U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/24/97 - 10/27/97 ** EVENT NUMBERS ** 32993 33140 33141 33142 33143 33144 33145 33146 33147 33148 33149 33150 33151 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32993 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 09/26/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 13:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/26/97 | +------------------------------------------------+EVENT TIME: 12:00[CDT]| |NRC NOTIFIED BY: CHARLES COTTON |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |ACNC 50.72(b)(1)(ii)(C) COND OUTSIDE EOPS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THEY DO NOT HAVE SAFETY RELATED CONTAINMENT | | RECIRCULATION COOLER FANS AS REQUIRED. | | | | THE WESTINGHOUSE OWNERS GROUP GENERIC GUIDELINES FOR EMERGENCY RESPONSE | | ASSUMES THAT SAFETY RELATED CONTAINMENT RECIRC COOLER FANS MIX THE | | CONTAINMENT AIR VOLUME. IT WAS DISCOVERED THAT THE PLANT DOES NOT HAVE | | SAFETY RELATED CONTAINMENT RECIRC FANS AND THE DESIGN DOCUMENTS DEPEND ON | | CONTAINMENT SPRAY TO MIX THE HYDROGEN IN THE CONTAINMENT AIR VOLUME. | | IN THE PLANT'S EMERGENCY RESPONSE GUIDELINES, THE CONTAINMENT SPRAY PUMPS | | ARE STOPPED BASED ON CONTAINMENT PRESSURE. PROCEDURE CHANGES HAVE BEEN | | INITIATED TO REMOVE THE STEPS WHICH SECURE THE CONTAINMENT SPRAY SYSTEMS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1645 EDT ON 10/24/97 FROM TIM CLOUSER TO S. SANDIN * * * | | | | "THIS IS A RETRACTION OF EVENT #32993 (1350 EDT ON SEPTEMBER 26, 1997). | | | | "THE SUBJECT EVENT WAS REPORTED TO THE NRC PURSUANT TO THE REQUIREMENTS | | OF 10CFR50.72(b)(1)(ii)(c) WHICH STATES IN PART '...A CONDITION NOT | | COVERED BY THE PLANT OPERATING AND EMERGENCY PROCEDURES.' SINCE THE PLANT | | WAS NOT IN A CONDITION WHICH REQUIRED THESE PROCEDURES, THE REPORT OF | | 10CFR50.72(b)(1)(ii)(c) WAS SUBSEQUENTLY DETERMINED TO NOT BE APPLICABLE | | TO THIS CONDITION (NUREG-1022 SECOND DRAFT REV. 1 PAGE 38). | | | | "IT WAS DETERMINED THAT ALTHOUGH THE EMERGENCY RESPONSE PROCEDURES LACKED | | PRESCRIPTIVE GUIDANCE TO CONTINUE THE OPERATION OF THE SPRAY PUMPS WHICH | | WAS INCONSISTENT WITH THE DESCRIPTION PROVIDED IN THE FSAR, CPES HAD | | ADEQUATE PROCEDURAL GUIDANCE AND DESIGN CONSIDERATION TO ENSURE ADEQUATE | | MIXING OF HYDROGEN INSIDE THE CONTAINMENT POST-LOCA. THESE INCLUDE: | | | | (1) AT THE POINT IN THE ACCIDENT WHEN THE OPERATOR IS DIRECTED TO SECURE | | THE CONTAINMENT SPRAY PUMPS, THE ELECTRIC HYDROGEN RECOMBINERS WOULD HAVE | | BEEN PLACED IN SERVICE PER EOP-1.0, LOSS OF REACTOR OR SECONDARY COOLANT, | | OR FRZ-0.1, RESPONSE TO HIGH CONTAINMENT PRESSURE: | | | | (2) CONTAINMENT HYDROGEN MONITORS WOULD BE AVAILABLE TO THE OPERATOR TO | | MONITOR HYDROGEN CONCENTRATION INSIDE CONTAINMENT WITHIN 30 MINUTES INTO AN | | EVENT. EMERGENCY PROCEDURES DIRECT THE OPERATOR TO MONITOR HYDROGEN | | CONCENTRATION. IN ADDITION, THERE IS AN ANNUNCIATOR TO ALERT THE OPERATOR | | WHEN CONTAINMENT HYDROGEN CONCENTRATION REACHES 3% (WET) VOLUME PERCENT. | | BASED ON CONTAINMENT CONDITIONS, THE OPERATOR IS DIRECTED TO PLACE THE | | ELECTRIC HYDROGEN