U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/07/95 - 04/10/95 ** EVENT NUMBERS ** 28521 28555 28623 28644 28645 28646 28647 28648 28649 28650 28651 28652 28653 28654 28655 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28521 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 02:35 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 01:15[CST]| |NRC NOTIFIED BY: VANBUSKIRK |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 +------------------------------------------------------------------------------+ | REACTOR BUILDING COOLING UNITS SEISMIC ANCHORS NOT INSTALLED | | | | THE AS-BUILT REACTOR BUILDING COOLING UNITS SEISMIC ANCHORS WERE FOUND NOT | | TO BE INSTALLED. THE DISCOVERY WAS MADE DURING A SYSTEM WALKDOWN. THERE | | ARE FOUR COOLING UNITS AND EACH SHOULD HAVE HAD MULTIPLE SEISMIC ANCHORS. | | NO SEISMIC ANCHORS WERE FOUND ON ANY OF THE COOLING UNITS. THE COOLING | | UNITS ARE NOT REQUIRED TO BE OPERABLE UNTIL PLANT TEMPERATURE IS RAISED | | ABOVE 200 DEGREES F. | | | | THE LICENSEE IS STILL ANALYZING THE PROBLEM AND DEVELOPING A PLAN OF | | ACTION. THE CURRENT REFUELING OUTAGE IS SCHEDULED TO END MARCH 25TH. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE 1005 04/07/95 FROM SCOTT TAKEN BY STRANSKY *** | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE FOLLOWING IS TEXT OF A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON 03/14/95, AT APPROXIMATELY 0135 CST, ARKANSAS NUCLEAR ONE, UNIT 1 | | (ANO-1) MADE A FOUR HOUR NOTIFICATION TO THE OPERATIONS CENTER IN | | ACCORDANCE WITH 10 CFR 50.72(b)(2)(i). THE NOTIFICATION REPORTED THAT THE | | ANO-1 REACTOR BUILDING (RB) COOLERS (VCC-2A, 2B, 2C, AND 2D) WERE FOUND TO | | HAVE NO POSITIVE ANCHORAGE TO THE BUILDING STRUCTURAL STEEL, AS SHOWN ON | | THE DESIGN DRAWINGS. THE PLANT WAS IN COLD SHUTDOWN AT THE TIME OF | | DISCOVERY OF THIS CONDITION AND THE RB COOLERS WERE NOT REQUIRED TO BE | | OPERABLE. AN ENGINEERING EVALUATION WAS COMPLETED ON 03/29/95 WHICH | | CONCLUDED THAT THE RB COOLERS AND THEIR RESPECTIVE NOZZLES WOULD HAVE | | MAINTAINED THEIR FUNCTIONAL INTEGRITY IF THE LIMITING DESIGN BASIS SEISMIC | | EVENT HAD OCCURRED WHILE THEY WERE NOT ANCHORED. SINCE THE RB COOLERS WERE | | CAPABLE OF PERFORMING THEIR DESIGN BASIS FUNCTION, THEY WERE CONSIDERED | | OPERABLE, AS FOUND. THEREFORE, ANO IS RETRACTING THE REFERENCED | | NOTIFICATION. | | | | THE RB COOLERS WERE WELDED IN PLACE PRIOR TO RESTART FROM REFUELING OUTAGE | | 1R12." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R4DO (MURRAY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28555 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/17/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 19:38 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/17/95 | +------------------------------------------------+EVENT TIME: 16:12[EST]| |NRC NOTIFIED BY: DAN MCDOUGOLD |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SAFEGUARDS ACTUATION SIGNAL OCCURRED DURING TESTING. NO COMPONENTS | | ACTUATED BECAUSE EITHER THEY HAD ALL BEEN PREVIOUSLY DEENERGIZED FOR | | MAINTENANCE, OR THE LOGIC FOR ACTUATION HAD NOT BEEN COMPLETED. | | | | WHILE SHUTDOWN WITH THE REACTOR DEFUELED A PARTIAL INADVERTENT SAFEGUARDS | | ACTUATION OCCURRED WITHOUT A PUMP START, VALVE MOVEMENT OR WATER FLOW. THE | | CAVITY LEVEL REMAINED CONSTANT. INSTRUMENT AND CONTROLS (I&C) TECHNICIANS | | WERE TESTING THE ACTUATION CIRCUITRY WITH THE ACTUATION CIRCUITRY IN | | 'BLOCK'. THE SAFEGUARDS ACTUATION WAS UNEXPECTED. THE REASON THAT | | COMPONENTS DID NOT ACTUATE IS BECAUSE THEY WERE ALL DEENERGIZED AND TAGGED | | FOR MAINTENANCE OR THEIR LOGIC HAD NOT BEEN COMPLETED. | | | | THE CAUSE OF THE PROBLEM APPEARS TO BE A BAD CONTACT ON ONE 'BLOCK RELAY' | | SUCH THAT IT CAUSED ONE TRAIN OF SAFETY INJECTION AND CONTAINMENT INTEGRITY | | TO ACTUATE DURING THE TESTING. THE CONTAINMENT SPRAY SIGNAL DID NOT | | ACTUATE SINCE THE PRECURSOR OF 20 PSIG IN CONTAINMENT WAS NOT MET. