U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/14/96 - 02/15/96 ** EVENT NUMBERS ** 29894 29974 29975 29976 29977 29978 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29894 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/26/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:21 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/25/96 | +------------------------------------------------+EVENT TIME: 21:40[EST]| |NRC NOTIFIED BY: PIKE |LAST UPDATE DATE: 02/14/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATORS (EDG) DECLARED INOPERABLE DUE TO A POSSIBLE | | PROBLEM WITH THE EXHAUST HEADER INSULATION. | | | | ON 01/24/96, A SECTION OF INSULATION FELL OFF THE EXHAUST HEADER OF THE "A" | | EDG. AT THIS TIME, THE "A" AND "C" EDGs WERE INOPERABLE DUE TO SCHEDULED | | MAINTENANCE ACTIVITIES. ENGINEERING HAS DETERMINED THAT THE INSULATION WAS | | NOT INSTALLED IN ACCORDANCE WITH DESIGN SPECIFICATIONS. AT THIS TIME, | | THERE IS A CONCERN THAT THE INSULATION FOR THE OTHER THREE EDGs WAS ALSO | | INSTALLED INCORRECTLY. | | | | A TEMPERATURE SENSOR LOCATED SIX FEET ABOVE THE EXPOSED PORTION OF THE "A" | | EDG EXHAUST HEADER ACTUATES THE CARBON DIOXIDE FIRE SUPPRESSION SYSTEM. THE | | OTHER THREE EDGs HAVE A SIMILAR CONFIGURATION, AND WITH THE INSULATION | | REMOVED, THE HEAT FROM THE EXPOSED PORTION OF THE EXHAUST HEADER DURING EDG | | OPERATION HAS THE POTENTIAL TO CAUSE THE TEMPERATURE SENSOR TO ACTUATE THE | | CARBON DIOXIDE FIRE SUPPRESSION SYSTEM. WHEN THE FIRE SUPPRESSION SYSTEM | | ACTUATES, THE VENTILATION DAMPERS SUPPLYING THE EDG ROOMS ISOLATE | | PREVENTING AIR FLOW AND COOLING TO THE EDGs. THIS WOULD LEAD TO | | OVERHEATING AND SUBSEQUENT FAILURE OF THE EDGs. THEREFORE, THE "B" AND "D" | | EDGs WERE DECLARED INOPERABLE AT 21:40 ON 01/25/96, AND THE PLANT ENTERED | | AN LCO ACTION STATEMENT. | | | | IF THE INSULATION FOR THE OTHER THREE EDGs IS INSTALLED INCORRECTLY, A | | SEISMIC EVENT MAY RESULT IN A SIMILAR SECTION OF INSULATION FALLING OFF AND | | SUBSEQUENTLY RENDERING THEM INOPERABLE IF NEEDED FOR A LOP/LOCA SITUATION. | | AT 10:00 ON 01/26/96, THE LICENSEE DETERMINED THAT ALTHOUGH A 10 CFR 50.72 | | NOTIFICATION WAS REQUIRED, IT HAD NOT YET BEEN MADE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH LOWER ALLOWAYS CREEK | | TOWNSHIP. | | | | * * * UPDATE AT 1635 ON 02/14/96, FROM PRIEST TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. ENGINEERING ANALYSIS HAS | | DETERMINED THAT OPERATION OF THE EDG WITHOUT THE EXHAUST INSULATION WOULD | | NOT CAUSE THE FIRE SUPPRESSION SYSTEM TO ACTUATE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (BELLAMY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29974 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 02/14/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 00:09 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/13/96 | +------------------------------------------------+EVENT TIME: 22:28[EST]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 02/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 90 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP ON HIGH STEAM GENERATOR LEVEL DUE TO FAILURE OF A | | MAIN FEEDWATER REGULATING VALVE | | | | AT 22:28 ON FEBRUARY 13, 1996, THE NUMBER 3 MAIN FEEDWATER REGULATING VALVE | | FAILED OPEN WITH THE CONTROL SYSTEM IN AUTOMATIC. STEAM GENERATOR WATER | | LEVEL INCREASED TO APPROXIMATELY 88% (NARROW RANGE), AND THE UNIT | | AUTOMATICALLY TRIPPED ON HIGH FEEDWATER LEVEL. ALL RODS FULLY INSERTED, | | AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE MAIN FEEDWATER PUMPS | | AUTOMATICALLY TRIPPED, AND EMERGENCY FEEDWATER AUTOMATICALLY INITIATED AS | | DESIGNED. FOLLOWING THE REACTOR PROTECTION SYSTEM ACTUATION, STEAM | | GENERATOR LEVEL DECREASED TO 20% AND WAS SUBSEQUENTLY RECOVERED TO NORMAL | | LEVEL (APPROXIMATELY 60%). THE MAIN STEAM SUPPLY VALVES REMAINED OPEN | | DURING THIS TRANSIENT. | | | | THE UNIT IS CURRENTLY STABLE IN HOT STANDBY, AND THE LICENSEE PLANS TO | | PLACE THE UNIT IN HOT SHUTDOWN. OPERATORS ARE UTILIZING NORMAL CHARGING | | AND MAKEUP, PRESSURIZER HEATERS AND SPRAYS, AND REACTOR COOLANT PUMPS FOR | | PRIMARY INVENTORY, PRESSURE, AND TRANSPORT CONTROL. EMERGENCY FEEDWATER IS | | BEING SUPPLIED TO THE STEAM GENERATORS, AND SECONDARY STEAM IS BEING DUMPED | | TO THE CONDENSER. THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE | | FEEDWATER REGULATING VALVE FAILURE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE AND MAY | | ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29975 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 02/14/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/14/96 | +------------------------------------------------+EVENT TIME: 10:15[EST]| |NRC NOTIFIED BY: JAMES KRITZER |LAST UPDATE DATE: 02/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | INOPERABILITY OF CONTAINMENT COOLING, RESIDUAL HEAT REMOVAL SERVICE WATER, | | AND ALTERNATE COOLING AS A RESULT OF LOOSE RESIDUAL HEAT REMOVAL HEAT | | EXCHANGER OUTLET VALVE OPERATORS | | | | BECAUSE THE OPERATORS ON THE RESIDUAL HEAT REMOVAL HEAT EXCHANGER OUTLET | | VALVES WERE DISCOVERED TO BE LOOSE, THE LICENSEE CANNOT GUARANTEE THAT | | THESE VALVES WOULD REMAIN OPEN IF THE VALVE OPERATORS (THE BOLTS HOLDING | | THE VALVE OPERATORS ON) WERE TO FAIL OR FALL OFF. AS A RESULT, THE | | LICENSEE DECLARED CONTAINMENT COOLING, RESIDUAL HEAT REMOVAL SERVICE WATER, | | AND ALTERNATE COOLING INOPERABLE AT 1015 ON FEBRUARY 14, 1996, AND | | TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION (24-HOUR, | | 24-HOUR, AND 7-DAY, RESPECTIVELY) WERE ENTERED. A UNIT SHUTDOWN HAD NOT | | BEEN COMMENCED AT THE TIME OF THIS EVENT NOTIFICATION. | | | | THE ROOT CAUSE OF THE LOOSE VALVE OPERATORS IS CURRENTLY UNDER | | INVESTIGATION. THE LICENSEE PLANS TO PERFORM REPAIRS ON ONE LOOP AT A TIME | | AND ANTICIPATES THAT THE REPAIRS WILL BE COMPLETED PRIOR TO THE END OF THE | | MOST LIMITING TECHNICAL SPECIFICATION ACTION STATEMENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY THE | | STATE OF VERMONT. | | | | * * * UPDATE AT 1514 ON 02/14/96, FROM KRITZER TAKEN BY STRANSKY * * * | | | | THE UNIT EXITED THE LIMITING CONDITIONS FOR OPERATION AT 1500, AND NO POWER | | REDUCTION OCCURRED. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. THE NRC | | OPERATIONS CENTER NOTIFIED THE R1DO (BELLAMY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29976 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 02/14/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 18:21 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 02/14/96 | +------------------------------------------------+EVENT TIME: 14:40[CST]| |NRC NOTIFIED BY: HARRINGTON |LAST UPDATE DATE: 02/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RING 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROCEDURE FOR CALIBRATION OF MAIN STEAM LINE HIGH STEAM FLOW SETPOINT COULD | | CAUSE SETPOINT TO BE NONCONSERVATIVELY HIGH. | | | | THE LICENSEE DETERMINED THAT THE PROCEDURES USED TO CALIBRATE THE MAIN | | STEAM LINE HIGH STEAM FLOW SETPOINT COULD RESULT IN THE SETPOINT BEING SET | | APPROXIMATELY 0.4% HIGHER THAN THE TECHNICAL SPECIFICATION LIMIT. THE | | LICENSEE STATED THAT, AS OF 02/96, THE SETPOINT IS SET WITHIN THE TECHNICAL | | SPECIFICATION LIMIT BUT THAT IT COULD HAVE BEEN SET INCORRECTLY IN THE | | PAST. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29977 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 02/14/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/14/96 | +------------------------------------------------+EVENT TIME: 08:30[CST]| |NRC NOTIFIED BY: CLAUSER |LAST UPDATE DATE: 02/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAIN RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 89 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT REQUIRED BY OPERATING LICENSE DUE TO EXCEEDING 100% POWER | | | | WITH THE UNIT OPERATING AT 95% POWER, A FEEDWATER HEATER BYPASS VALVE | | OPENED CAUSING A PARTIAL LOSS OF FEEDWATER HEATING. TURBINE LOAD REMAINED | | UNCHANGED, AND REACTOR POWER INCREASED IN RESPONSE TO DECREASING REACTOR | | COOLANT SYSTEM TEMPERATURE. REACTOR POWER REACHED A PEAK OF 102.5% FOR | | SEVERAL SECONDS BEFORE BEING REDUCED BY AN AUTOMATIC TURBINE RUNBACK DUE TO | | OVERPOWER DIFFERENTIAL TEMPERATURE (OPdT). REACTOR POWER WAS STABILIZED AT | | 89% OF RATED. | | | | THE CAUSE OF THE BYPASS VALVE OPENING IS CURRENTLY UNDER INVESTIGATION, BUT | | THE LICENSEE BELIEVES THAT IT MAY HAVE BEEN CAUSED BY UNRELATED CALIBRATION | | ACTIVITIES. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29978 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 02/14/96 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 20:21 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 02/14/96 | +------------------------------------------------+EVENT TIME: 19:55[EST]| |NRC NOTIFIED BY: FRITZ |LAST UPDATE DATE: 02/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELLAMY 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 Y 87 POWER OPERATION | 87 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL EMERGENCY SIRENS SPURIOUSLY ACTIVATED FOR APPROXIMATELY 5 MINUTES. | | | | THE LICENSEE REPORTED THAT ALL EMERGENCY PLANNING ZONE SIRENS SPURIOUSLY | | SOUNDED DUE TO A STATIC DISCHARGE AT THE ROCKINGHAM COUNTY POLICE DISPATCH | | CENTER. ALL SIRENS HAVE BEEN SHUT DOWN, AND AN INVESTIGATION IS UNDERWAY | | AS TO THE EXACT CAUSE OF THE ACTIVATION. THE LICENSEE REPORTED THAT ALL | | SIRENS APPEAR TO BE OPERABLE AT THIS TIME. | | | | THE ROCKINGHAM COUNTY POLICE DISPATCH CENTER IS MAKING NOTIFICATIONS TO | | ALERT CITIZENS THAT THE SIRENS ACTIVATION WAS INADVERTENT. STATE POLICE | | OFFICES IN NEW HAMPSHIRE AND MASSACHUSETTS HAVE BEEN NOTIFIED BY THE | | LICENSEE. A PRESS RELEASE IS PLANNED. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+