RECOMBINERS IN SERVICE, PLACE THE HYDROGEN PURGE SUPPLY | | AND EXHAUST SYSTEM IN SERVICE, OR TO CONSULT THE PLANT STAFF FOR ADDITIONAL | | RECOVERY ACTIONS. THE HYDROGEN MONITORS ARE QUALIFIED FOR ACCIDENT | | CONDITIONS. | | | | (3) EOP-0.0A [EOP-0.0B] PROVIDES GUIDANCE ON POST-SAFETY INJECTION SYSTEM | | ALIGNMENT. THE OPERATOR IS DIRECTED TO RESTORE CONTAINMENT VENTILATION | | FANS. ALTHOUGH THE CONTAINMENT VENTILATION FANS ARE NOT SAFETY RELATED, | | THE FANS WOULD PROVIDE FORCED CIRCULATION FOR HYDROGEN MIXING. | | | | (4) DESIGN BASIS DOCUMENTS STATE THAT COMPLETE MIXING SHOULD OCCUR WITHIN | | A FEW MINUTES FOLLOWING A LOCA WITH THE CONTAINMENT SPRAY OPERATION. | | ALTHOUGH CONTAINMENT SPRAY OPERATION MAINTAINS THE MIXING BY ENHANCING | | NATURAL CIRCULATION, MIXING INSIDE CONTAINMENT IS PROVIDED THROUGH VARIOUS | | OTHER METHODS AS DOCUMENTED IN THE DESIGN DOCUMENTS AND FSAR: | | | | - MOMENTUM TRANSFER FROM THE FLUID JET EXITING THE BREAK WILL RESULT IN | | GOOD COMPARTMENT MIXING; | | | | - NATURAL CONVECTION CAUSES GOOD MIXING IN A LARGE VESSEL DUE TO THE | | PRESENCE OF LARGE HEAT SINKS SUCH AS INTERNAL WALLS AND THE PRESENCE OF | | LOCALIZED HEAT SOURCES; | | | | - NATURAL CONVECTION FLOWS WILL BE DEVELOPED DUE TO THE BREAK EFFLUENT | | AFTER COMPLETION OF THE BLOWDOWN PERIOD; | | | | - MOLECULAR DIFFUSION DUE TO CONCENTRATION GRADIENTS; | | | | - SUBCOMPARTMENTS ARE PROVIDED WITH VENTS TO AID IN HYDROGEN MIXING AND TO | | AVOID HIGH CONCENTRATION POCKETS OF HYDROGEN. THESE VENTS CAUSE A STACK | | EFFECT WHICH MAINTAINS THE SUBCOMPARTMENTS AT VIRTUALLY THE SAME HYDROGEN | | CONCENTRATION AS THE REMAINDER OF THE CONTAINMENT; AND | | | | - OPENINGS ARE PROVIDED BETWEEN THE FLOORS TO AVOID ACCUMULATION OF | | HYDROGEN BETWEEN FLOORS TO PERMIT MIXING WITH THE BULK CONTAINMENT. | | | | "SINCE THE REQUIREMENTS OF 10CFR50.72(b)(1)(ii)(c) WAS DETERMINED TO NOT BE | | APPLICABLE TO THIS CONDITION, SECTION 10CFR50.72(b)(2)(iii) REPORTING | | REQUIREMENT FOR 'ANY EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE | | FULFILLMENT OF THE SAFETY FUNCTION OF STRUCTURES OR SYSTEMS...' WAS | | REVIEWED FOR THIS CONDITION. THE REQUIREMENT FOR HYDROGEN MIXING, BASED ON | | ENGINEERING JUDGMENT AND THE ABOVE DISCUSSION, WAS ADDRESSED WITH ADEQUATE | | PROCEDURAL GUIDANCE AND DESIGN CONSIDERATIONS. THEREFORE, THIS CONDITION | | IS NOT CONSIDERED REPORTABLE PURSUANT TO 10CFR50.72 OR 10CFR50.73." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED THE R4DO (DALE POWERS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33140 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/24/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 02:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 00:08[EDT]| |NRC NOTIFIED BY: ACKERMAN |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT VENTILATION ISOLATION. | | | | A CONTAINMENT VENTILATION ISOLATION OCCURRED DUE TO A HIGH FAILURE OF THE | | UPPER CONTAINMENT AREA RADIATION MONITOR "VRS2101". THERE WAS NO | | INDICATION OF HIGH RADIATION ON ANY OTHER RADIATION MONITORS; THEREFORE, | | THE ACTUATION SIGNAL IS CONSIDERED TO BE INVALID. CONTAINMENT