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | | | | * * * UPDATE 1021 4/7/95 FROM WALDMAN TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE HAS DETERMINED | | THAT THIS EVENT WAS NOT REPORTABLE BECAUSE THE INITIATION WAS INVALID AND | | THE SYSTEM WAS PROPERLY REMOVED FROM SERVICE. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED. NOTIFIED R1DO (MEYER). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/01/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 08:08 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/01/95 | +------------------------------------------------+EVENT TIME: 04:42[EST]| |NRC NOTIFIED BY: SCHALL |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL KELLOGG 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 24 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A MANUAL REACTOR SCRAM FROM 24% POWER AS PER SHUTDOWN | | PROCEDURES. | | | | THE PLANT WAS BEING SHUTDOWN FOR A REFUELING OUTAGE AND AS PER THEIR | | SHUTDOWN PROCEDURE, OGP-05, THEY HAD A CHOICE OF MANUALLY SCRAMMING THE | | REACTOR OR INSERTING INDIVIDUAL RODS FOR SHUTDOWN. THE WATER LEVEL | | TRANSIENT DURING THE SCRAM RESULTED IN AN AUTOMATIC SCRAM SIGNAL AND GROUP | | 2, 6, AND 8 ISOLATION SIGNALS ON LOW WATER LEVEL. ALL RODS FULLY INSERTED | | AND THERE WAS NO ECCS INJECTION OR SAFETY RELIEF VALVES LIFTING. THE GROUP | | 2(DRYWELL FLOOR & EQUIPMENT DRAIN ISOLATION VALVES) AND GROUP 6(CONTAINMENT | | ATMOSPHERIC CONTROL VALVES) ISOLATION VALVES CLOSED. THE GROUP 8(SHUTDOWN | | COOLING ISOLATION VALVES) ISOLATION VALVES WERE ALREADY CLOSED. ALL SYSTEMS | | FUNCTIONED AS REQUIRED. THE LEVEL WAS RESTORED TO NORMAL BAND USING | | FEEDWATER AND CONDENSATE SYSTEM. PRESSURE CONTROL IS BEING MAINTAINED BY | | THE BYPASS VALVES TO THE CONDENSER. THE REACTOR IS STABLE AND THEY ARE | | COOLING DOWN TO GO INTO THEIR REFUELING OUTAGE. THE GROUP ISOLATIONS WERE | | RESET AND SYSTEMS WERE RESTORED TO NORMAL. THE RI WAS INFORMED. | | | | ****RETRACTION 04/07/95 1549ET BY MARK SCHALL TAKEN BY MACKINNON**** | | | | THE ENS NOTIFICATION OF THIS EVENT MADE ON 04/01/95 IS BEING RETRACTED. | | UPON FURTHER REVIEW, IT HAS BEEN CONCLUDED THAT THE MANUAL REACTOR SCRAM | | AND SUBSEQUENT GROUP 2, 6, AND 8 ISOLATION SIGNALS WERE A RESULT OF A | | PREPLANNED SEQUENCE WHICH WAS CONTROLLED WITH THE EXPECTED RESULTS AS | | DOCUMENTED IN UNIT SHUTDOWN PROCEDURE, 0GP-05. THEREFORE, IN ACCORDANCE | | WITH 10 CFR 50.72(b)(2)(1) THIS EVENT IS NOT REPORTABLE. HOO NOTIFIED R2DO | | (CHUCK HOSEY). RESIDENT INSPECTOR NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28644 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/07/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:59 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/07/95 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: EVERETT |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT SAFETY INJECTION (SI) ACTUATION SIGNAL CAUSED WHEN INSTRUMENT & | | CONTROL (I & C) TECHNICIANS WERE WORKING ON PRIMARY PRESSURE CHANNELS. NO | | SAFETY INJECTION INTO THE REACTOR COOLANT SYSTEM. | | | | THE FOLLOWING EVENT IS TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "PLANT IN ANNUAL REFUELING OUTAGE. RCS DEPRESSURIZED, APPROXIMATELY 100 | | DEGREES WITH LOOP LEVELS AT 80 INCHES (4 INCHES BELOW VESSEL FLANGE). | | AT 0900 (EST), WE EXPERIENCED AN INADVERTENT SI SIGNAL. I & C TECHNICIANS | | HAD PREVIOUSLY DEFEATED A PRIMARY PRESSURE CHANNEL (P-0431) AND THEN | | DEFEATED A SECOND PRIMARY PRESSURE CHANNEL (P-0429) WHICH CAUSED SI TO | | AUTOMATICALLY UNBLOCK. THE ALREADY PRESENT SI SIGNAL FROM LOW STEAM | | GENERATOR PRESSURE THEN ACTUATED SI RESULTING IN CONTAINMENT ISOLATION AND | | CONTAINMENT VENTILATION ISOLATION SIGNALS ALSO. ALL PREVIOUSLY OPERABLE | | ESF EQUIPMENT WAS OBSERVED TO FUNCTION PROPERLY WITH THE EXCEPTION OF | | RECEIVING MIDPOSITION INDICATION FOR MOV-852B (RHR DISCHARGE TO REACTOR | | VESSEL DELUGE). MOV-852B WAS SUBSEQUENTLY