U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/28/98 - 05/29/98 ** EVENT NUMBERS ** 34232 34293 34294 34295 34296 34297 34298 34299 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34232 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 05/14/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 13:37 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 05/14/98 | +------------------------------------------------+EVENT TIME: 10:15[EDT]| |NRC NOTIFIED BY: TIM CHAMBERS |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF THE ANTICIPATORY REACTOR TRIP SYSTEM (OPENING OF THE CONTROL | | ROD DRIVE BREAKERS) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "IN PREPARATION FOR PLANT STARTUP FOLLOWING THE REFUELING OUTAGE, THE | | CONTROL ROD DRIVE (CRD) BREAKERS TRIPPED OPEN. THIS OCCURRED WHEN VACUUM | | WAS PLACED ON [THE] #2 MAIN FEEDWATER PUMP TURBINE (MFPT), WHICH ENABLED | | THE MFP VACUUM TRIPS. AT THIS TIME, A VACUUM LEAK WAS FOUND ON [THE] #2 | | MFPT, AND THE MFPT WAS ISOLATED FROM THE CONDENSER CAUSING THE ANTICIPATORY | | REACTOR TRIP SYSTEM (ARTS) TO ACTUATE AND OPERATE THE CRD BREAKERS. THE | | CRD BREAKERS WERE DISCONNECTED FROM THE CRDs VIA DISCONNECT SWITCHES [PRIOR | | TO THE EVENT], AND NO CONTROL ROD MOVEMENT OCCURRED OR WAS REQUIRED AT THIS | | TIME." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION 0915 5/28/98 FROM WOLF TAKEN BY STRANSKY * * * | | | | AFTER REVIEW OF THE UFSAR, THE LICENSEE HAS DETERMINED THAT THE CONTROL ROD | | DRIVE SYSTEM, INCLUDING THE CRD BREAKERS, IS NOT DEFINED AS PART OF THE | | REACTOR PROTECTION SYSTEM. FURTHER, THE ANTICIPATORY REACTOR TRIP SYSTEM IS | | NOT DEFINED AS AN ENGINEERED SAFETY FEATURE SYSTEM. THEREFORE, THE LICENSEE | | IS RETRACTING THIS EVENT NOTIFICATION. HOWEVER, THE LICENSEE PLANS TO | | SUBMIT A VOLUNTARY LER REGARDING THIS EVENT. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED. NOTIFIED R3DO (MADERA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34293 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 05/28/98 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 12:10 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/27/98 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: M. DAVID |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 24-HOUR NOTIFICATION PER CONDITION OF LICENSE AS REQUIRED BY TECH SPECS | | | | SECTION 2G OF THE SEABROOK STATION OPERATING LICENSE REQUIRES THE REPORTING | | OF VIOLATIONS OF SECTION 2C OF THE LICENSE WITHIN 24 HOURS. ONE OF THE | | CONDITIONS STATES THAT THE FACILITY SHALL BE OPERATED IN ACCORDANCE WITH | | THE TECHNICAL SPECIFICATIONS (TECH SPECS OR TS). | | | | IN ACTION PRECIPITATED FROM AN EARLIER EVENT REPORT, #34181 OF MAY 5, 1998, | | A REVIEW OF INSTRUMENTATION WAS UNDERTAKEN BY A TEAM. THE REVIEW TEAM | | DISCOVERED THAT THE STEAM GENERATOR PRESSURE PROTECTION CHANNEL CALIBRATION | | PROCEDURES DID NOT INCLUDE VERIFICATION OF THE RATE TIME CONSTANT VALUE OF | | THE NEGATIVE RATE-HIGH STEAM PRESSURE FUNCTION. THIS FUNCTION IS REQUIRED | | AS PART OF THE ENGINEERED SAFETY FEATURES DURING MODE 3 OPERATION BELOW THE | | P-11 PERMISSIVE SETPOINT. THE PLANT WAS LAST IN MODE 3 IN JANUARY, 1998. | | | | THE STEAM GENERATOR PRESSURE CHANNEL CALIBRATION PROCEDURES WILL BE REVISED | | TO INCLUDE VERIFICATION OF THE RATE TIME CONSTANT PORTION OF THE NEGATIVE | | RATE-HIGH STEAM