PURGE WAS | | IN SERVICE AT THE TIME OF THE ACTUATION. THE CONTAINMENT VENTILATION | | ISOLATION VALVES ARE CURRENTLY CLOSED, AND WILL REMAIN SO UNTIL | | TROUBLESHOOTING AND NECESSARY REPAIRS ARE COMPLETED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33141 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 10/24/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 10:24 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 05:30[CDT]| |NRC NOTIFIED BY: DAVE DEES |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 +------------------------------------------------------------------------------+ | LOCAL LEAK RATE TEST OF CONTAINMENT PENETRATION EXCEEDED ALLOWABLE LIMIT. | | | | RESULTS OF A LOCAL LEAK RATE TEST PERFORMED ON CONTAINMENT PENETRATION #28 | | (VALVES #EFHV-32 AND #EFHV-34) EXCEEDED THE ALLOWABLE LEAKAGE RATE. THIS | | CONDITION RESULTED IN TOTAL CONTAINMENT INTEGRATED LEAKAGE EXCEEDING THE | | USAR LIMIT OF 0.6 La. THE LICENSEE PLANS TO CONDUCT FURTHER TESTING TO | | DETERMINE THE LEAKAGE RATES OF THE TWO VALVES INDIVIDUALLY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33142 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 10/24/97 | |UNIT: [1] [ ] [ ] STATE: MD |NOTIFICATION TIME: 10:57 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 09:30[EDT]| |NRC NOTIFIED BY: TOM O'MEARA |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO LOSS OF MAIN CONDENSER VACUUM. | | | | AN AUTOMATIC TURBINE TRIP/REACTOR TRIP OCCURRED WHEN THE MAIN CONDENSER | | VACUUM BREAKER WAS INADVERTENTLY OPENED. ALL CONTROL RODS INSERTED AND | | ALL SYSTEMS FUNCTIONED, AS EXPECTED. OPERATORS MANUALLY STARTED THE | | AUXILIARY FEEDWATER SYSTEM IN ANTICIPATION OF AN AUTOMATIC START SIGNAL. | | UNIT 1 IS CURRENTLY STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE REPORTED THAT, AT THE TIME OF THE EVENT, MAINTENANCE ACTIVATES | | WERE UNDERWAY IN AN ELECTRICAL CUBICLE DIRECTLY ABOVE THE CONTROLS FOR | | THE MAIN CONDENSER VACUUM BREAKER. THE LICENSEE SPECULATES THAT A WORKER | | INADVERTENTLY OPERATED THE (MOMENTARY CONTACT) SWITCH, CAUSING THE CONTROL | | CIRCUITRY TO SEAL IN AN OPEN SIGNAL, AND CAUSING A LOSS OF MAIN CONDENSER | | VACUUM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33143 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/24/97 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 12:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 08:32[PDT]| |NRC NOTIFIED BY: DAVID PIERCE |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STU RICHARDS, NRR EO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION |RICE FEMA | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOE GIITTER IRD | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO AUTO REACTOR TRIP & SAFETY INJECTION TO RCS. | | | | AT 0832 PDT, AN AUTO REACTOR TRIP AND SAFETY INJECTION OCCURRED DUE TO | | SENSED LOW MAIN STEAM LINE PRESSURE CAUSED BY AN INADVERTENT CLOSURE | | OF THE #44 MAIN STEAM ISOLATION VALVE (MSIV). FOLLOWING THE TRIP, | | ALL CONTROL RODS FULLY INSERTED AND ALL SYSTEMS FUNCTIONED AS REQUIRED. ALL | | THREE AUXILIARY FEEDWATER (AFW) PUMPS AUTOMATICALLY STARTED AND