STROKED FROM THE CONTROL ROOM | | WITH PROPER INDICATION LOCALLY AND IN THE CONTROL ROOM. EMERGENCY | | DIESEL GENERATOR 'A' STARTED AND ATTAINED REQUIRED VOLTAGE AND FREQUENCY. | | PLANT CONDITIONS DID NOT WARRANT AUTOMATIC LOADING OF SAFEGUARDS BUSSES. | | EMERGENCY DIESEL GENERATOR 'B' WAS HELD (INOPERABLE) AT THIS TIME FOR | | SCHEDULED OUTAGE WORK. EDG 'A' WAS SECURED AT 0930. ALL SI PUMPS WERE OUT | | OF AUTO START DUE TO PLANT CONDITIONS; THEREFORE, NO SI FLOW OCCURRED. | | INITIALLY ONE RHR PUMP WAS IN SERVICE, AUTO START OF THE SECOND RHR PUMP | | OCCURRED. NO DISTURBANCE OF PRIMARY SYSTEM CONDITIONS WAS NOTED. | | THE SECOND RHR PUMP WAS SECURED AT 0920. THE RCS REMAINED STABLE AT | | INITIAL CONDITIONS DURING THE EVENT AND DURING SUBSEQUENT RESTORATION | | ACTIONS. ALL EQUIPMENT HAS BEEN RESTORED TO STATUS PRIOR TO THE EVENT." | | | | ALL CONTAINMENT ISOLATION VALVES AND CONTAINMENT VENTILATION ISOLATION | | VALVES WHICH CHANGED POSITION DUE TO THE SI ACTUATION SIGNAL WERE RETURNED | | TO THEIR FORMER POSITION. SPENT FUEL POOL COOLING WAS NOT LOST DURING THIS | | EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28645 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/07/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:19 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/07/95 | +------------------------------------------------+EVENT TIME: 09:40[CDT]| |NRC NOTIFIED BY: JIM TILLS |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT A SCENARIO INVOLVING A HEAVY LOAD DROP FROM | | THE CONTAINMENT POLAR CRANE OVER IRRADIATED FUEL WITHOUT THE CAPABILITY FOR | | CONTAINMENT CLOSURE IS NOT ADDRESSED IN THE SITE'S CURRENT HEAVY LOAD | | INCIDENT ANALYSIS & COULD HAVE PREVENTED FULFILLMENT OF THE SAFETY FUNCTION | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "THE CURRENT FORT CALHOUN STATION HEAVY LOAD INCIDENT ANALYSIS (USAR | | SECTION 14.24) ADDRESSES LOAD DROPS FROM THE CONTAINMENT POLAR CRANE THAT | | COULD AFFECT IRRADIATED FUEL IN THE REACTOR VESSEL. THE CURRENT USAR | | DISCUSSION DOES NOT IDENTIFY AN ASSUMPTION IN AN ENGINEERING EVALUATION | | DONE IN RESPONSE TO NUREG-0612. THE EVALUATION ASSUMES CONTAINMENT CLOSURE | | (INTEGRITY) OR THE CAPABILITY TO RAPIDLY ISOLATE CONTAINMENT PRIOR TO ANY | | HEAVY LOAD LIFTS OVER IRRADIATED FUEL IN THE REACTOR VESSEL WITH THE HEAD | | REMOVED. CURRENT PROCEDURES FOR REMOVING/INSTALLING THE REACTOR VESSEL | | INTERNALS DO NOT CONTAIN PREREQUISITES FOR CONTAINMENT CLOSURE. USE OF THE | | PROCEDURES COULD HAVE RESULTED IN MOVEMENT OF HEAVY LOADS WITHOUT | | CONTAINMENT CLOSURE. THE REACTOR VESSEL HEAD IS CURRENTLY INSTALLED, | | THEREFORE, THIS IS NOT A CONCERN FOR THE CURRENT CONFIGURATION. THE LIFTS | | MADE PREVIOUSLY DURING THE 1995 REFUELING OUTAGE APPEAR TO HAVE BEEN MADE | | WITH CONTAINMENT CLOSED, BUT THIS HAS NOT BEEN VERIFIED. | | | | THE SAFETY FUNCTION OF CONTAINMENT CLOSURE IS TO CONTROL RADIOLOGICAL | | RELEASES TO ENSURE THAT ANY RADIOLOGICAL RELEASES ARE WELL WITHIN 10CRF100 | | LIMITS. A SCENARIO INVOLVING A HEAVY LOAD DROP OVER IRRADIATED FUEL | | WITHOUT THE CAPABILITY FOR CONTAINMENT CLOSURE IS NOT ADDRESSED IN THE | | CURRENT USAR SECTION 14.24 ANALYSIS AND COULD HAVE PREVENTED FULFILLMENT OF | | THIS SAFETY FUNCTION." THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28646 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/07/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 14:27 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/07/95 | +------------------------------------------------+EVENT TIME: 10:40[CDT]| |NRC NOTIFIED BY: G HARRINGTON |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON GARDNER 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 +------------------------------------------------------------------------------+ | STEAM GENERATOR EDDY CURRENT INSPECTION RESULTS HAVE DETERMINED THAT MORE | | THAN 1% OF TUBES IN STEAM GENERATOR "A" ARE DEFECTIVE. | | | | 