U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/26/95 - 12/27/95 ** EVENT NUMBERS ** 29751 29767 29768 29769 29770 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29751 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 12/20/95 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 20:55 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/20/95 | +------------------------------------------------+EVENT TIME: 17:30[EST]| |NRC NOTIFIED BY: WALSH |LAST UPDATE DATE: 12/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY SYSTEM FAILED TO START DURING | | TESTING. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "DIVISION I OF THE CONTROL ROOM OUTSIDE AIR SUPPLY SYSTEM (CREOASS) FAILED | | TO START WHEN THE EMERGENCY OUTSIDE AIR INTAKE PORTION OF THE LOGIC WAS | | INITIATED DURING TESTING. | | | | EARLIER IN THE DAY THE CHLORINE DETECTION PORTION OF THE CREOASS INITIATION | | LOGIC WAS REMOVED FROM THE CIRCUIT SINCE IT IS NO LONGER REQUIRED. THE | | POST DEACTIVATION TESTING REQUIRED WAS THE 18 MONTH LOGIC SYSTEM FUNCTIONAL | | TEST. DURING PERFORMANCE OF THE LOGIC FUNCTIONAL TESTS, THE SYSTEM FAILED | | TO INITIATE ON THE OUTSIDE AIR INTAKE RADIATION SIGNAL. SUBSEQUENT | | INVESTIGATION HAS IDENTIFIED A FAULTY AGASTAT RELAY. THE RELAY WAS | | REPLACED AND THE CREOASS SYSTEM WAS SUCCESSFULLY TESTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | ****RETRACTION 12/26/95 @ 1556ET BY DAN BOYLE TAKEN BY MACKINNON**** | | | | UPON FURTHER EVALUATION IT HAS BEEN DETERMINED THAT THIS WAS NOT A | | REPORTABLE EVENT BASED UPON A REVIEW OF NUREG-1022 AND THE STATEMENTS OF | | CONSIDERATIONS FOR ENGINEERED SAFETY FEATURES ACTUATIONS. THESE DOCUMENTS | | STATE THAT FAILURE TO ACTUATE WHEN CALLED UPON OR WHEN NEEDED TO MITIGATE | | THE CONSEQUENCES OF AN ACCIDENT ARE REPORTABLE. LICENSEES' INTERPRETATION | | OF WHEN CALLED UPON OR NEEDED TO MITIGATE IS THE EXISTENCE OF ACTUAL PLANT | | CONDITIONS WHICH WOULD INITIATE THE ESF LOGIC. IN THIS CASE THE SYSTEM WAS | | NOT CALLED UPON TO OPERATE BUT WAS RATHER BEING TESTED FOLLOWING A | | MAINTENANCE ACTIVITY. IN ADDITION THIS CONDITION ONLY EXISTED IN DIVISION 1 | | AND THEREFORE, HAD AN ACTUAL CONDITION EXISTED WHICH CALLED FOR CREOASS TO | | ACTUATE THE SYSTEM WOULD HAVE STARTED AND FULFILLED ITS ESF FUNCTION. THIS | | EVENT IS, THEREFORE, CONSIDERED TO BE NOT REPORTABLE. R1DO (HAROLD GRAY) | | NOTIFIED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29767 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 12/26/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 07:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/26/95 | +------------------------------------------------+EVENT TIME: 05:00[EST]| |NRC NOTIFIED BY: MCGINNIS |LAST UPDATE DATE: 12/26/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 +------------------------------------------------------------------------------+ | THE PLANT HAD A FEEDWATER ISOLATION SIGNAL ON TRAIN "A" POSSIBLY DUE TO | | PROCEDURAL INADEQUACIES. | | | | THIS OCCURRED WHILE THEY WERE PERFORMING A SURVEILLANCE TEST ON THE "A" | | REACTOR TRIP BREAKER AND THE SOLID STATE PROTECTION SYSTEM. AT THIS POINT, | | A FEEDWATER ISOLATION SIGNAL(FWIS) WAS GENERATED DUE TO AN APPARENT | | PROCEDURAL ERROR. THEY ARE CURRENTLY INVESTIGATING THE CAUSE. ALL EQUIPMENT | | AFFECTED BY THE FWIS FUNCTIONED AS EXPECTED. THE FWIS WAS RESET WITHIN | | APPROX. 30 MINUTES AND THE PLANT WAS RETURNED TO THE DESIRED LINEUP. | | SURVEILLANCE TESTING WILL BE COMPLETED SUBSEQUENT TO PROCEDURE CORRECTION | | AND REVIEW. THE RI WAS INFORMED. | | | | NOTE SEE EVENT #29766 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29768 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/26/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/26/95 | +------------------------------------------------+EVENT TIME: 18:40[CST]| |NRC NOTIFIED BY: JAMES DEDIC |LAST UPDATE DATE: 12/26/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SERVICE WATER (SW) RESIDUAL HEAT REMOVAL HEAT EXCHANGER (RHR HX) "B" OUTLET | | COOLING WATER THROTTLE VALVE (SW-MO-89B) SLIDE WIRE AND GEAR ASSEMBLY WHICH | | PROVIDES VALVE POSITION FEEDBACK TO THE CONTROLLER, WAS LISTED AS | | NON-ESSENTIAL INSTEAD OF BEING AN ESSENTIAL COMPONENT. | | | | DURING