THE RCIC SYSTEM REMAINS INOPERABLE AND TECHNICIANS CONTINUE TO | | ADJUST THE THERMAL LOAD SETTING OF THE OPERATOR CIRCUITRY. THE LICENSEE | | NOTIFIED THE VERMONT STATE DEPARTMENT OF PUBLIC SERVICE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28752 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/03/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/03/95 | +------------------------------------------------+EVENT TIME: 00:15[EDT]| |NRC NOTIFIED BY: MCKENNEY |LAST UPDATE DATE: 05/03/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 10 STARTUP | 10 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ENTERED A 7 DAY LCO ACTION STATEMENT WHEN THEY DECLARED HPCI | | INOPERABLE. | | | | HPCI WAS DECLARED INOPERABLE WHEN THEY TOOK IT OUT OF SERVICE IN ORDER TO | | PERFORM MAINTENANCE ON THE 14 HPCI STEAM SUPPLY VALVE. HPCI WAS RETURNED TO | | SERVICE AND THEY EXITED THE LCO AT 03:20. THE RI AND STATE WILL BE | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28753 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/03/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:52 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/03/95 | +------------------------------------------------+EVENT TIME: 04:15[EDT]| |NRC NOTIFIED BY: SHELTON |LAST UPDATE DATE: 05/03/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT DISCOVERED THAT THEIR SPDS IS INOPERABLE. | | | | THIS WAS DETERMINED WHEN THEY FOUND THAT SPDS WAS NOT UPDATING PROPERLY | | WITH RESPECT TO PLANT DATA. THE PROCESS COMPUTER IS OPERATING AT THIS TIME | | AND PROVIDING ALARM STATUS. THEY ALSO HAVE OTHER REDUNDANT CONTROL OF | | INSTRUMENTATION AVAILABLE. THE CAUSE OF THE CONDITION IS UNDER | | INVESTIGATION AND THEY HAVE CALLED PERSONNEL IN TO GET THE SYSTEM | | RESTARTED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+