U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/03/97 - 04/04/97 ** EVENT NUMBERS ** 32003 32075 32076 32077 32078 32079 32080 32081 32082 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32003 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 03/24/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 12:31 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/24/97 | +------------------------------------------------+EVENT TIME: 10:45[CST]| |NRC NOTIFIED BY: KARL EHRHARDT |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPARE 480-VOLT CIRCUIT BREAKERS WERE RACKED TO A POSITION FOR WHICH THEY | | ARE NOT SEISMICALLY QUALIFIED. BOTH DIVISIONS OF 480-VOLT POWER ARE | | AFFECTED; THEREFORE, THIS CONDITION REPRESENTS A POTENTIAL COMMON MODE | | FAILURE MECHANISM. | | | | THREE CIRCUIT BREAKERS FOR DIVISION-1 480-VOLT POWER AND ONE CIRCUIT | | BREAKER FOR DIVISION-2 POWER WERE FOUND TO BE RACKED PAST THE DISCONNECT | | POSITION. WITH THE CIRCUIT BREAKERS IN THIS POSITION, THEIR SEISMIC | | QUALIFICATION IS IN QUESTION. SINCE BOTH DIVISIONS ARE AFFECTED, OPERATION | | OF THE SAFETY SYSTEMS COULD HAVE BEEN COMPROMISED. THE LICENSEE IS | | CONDUCTING AN INVESTIGATION TO DETERMINE THE CONSEQUENCES OF THIS | | CONDITION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE ON 04/03/97 AT 1546 FROM HOLIFIELD TAKEN BY BAILEY * * * | | | | THE LICENSEE COMPLETED AN ENGINEERING EVALUATION AND CONCLUDED THAT | | ALTHOUGH THE BREAKERS WERE LEFT IN A NONQUALIFIED POSITION, A SEISMIC EVENT | | WOULD NOT HAVE RESULTED IN A COMMON MODE FAILURE OF THE DIVISION I AND | | DIVISION II LOAD CENTERS, NOR WOULD IT HAVE SIGNIFICANTLY AFFECTED OTHER | | COMPONENTS SUCH THAT PLANT SAFETY WOULD BE COMPROMISED. THEREFORE, THE | | LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE NOTIFIED THE NRC | | RESIDENT INSPECTOR. THE HOO NOTIFIED R4DO (POWERS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32075 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/03/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 01:12 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: DARYL CLARK |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 1 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE | | FOLLOWING QUARTERLY SURVEILLANCE TEST. | | | | THE FOLLOWING TEXT IS FROM A FAX SENT BY THE LICENSEE: | | | | "ON APRIL 2, 1997, AT APPROXIMATELY 1700 CST, THE HPCI TURBINE WAS SHUT | | DOWN AFTER QUARTERLY FLOW RATE TESTING. WHEN THE TURBINE CAME TO REST, | | THE TURNING GEAR FAILED TO AUTOMATICALLY ENGAGE. AFTER SUBSEQUENT TESTING | | OF THE TURNING GEAR, IT WAS DETERMINED THAT THERE WAS A PROBLEM WITH THE | | TURNING GEAR ENGAGE LINKAGE. THE UNIT 1 HPCI SYSTEM WAS DECLARED | | INOPERABLE AT 2300 CST. UNIT 1 ENTERED A 14 DAY LCO PER TECHNICAL | | SPECIFICATION 3.5.A.3 AND ACTION 3." | | | | THE LICENSEE IS PREPARING A WORK ORDER TO ADJUST THE TURNING GEAR LINKAGE. | | COMPLETION OF THE WORK IS PLANNED FOR DAY SHIFT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32076 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 04/03/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 13:10 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 04/03/97 | +------------------------------------------------+EVENT TIME: 08:19[CST]| |NRC NOTIFIED BY: WOOD |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A POTENTIAL TO