52 OF 428 TUBES OF STEAM GENERATOR "A" WERE FOUND TO BE DEFECTIVE DURING | | EDDY CURRENT TESTING. THIS PLACED "A" STEAM GENERATOR IN C-3 CLASSIFICATION | | PER THEIR TECH SPECS. A DEFECTIVE TUBE IS ANY TUBE WITH AN INDICATION | | BELIEVED TO BE MORE THAN 50% THROUGH WALL. 52 OF THE 428 STEAM GENERATOR | | "A" TUBES TESTED WERE FOUND TO BE DEFECTIVE IN THE AREA OF THE UPPER | | EXPANSION JOINT. LICENSEE WILL EXPAND TO 100% EDDY CURRENT TESTING OF THE | | SLEEVED TUBES IN STEAM GENERATOR "A". LICENSEE WILL THEN PLUG ALL DEFECTIVE | | TUBES. AN ANALYSIS WILL BE PERFORMED TO DETERMINE PLUGGING IMPACT ON THE | | ACCIDENT ANALYSIS. ADDITIONALLY, THE LICENSEE WILL ENSURE THAT THE PLUGGING | | RATE DOES NOT RESULT IN AN UNANALYZED CONDITION. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28647 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GEORGIA RADIOACTIVE MATERIAL PROG. |NOTIFICATION DATE: 04/07/95 | | CITY: LAWRENCEVILLE REGION: 2 |NOTIFICATION TIME: 16:08 [ET]| | COUNTY: GWINNETT STATE: GA |EVENT DATE: 04/06/95 | |LICENSE#: GA677-1 AGREEMENT: Y |EVENT TIME: 10:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/07/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHUCH HOSEY RDO | | |DONALD COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: HENRY COPELAND | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HENRY COPELAND CALLED FOR GEORGIA RADIOACTIVE MATERIAL PROGRAM FOR THE | | STATE OF GEORGIA TO REPORT AN AGREEMENT STATE INCIDENT (OVEREXPOSURE) WHICH | | OCCURRED THE MORNING OF 04/06/95 AT THE GWINNETT MEDICAL CENTER, | | LAWRENCEVILLE, GA. | | | | HENRY COPELAND OF THE GEORGIA RADIOACTIVE MATERIAL PROGRAM OFFICE FOR THE | | STATE OF GEORGIA REPORTED THAT TWO PART-TIME RADIATION PHYSICISTS AT THE | | GWINNETT MEDICAL CENTER THOUGHT THEY HAD A DUMMY IR-192 RIBBON. INSTEAD THE | | MALE RADIATION PHYSICIST HANDLED A 300 MILLICURIE IR-192 RIBBON YESTERDAY | | MORNING (04/06/95). THE CALCULATED DOSE TO HIS HAND WAS 1212 REM. THEY | | BELIEVE THAT HIS WHOLE BODY EXPOSURE WAS MUCH LESS (WAITING FOR HIS FILM | | BADGE TO BE PROCESSED). THE MALE RADIATION PHYSICIST HAS SHOWN NO MEDICAL | | PROBLEMS SO FAR FROM THE EXPOSURE TO THE IR-192 RIBBON. THE SECOND | | RADIATION HEALTH PHYSICIST IS A FEMALE WHO IS 3 MONTHS PREGNANT. SHE DID | | NOT TOUCH THE IR-192 RIBBON BUT THE CALCULATED EXPOSURE TO HER FETUS WAS | | 110 MILLIREM (LIMIT IS 500 MILLIREM TO AN UNBORN CHILD IN 9 MONTHS). THE | | STATE OF GEORGIA REPORT NUMBER FOR THIS INCIDENT IS GA-95-06I. SEE HOO LOG | | BOOK FOR PHONE NUMBER AND ADDRESS OF THE GEORGIA RADIOACTIVE MATERIAL | | PROGRAM OFFICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28648 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 04/07/95 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/07/95 | +------------------------------------------------+EVENT TIME: 13:00[MST]| |NRC NOTIFIED BY: KATHLEEN ROBERSON |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CORROSION NODULES FOUND ON EDG HEAT EXCHANGER INLET TUBESHEETS - | | | | AT 1300 (MST), DURING A UNIT 1 REFUELING OUTAGE, LICENSEE DISCOVERED THAT | | CORROSION NODULES WERE LODGED IN THE SPRAY POND SYSTEM INLET TUBESHEETS TO | | THE JACKET WATER HEAT EXCHANGER OF 1 OF 2 UNIT 1 EDGs (#1B). THESE NODULES | | COULD REDUCE SPRAY POND COOLANT FLOW AND POTENTIALLY ADVERSELY AFFECT THE | | PERFORMANCE OF EDG #1B UNDER DESIGN BASIS ACCIDENT CONDITIONS. | | | | THE SPRAY POND SYSTEM IS REQUIRED TO PROVIDE SUFFICIENT COOLING TO KEEP | | THE EDG LUBE OIL, JACKET WATER, INTAKE AIR, AND BYPASS FUEL OIL FROM | | OVERHEATING UNDER BOTH NORMAL AND DESIGN BASIS ACCIDENT CONDITIONS | | (ASSUMING WORST CASE SPRAY POND TEMPERATURES OF 110 DEGREES F). JACKET | | WATER CIRCULATES AROUND THE EDG CYLINDER LINERS AND HEADS AND WASTE HEAT | | IS REJECTED TO THE HEAT EXCHANGERS. | | | | THE EXTENT OF THE ESTIMATED TUBESHEET BLOCKAGE FOUND IN THE LUBE OIL HEAT | | EXCHANGER, THE BYPASS FUEL OIL HEAT EXCHANGER, AND