U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/29/96 - 03/01/96 ** EVENT NUMBERS ** 29989 29998 30024 30044 30045 30046 30047 30048 30049 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29989 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 02/17/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 05:20 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/17/96 | +------------------------------------------------+EVENT TIME: 01:51[EST]| |NRC NOTIFIED BY: JOHN REINSBURROW |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 +------------------------------------------------------------------------------+ | WITH THE REACTOR DEFUELED, A MAIN STEAM LINE DRAIN VALVE CLOSED | | UNEXPECTEDLY WHILE MODIFICATIONS WERE BEING PERFORMED ON THE MAIN STEAM | | LINE RADIATION MONITORS. | | | | DURING PERFORMANCE OF A MAIN STEAM LINE RADIATION MONITOR ISOLATION | | MODIFICATION, AN UNEXPECTED GROUP 1 PRIMARY CONTAINMENT ISOLATION SIGNAL | | WAS RECEIVED. THIS CAUSED THE OUTBOARD MAIN STEAM LINE DRAIN VALVE | | (2-B21-F019) WHICH WAS OPEN, TO CLOSE. THE MAIN STEAM ISOLATION VALVES AND | | SAMPLE VALVES WHICH ARE PART OF A GROUP 1 ISOLATION WERE EITHER ALREADY | | CLOSED OR TAGGED OUT FOR MAINTENANCE. THE INBOARD DRAIN VALVE (2-B21-F016) | | WAS NOT AFFECTED BY THE GROUP 1 ISOLATION SIGNAL. DIVISION 1 OF THE GROUP | | 1 LOGIC HAD BEEN PREVIOUSLY DEENERGIZED IN SUPPORT OF THE PLANT | | MODIFICATION. THE ISOLATION OCCURRED AFTER A TECHNICIAN LIFTED A WIRE PER | | THE PROCEDURE AND DEENERGIZED ONE CHANNEL OF THE DIVISION 2 GROUP 1 LOGIC. | | THE LICENSEE IS CONDUCTING AN INVESTIGATION TO DETERMINE THE CAUSE OF THIS | | OCCURRENCE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1513 EST ON 2/29/96 FROM KITCHEN TAKEN BY KARSCH * * * | | THE LICENSEE IS RETRACTING THIS EVENT BECAUSE THE INITIATING SIGNAL WAS NOT | | A VALID SIGNAL AND THE AFFECTED SYSTEM HAD BEEN PROPERLY REMOVED FROM | | SERVICE. THE LIFTED WIRE FED "DIVISION 2" RATHER THAN "DIVISION 1" DUE TO | | AN ERROR ON THE WIRE LIST. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. R2DO (McALPINE) NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29998 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 02/19/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 21:45 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 02/19/96 | +------------------------------------------------+EVENT TIME: 21:00[EST]| |NRC NOTIFIED BY: H LILES |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BUILDING PURGE INLET CONTAINMENT ISOLATION VALVES FAILED THEIR | | LOCAL LEAK RATE TEST (LLRT). | | | | WHILE ENTERING A REFUELING OUTAGE, A LLRT OF REACTOR BUILDING PURGE INLET | | ISOLATION VALVES (AHV-1C AND AHV-1D) WAS PERFORMED, AND THE LEAKAGE RATE | | FOR THE VALVES WAS >0.6 La. (THE LIMIT IS 266.4 liters/min.) THE LEAKAGE | | RATE FOR THE REACTOR BUILDING PURGE INLET ISOLATION VALVES WAS >500 | | liters/min. (MAXIMUM READING ON LEAKAGE FLOW METER.) PER TECHNICAL | | SPECIFICATION 3.6.1.b (OVERALL CONTAINMENT LEAKAGE TESTING) AND TECHNICAL | | SPECIFICATION 3.6.3.d (CONTAINMENT ISOLATION VALVE LEAKAGE LIMITS), THE | | LICENSEE HAS 36 HOURS TO BE IN A COLD SHUTDOWN CONDITION SINCE THERE ARE NO | | ISOLATION VALVES TO ISOLATE AHV-1C AND AHV-1D. AFTER REACHING COLD | | SHUTDOWN CONDITION, THE LICENSEE WILL OPEN THE VALVES AND ESTABLISH A | | CONTAINMENT ATMOSPHERE PURGE TO CLEAN THE CONTAINMENT ATMOSPHERE. THE | | VALVES WILL BE REPAIRED BEFORE EXITING THE REFUELING OUTAGE. THE REACTOR | | BUILDING INLET PURGE ISOLATION VALVES ARE PRESSURIZED TO BETWEEN 54.2 psig | | AND 54.7 psig (AIR IS INTRODUCED BETWEEN THE TWO INLET PURGE ISOLATION | | VALVES.), AND THEN THE LEAKAGE RATE IS MEASURED. THE NRC RESIDENT | | INSPECTOR WAS WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * 1256 FEBRUARY 29, 1996, UPDATE FROM PORTER TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE DETERMINED THAT THE | | VALVE INSIDE CONTAINMENT WAS NOT LEAKING AND CONCLUDED THAT THERE WAS NO | | LOSS OF CONTAINMENT BECAUSE ONE BARRIER EXISTED. THE LICENSEE WILL NOTIFY | | THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE R2DO (MCALPINE). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30024 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 02/25/96 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 07:41 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 02/25/96 | +------------------------------------------------+EVENT TIME: 04:05[CST]| |NRC NOTIFIED BY: ROGERS |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LESSER RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 91 POWER OPERATION | 91 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEM DEGRADATION RELATED TO SECURITY COMPUTER SYSTEM FAILURE. | | IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY. SEE HOO LOG FOR | | DETAILS. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | NOTE: THE LICENSEE DID NOT DETERMINE REPORTABILITY OF THIS EVENT UNTIL 0540 | | CST. | | | | | | ****RETRACTION BY R.G. JONES 02/29/96 @ 1122ET TAKEN BY MACKINNON**** | | | | THE ABOVE EVENT IS BEING RETRACTED BY THE LICENSEE AFTER A DETAILED REVIEW | | OF THE FACTS. APPROPRIATE COMPENSATORY MEASURES WERE TAKEN AT THE FIRST | | INDICATION OF A SECURITY COMPUTER FAILURE AND WERE IN PLACE (IMMEDIATE | | DEPLOYMENT) IN ACCORDANCE WITH AN APPROVED SITE SECURITY PROCEDURE AND | | REGULATORY GUIDE 5.62. THEREFORE, TVA RETRACTS THIS 1-HOUR NOTIFICATION. | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. R4DO (McALPINE) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 02/29/96 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 05:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 02/29/96 | +------------------------------------------------+EVENT TIME: 01:58[CST]| |NRC NOTIFIED BY: ROGERS |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McALPINE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAMMED ON HIGH APRM FLUX. LICENSEE INVESTIGATING MALFUNCTION OF | | THEIR ELECTRO-HYDRAULIC CONTROL (EHC) SYSTEM. | | | | REACTOR SCRAMMED ON APRM HIGH FLUX DUE TO A MALFUNCTION OF THE EHC SYSTEM. | | ALL RODS FULLY INSERTED INTO THE CORE. LICENSEE DOES NOT KNOW WHAT CAUSED | | THE APRM HIGH FLUX SCRAM SIGNAL BUT THEY BELIEVE THEY HAD SOME TYPE OF | | MALFUNCTION OF THEIR EHC SYSTEM. LICENSEE DID NOT KNOW IF A MAIN TURBINE | | CONTROL VALVE PARTIALLY CLOSED WHICH COULD HAVE CAUSED REACTOR VESSEL | | PRESSURE TO INCREASE TO CAUSE THE APRM HIGH FLUX SCRAM. NO SAFETY RELIEF | | VALVES OPENED. LICENSEE MANUALLY TRIPPED THEIR MAIN TURBINE PER PROCEDURE | | AT 50 MWe TO PREVENT A REVERSE POWER TRIP. THE LICENSEE RECEIVED THE | | FOLLOWING AUTOMATIC ISOLATIONS: GROUP 2 (DRYWELL FLOOR AND EQUIPMENT | | DRAIN), GROUP 3 (REACTOR WATER CLEANUP), GROUP 6 (PRIMARY & SECONDARY | | CONTAINMENT VENTILATION), AND GROUP 8 (TIPs WHICH WAS ALREADY ISOLATED). | | REACTOR VESSEL WATER LEVEL DID NOT GET LOW ENOUGH TO CAUSE HPCI AND RCIC TO | | AUTOMATICALLY START. ALL SYSTEMS OPERATED AS EXPECTED. NO TESTING OR | | MAINTENANCE WAS IN PROGRESS WHEN THE REACTOR SCRAMMED. LICENSEE IS | | INVESTIGATING WHAT CAUSED THE REACTOR SCRAM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30045 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/29/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 14:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/20/96 | +------------------------------------------------+EVENT TIME: 20:13[EST]| |NRC NOTIFIED BY: DAVID NEFF |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LATE REPORT OF A LOSS OF RESIDUAL HEAT REMOVAL (RHR), FUEL POOL COOLING | | SYSTEM (FPCS) FOR 57 MINUTES. | | | | THE LICENSEE WAS RESTORING THE "1A" RHR SYSTEM TO THE SHUTDOWN COOLING | | MODE. FLUSH VALVE OPERATIONS RESULTED IN A ONE INCH LEVEL DROP IN THE | | REACTOR CAVITY CAUSING A REDUCTION IN FLOW INTO A SKIMMER TANK USED AS A | | SUCTION SOURCE FOR THE FPCS. THIS CAUSED THE FPCS PUMP TO TRIP. THE | | LICENSEE RESTORED COOLING IN 57 MINUTES. THE LICENSEE DETERMINED THAT THE | | TIME TO REACTOR COOLANT BOILING WAS OVER 34 HOURS. THE "1A" RHR COULD ALSO | | HAVE BEEN PLACED INTO SERVICE. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30046 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 02/29/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/29/96 | +------------------------------------------------+EVENT TIME: 13:50[EST]| |NRC NOTIFIED BY: BOB MALONEY |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND 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 Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT RELEASE OF NOBLE GASES DURING REPAIR OF A VALVE. | | | | THE LICENSEE NOTIFIED THE STATE OF MAINE DEPARTMENT OF HEALTH ENGINEERING | | AND THE MAINE EMERGENCY MANAGEMENT AGENCY THAT THEY HAD AN INADVERTENT | | RELEASE OF 0.16 Ci OF NOBLE GASES. THE LICENSEE WAS PERFORMING MAINTENANCE | | ON A BALL VALVE ON THE COLLECTION TANK LEVEL COLUMN. SOME GAS WAS HEARD | | ESCAPING WHILE CAP SCREWS HOLDING THE VALVE BODY TOGETHER WERE TIGHTENED. | | PORTAL MONITORS AND FRISKERS CONFIRMED THE RELEASE. MAXIMUM PERSONNEL | | EXPOSURE WAS CALCULATED AT 3 EXP -5 mREM. THE DURATION OF THE RELEASE WAS | | 30 MINUTES. TIGHTENING THE CAP SCREWS STOPPED THE RELEASE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30047 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 02/29/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 17:26 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 02/29/96 | +------------------------------------------------+EVENT TIME: 14:45[EST]| |NRC NOTIFIED BY: JIM McGEE |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OHIO DEPARTMENT OF NATURAL RESOURCES, U.S. COAST GUARD, AND LOCAL LAW | | ENFORCEMENT AGENCIES WERE NOTIFIED THAT A PIECE OF ORDINANCE WAS FOUND | | WASHED UP ON THE BANK OF THE TOUSSIANT RIVER AT THE EDGE OF THE OWNER | | CONTROLLED PROPERTY. THE ORDINANCE APPEARS TO BE FUSED AND VIABLE. THE | | LOCATION IS ABOUT 100 FEET FROM A 345 KV OFF SITE LINE. A BOMB DISPOSAL | | TEAM FROM WRIGHT-PATERSON AIR FORCE BASE WILL BE ON SITE TOMORROW TO | | ADVISE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30048 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 02/29/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 20:39 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 02/29/96 | +------------------------------------------------+EVENT TIME: 20:25[EST]| |NRC NOTIFIED BY: CHRIS AVERY |LAST UPDATE DATE: 02/29/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ELINOR ADENSAM EO | | |DAMICO FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO A FIRE LASTING MORE THAN TEN MINUTES. | | | | WELDING AND GRINDING UNDER THE TURBINE CAUSED SPARKS WHICH IGNITED OIL | | SOAKED INSULATION. THE FIRE WAS PUT OUT BY A WORKER WITH A FIRE | | EXTINGUISHER. NO DAMAGE TO PLANT EQUIPMENT RESULTED. THE LICENSEE | | NOTIFIED STATE AND COUNTY GOVERNMENT AGENCIES. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2243 EST FROM BOSS TAKEN BY KARSCH * * * | | UNUSUAL EVENT TERMINATED AT 2236 EST. INSPECTION DETERMINED THAT THE FIRE | | WAS COMPLETELY OUT AND CONFIRMED THAT NO PLANT EQUIPMENT WAS DAMAGED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R3DO (PHILLIPS), EO | | (ADENSAM), AND FEMA (DAMICO) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30049 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/01/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 04:18 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/01/96 | +------------------------------------------------+EVENT TIME: 03:45[EST]| |NRC NOTIFIED BY: S SMITH |LAST UPDATE DATE: 03/01/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO OF THREE EMERGENCY DIESEL GENERATORS (EDGs) DECLARED OPERABLE DUE TO | | LUBE OIL PROBLEM. | | | | AT APPROXIMATELY 0345ET IT WAS DETERMINED THAT #32 EDG HAD HIGHER THAN | | NORMAL LUBE OIL TEMPERATURES, AND THE #32 EDG WAS DECLARED INOPERABLE. THE | | LICENSEE DID NOT KNOW THE EXACT TEMPERATURE OF THE LUBE OIL. EDG #33 IS | | CURRENTLY OUT OF SERVICE DUE TO A LUBE OIL SYSTEM CHECK VALVE PROBLEM, BUT | | IT IS IN THE PROCESS OF BEING TESTED FOR OPERABILITY AND IT SHOULD BE BACK | | IN SERVICE BY 0630ET. EDG #31 IS OPERABLE. THE LICENSEE IS IN TECHNICAL | | SPECIFICATION ACTION STATEMENT 3.7.b.1 (EDG FUEL OIL SYSTEM INOPERABLE). | | TECHNICAL SPECIFICATIONS REQUIRE THAT TWO EDGs BE OPERABLE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+