OVERPRESSURIZE THE RHR SYSTEM PIPING | | INSIDE CONTAINMENT DURING CERTAIN POSTULATED ACCIDENT CONDITIONS. | | | | THIS CONDITION, WHICH EXISTS ON BOTH UNITS, IS DUE TO A SECTION OF PIPING | | BETWEEN TWO MOTOR OPERATED VALVES, #1(2)RH-700 AND #1(2)RH-701 (RHR PUMPS | | SUCTION HEADER MOVs), NOT BEING PROTECTED FROM OVERPRESSURIZATION. THIS | | OVERPRESSURIZATION IS DUE TO CHANGES IN TEMPERATURE THAT COULD OCCUR INSIDE | | CONTAINMENT DURING NORMAL OPERATION (AMBIENT HEATUP) AND CERTAIN POSTULATED | | ACCIDENT CONDITIONS. THE LICENSEE IS PERFORMING CALCULATIONS TO DETERMINE | | IF THE PIPING IS SUSCEPTIBLE TO PRESSURIZATION BEYOND CODE ALLOWABLES. NRC | | GENERIC LETTER 96-06 IDENTIFIED THE POTENTIAL FOR WATER FILLED PIPING | | SECTIONS TO BE SUBJECTED TO OVERPRESSURIZATION WHEN THE TRAPPED FLUID IS | | HEATED BY THE CONTAINMENT ACCIDENT ENVIRONMENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32077 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/03/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:27 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/03/97 | +------------------------------------------------+EVENT TIME: 14:45[EST]| |NRC NOTIFIED BY: PATROU |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THE PLANT MAY HAVE OPERATED WITH THE | | REACTOR WATER CLEANUP SYSTEM IN A DEGRADED CONDITION. | | | | THIS WAS DETERMINED UPON REVIEW OF GE SERVICE INFORMATION LETTER #SIL-604, | | WHICH DISCUSSES REACTOR WATER CLEANUP SYSTEM LEAK DETECTION CAPABILITY. | | SPECIFICALLY, UPON A HIGH ENERGY LINE BREAK IN THE AUXILIARY CLEANUP PUMP | | ROOM, SAFETY RELATED EQUIPMENT IN THE REACTOR BUILDING MAY HAVE BEEN | | PREVENTED FROM PERFORMING ITS SAFETY FUNCTION PRIOR TO ISOLATION OF THE | | LINE BREAK. ON UNIT 1, RTDs ARE USED TO ISOLATE THE CLEANUP ON A HIGH | | ENERGY LINE BREAK. HOWEVER, THE AUXILIARY CLEANUP PUMP ROOM AREA IS NOT | | PROVIDED WITH RTDs. UNIT 1 IS CURRENTLY SHUT DOWN FOR A REFUEL OUTAGE AND | | ANALYSIS AND MODIFICATIONS ARE PLANNED TO ADDRESS THIS ISSUE PRIOR TO PLANT | | STARTUP. MODES OF OPERATION UNTIL CORRECTED WILL BE MAJOR MAINTENANCE | | (CORE OFF-LOADED), REFUELING OR COLD SHUTDOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32078 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/03/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:47 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/03/97 | +------------------------------------------------+EVENT TIME: 11:40[CST]| |NRC NOTIFIED BY: HIGINBOTHAM |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED OFFSITE AGENCIES THAT A FUEL OIL SPILL OCCURRED AT | | THEIR FACILITY. | | | | THE FUEL OIL SPILL WAS DUE TO A BROKEN GASKET ON A FUEL OIL TANK FILTER. | | THE FUEL OIL TANK WAS AN ATTACHED ASSEMBLY TO THE BED OF A COMED UTILITY | | VEHICLE. ESTIMATED SPILLAGE WAS 100 TO 150 GALLONS, ALL OF WHICH WAS | | CONTAINED BUT SOAKED INTO THE ASPHALT ROAD ADJACENT TO THE PLANT TURBINE | | BUILDING. NO WATERWAYS OR STORM SEWERS WERE AFFECTED. THE LICENSEE | | NOTIFIED THE NATIONAL RESPONSE CENTER AND THE ILLINOIS ENVIRONMENTAL | | MANAGEMENT AGENCY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32079 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 04/03/97 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/03/97 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: ALLGEYER |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |NLTR LICENSEE 24 HR REPORT | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT TWO MAIN STEAM LINE CODE SAFETY VALVES DID NOT | | MEET THEIR TEST SETPOINT. | | | | TWO MAIN STEAM LINE CODE SAFETY VALVES ("MS-PSV-7430A" AND "MS-PSV-7430B") | | WERE TESTED IN THE AS-FOUND CONDITION WITH THE FOLLOWING RESULTS: VALVE | | "7430A" WITH SETPOINT AT 1295 PSIG AND THE AS-FOUND CONDITION BEING 1419 | | PSIG, VALVE "7430B" WITH SETPOINT AT 1305 PSIG AND THE AS-FOUND CONDITION | | BEING 1393 PSIG. TESTING REQUIREMENTS ARE FOR THE AS-FOUND SETPOINT TO BE | | WITHIN 3% OF THE TECH SPEC SETPOINT WITH THE SUBSEQUENT (AS-LEFT) SETPOINT | | TO BE WITHIN 1% OF THE TECH SPEC SETPOINT. THE VALVES WERE TESTED ONE AT A | | TIME, ADJUSTED AS NECESSARY, AND RETESTED TO AS-LEFT SETTINGS WITHIN 1% OF | | LIFT SETTING. ALL 20 VALVES HAVE BEEN TESTED AND ONLY TWO ("7430A" AND | | "7430B") TESTED UNSATISFACTORILY. THE PLANT WAS IN A 24 HR LCO ACTION | | STATEMENT TO RESET THE CORRECT SETPOINTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32080 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/03/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/03/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:25[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/03/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER RDO | | DOCKET: 0707001 |MARGARET FEDERLINE EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: MAURER | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT A 3" BRANCH LINE ON THE HIGH PRESSURE FIRE | | WATER SPRINKLER SYSTEM WAS DISCONNECTED FROM THE SYSTEM SUPPLY PIPING. | | | | DURING A WALKDOWN OF THE C-333 BUILDING HIGH PRESSURE FIRE WATER SPRINKLER | | SYSTEMS, A THREE INCH BRANCH LINE ON SPRINKLER SYSTEM B-9 WAS DISCOVERED | | TO BE DISCONNECTED FROM THE SYSTEM SUPPLY PIPING ON THE GROUND FLOOR AT | | COLUMN X-15. THE DISCONNECTED BRANCH PIPING PROVIDES FIRE PROTECTION FOR | | BUILDING EXHAUST FANS #EE-35 AND #EE-35A. AN HOURLY FIRE PATROL WAS | | ESTABLISHED FOR THE AFFECTED AREA. THEY SPECULATE THAT WHEN THIS BRANCH | | LINE WAS INSTALLED IN 1970, IT WAS NEVER CONNECTED TO THE EXISTING LINE. | | PLANS ARE TO CONNECT THE PIPING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32081 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/03/97 | |UNIT: [ ] [4] [ ] STATE: FL |NOTIFICATION TIME: 22:20 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/03/97 | +------------------------------------------------+EVENT TIME: 21:40[EST]| |NRC NOTIFIED BY: FLYNN |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 72 HOUR LCO ACTION STATEMENT WHEN THE HIGH HEAD SAFETY | | INJECTION SYSTEM WAS DECLARED INOPERABLE. | | | | A HIGH HEAD SAFETY INJECTION PUMP CASING FLANGE WAS DISCOVERED LEAKING AT | | 2030 ON 04/03/97. THIS LEAKAGE WAS CONFIRMED TO BE IN EXCESS OF THE | | CONSERVATIVE ASSUMPTIONS (2.325 L/HR) FOR EMERGENCY CORE COOLING SYSTEM | | RECIRCULATION LOOP LEAKAGE. THESE ASSUMPTIONS ARE USED IN THE CALCULATION | | FOR ASSURING THAT THE LEAKAGE IS LIMITED TO THAT WHICH WOULD MEET 10CFR100 | | LIMITS. THE AMOUNT OF LEAKAGE (3.4 L/HR) WAS CONFIRMED TO BE LARGER THAN | | THAT ASSUMED IN THE FSAR ON AT 2140 ON 04/03/97. THEREFORE, THIS CONDITION | | IS CONSIDERED TO BE OUTSIDE THE PLANT DESIGN BASIS AND IS REPORTABLE. THE | | "4A" PUMP HAS BEEN ISOLATED AND WILL BE REPAIRED IN THE NEAR FUTURE. THE | | LCO ACTION STATEMENT ALLOWS 72 HOURS TO RETURN THE PUMP TO SERVICE OR BE IN | | HOT STANDBY MODE WITHIN THE NEXT 6 HOURS AND HOT SHUTDOWN MODE WITHIN THE | | FOLLOWING 6 HOURS. THE LICENSEE BELIEVES THAT THEY WILL HAVE THE PUMP | | RESTORED WITHIN THE 72 HOUR PERIOD. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32082 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/04/97 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 03:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/04/97 | +------------------------------------------------+EVENT TIME: 01:29[EST]| |NRC NOTIFIED BY: CHRIS REEVES |LAST UPDATE DATE: 04/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS EXPERIENCED AN AUTOSTART OF THE STATION EMERGENCY DIESEL | | GENERATORS (EDGs) AND AN AUXILIARY BUILDING VENTILATION ISOLATION DUE TO AN | | ELECTRICAL GROUND DURING MAINTENANCE ACTIVITIES. | | | | THE FOLLOWING TEXT WAS RECEIVED VIA FAX FROM THE LICENSEE: | | | | "AT 0129 EST MODIFICATIONS PERSONNEL WERE DRILLING INTO THE #1-M-1 CONTROL | | PANEL IN PREPARATION OF INSTALLING A METAL PATCH. WHILE DRILLING, THEY | | ACCIDENTALLY DRILLED INTO A CONTROL POWER CABLE (125 VDC) AND CAUSED THE | | NORMAL AC SUPPLY BREAKER (#ACB-1718) TO TRIP OPEN WHICH DEENERGIZED THE | | #1A-A 6.9 KV SHUTDOWN BOARD. THIS RESULTED IN THE #1A-A EDG STARTING AND | | CONNECTING TO THE #1A-A 6.9 KV SHUTDOWN BOARD. THE #2A-A AND #2B-B EDGs | | ALSO STARTED AS EXPECTED DUE TO THE LOSS OF VOLTAGE TO THE #1A-A 6.9 KV | | SHUTDOWN BOARD. THE #2A-A AND #2B-B EDGs DID NOT TIE ONTO THEIR RESPECTIVE | | BOARDS, SINCE THEY WERE STILL BEING SUPPLIED BY THEIR NORMAL (OFFSITE) | | POWER SUPPLIES. THE #1B-B EDG DID NOT START, SINCE IT IS CURRENTLY | | INOPERABLE AND REMOVED FROM SERVICE UNDER A HOLD ORDER. ALL SYSTEMS | | RESPONDED CORRECTLY TO THE ESF CONDITION. THE PLANT ALSO RECEIVED AN | | AUXILIARY BUILDING ISOLATION (ABI) DUE TO 1-RM-90-101 AS A RESULT OF THE | | LOSS OF THE 6.9 KV SHUTDOWN BOARD. LCOs UNIT 1: NONE, UNIT 2: 3.8.1.1.b | | (DUE TO THE #1B-B EDG BEING INOPERABLE). ABNORMAL OPERATING PROCEDURE, | | #AOP-P.05 WAS IMPLEMENTED DUE TO THE LOSS OF POWER TO THE #1A-A 6.9 KV | | SHUTDOWN BOARD. RECOVERY OF THE PLANT IS IN PROGRESS AT THIS TIME." | | | | UNIT 1 SHUT DOWN ON 03/22/97 FOR A REFUELING OUTAGE AND IS CURRENTLY | | DEFUELED. BOTH UNITS SHARE A COMMON SPENT FUEL POOL (SFP). AT THE TIME OF | | THE EVENT, BOTH SFP PUMPS 'A' AND 'B' WERE IN OPERATION. AFTER THE | | SPURIOUS BLACKOUT SIGNAL WAS RECEIVED, ALL UNIT 1 ELECTRICAL LOADS WERE | | STRIPPED INCLUDING SFP PUMP 'A'. OPERATORS RESPONDED PROMPTLY BY PLACING | | THE 'CS' PUMP ALIGNED TO UNIT 2 IN SERVICE. SFP TEMPERATURE REMAINED AT | | 97øF DURING THE TRANSIENT (HIGH TEMPERATURE ALARM SETPOINT 110 øF). A | | COUPLE OF AIR COMPRESSORS SUPPLYING SERVICE AND INSTRUMENT AIR WERE ALSO | | DEENERGIZED; HOWEVER, NO LOW AIR PRESSURE ALARMS WERE RECEIVED. EDG #1A-A | | WILL REMAIN IN SERVICE CARRYING REQUIRED ELECTRICAL LOADS UNTIL CORRECTIVE | | ACTIONS ARE COMPLETED. THIS INCLUDES IDENTIFICATION AND REPAIR OF AFFECTED | | WIRING. A VISUAL EXAMINATION OF THE DAMAGE SHOWED 'GRAZING' OF THE WIRING | | BUNDLE. THE UNIT 2 EDGs AND AUXILIARY BUILDING VENTILATION SYSTEM HAVE | | BEEN RETURNED TO STANDBY AND RESTORED, RESPECTIVELY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+