THE TWO TURBOCHARGER | | INTERCOOLERS FOR EDG #1B HAS BEEN DETERMINED NOT TO ADVERSELY AFFECT | | OPERABILITY OF EDG #1B. | | | | EDG #1B AND ITS ASSOCIATED HEAT EXCHANGERS WERE LAST INSPECTED AND SERVICED | | 35 MONTHS AGO AND ARE PRESENTLY INOPERABLE FOR SURVEILLANCE TESTING AND | | INSPECTION DURING THE PRESENT REFUELING OUTAGE. | | | | EDG #1A AND ITS ASSOCIATED HEAT EXCHANGERS WERE LAST INSPECTED AND SERVICED | | 18 MONTHS AGO AND WILL BE INSPECTED AND SERVICED DURING THE PRESENT | | REFUELING OUTAGE. | | | | EDG #3A AND ITS ASSOCIATED HEAT EXCHANGERS WERE LAST INSPECTED AND SERVICED | | 29 MONTHS AGO. EDG #3B AND ITS ASSOCIATED HEAT EXCHANGERS WERE LAST | | INSPECTED AND SERVICED 11 MONTHS AGO. THE LENGTH OF TIME UNTIL UNIT 3 EDGs | | AND THEIR ASSOCIATED HEAT EXCHANGERS WILL NEXT BE INSPECTED AND SERVICED | | WILL BE BASED ON THE COMPLETED RESULTS OF THE INSPECTIONS OF THE UNIT 1 | | EDGs AND THEIR ASSOCIATED HEAT EXCHANGERS. | | | | A CONDITION SIMILAR TO THAT ON UNIT 1 WAS PREVIOUSLY DISCOVERED IN UNIT 2 | | ON 02/21/95. EDG #2A AND ITS ASSOCIATED HEAT EXCHANGERS WERE LAST | | INSPECTED AND SERVICED 39 MONTHS AGO. EDG #2B AND ITS ASSOCIATED HEAT | | EXCHANGERS WERE LAST INSPECTED AND SERVICED 23 MONTHS AGO. BASED ON THE | | PREVIOUSLY MEASURED FLOWRATES TO THE HEAT EXCHANGERS, THE HEAT EXCHANGERS | | ESTIMATED TUBESHEET BLOCKAGE, AND THE CALCULATED MINIMUM REQUIRED FLOWRATES | | BASED ON ESTIMATED TUBESHEET BLOCKAGE, EDGs #2A AND #2B WERE CONSIDERED | | OPERABLE IN THE AS-FOUND CONDITION ON 02/21/95. | | | | THE INSPECTIONS OF THE UNIT 2 HEAT EXCHANGERS INDICATED THAT THE DEBRIS | | BUILDUP ON THE TUBESHEETS IS AT LEAST PARTIALLY TIME DEPENDENT. WITH THE | | EDG #2A HEAT EXCHANGERS HAVING BEEN THE LONGEST IN-SERVICE (39 MONTHS SINCE | | LAST INSPECTED), THE POTENTIAL FOR TUBESHEET BLOCKAGE APPEARED TO BE | | BOUNDED BY THE EDG #2A HEAT EXCHANGERS. SINCE THE WORST CASE CONDITIONS | | WERE BOUNDED BY HOT WEATHER CONDITIONS (i.e., TEMPERATURE AND HUMIDITY), | | THERE WERE NO IMMEDIATE CONCERNS THAT THE EDGs WOULD NOT HAVE BEEN ABLE TO | | PERFORM THEIR SAFETY FUNCTION IF CALLED UPON DURING MARCH AND APRIL, 1995. | | | | IMMEDIATE ACTION FOR THE UNIT 1 AND UNIT 3 EDGs AND THEIR ASSOCIATED HEAT | | EXCHANGERS WAS NOT CONSIDERED NECESSARY. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28649 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/07/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 23:25 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/07/95 | +------------------------------------------------+EVENT TIME: 22:20[EDT]| |NRC NOTIFIED BY: MICHAEL MATUSZEWSKI |LAST UPDATE DATE: 04/07/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | M/R Y 0 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM THE INTERMEDIATE RANGE DUE TO A ROD CONTROL URGENT | | FAILURE ALARM. | | | | AN URGENT FAILURE ALARM WAS RECEIVED WHILE UNIT 3 WAS IN THE PROCESS OF | | SHUTTING DOWN TO REPLACE THE ROD CONTROL POWER SUPPLIES DUE TO FLUCTUATING | | VOLTAGES IN ROD CABINET 2AC. THE TURBINE WAS TRIPPED AT 22:00 AND THE | | LICENSEE RECEIVED THE URGENT FAILURE ALARM AT 22:12. INSTRUMENT AND CONTROL | | PERSONNEL WERE UNABLE TO CLEAR THE CAUSE OF THE URGENT FAILURE ALARM, | | THEREFORE, THE LICENSEE DECIDED TO TRIP THE REACTOR AT 22:20. REACTOR POWER | | WAS AT 1E-9 AMPS IN THE INTERMEDIATE RANGE AT THE TIME OF THE TRIP. | | | | THE POST TRIP RESPONSE WAS NORMAL. ALL RODS FULLY INSERTED. THE LICENSEE | | IS REMOVING DECAY HEAT VIA THE ATMOSPHERIC DUMP VALVES AND THROUGH THE | | STEAM GENERATOR BLOWDOWN LINE. THE ACTIVITY IN THE STEAM GENERATORS IS LESS | | THAN THE MINIMUM DETECTABLE. ALL ECCS AND EDGS ARE OPERABLE. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FLUCTUATING VOLTAGES IN ROD | | CABINET 2AC. THE PROBLEM FIRST APPEARED THIS MORNING. THE LICENSEE WAS | | NOT IN A TECH SPEC ACTION STATEMENT TO SHUT DOWN THE REACTOR. THE DECISION | | TO SHUT DOWN THE REACTOR TO REPLACE THE POWER SUPPLIES WAS MADE BY | | MANAGEMENT. THE LICENSEE SUSPECTS AT THIS TIME THAT THE URGENT FAILURE | | ALARM AND THE FLUCTUATING VOLTAGES IN THE ROD CABINET ARE RELATED PROBLEMS. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28650 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/08/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 11:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/08/95 | +------------------------------------------------+EVENT TIME: 10:45[EDT]| |NRC NOTIFIED BY: JIM BROOKS |LAST UPDATE DATE: 04/08/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |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 +------------------------------------------------------------------------------+ | THE TORUS TO DRYWELL VACUUM BREAKERS FAILED TO MEET THE REQUIREMENTS OF THE | | TECHNICAL SPECIFICATIONS. THE PROBLEM WAS IDENTIFIED DURING AN 18 MONTH | | SURVEILLANCE TEST. | | | | THERE ARE TWO TECHNICAL SPECIFICATION REQUIREMENTS ON THE LIMIT SWITCHES | | ASSOCIATED WITH THE TEN VACUUM BREAKERS. (THERE ARE TWO LIMIT SWITCHES PER | | VACUUM BREAKER). TECHNICAL SPECIFICATION 3.7.A.6.A.3 REQUIRES THAT | | THE LIMIT SWITCHES BE SET TO DETECT WHEN THE VACUUM BREAKERS ARE GREATER | | THAN AN EQUIVALENT 0.05 INCHES OPEN FROM THE VALVE DISK TO ITS SEAT. | | THIS IS BASED ON A REQUIREMENT IN THE TECHNICAL SPECIFICATION BASIS | | THAT THE COMBINED OPENING FROM ALL TEN VACUUM BREAKERS NOT BE GREATER | | THAN 0.5 INCHES. | | | | DURING A SURVEILLANCE TEST IT WAS DISCOVERED THAT ON FIVE OF THE TEN VACUUM | | BREAKERS ONE OF THE LIMIT SWITCHES WAS SET INCORRECTLY. THESE | | LIMIT SWITCHES WERE SET SUCH THAT THE VALVES WOULD HAVE EXCEEDED THE | | 0.05 INCH CRITERIA. IN ADDITION THE LIMIT SWITCHES FOR ALL TEN OF THE | | VALVES WERE SET SUCH THAT THE LICENSEE EXCEEDED THE 0.5 INCH CRITERIA IN | | THE TECHNICAL SPECIFICATION BASIS. THERE WAS ALSO ONE VACUUM BREAKER | | (BREAKER 'E') WHERE BOTH LIMIT SWITCHES WERE SET INCORRECTLY. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE PROBLEM. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR AND STATE OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28651 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/08/95 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 20:47 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/08/95 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 04/08/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LICENSEE SPILLED 5 GALLONS OF ANTIFREEZE ONTO THE GROUND - | | | | WHILE PERFORMING MAINTENANCE ON A HYDROLASING MACHINE, TECHNICIANS STARTED | | THE MACHINE AND APPROXIMATELY 5 GALLONS (APPROXIMATELY 40 POUNDS) OF | | ETHYLENE GLYCOL (ANTIFREEZE) SPILLED ONTO THE GROUND. LICENSEE IS CLEANING | | UP THE SPILL. | | | | LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, STATE AND LOCAL OFFICIALS, | | AND THE USCG NATIONAL RESPONSE CENTER. | | | | THE USCG NATIONAL RESPONSE CENTER NOTIFIED THE NRC OPERATIONS CENTER AND | | EPA REGION 3. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28652 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/09/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 06:37 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/09/95 | +------------------------------------------------+EVENT TIME: 03:11[CDT]| |NRC NOTIFIED BY: GARY BAL |LAST UPDATE DATE: 04/09/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 99 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 99% POWER DUE TO A TURBINE TRIP FROM A HIGH STEAM | | GENERATOR (SG) WATER LEVEL. | | | | AT 03:10 (CDT), UNIT 1 EXPERIENCED A COMPLETE LOSS OF INSTRUMENT BUS 111 | | WHICH IS ONE OF THE FOUR 120 VOLT VITAL INSTRUMENT BUSSES. THE 1A SG FEED | | REGULATING VALVE (FRV) FAILED OPEN WHILE IT WAS IN AUTOMATIC CONTROL AFTER | | THE LOSS OF THIS BUS. AN OPERATOR TOOK MANUAL CONTROL OF THE 1A FRV BUT | | WAS UNABLE TO KEEP THE SG LEVEL FROM REACHING THE HIGH LEVEL TRIP POINT FOR | | THE MAIN TURBINE. THE MAIN TURBINE TRIP THEN CAUSED A REACTOR TRIP. | | | | THE POST TRIP RESPONSE WAS NORMAL. ALL CONTROL RODS INSERTED. ALL ECCS | | AND EDGS ARE OPERABLE. THE AUXILIARY FEEDWATER PUMPS (AFW) STARTED ON LOW | | SG LEVEL DUE TO THE SHRINK FOLLOWING THE REACTOR TRIP. THE MAIN CONDENSER | | IS AVAILABLE AS A HEAT SINK AND THE AFW SYSTEM HAS BEEN SECURED. STEAM | | GENERATOR WATER LEVEL IS CURRENTLY BEING MAINTAINED BY A STARTUP FEEDWATER | | PUMP. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE LOSS OF THE INSTRUMENT BUS. | | HEAVY LIGHTNING ACTIVITY WAS NOTED IN THE REGION SURROUNDING THE PLANT | | PRIOR TO THE TRIP. THE 111 BUS TYPICALLY FEEDS ONE OF THE FOUR CHANNELS OF | | SAFETY RELATED INSTRUMENTATION. THIS BUS CAN BE FED EITHER THROUGH AN | | INVERTER, WHICH WAS THE CONDITION PRIOR TO ITS LOSS, OR THROUGH A CONSTANT | | VOLTAGE TRANSFORMER, WHICH IS THE NON-PREFERRED POWER SUPPLY. THE LICENSEE | | RESTORED POWER TO THE BUS THROUGH THE CONSTANT VOLTAGE TRANSFORMER AT 0326 | | (CDT). SOME OF THE INSTRUMENTATION FED FROM THE 111 BUS FAILED TO ENERGIZE | | AFTER POWER TO THE BUS WAS RESTORED. THE LICENSEE IS NOT IN ANY TECH SPEC | | ACTION STATEMENT BECAUSE OF THE FAILURE OF SOME OF THE INSTRUMENTATION TO | | REENERGIZE. | | | | THE CAUSE OF THE FRV OPENING IS ALSO BEING INVESTIGATED. THERE ARE FOUR | | LEVEL INSTRUMENTS FOR EACH STEAM GENERATOR. TWO OF THESE FOUR INSTRUMENTS | | CAN BE USED AS AN INPUT TO THE STEAM GENERATOR WATER LEVEL CONTROL (SGWLC) | | SYSTEM. THE OPERATOR HAS THE ABILITY TO CHOOSE WHICH OF THE TWO LEVEL | | INSTRUMENTS SERVES AS AN INPUT TO THE SGWLC SYSTEM. THE CHANNEL THAT WAS | | SELECTED AS THE INPUT TO THE SGWLC SYSTEM AT THE TIME OF THE PROBLEM WAS | | NOT POWERED BY BUS 111, AND THE OPERATORS NOTICED NO PROBLEM WITH THIS | | LEVEL INDICATION AFTER THE LOSS OF BUS 111. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | | | | ***UPDATE DURING MORNING STATUS CALL OF 4/10/95 TAKEN BY SEBROSKY *** | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE CAUSE OF THE FRV OPENING. IT | | APPEARS THAT THE PROBLEM MAY HAVE BEEN WITH THE FEED FLOW INPUT TO THE | | SGWLC SYSTEM WHICH WAS POWERED FROM BUS 111 AT THE TIME OF THE EVENT. | | | | HOO NOTIFIED R3DO(GARDNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28653 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/09/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 13:56 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/09/95 | +------------------------------------------------+EVENT TIME: 10:30[CDT]| |NRC NOTIFIED BY: SCOTT HAWN |LAST UPDATE DATE: 04/09/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 +------------------------------------------------------------------------------+ | - MORE THAN 1% OF 'B' STEAM GENERATOR TUBES INSPECTED ARE DEFECTIVE - | | | | AN ANALYSIS OF THE RESULTS OF EDDY CURRENT TESTS OF THE 'B' STEAM GENERATOR | | DETERMINED THAT MORE THAN 1% OF THE S/G TUBES INSPECTED ARE DEFECTIVE. | | 33 OF 973 TUBES IN THE 'B' S/G TUBESHEET SERVICE AREA INSPECTED WERE | | DETERMINED TO BE DEFECTIVE. A DEFECTIVE S/G TUBE IS DEFINED AS ANY | | S/G TUBE WITH AN INDICATION BELIEVED TO BE MORE THAT 50% THROUGH THE | | TUBE WALL THICKNESS. THESE TEST RESULTS PLACE THE 'B' STEAM GENERATOR IN | | THE "C-3" STEAM GENERATOR CLASSIFICATION (REQUIRING 100% TUBE INSPECTION) | | IN ACCORDANCE WITH KEWAUNEE TECH SPECS. THE INSPECTION SCOPE OF THE | | 'B' S/G WILL NOT HAVE TO BE EXPANDED SINCE 100% OF THE TUBES HAVE BEEN | | INSPECTED. | | | | LICENSEE PLANS THE FOLLOWING CORRECTIVE ACTIONS FOR THE TUBES IN THE 'B' | | STEAM GENERATOR: | | - PLUG OR REPAIR THOSE TUBES DETERMINED TO BE DEFECTIVE BY CONFIRMATORY | | EXAMINATION PRIOR TO PLANT RESTART | | - PERFORM AN ANALYSIS TO DETERMINE THE IMPACT OF TUBE PLUGGING ON | | ACCIDENT ANALYSIS AND TO ENSURE THAT TUBE PLUGGING DOES NOT RESULT | | IN AN UNANALYZED CONDITION. | | | | LICENSEE PLANS TO INSPECT 100% OF THE TUBES IN THE 'A' STEAM