TROUBLE SHOOTING ACTIVITIES ON "SW-MO-89B" (RHR HX OUTLET COOLING | | WATER THROTTLE VALVE), IT WAS DISCOVERED THAT THE SLIDE WIRE AND GEAR | | ASSEMBLY THAT PROVIDES VALVE POSITION FEEDBACK TO THE CONTROLLER WAS | | CONSIDERED NON-ESSENTIAL. TROUBLE SHOOTING ACTIVITIES WERE BEING PERFORMED | | BECAUSE THE "SW-MO-89B" VALVE WAS NOT CONTROLLING PROPERLY DURING A | | RESIDUAL HEAT REMOVAL SERVICE WATER PUMP SURVEILLANCE TEST. | | THE CONTROLLER AND THE REST OF THE FEEDBACK LOOP ARE ESSENTIAL COMPONENTS. | | WITH A NON-ESSENTIAL COMPONENT INSTALLED IN AN ESSENTIAL APPLICATION, | | SHOULD A FAILURE OCCUR, THE POTENTIAL EXISTS TO LOSE COOLING DESPITE THE | | REQUIREMENT TO ASSURE RESIDUAL HEAT REMOVAL OPERABILITY. ALTHOUGH LOW | | PRESSURE COOLANT INJECTION MODE WOULD STILL BE AVAILABLE THERE WOULD BE NO | | COOLING FOR CONTAINMENT OR THE TORUS. THIS COULD INHIBIT THE OPERABILITY OF | | THE RESIDUAL HEAT REMOVAL SYSTEMS, CAUSED BY A HIGH ENERGY PIPE BREAK IN | | THE REACTOR BUILDING, WHICH COULD DISABLE THESE NON-ESSENTIAL COMPONENTS. | | THE LICENSEE THINKS THAT RHR LOOP "A" SW-MO-89A VALVE HAS THE SAME PROBLEM. | | BOTH LOOPS OF RHR WERE DECLARED INOPERABLE BY THE LICENSEE, BUT THEY ARE | | AVAILABLE IF NEEDED. THE PLANT IS EXITING FROM A 72 DAY REFUELING OUTAGE | | AND THE REACTOR VESSEL WATER TEMPERATURE IS 157 DEGREES F (AS MEASURED ON | | THE RHR LOOP), AND THEY DO NOT HAVE TO RUN RHR TO MAINTAIN THE REACTOR | | VESSEL WATER TEMPERATURE AT THAT TEMPERATURE. | | LICENSEE IS STILL INVESTIGATING THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29769 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 12/26/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 23:39 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/26/95 | +------------------------------------------------+EVENT TIME: 23:00[EST]| |NRC NOTIFIED BY: M DAMMANN |LAST UPDATE DATE: 12/26/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CREED 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 88 POWER OPERATION | 88 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE AFTER FAILING ITS FIRST | | SURVEILLANCE. | | | | LICENSEE ENTERED TECHNICAL SPECIFICATION 3.5.1 (14 DAY LIMITING CONDITION | | OF OPERATION) FOR HPCS AFTER IT FAILED ITS FIRST SURVEILLANCE. WITH HPCS | | FLOW AT 6200gpm ITS DIFFERENTIAL PRESSURE SHOULD BE LESS THAN 509 psid. | | WHEN ITS DIFFERENTIAL PRESSURE WAS MEASURED AT A FLOW RATE OF 6200 gpm IT | | WAS FOUND TO BE 518.5 psid (DIFFERENCE BETWEEN SUCTION AND DISCHARGE | | PRESSURE). HPCS WAS DECLARED INOPERABLE PER TECHNICAL SPECIFICATION 3.5.1. | | LICENSEE IS INVESTIGATING THIS PROBLEM. | | RCIC AND THEIR EMERGENCY CORE COOLING SYSTEMS ARE FULLY OPERABLE IF NEEDED. | | | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29770 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/27/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 01:56 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/26/95 | +------------------------------------------------+EVENT TIME: 23:23[EST]| |NRC NOTIFIED BY: DeDOMENICO |LAST UPDATE DATE: 12/27/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED START OF SERVICE WATER PUMP AND CONTROL ROOM EMERGENCY | | FILTRATION FAN DURING TESTING. | | | | WHILE PERFORMING THE 'D' CHANNEL LOOP/LOCA 18-MONTH SURVEILLANCE TEST, THE | | 'D' SERVICE WATER PUMP AND 'B' CONTROL ROOM EMERGENCY FILTER (CREF) FAN | | UNEXPECTEDLY STARTED. BOTH PIECES OF EQUIPMENT HAD STARTED AS EXPECTED | | EARLIER IN THE TEST, BUT HAD BEEN SECURED DUE TO PROBLEMS. THE 'D' SERVICE | | WATER PUMP HAD BEEN SECURED DUE TO A PROBLEM WITH THE SERVICE WATER | | STRAINER BACKWASH LINE. THE 'B' CREF FAN HAD TRIPPED APPROXIMATELY 10 | | SECONDS AFTER ITS INTIAL START, AND COULD NOT BE MANUALLY RESTARTED FROM | | THE CONTROL ROOM. | | | | THE LICENSEE WAS IN THE PROCESS OF BACKING OUT OF THE TEST PROCEDURE WHEN | | THE AUTOMATIC STARTS OCCURRED. SPECIFICALLY, THE LICENSEE WAS PERFORMING | | STEPS TO REMOVE TEST EQUIPMENT AND RESTORE THE ECCS LOGIC TO ITS INITIAL | | STATE. BOTH THE 'D' SERVICE WATER PUMP AND THE 'B' CREF FAN HAVE BEEN | | REMOVED FROM SERVICE. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE | | AUTOMATIC INTIATIONS. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+