PRESSURE RATE FUNCTION. THE INSPECTION OF ALL SAFETY | | RELATED RATE/LAG AND LEAD/LAG CIRCUITS HAS BEEN COMPLETED AND NO OTHER | | DISCREPANCIES WERE NOTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34294 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/28/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 12:15 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/28/98 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: R.S. FRANTZ |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 FINAL REPORT REGARDING WESTINGHOUSE MODEL DHP CIRCUIT | | BREAKER AUXILIARY SWITCH OPERATING ASSEMBLY ANOMALIES | | | | ON JANUARY 16, 1998, ILLINOIS POWER (IP) ISSUED 10CFR21 INTERIM REPORT | | 21-97-055 IN LETTER U-602910. THIS NOTIFIED THE NRC THAT AN EVALUATION | | UNDER THE PROVISIONS OF PART 21 OF 10CFR WAS NOT COMPLETE FOR ANOMALIES IN | | SAFETY-RELATED WESTINGHOUSE MODEL DHP CIRCUIT BREAKER AUXILIARY SWITCH | | OPERATING ASSEMBLIES. IP PROVIDED AN UPDATE IN LETTER U-602968 ON MARCH | | 24, 1998 TO THE NRC. IP HAS COMPLETED THE EVALUATION OF THIS ISSUE AND | | CONCLUDES THAT IT SHOULD BE REPORTED UNDER THE PROVISIONS OF 10CFR21. THE | | BASIS FOR THIS CONCLUSION IS THAT THE ANOMALIES COULD CAUSE A FAILURE OF | | THE AUXILIARY SWITCH OPERATING ASSEMBLY DURING BREAKER OPERATION, RESULTING | | IN LOSS OF THE BREAKER SAFETY FUNCTION. | | | | THE ANOMALIES INCLUDED FOUR CASES OF BENT AUXILIARY SWITCH LINK AND TWO | | CASES OF MISSING "E" CLIPS. THE BASIC COMPONENT INVOLVED IN THIS CONDITION | | IS THE AUXILIARY SWITCH OPERATING ASSEMBLY, INCLUDING THE AUXILIARY | | SWITCHES, THE OPERATING LINK, AND THE OPERATING CAM (IF APPLICABLE), FOR | | WESTINGHOUSE MODEL DHP 4160-VOLT AND 6900-VOLT CIRCUIT BREAKERS. THE | | ASSEMBLY WAS SUPPLIED BY WESTINGHOUSE, PITTSBURGH, PA, AS PART OF MODEL DHP | | CIRCUIT BREAKERS. | | | | CLINTON POWER STATION HAS 43 DHP BREAKERS INSTALLED IN SAFETY-RELATED | | APPLICATIONS AND 2 SPARE SAFETY-RELATED DHP BREAKERS POTENTIALLY AFFECTED | | BY THE AUXILIARY SWITCH OPERATING ASSEMBLY DEFICIENCIES. DHP CIRCUIT | | BREAKERS WILL BE INSPECTED AND REWORKED/REFURBISHED AS NECESSARY PRIOR TO | | STARTUP FROM THE CURRENT OUTAGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 05/28/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 13:08 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 05/27/98 | | LEU FABRICATION |EVENT TIME: 14:00[EDT]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 05/28/98 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |KENNETH BARR RDO | | DOCKET: 07001113 |DON COOL EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: LON E. PAULSON | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BULLETIN 91-01 24-HOUR REPORT, LOSS OF ONE OF TWO CRITICALITY CONTROLS | | | | DURING A REVIEW OF SCALE MAINTENANCE RECORDS, IT WAS DISCOVERED THAT A LOSS | | OF ONE OF TWO CRITICALITY CONTROLS TOOK PLACE WHEN AN OPERATOR MADE AN | | ADDITION OF MATERIAL ADDITIVE TO A PRODUCTION UO2 TUMBLER. THE PROCEDURE | | HAS AN ADMINISTRATIVE CONTROL FOR TWO INDEPENDENT SCALE MEASUREMENTS | | (PROCESS SCALE AND ACCOUNTABILITY SCALE) TO VERIFY ADDITIVE WEIGHT FOR THE | | CRITICALITY SAFETY BASIS. THE PROCESS SCALE WAS TAGGED OUT FOR MAINTENANCE | | AND THE OPERATOR MADE UP THE REQUIRED ADDITIVE USING ONLY THE | | ACCOUNTABILITY SCALE. | | | | THE AMOUNT OF MATERIAL ADDED TO THE TUMBLER WAS WITHIN