GENERATOR | | DURING THE PRESENT REFUELING OUTAGE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28654 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/09/95 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 15:35 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/09/95 | +------------------------------------------------+EVENT TIME: 15:03[EDT]| |NRC NOTIFIED BY: PAUL KIEL |LAST UPDATE DATE: 04/09/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |GARY HOLAHAN EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |CARR FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | M/R Y 80 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UE DUE TO WATER INJECTION INTO Rx VESSEL FOLLOWING MANUAL Rx SCRAM - | | | | CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE PLANT FROM 80% POWER IN ORDER | | TO MONITOR THE VIBRATION LEVELS OF THE MAIN TURBINE DURING COAST DOWN. | | THIS EVOLUTION WAS A PREPLANNED ACTIVITY PERFORMED IN ACCORDANCE WITH A | | SPECIAL TEST PROCEDURE. ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS | | BEING DUMPED TO THE MAIN CONDENSER. | | | | HOWEVER, FOLLOWING THE SCRAM, REACTOR VESSEL WATER LEVEL DROPPED TO | | LEVEL 2. NORMAL Rx VESSEL WATER LEVEL IS 193 TO 201 INCHES, LEVEL 3 | | IS 173 INCHES, LEVEL 2 IS 110 INCHES. | | | | AT LEVEL 3, THE PLANT RECEIVED THE FOLLOWING SIGNALS: | | | | ACTUATIONS - Rx SCRAM SIGNAL (Rx ALREADY SCRAMMED), | | AUTO DEPRESSURIZATION PERMISSIVE SIGNAL, | | TIP DETECTORS SYSTEM AUTO RETRACTION SIGNAL; | | | | ISOLATIONS - PCIS GROUP 4 - RHR SHUTDOWN COOLING, | | GROUP 13 - DRYWELL SUMPS, | | GROUP 15 - TIP SYSTEM (AUTO RETRACTION). | | | | AT LEVEL 2, THE PLANT RECEIVED THE FOLLOWING SIGNALS: | | | | ACTUATIONS - HPCI SYSTEM (DIV 1) (DID NOT INJECT INTO Rx VESSEL), | | RCIC SYSTEM (DIV 1) (DID INJECT INTO Rx VESSEL), | | SBGT SYSTEM (DIV 1), | | CONTROL ROOM VENT SYSTEM SHIFTED TO RECIRC MODE (DIV 1 & 2), | | Rx BUILDING VENT SYSTEM TRIPPED (DIV 1), | | CONTROL AIR COMPRESSORS STARTED (DIV 1), | | Rx RECIRC PUMPS TRIPPED (DIV 1), | | LPCI LOOP SELECT LOGIC (DIV 1), | | ALTERNATE ROD INSERTION SYSTEM (BACKUP SCRAM SIGNAL) (DIV 2); | | | | ISOLATIONS - PCIS GROUP 2 - Rx WATER SAMPLE SYSTEM (DIV 1), | | GROUP 10 - RWCU SYSTEM (DIV 1), | | GROUP 12 - TORUS WATER MANAGEMENT SYSTEM (DIV 1), | | GROUP 14 - DRYWELL & TORUS VENT SYSTEM (DIV 1), | | GROUP 16 - NITROGEN INERTING SYSTEM (DIV 1), | | GROUP 17 - Rx RECIRC PUMP SEAL VALVES (DIV 1), | | GROUP 18 - PRIMARY CONTAINMENT PNEUMATIC SUPPLY SYSTEM (DIV 1) | | | | AT 1503, LICENSEE DECLARED AN UNUSUAL EVENT DUE TO AN INJECTION INTO THE | | Rx VESSEL (RCIC SYSTEM). WATER INJECTION INTO THE Rx VESSEL WAS STOPPED | | AND Rx VESSEL WATER LEVEL WAS RESTORED TO NORMAL LEVEL WITHIN A FEW | | MINUTES. NORMAL Rx VESSEL WATER LEVEL IS BEING MAINTAINED WITH THE MAIN | | FEEDWATER SYSTEM. | | | | THE PLANT IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE Rx VESSEL WATER INJECTION AND | | THE POST SCRAM PLANT RESPONSE. | | | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1748 BY PAUL KIEL ENTERED BY HOO JOLLIFFE * * * | | | | AT 1702, LICENSEE STARTED THE Rx RECIRC PUMPS AND TERMINATED THE UNUSUAL | | EVENT. LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS, THE NRC RESIDENT | | INSPECTOR, AND THE PROVINCE OF ONTARIO. | | | | HOO NOTIFIED R3DO GARDNER, NRR EO HOLAHAN, FEMA CARR OF THE TERMINATION OF | | THE UNUSUAL EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28655 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/09/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/09/95 | +------------------------------------------------+EVENT TIME: 13:25[CDT]| |NRC NOTIFIED BY: G. DEMPSEY, SECURITY SUP |LAST UPDATE DATE: 04/09/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SECURITY GUARD (LICENSEE EMPLOYEE) TAKEN TO LOCAL HOSPITAL FOR | | EVALUATION. COMPENSATORY MEASURES TAKEN. SEE HOO LOG FOR DETAILS. | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+