INJECTED | | INTO THE STEAM GENERATORS. THE SAFETY INJECTION WAS TERMINATED AFTER 16 | | MINUTES AND NORMAL REACTOR COOLANT SYSTEM (RCS) LETDOWN WAS REESTABLISHED | | WITHIN THE FOLLOWING 10 MINUTES. UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). | | | | FOLLOWING THE MSIV CLOSURE, THE ATMOSPHERIC DUMP VALVE FOR THE #4 STEAM | | GENERATOR OPENED FOR A SHORT TIME. ADDITIONALLY, THE PRESSURIZER POWER | | OPERATED RELIEF VALVE, #PCV-456, LIFTED NUMEROUS TIMES DUE TO RCS PRESSURE | | RECOVERY FOLLOWING A LARGE INJECTION OF WATER TO THE STEAM GENERATORS VIA | | THE AFW SYSTEM. BOTH VALVES HAVE PROPERLY RESEATED. | | | | THE CAUSE OF THE EVENT WAS A CONTRACTOR REMOVING SCAFFOLDING FROM THE | | VICINITY OF THE #44 MSIV, SOMEHOW CAUSING IT TO CLOSE. THE LICENSEE IS | | INVESTIGATING THE DETAILS OF THIS EVENT. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE DECLARATION OF THE UNUSUAL EVENT. | | | | * * * UPDATE AT 1258 ON 10/24/97 FROM PIERCE TAKEN BY STRANSKY * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0938 PDT. ALL PRIMARY | | SYSTEMS FUNCTIONED AS EXPECTED, BUT SEVERAL SMALL LEAKS WERE DETECTED | | IN SECONDARY SYSTEMS FOLLOWING THE REACTOR TRIP. UNIT 2 IS STABLE IN | | MODE 3 (HOT STANDBY). | | | | THE LICENSEE ISSUED A PRESS RELEASE. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE TERMINATION OF THE UNUSUAL EVENT. | | | | THE OPERATIONS OFFICER NOTIFIED R4DO (DALE POWERS), NRR EO (STU RICHARDS), | | AND FEMA (RICE) OF THE TERMINATION OF THE UNUSUAL EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33144 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CONVAL, INC. |NOTIFICATION DATE: 10/24/97 | | CITY: SOMERS REGION: 1 |NOTIFICATION TIME: 14:09 [ET]| | COUNTY: TOLLAND STATE: CT |EVENT DATE: 10/24/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/24/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CURTIS COWGILL RDO | | | | +------------------------------------------------+GEOFFREY WRIGHT RDO | |NRC NOTIFIED BY: EDWARD N. SHARPLESS |VERN HODGE NRR | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10CFR21 REPORT - | | | | FIVE (5) CONVAL FORGED VALVE BODIES 1"-1500# DESIGN, #5, Y-GLOBE, STOP AND | | CHECK VALVE, WHICH ARE IDENTIFIED BY CONVAL'S BASIC FIG. # 1.00-12G2J-S165F | | AND FIG. # 1.00-12C2-S165F SUPPLIED TO BOTH MAINE YANKEE ATOMIC POWER (3 | | VALVES) AND INDIANA & MICHIGAN POWER (D.C. COOK 1 & 2) (2 VALVES) MAY HAVE | | A DEFECT RELATED TO A POSSIBLE CRACK WITHIN THE FORGING WALL AT THE DIE | | FLASH LINE. ONLY ONE OF THE FIVE VALVES IS KNOWN TO BE INSTALLED AT THE | | D.C. COOK SITE. THE FORGINGS FOR THESE FIVE VALVES ARE IDENTIFIED AS IDEAL | | FORGE HEAT CODE LOT "M7", WHICH IS STAMPED ON EACH BODY FORGING. CONVAL | | DISCOVERED THE FORGING DEFECT DURING AN INVESTIGATION OF A VALVE RETURNED | | BY A CUSTOMER. IDEAL HAS TAKEN CORRECTIVE ACTION TO ELIMINATE THE | | PROCESSING PROBLEMS. THE AFFECTED NUCLEAR POWER PLANTS HAVE BEEN NOTIFIED | | BOTH VERBALLY AND IN WRITING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33145 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/24/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 