ESTABLISHED | | MODERATION LIMITS, THEREFORE NO UNSAFE CONDITION EXISTED. CONTROLS WERE | | REESTABLISHED WITHIN 4 HOURS. DCP TUMBLING ACTIVITIES WERE SHUT DOWN | | PENDING INVESTIGATIONS AND IMPLEMENTATION OF CORRECTIVE ACTIONS. | | | | GE NUCLEAR ENERGY PLANS TO INFORM LOCAL/STATE AUTHORITIES AND NRC REGION 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34296 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/28/98 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 13:20 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/28/98 | +------------------------------------------------+EVENT TIME: 10:04[EDT]| |NRC NOTIFIED BY: TOM McKEE |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 1 OF 3 EDGs STARTED; DECLARED INOPERABLE WHEN MCC STRIPPED UNEXPECTEDLY - | | | | A CONTRACTOR BUMPED INTO THE CONTROL SWITCH FOR THE NORMAL SUPPLY BREAKER | | TO 480 VOLT SAFEGUARDS BUS #6A, CAUSING EMERGENCY DIESEL GENERATOR (EDG) | | #32 TO START ON A NON-SAFETY INJECTION BLACKOUT SIGNAL AND AUTOMATICALLY | | CONNECT TO SAFEGUARDS BUS #6A. EDG LOADS STRIPPED, AS EXPECTED, AND THE | | FOLLOWING PUMPS STARTED: SERVICE WATER PUMP #36, COMPONENT COOLING WATER | | PUMP #33, STEAM DRIVEN AUXILIARY BOILER FEEDWATER PUMP #32, MOTOR DRIVEN | | AUXILIARY BOILER FEEDWATER PUMP #33 (MOTOR DRIVEN AUXILIARY BOILER | | FEEDWATER PUMP #32 IS IN STANDBY MODE). MOTOR CONTROL CENTER (MCC) #36D, | | WHICH SUPPLIES POWER TO EDG SUPPORT EQUIPMENT THAT IS NOT IMMEDIATELY | | REQUIRED FOR EDG OPERABILITY (i.e., EXHAUST FANS #316 AND #317, CRANKCASE | | EXHAUSTER AND FUEL OIL TRANSFER PUMP), STRIPPED WHEN IT WAS SUPPOSED TO | | STAY ENERGIZED. | | | | CONTROL ROOM OPERATORS MANUALLY ENERGIZED MCC #36D, RESTORED SAFEGUARDS | | BUS #6A TO NORMAL SUPPLY, AND STOPPED EDG #32 AND PLACED IT IN AUTOMATIC. | | | | THE LICENSEE DECLARED EDG #32 INOPERABLE, EVEN THOUGH IT IS FUNCTIONAL, | | AND IS INVESTIGATING THE CAUSE OF MCC #36D STRIPPING. TECH SPEC LCO A/S | | 3.7.A.5 REQUIRES THE LICENSEE TO RESTORE THE INOPERABLE EDG TO OPERABLE | | STATUS WITHIN 72 HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE ON 5/28/98 @ 1955 BY LONG TO GOULD *** | | | | THE LICENSEE IS CURRENTLY INVESTIGATING WHETHER MCC "36D" STRIPPED BECAUSE | | THE LEADS WHICH OPEN THE FEED BREAKER ON AN UNDERVOLTAGE CONDITION WERE NOT | | REMOVED WHEN THE BREAKER WAS INSTALLED DURING THE LAST REFUELING OUTAGE. | | CORRECTIVE ACTION WAS TAKEN TO ENSURE THE CONTINUED OPERABILITY OF EDG 32 | | AND EDG 33 WHOSE SUPPORT SYSTEMS ARE POWERED BY MCC "36E" WHICH WAS ALSO | | ADDED DURING THE REFUEL OUTAGE. A TEMPORARY PROCEDURE CHANGE IS BEING MADE | | TO VERIFY THE MCC IS POWERED IF A HIGH TEMPERATURE ALARM IS RECEIVED IN THE | | CONTROL ROOM. A SHIFT ORDER HAS BEEN ISSUED TO INSTRUCT THE LICENSED | | CONTROL ROOM OPERATOR TO CLOSE THE BREAKER FOLLOWING A NON-SI STATION | | BLACKOUT. THE ABILITY OF THE OPERATOR TO CLOSE A BREAKER FROM THE CONTROL | | ROOM WAS TESTED. A DEDICATED NUCLEAR PLANT OPERATOR HAS BEEN STATIONED | | LOCALLY WITH INSTRUCTIONS TO CLOSE THE MCC BREAKERS FOLLOWING A LOSS OF | | OFFSITE POWER IF IT IS NOT CLOSED FROM THE CONTROL ROOM. MCC "36D" WAS | | MANUALLY CLOSED IN ABOUT 30 MINUTES AT THE BREAKER DURING THE EVENT. BASED | | ON THIS, THE LICENSEE DETERMINED THAT THE EDG SUPPORT SYSTEMS HAD BEEN | | DEGRADED BUT NOT INOPERABLE SINCE THE LAST REFUEL OUTAGE. ACTION TO ENSURE | | THE BREAKERS DO NOT STRIP IS BEING PLANNED. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | | | | THE REG 1 RDO(DURR) WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34297 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/28/98 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 17:31 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/28/98 | +------------------------------------------------+EVENT TIME: 16:50[EDT]| |NRC NOTIFIED BY: NEMCEK |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT DECLARED THEIR EMERGENCY OPERATIONS FACILITY (EOF) OUT OF SERVICE. | | | | THE EOF WAS TAKEN OUT OF SERVICE DUE TO PLANNED MAINTENANCE ON ELECTRICAL | | BUS "L20". THIS BUS SUPPLIES THE "H21" BUS WHICH IN TURN SUPPLIES THE EOF. | | SINCE NO POWER IS BEING SUPPLIED TO THE EOF IT WAS DECLARED OUT OF SERVICE. | | THE BACKUP EOF IS AVAILABLE IF NEEDED. THIS BUS OUTAGE WILL LAST UNTIL | | 0200 @ 5/31/98. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 05/28/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:57 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/28/98 | +------------------------------------------------+EVENT TIME: 13:12[CDT]| |NRC NOTIFIED BY: MATZKE |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT EXCEEDED ITS DESIGN PRESSURE FOR THE AUXILIARY FEEDWATER(AFW) PIPING. | | | | IN PREPARATION FOR POST MAINTENANCE TESTING (5/27/98), THE STEAM DRIVEN AFW | | PUMP (FW-10) WAS RUN TO AN OVERSPEED CONDITION RESULTING IN THE AFW | | DISCHARGE PRESSURE OF 1660 PSIG (2309 PSIG WAS SEEN BY PIPING). THE | | TURBINE OVERSPEED WAS TERMINATED MANUALLY. | | | | IN 1990 THE LICENSEE REPORTED AN OUTSIDE DESIGN BASIS PROBLEM (LER90-016) | | IN WHICH CERTAIN ACCIDENT SCENARIOS WERE WHERE A SINGLE ACTIVE FAILURE OF | | THE FW-10 RESULTED IN FAILURE OF THE COMMON LEG OF AFW PIPING DUE TO | | OVERPRESSURIZATION OF THE PIPING FROM FW-10. ANALYSIS EA-FC-90-028 (EFFECT | | OF SINGLE FAILURE OF FW-10 OVERSPEED LIMITING GOVERNOR) DETERMINED THAT THE | | PIPING FAILURE WOULD NOT OCCUR. A CRITICAL INPUT TO THIS ANALYSIS WAS | | WRITTEN COMMUNICATION WITH THE TURBINE VENDOR (COFFIN TURBO PUMP, INC.) | | THAT STATED THE TURBINE WOULD CATASTROPHICALLY FAIL IN A RANGE OF 10,200 | | RPM TO 10,500 RPM (ESTIMATED DISCHARGE PRESSURE OF 2235 PSIG). THE | | ANALYSIS CONCLUDED THAT THIS PRESSURE WOULD NOT CAUSE A PRESSURE BOUNDARY | | FAILURE IN THE AFW PIPING SYSTEM. THE TURBINE SPEED ON 5/27/98 IS | | ESTIMATED TO HAVE BEEN SLIGHTLY GREATER THAN 10,600 RPM AND IT APPEARS THAT | | A SINGLE ACTIVE FAILURE COULD RESULT IN OVERPRESSURIZATION OF THE AFW | | PIPING. THIS ISSUE IS BEING CONSERVATIVELY REPORTED, BUT IS STILL UNDER | | REVIEW. | | | | THE RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34299 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/28/98 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 23:36 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/28/98 | +------------------------------------------------+EVENT TIME: 21:50[CDT]| |NRC NOTIFIED BY: SAMPSON |LAST UPDATE DATE: 05/28/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | 3 | N Y 85 POWER OPERATION | 85 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO POWER SUPPLY FUNCTIONS. | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. | | | | RESIDENT INSPECTOR WAS NOTIFIED. | | | | SEE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+