U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/16/95 - 11/17/95 ** EVENT NUMBERS ** 29601 29604 29605 29606 29607 29608 29609 29610 29611 +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29601 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PERMAGRAIN PRODUCTS |NOTIFICATION DATE: 11/15/95 | | CITY: KARTHUS REGION: 1 |NOTIFICATION TIME: 10:26 [ET]| | COUNTY: CLEARFIELD STATE: PA |EVENT DATE: 11/15/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/16/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHANSEN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LARRY GREIST | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF OFFSITE POWER TO FACILITY DUE TO HEAVY SNOWFALL THROUGHOUT CENTRAL | | PENNSYLVANIA. | | | | MR. GRIEST FROM PERMAGRAIN PRODUCTS, AN IRRADIATOR FACILITY, CALLED TO | | REPORT THAT THE FACILITY HAS LOST OFFSITE POWER DUE TO THE HEAVY SNOWFALL | | BEING EXPERIENCED IN THE AREA. AN EMERGENCY GENERATOR IS OPERATING AT THE | | FACILITY, AND IS SUPPLYING POWER TO NECESSARY RADIATION MONITORS AND | | EQUIPMENT. THE FACILITY HAS A SUBMERGED POOL IRRADIATOR, AND SOME | | CONTAMINATED MATERIAL LOCATED IN HOT CELLS. | | | | * * * UPDATE 0756 11/16/95 * * * | | | | OFFSITE POWER WAS RESTORED AT 0330 THIS MORNING. NOTIFIED R1DO(JOHANSEN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29604 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 04:59 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 03:15[EST]| |NRC NOTIFIED BY: MICHAEL BOURASSA |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURGESS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 22 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM DUE TO HIGH STARTUP RATE DURING UNIT STARTUP | | | | WHILE PREPARING TO SYNCHRONIZE THE MAIN GENERATOR TO THE GRID, THE UNIT | | SCRAMMED DUE TO HIGH RATE (50 MWt/MIN) WHEN THE FEEDWATER REGULATING VALVE | | SUDDENLY OPENED ADDING COLD WATER TO THE REACTOR VESSEL. THE LICENSEE | | VERIFIED THAT ALL CONTROL RODS INSERTED INTO THE CORE, EXCEPT CONTROL ROD | | D-3 WHICH HAS LOST POSITION INDICATION, ALTHOUGH THE LICENSEE BELIEVES IT | | TO BE FULLY INSERTED AS WELL. | | | | THE LICENSEE WAS RESTARTING THE UNIT FOLLOWING A THREE-DAY OUTAGE. IN | | PREPARATION FOR BRINGING THE MAIN GENERATOR ON LINE, OPERATORS WERE | | BYPASSING APPROXIMATELY 160,000 LBM/HR OF STEAM TO THE MAIN CONDENSER. | | OPERATORS HAD ALSO JUST PLACED THE FEEDWATER REGULATING VALVE IN AUTOMATIC | | CONTROL. STEAM DRUM LEVEL, WHICH HAD BEEN STEADY AT +1" ABOVE CENTER LINE, | | SLOWLY DROPPED TO -2", BUT THE FEEDWATER REGULATING VALVE DID NOT RESPOND. | | WHEN LEVEL DROPPED TO -3", THE VALVE SUDDENLY OPENED WIDE ADDING COLD WATER | | TO THE STEAM DRUM AND INCREASING REACTIVITY. THE UNIT AUTOMATICALLY | | SCRAMMED ON HIGH RATE IN RESPONSE TO THE RESULTING POWER INCREASE. | | | | THE LICENSEE IS EXPECTING TO RESTART THE UNIT LATER TODAY. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29605 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 08:41 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 05:21[EST]| |NRC NOTIFIED BY: JOHN DEDOMINICO |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION DURING VITAL BUS UNDER VOLTAGE (UV) RELAY TESTING | | | | DURING SCHEDULED TESTING OF THE UV RELAYS ON THE "A" 4KV VITAL BUS, A | | TECHNICIAN ERROR CAUSED A DEAD BUS TRANSFER. THE TECHNICIAN ACCIDENTALLY | | MADE CONTACT WITH THE WRONG CONNECTION ON THE UV RELAY. THIS CAUSED THE | | BUS TO SWITCH FROM ITS NORMAL POWER SUPPLY TO ITS ALTERNATE SUPPLY. THIS | | WAS THE EXPECTED RESPONSE BASED ON THE ERROR THAT OCCURRED. | | | | BECAUSE POWER WAS MOMENTARILY LOST TO THE BUS, THE LOSS OF POWER (LOP) | | SEQUENCER INITIATED AS PER DESIGN. SOME OF THE LAMP CONDITIONS OBSERVED ON | | THE LOP SEQUENCER WERE QUESTIONED BY OPERATORS AND ARE BEING INVESTIGATED. | | THEY SPECIFICALLY QUESTIONED WHETHER SOME OF THE LIGHTS SHOULD HAVE BEEN | | DIMLY OR BRIGHTLY LIT. | | | | THE "B" RHR PUMP WAS OPERATING IN THE SHUTDOWN COOLING MODE DURING THIS | | EVENT AND WAS UNAFFECTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE LOWER ALLOWAYS | | CREEK TOWNSHIP WAS ALSO NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29606 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:02 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 09:47[EST]| |NRC NOTIFIED BY: J. STANFORD |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHANSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH CHARGING PUMPS INOPERABLE SIMULTANEOUSLY | | | | ON 11/7/95, A MINOR LEAK (4 DROPS PER MINUTE) WAS DISCOVERED ON ONE OF THE | | TWO CHARGING PUMP DISCHARGE LINES. DUE TO THE SMALL SIZE OF THE LEAK, THE | | LICENSEE DETERMINED THAT PUMP OPERABILITY WAS MAINTAINED. THE FOLLOWING | | MORNING, AN ENGINEERING STRESS REVIEW WAS CONDUCTED. WHILE THIS REVIEW WAS | | BEING CONDUCTED, THE EMERGENCY DIESEL GENERATOR FOR THE OPPOSITE TRAIN WAS | | PHASED TO THE GRID FOR A MONTHLY RUN, WHICH LASTED 2-1/2 HOURS. LATER THAT | | SAME DAY, THE STRESS REVIEW WAS COMPLETED, AND THE LICENSEE DETERMINED THAT | | THE LEAKING CHARGING PUMP WAS ACTUALLY INOPERABLE. BECAUSE THE EDG FOR THE | | SECOND PUMP HAD BEEN SYNCHRONIZED TO THE GRID, THE SECOND PUMP WAS ALSO | | CONSIDERED INOPERABLE FOR THE DURATION OF THE 2-1/2 HOUR EMERGENCY DIESEL | | GENERATOR RUN. SIMULTANEOUS INOPERABILITY OF BOTH CHARGING PUMPS PLACED | | THE UNIT IN TECHNICAL SPECIFICATION 3.0.3. | | | | THE LICENSEE STATED THAT THIS EVENT WAS NOT DETERMINED TO BE REPORTABLE | | UNTIL TODAY. THE LEAK HAS SINCE BEEN REPAIRED. THE NRC RESIDENT INSPECTOR | | WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29607 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 11:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 09:25[CST]| |NRC NOTIFIED BY: ROGERS |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SKINNER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE OF ALABAMA REGARDING IMPROPER DISPOSAL OF ASBESTOS | | FLOOR TILES. | | | | THE LICENSEE NOTIFIED THE STATE OF ALABAMA THAT DURING RENOVATIONS TO A | | SITE FACILITY EARLIER THIS MONTH, ASBESTOS FLOOR TILES HAD BEEN REMOVED AND | | DISPOSED OF WITHOUT PROPER ASBESTOS REMOVAL PERMITS. THESE TILES WERE | | DISPOSED OF IN A LOCAL SANITARY LANDFILL. AT THE TIME OF REMOVAL, THE | | LICENSEE HAD NOT VERIFIED THE PRESENCE OF ASBESTOS IN THE TILES. NO | | FURTHER ACTIONS ARE PLANNED. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29608 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 13:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 13:15[EST]| |NRC NOTIFIED BY: SERWAN |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO ENSURE THE INTEGRITY OF THE TURBINE-DRIVEN AUXILIARY PUMP | | ENCLOSURES BECAUSE A HIGH ENERGY LINE BREAK RELIEF DAMPER WOULD NOT FULLY | | OPEN AS ASSUMED IN THE DESIGN CALCULATIONS | | | | DURING A SYSTEM WALK THROUGH ON NOVEMBER 6, 1995, THE VENTILATION SYSTEMS' | | SYSTEM MANAGER DETERMINED THAT A HIGH ENERGY LINE BREAK RELIEF DAMPER | | (NUMBER ABS6) IN THE UNIT 1 TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP | | ENCLOSURE WOULD NOT OPEN FULLY. THE DESIGN CALCULATIONS FOR THIS ENCLOSURE | | ASSUMED THAT THIS NORMALLY CLOSED DAMPER WOULD OPEN TO 100% TO LIMIT THE | | INTERNAL PRESSURE OF THE ENCLOSURE DURING A HIGH ENERGY LINE BREAK | | SCENARIO. BECAUSE THE DAMPER WOULD NOT OPEN FULLY, THE LICENSEE CANNOT | | ENSURE THE INTEGRITY OF THE ENCLOSURE. UNIT 2 HAS A SIMILAR CONFIGURATION, | | AND THE LICENSEE HAS ASSUMED THAT A SIMILAR CONDITION MAY APPLY FOR THE | | SAME DAMPER ON UNIT 2. AS A RESULT, BOTH DAMPERS ARE CURRENTLY CONSIDERED | | TO BE INOPERABLE. THERE HAS NOT BEEN A NEED FOR THESE DAMPERS TO FULLY | | OPEN. ALTHOUGH THERE ARE NO APPLICABLE TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION IN THE CURRENT MODES OF OPERATION, THIS CONDITION | | WOULD HAVE SERIOUSLY DEGRADED THE CAPABILITIES OF THE AUXILIARY FEEDWATER | | SYSTEM. THE LICENSEE DOES NOT PLAN ON PLACING EITHER UNIT IN MODE 4 UNTIL | | THIS ISSUE HAS BEEN CORRECTED. | | | | ALTHOUGH THIS CONDITION WAS IDENTIFIED ON NOVEMBER 6, 1995, IT WAS NOT | | ADDRESSED UNTIL THIS MORNING DUE TO AN ADMINISTRATIVE PROBLEM. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE LOWER ALLOWAYS | | CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 19:24 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 14:50[EST]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | QUESTIONABLE SEISMIC ADEQUACY OF A PREVIOUSLY REPAIRED WELDING FLAW IN A | | 3/4-INCH LOW PRESSURE SAFETY INJECTION SYSTEM PIPE | | | | AT 14:50 ON NOVEMBER 16, 1995, AN ENGINEERING EVALUATION CONCLUDED THAT THE | | SEISMIC ADEQUACY OF A PREVIOUSLY REPAIRED WELDING FLAW IN A 3/4-INCH PIPE | | (WHICH GOES FROM THE MAIN HEADER OF THE LOW PRESSURE SAFETY INJECTION | | SYSTEM TO A SAFETY RELIEF VALVE) COULD NOT BE ASSURED. IF THE PIPE WERE TO | | BREAK WHILE ON SUSTAINED LOW PRESSURE SAFETY INJECTION, A CONTINUOUS | | SPILLAGE OF 130 GALLONS PER MINUTE IN EXCESS OF THE SPILLAGE ASSUMED IN THE | | SAFETY ANALYSIS WOULD OCCUR. | | | | THE FLAW WAS ORIGINALLY DISCOVERED AT 12:00 ON NOVEMBER 7, 1995, AND AT THE | | TIME OF ITS ORIGINAL DISCOVERY, THE DEFECT WAS BELIEVED TO BE LESS THAN 10% | | OF THE CIRCUMFERENCE OF THE PIPE. THE LICENSEE REPAIRED THIS FLAW ON | | NOVEMBER 10, 1995. ON NOVEMBER 16, 1995, THE LICENSEE'S ENGINEERING | | EVALUATION DETERMINED THE EXTENT OF THE FLAW TO BE APPROXIMATELY 33% AND | | THE FAILURE MODE TO BE FATIGUE. THE SIZE OF THE FLAW CALLED INTO QUESTION | | THE ADEQUACY OF THE REPAIR TO WITHSTAND A SEISMIC EVENT. THE LICENSEE | | CURRENTLY PLANS TO MAKE A BIGGER WELD IN THE AREA OF THE FLAW. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/16/95 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 21:09 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 17:41[EST]| |NRC NOTIFIED BY: KELLY KORTH |LAST UPDATE DATE: 11/16/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DECREASING STEAM GENERATOR LEVEL AND SUBSEQUENT MANUAL REACTOR TRIP DUE TO | | PARTIAL CLOSURE OF A FEEDWATER REGULATING VALVE | | | | DURING STEADY STATE OPERATION, THE CONTROLLER FOR THE '1B' MAIN FEEDWATER | | REGULATING VALVE FAILED CAUSING THE VALVE TO PARTIALLY CLOSE (TO ABOUT THE | | 50% POSITION). THIS IN TURN CAUSED LEVEL IN THE '1B' STEAM GENERATOR TO | | DECREASE. IN RESPONSE TO THE LOWERING LEVEL IN THE '1B' STEAM GENERATOR, | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR WHEN WATER LEVEL IN THE | | '1B' STEAM GENERATOR HAD DECREASED TO 40% (NARROW RANGE). ALL RODS FULLY | | INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED WITH ONE EXCEPTION. THE | | '1B' MAIN FEEDWATER REGULATING VALVE DID NOT FULLY CLOSE AS DESIGNED | | FOLLOWING THE TRIP BECAUSE IT HAD FAILED IN THE 50% POSITION. THIS CAUSED | | AN INCREASE IN THE WATER LEVEL IN THE '1B' STEAM GENERATOR FOLLOWING THE | | REACTOR TRIP AND SUBSEQUENT STEAM GENERATOR LEVEL SHRINKAGE. AS A RESULT, | | OPERATORS MANUALLY STOPPED THE MAIN FEEDWATER PUMPS, AND AUXILIARY | | FEEDWATER ACTUATED AS EXPECTED ON LOW LEVEL IN THE '1A' STEAM GENERATOR. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. THE '1A' MAIN FEEDWATER PUMP HAS | | BEEN RESTORED, AND AUXILIARY FEEDWATER HAS BEEN SECURED. THE STEAM BYPASS | | CONTROL SYSTEM IS BEING UTILIZED TO REMOVE DECAY HEAT. THE LICENSEE IS | | ALSO UTILIZING PRESSURIZER HEATERS AND SPRAYS, NORMAL CHARGING AND MAKEUP, | | AND THE REACTOR COOLANT PUMPS FOR PRIMARY PRESSURE, INVENTORY, AND | | TRANSPORT CONTROL. | | | | THE SECONDARY RELIEF VALVES LIFTED AND IMMEDIATELY RESET FOLLOWING THE | | MANUAL REACTOR TRIP. THIS WAS EXPECTED FOR THIS TYPE OF TRANSIENT AT THIS | | PLANT. THERE HAS BEEN NO PRIMARY TO SECONDARY LEAKAGE. | | | | THE LICENSEE IS CURRENTLY PERFORMING A ROOT CAUSE INVESTIGATION ON THE | | CONTROLLER FAILURE, AND THE PRELIMINARY INVESTIGATION HAS REVEALED THAT A | | VOLTAGE TRANSIENT MAY HAVE CONTRIBUTED TO THE CONTROLLER FAILURE. | | APPARENTLY, AT THE TIME OF THE TRANSIENT, THE LICENSEE WAS PERFORMING A | | FIRE PUMP SURVEILLANCE WHICH INVOLVED BOTH FIRE PUMPS STARTING AT THE SAME | | TIME. WHEN THIS OCCURRED, VARIOUS ANNUNCIATORS WERE RECEIVED IN THE | | CONTROL ROOM (WHICH HAVE BEEN EXPERIENCED IN THE PAST) DUE TO THE VOLTAGE | | PERTURBATION. CONTROL ROOM OPERATORS WERE ACKNOWLEDGING THESE ALARMS WHEN | | THE LOW STEAM GENERATOR ALARM CAME IN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 11/17/95 | |UNIT: [1] [ ] [ ] STATE: MD |NOTIFICATION TIME: 00:02 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 22:52[EST]| |NRC NOTIFIED BY: FRY |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHANSEN 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO FAILURE OF MAIN FEEDWATER PUMP. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE UNIT AFTER RECEIVING INDICATION | | OF THE LOSS OF THE #12 STEAM GENERATOR FEED PUMP AND DECREASING STEAM | | GENERATOR WATER LEVELS. THE TRIP WAS UNCOMPLICATED, AND ALL CONTROL RODS | | INSERTED PROPERLY. THE LICENSEE REPORTED THAT THE AUXILIARY FEEDWATER | | SYSTEM AUTOMATICALLY STARTED DUE TO LOW STEAM GENERATOR LEVELS. ALL | | SYSTEMS FUNCTIONED AS DESIGNED. | | | | THE LICENSEE STATED THAT THE FEEDWATER PUMP TRIP APPEARS TO HAVE BEEN | | CAUSED BY A PROBLEM WITH THE CONTROL OIL SYSTEM. THE NRC RESIDENT HAS BEEN | | INFORMED BY THE LICENSEE. | | | | | | | +------------------------------------------------------------------------------+