14:45[CDT]| |NRC NOTIFIED BY: DAVID A. SCHULLER |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A MISSED SURVEILLANCE IN 1996 WHICH RENDERED A SAFETY | | INJECTION TRAIN INOPERABLE. | | | | "DURING THE PERFORMANCE OF A QUALITY SITE ASSURANCE INSERVICE TESTING (QSA | | IST) AUDIT, IT WAS IDENTIFIED THAT 2-MOV-SI-8923A BECAME INOPERABLE ON | | 4/8/96 WHEN THE VALVE EXCEEDED THE REQUIRED TECHNICAL SPECIFICATION | | SURVEILLANCE PERIODICITY INCLUDING THE ALLOWED 25% GRACE PERIOD. THIS | | RENDERED THE '2A' SAFETY INJECTION PUMP INOPERABLE. 2-MOV-SI-8923A WAS | | SUBSEQUENTLY TESTED SATISFACTORILY ON 5/29/96. 2-MOV-SI-8923A IS REQUIRED | | TO BE TESTED QUARTERLY PER TS 4.0.5. THEREFORE, DURING A PERIOD OF 4/8/96 | | THROUGH 5/29/96, UNIT 2 OPERATED WITH A SINGLE OPERABLE SAFETY INJECTION | | TRAIN." | | | | 2-MOV-SI-8923A, WHICH IS THE SUCTION VALVE FOR THE '2A' SI PUMP, WAS NOT | | STROKE TIME TESTED AS REQUIRED PER TS. THE LICENSEE HAS THE ROOT CAUSE | | UNDER INVESTIGATION AND HAS INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33146 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/24/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/23/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/24/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT RDO | | DOCKET: 0707002 |JOHN GREEVES,NMSS EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: JOHN JORDAN | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PORTSMOUTH GDP REPORTED UNDER 24-HOUR BULLETIN 91-01 A CELL WAS LOWER THAN | | THE MINIMUM SAFE TEMPERATURE. | | | | "AT 1800 HOURS ON 10/23/97 AND 0356 HOURS ON 10/24/97, OPERATIONS PERSONNEL | | DISCOVERED THAT CELL 31-2-10, LOCATED IN THE X-330 PROCESS BUILDING HAD | | CELL COOLANT TEMPERATURES WHICH WERE LOWER THAN THE MINIMUM SAFE | | TEMPERATURE AS DEFINED IN NCSA-0330-004-A00. THIS NON-COMPLIANCE | | CONSTITUTES THE LOSS OF ONE (1) NUCLEAR CRITICALITY SAFETY CONTROL IN A TWO | | (2) CONTROL SYSTEM. THE CONTROL WHICH WAS VIOLATED (MINIMUM CELL COOLANT | | TEMPERATURE) IS IN PLACE TO PREVENT A FREEZE-OUT OF UF6 MATERIAL. THERE IS | | NO EVIDENCE OF UF6 FREEZE-OUT OR FORMATION OF DEPOSITS IN ANY OF THE CELL | | AS A RESULT OF THE NCSA NONCOMPLIANCE. THERE WAS NO RELEASE OF HAZARDOUS | | MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE ASSOCIATED WITH THIS | | EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE RELATED EVENT #33134. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33147 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/24/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/23/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/24/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT RDO | | DOCKET: 0707002 |JOHN GREEVES, NMSS EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM AUTOCLAVE DECLARED INOPERABLE DUE TO FAILURE OF UF6 CYLINDER HIGH | | PRESSURE AUTOCLAVE STEAM SHUTOFF. | | | | "AT 1800 HOURS ON 10/23/97, ENGINEERING DETERMINED THAT A COMPONENT WITHIN | | THE UF6 CYLINDER PRESSURE LOOP HAD FAILED, RENDERING THE UF6 CYLINDER HIGH | | PRESSURE AUTOCLAVE STEAM SHUTOFF INOPERABLE. THE UF6 CYLINDER HIGH | | PRESSURE