U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/03/96 - 01/04/96 ** EVENT NUMBERS ** 29679 29764 29788 29789 29790 29791 29792 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29679 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 12/06/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 18:41 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/06/95 | +------------------------------------------------+EVENT TIME: 16:41[EST]| |NRC NOTIFIED BY: TOM WALLACE |LAST UPDATE DATE: 01/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID VERRELLI 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP SIGNAL GENERATED WHILE IN MODE 5 | | | | DURING TROUBLESHOOTING ON SOURCE RANGE CHANNEL N-131, ELECTRICAL SHORTING | | OCCURRED IN THE PRE-AMP CABINET. THE TECHNICAL SUPPORT SYSTEM ENGINEER AND | | A LICENSED OPERATOR ASSIGNED TO THE TROUBLESHOOTING ACTIVITY MADE THE | | DECISION TO REMOVE POWER FROM THE SOURCE RANGE INSTRUMENT TO MINIMIZE | | POSSIBLE DAMAGE. REMOVING POWER FROM THE SOURCE RANGE INSTRUMENT CAUSED A | | REACTOR TRIP SIGNAL TO BE GENERATED. THE REACTOR PROTECTION SYSTEM | | RESPONDED AS DESIGNED. | | | | ALTHOUGH PLANT OPERATING CONDITIONS DID NOT EXIST WHICH WOULD HAVE | | GENERATED THE TRIP SIGNAL, THE EVENT IS BEING REPORTED AS A VALID SIGNAL | | BECAUSE THE TRIP LOGIC WAS MADE UP BY THE REMOVAL OF POWER FROM THE | | INSTRUMENT. AN INVESTIGATION IS UNDERWAY TO DETERMINE THE CAUSE OF THE | | ELECTRICAL SHORTING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1525 EST ON 1/3/96 FROM PAUL PACE TAKEN BY KARSCH * * * | | THE LICENSEE HAS DETERMINED THAT THIS EVENT IS NOT REPORTABLE PER THE NRC | | GUIDANCE IN NUREG 1022 REV 1. IN THAT THE TRIP SIGNAL OCCURRED AS A RESULT | | OF PLANNED OPERATOR ACTION TO REMOVE THE SOURCE RANGE INSTRUMENT CHANNEL | | FROM SERVICE. THE ACTUATION WAS, THEREFORE, NOT VALID AS IT OCCURRED AFTER | | THE SYSTEM WAS PROPERLY REMOVED FROM SERVICE AND RESULTED FROM SHUTTING OF | | POWER TO THE INSTRUMENT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | HOO FAXED A COPY OF THE RETRACTION TO R2DO (CHRISTIANSEN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29764 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 12/25/95 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 12:31 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 12/25/95 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: DAVE LEWIS |LAST UPDATE DATE: 01/03/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE INJECTION (HPCI) DECLARED INOPERABLE FOR 5 MINUTES. | | | | HPCI WAS DECLARED INOPERABLE AND LICENSEE ENTERED TECHNICAL SPECIFICATION | | 3.5.C (7 DAY LIMITING CONDITION OF OPERATION) WHEN A WATER/STEAM LEAK WAS | | DISCOVERED ON PIPING FOR THE HPCI STEAMLINE DRAIN POT LEVEL | | INSTRUMENTATION. MOSTLY WATER WAS LEAKING FROM A TEST CONNECTION (PIPE | | CAP). WATER LEAKING FROM THE HPCI STEAM LINE INDICATES THAT THE STEAM LINE | | TO THE HPCI TURBINE IS NOT PROPERLY DRAINED. LICENSEE OPENED AN AIR | | OPERATED BYPASS VALVE (AOV-53) TO DRAIN THE STEAM LINE TO THE MAIN | | CONDENSER. WITH AOV-53 OPEN (INSURES THAT HPCI STEAM LINE IS DRAINED) | | LICENSEE EXITED TECHNICAL SPECIFICATION 3.5.C AT 0905 ET. LICENSEE WILL | | REPAIR THE LEAKING TEST CONNECTION. ALL THEIR EMERGENCY CORE COOLING | | SYSTEMS WERE FULLY OPERABLE DURING THE TIME PERIOD HPCI WAS DECLARED | | INOPERABLE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | * * * UPDATE 0854 1/3/96 FROM FOSS TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. UPON FURTHER INVESTIGATION, | | THE LICENSEE HAS DETERMINED THAT WATER DRAINED FROM THE HPCI STEAM LINE WAS | | DUE TO CONDENSATION, AND THAT THE HPCI STEAM LINE WAS NOT FULL OF WATER. | | THEREFORE, THE HPCI SYSTEM WAS NOT INOPERABLE. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED. NOTIFIED R1DO (COSTELLO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29788 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 01/03/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:04 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 01/03/96 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: STEVE ARENINGHAUS |LAST UPDATE DATE: 01/03/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION | | THAT THEY WILL SHUT THE PLANT DOWN ON FRIDAY. STATE NOTIFICATION IS | | REQUIRED WHEN THE PLANT IS SHUT DOWN WITH THE INLET WATER TEMPERATURE LOWER | | THAN 47.3ø F. REPAIR OF A CONDENSER VALVE WILL REQUIRE REACTOR SHUTDOWN. | | THE LICENSEE MAY ISSUE A PRESS RELEASE, AND WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29789 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 01/03/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 01/03/96 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: DAVID BRAC |LAST UPDATE DATE: 01/03/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT TWO AVERAGE POWER RANGE MONITORING (APRM) | | CHANNELS WERE INOPERABLE SIMULTANEOUSLY. | | | | ON JANUARY 3, 1996 THE LICENSEE DETERMINED THAT TWO APRM CHANNELS WERE OUT | | OF SERVICE SIMULTANEOUSLY FOR APPROXIMATELY 19 HOURS ON SEPTEMBER 16 AND | | 17, 1995. THIS IS A VIOLATION OF THE TWELVE HOUR LIMIT IMPOSED BY SECTION | | 2.E OF THE TECHNICAL SPECIFICATIONS. APRM #2 WAS INOPERABLE FROM AUGUST | | 29, 1995 TO JANUARY 2, 1996, BECAUSE A TRIP BIAS UNIT WAS REPLACED, BUT NOT | | PROPERLY ADJUSTED. THIS RESULTED IN A NON-CONSERVATIVELY HIGH FLOW BIAS | | SCRAM SET POINT. APRM #1 WAS REMOVED FROM SERVICE BETWEEN SEPTEMBER 16 & | | 17, 1995, FOR TROUBLESHOOTING. THE LICENSEE DETERMINED THAT BOTH CHANNELS | | WERE INOPERABLE FOR APPROXIMATELY 19 HOURS. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29790 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 01/03/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 22:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/03/96 | +------------------------------------------------+EVENT TIME: 19:15[EST]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 01/03/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THERMAL OVERLOAD PROTECTORS FOR NUMEROUS SAFETY RELATED MOTOR LOADS ARE TOO | | LOW AND COULD LEAD TO SPURIOUS TRIPPING OF THE LOADS DURING ACCIDENT | | CONDITIONS. | | | | THE LICENSEE DETERMINED THAT THE OVERLOAD PROTECTORS NOW IN USE DO NOT | | CONFORM TO THE INDUSTRY TECHNICAL STANDARD REQUIRING A 10% MARGIN. ASSUMING | | THE WORST CASE POST ACCIDENT CONDITIONS OF DEGRADED VOLTAGE AND AMBIENT | | TEMPERATURE, SPURIOUS EQUIPMENT TRIPS COULD RESULT. THE LICENSEE HAS | | DECLARED THE AFFECTED EQUIPMENT INOPERABLE, AND WILL MAKE THE NECESSARY | | REPAIRS PRIOR TO PLANT RESTART. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR AND WILL INFORM LOWER ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29791 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 01/04/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 01:18 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/04/96 | +------------------------------------------------+EVENT TIME: 00:20[EST]| |NRC NOTIFIED BY: COLEMAN |LAST UPDATE DATE: 01/04/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 95 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAMMED ON HIGH REACTOR PRESSURE DUE TO MAIN TURBINE CONTROL VALVE | | CLOSURE (FOR UNKNOWN REASON). | | | | INITIAL CONDITION: MAIN TURBINE CONTROL VALVES 1, 2, & 3 WERE OPEN AND MAIN | | TURBINE CONTROL VALVE #4 WAS CLOSED FOR END OF CYCLE COASTDOWN. | | | | ABOUT 10 MINUTES BEFORE THE REACTOR SCRAM, THE LICENSEE NOTICED THAT THE | | MAIN TURBINE BYPASS VALVES WERE OPENING. UPON FURTHER INVESTIGATION, THE | | LICENSEE FOUND THAT MAIN TURBINE CONTROL VALVE #2 HAD CLOSED. WHEN MAIN | | TURBINE CONTROL VALVE #2 CLOSED MAIN TURBINE CONTROL VALVE #4 SHOULD HAVE | | OPENED. | | | | REACTOR POWER WAS REDUCED TO APPROXIMATELY 50% SO AS TO STAY WITHIN THE | | CAPACITY OF THE REMAINING TWO OPEN MAIN TURBINE CONTROL VALVES (#1 & #3). | | SHORTLY AFTER REACHING 50% POWER LEVEL MAIN TURBINE CONTROL VALVES #1 & #3 | | BEGAN TO CLOSE. | | | | THE SHIFT SUPERVISOR INSTRUCTED THE REACTOR OPERATOR TO MANUALLY SCRAM THE | | PLANT. BEFORE THE MANUAL REACTOR SCRAM COULD BE PERFORMED THE REACTOR | | SCRAMMED ON HIGH REACTOR PRESSURE (SETPOINT 1042 psig). ALL RODS FULLY | | INSERTED INTO THE CORE. THE HIGHEST REACTOR PRESSURE DURING THIS EVENT WAS | | 1050 psig (NO SRVs OPENED). DURING THE TRANSIENT REACTOR VESSEL WATER | | LEVEL DECREASED FORM ITS NORMAL OPERATING LEVEL OF +37" TO 0". HPCI/RCIC | | DID NOT START BECAUSE REACTOR VESSEL WATER LEVEL DID NOT DECREASE TO -35". | | ALL EMERGENCY CORE COOLING SYSTEMS AND EMERGENCY DIESEL GENERATORS ARE | | OPERABLE IF NEEDED. | | | | THE LICENSEE THINKS THAT THIS EVENT COULD HAVE BEEN CAUSED BY BLOCKAGE IN | | THE EHC OIL SERVO STRAINER. THEY HAVE HAD PROBLEMS IN THE PAST WITH THE | | STRAINER. LICENSEE SAID THAT THEY DID NOT SEE ANY EHC PRESSURE | | FLUCTUATIONS OR ANY INCREASE IN THE AMPERAGE TO THE EHC PUMPS. | | | | THE LICENSEE WILL RESTART THE PLANT AFTER THE PROBLEMS HAVE BEEN FOUND AND | | CORRECTED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ***UPDATE 01/04/96 0410 ET BY COLEMAN TAKEN BY MACKINNON*** | | | | LICENSEE HAD A GROUP 2 ISOLATION (DRYWELL DRAINS, VENTS, ETC.) CAUSED BY | | LOW REACTOR VESSEL WATER LEVEL (+3") FOLLOWING THE REACTOR SCRAM. A GROUP | | 2 ISOLATION IS AN EFS ACTUATION. THE RESIDENT INSPECTOR WAS NOTIFIED. R2DO | | (CHRIS CHRISTENSEN) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29792 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/04/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/04/96 | +------------------------------------------------+EVENT TIME: 04:30[EST]| |NRC NOTIFIED BY: LIJOI |LAST UPDATE DATE: 01/04/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO 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 +------------------------------------------------------------------------------+ | FIRE PROTECTION SYSTEM BEING REMOVED FROM SERVICE. | | | | PER TECHNICAL SPECIFICATION 3.13.a.3, WHEN A FIRE PROTECTION SYSTEM IS | | TAKEN OUT OF SERVICE, THE LICENSEE MUST REPORT WITHIN 24 HOURS THAT IT WAS | | TAKEN OUT OF SERVICE. THE LICENSEE IS TAKING THE FIRE PROTECTION SYSTEM FOR | | THEIR INTAKE STRUCTURE OUT OF SERVICE FOR 8 TO 10 HOURS TO REPAIR A LEAKING | | DRAIN VALVE IN THE SYSTEM. THE LICENSEE HAS FIRE HOSES IN PLACE AND HAS A | | FIRE WATCH PATROLLING THE INTAKE STRUCTURE EVERY 4 HOURS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+