AUTOCLAVE STEAM SHUTOFF IS REQUIRED TO BE OPERABLE PER TSR | | 2.1.3.2A. THE AUTOCLAVE REMAINS INOPERABLE PENDING MAINTENANCE | | DETERMINATION OF WHAT COMPONENT FAILED. | | | | "THIS FAILURE WAS ASSOCIATED WITH AN AUTOCLAVE #7 FALSE STEAM SHUTDOWN | | ALARM WHICH OCCURRED AT 0635 HOURS ON 10/22/97 IN THE X-343 FEED AND | | SAMPLING FACILITY. AT THE TIME OF THE FALSE ACTIVATION, IT WAS NOT KNOWN | | THAT THE FAILED COMPONENT WHICH CAUSED THE FALSE ACTIVATION ALSO CAUSED THE | | UF6 CYLINDER HIGH PRESSURE AUTOCLAVE STEAM SHUTOFF TO BE INOPERABLE. | | | | "THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION | | EXPOSURE ASSOCIATED WITH THIS EVENT. THIS EVENT IS BEING REPORTED PER | | NUCLEAR REGULATORY EVENT PROCEDURE UE2-RA-RE1030, APP. D CRITERIA J, | | PARAGRAPH 4A (CFR SECTION 76.120[c][2][i])." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33148 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 10/24/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 22:10 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 20:40[EDT]| |NRC NOTIFIED BY: DAN HUNT |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT HIGH PRESSURE COOLANT INJECTION (HPCI) SIGNAL INITIATED DURING | | MAINTENANCE DUE TO ELECTRICAL SHORT. | | | | "WHILE PERFORMING TROUBLESHOOTING ON 23PS-84B (HPCI PUMP LOW SUCTION | | PRESSURE SWITCH) FOR THE SOURCE OF A DC GROUND, A NUT WAS INADVERTENTLY | | PLACED ACROSS TWO HOT TEST POINTS IN JUNCTION BOX J.B.-R2550E. AT THIS | | POINT ANNUNCIATOR 09-3-3-4 ALARMED (HPCI TURBINE EXHAUST DIAPHRAGM PRESSURE | | HIGH) AND CLEARED AND ANNUNCIATOR 09-3-3-33 SEALED IN (HPCI ISOLATION TRIP | | INITIATED). FUSES PULLED IN THE 'B' HPCI LOGIC PREVENTED THE ACTUAL | | ISOLATION FROM OCCURRING. AFFECTED ISOLATION VALVES WERE MANUALLY ENSURED | | CLOSED AND I&C TROUBLESHOOTING WAS HALTED." | | | | THE HPCI SYSTEM WAS REMOVED FROM SERVICE ON 10/22/97 FOR MAINTENANCE | | PLACING THE UNIT IN A 7 DAY LCO ACTION STATEMENT. THE LICENSEE IS | | CONDUCTING A ROOT CAUSE INVESTIGATION. THERE IS NO INDICATION OF DAMAGE | | CAUSED BY THE ELECTRICAL SHORT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33149 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 10/24/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 22:43 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 19:19[EDT]| |NRC NOTIFIED BY: MIKE MICKLOW |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 +------------------------------------------------------------------------------+ | EXPECTED CONTAINMENT VENTILATION ISOLATION DURING REMOVAL OF INSERTS OFF | | STEAM GENERATOR PRIMARY MANWAYS. | | | | "AT 1919 CONTROL ROOM OPERATORS RECEIVED MAIN CONTROL BOARD (MCB) ALARM | | A-25, CONTAINMENT VENTILATION ISOLATION (CVI), DUE TO HIGH RADIATION ON | | R-12 (CONTAINMENT GAS MONITOR). THE CVI WAS A VALID SIGNAL DUE TO HIGH | | RADIATION IN CONTAINMENT ASSOCIATED WITH REMOVING INSERTS OFF THE STEAM | | GENERATOR PRIMARY MANWAYS. THE PLANT IS CURRENTLY IN MODE 6 FOR A | | REFUELING OUTAGE, WITH LOOP LEVELS OF APPROXIMATELY 17 INCHES AND AVERAGE | | CORE EXIT THERMOCOUPLE TEMPERATURES OF 111øF. THE HIGH RADIATION IN | | CONTAINMENT WAS ANTICIPATED DUE TO INDICATIONS OF FUEL ROD DEGRADATION ON | | AN ESTIMATED 3 FUEL RODS. ALL AUTOMATIC ACTIONS OF CVI OCCURRED AS | | REQUIRED AND WERE VERIFIED AT APPROXIMATELY 1920. IN ANTICIPATION OF | | INSERT REMOVAL, NON-ESSENTIAL PERSONNEL WERE INHIBITED FROM CONTAINMENT | | ENTRY. EFFLUENT MONITOR SETPOINTS ARE DETERMINED AND CONSERVATIVELY SET | | USING THE METHODS PROVIDED IN THE OFFSITE DOSE CALCULATION MANUAL (ODCM) TO | | PRECLUDE EXCEEDING THE RELEASE LIMITS OF 10CFR50, APPENDIX I." | | | | THE R-12 RADIATION MONITOR SETPOINT WAS 25,000 COUNTS PER MINUTE WHICH | | CORRESPONDS TO LESS THAN 1 mr/HR. THE CVI WAS RESET AT 2125 EDT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33150 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 10/25/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 05:30 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/25/97 | +------------------------------------------------+EVENT TIME: 04:04[CDT]| |NRC NOTIFIED BY: BILL GULDEMAN |LAST UPDATE DATE: 10/25/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 10 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL REACTOR TRIP FROM 1O% POWER DUE TO FOUR DROPPED CONTROL RODS - | | | | WHILE SHUTTING UNIT 2 DOWN TO COMMENCE ITS THIRD REFUELING OUTAGE, THE | | CONTROL ROOM RECEIVED A ROD CONTROL URGENT FAILURE ALARM WHEN CONTROL | | BANK 'C' BEGAN TO INSERT INTO THE CORE. TECHNICIANS WERE TROUBLESHOOTING | | THE PROBLEM WHEN FOUR CONTROL BANK 'C', GROUP 2 CONTROL RODS DROPPED. | | ONE CONTROL ROD FULLY INSERTED AND THE OTHER THREE CONTROL RODS PARTIALLY | | INSERTED INTO THE CORE. | | | | AT 0404 CDT, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR AND | | MANUALLY STARTED THE AUXILIARY FEEDWATER PUMPS. ALL CONTROL RODS INSERTED | | COMPLETELY INTO THE CORE. DECAY HEAT IS BEING REMOVED WITH STEAM GENERATOR | | BLOWDOWN. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND IS INVESTIGATING THE | | CAUSE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/25/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:27 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/25/97 | +------------------------------------------------+EVENT TIME: 14:09[EDT]| |NRC NOTIFIED BY: PHILIP CHASE |LAST UPDATE DATE: 10/25/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE FOLLOWING | | SURVEILLANCE TESTING. | | | | "DURING PERFORMANCE OF ST-6-055-200-1, 'HPCI VALVE TEST', ON INCREASED | | FREQUENCY , THE HV-055-1F072, 'HPCI TURBINE EXHAUST VALVE', FAILED TO | | CLOSE IN THE REQUIRED TIME INTERVAL. UNIT 1 HPCI WAS DECLARED INOPERABLE | | AT 1409 EDT ON 10/25/97 AFTER CLOSING THE INOPERABLE PRIMARY CONTAINMENT | | ISOLATION VALVE. THE INOPERABLE PRIMARY CONTAINMENT ISOLATION VALVE | | WAS CLOSED TO MEET THE REQUIREMENTS OF TECHNICAL SPECIFICATION 3.6.3. | | ENGINEERING IS CURRENTLY PURSUING THIS PROBLEM. UNIT 1 RCIC, CORE SPRAY, | | LPCI AND ADS REMAIN OPERABLE AT THIS TIME." | | | | WITH HPCI INOPERABLE, THIS PLACES UNIT 1 IN A 14 DAY LCO. THE LICENSEE | | NOTED THAT THE VALVE TRIPPED ON THERMAL OVERLOAD AFTER WAITING | | APPROXIMATELY 6 MINUTES. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+