U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/12/97 - 08/13/97 ** EVENT NUMBERS ** 32722 32733 32747 32748 32749 32750 32751 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32722 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 08/04/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 20:07 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/03/97 | +------------------------------------------------+EVENT TIME: 23:23[EDT]| |NRC NOTIFIED BY: BRUCE BUTLER |LAST UPDATE DATE: 08/12/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 88 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO HAVE A BACKUP PRESSURE REGULATOR AVAILABLE WHEN THE REACTOR WAS | | LESS THAN 80% THERMAL POWER | | | | AT 1540 ON 08/03/97, THE LICENSEE BEGAN TO REDUCE REACTOR POWER FROM 100% | | DUE TO CYCLING OF THE MAIN TURBINE CONTROL VALVES. THE POWER REDUCTION WAS | | CEASED AT 1557 WITH THE REACTOR AT 88%, AND TROUBLESHOOTING WAS COMMENCED. | | THE LICENSEE IDENTIFIED THAT THE IN-SERVICE MAIN TURBINE PRESSURE REGULATOR | | WAS SLOWLY FAILING HIGH. THIS, IN TURN, WAS CAUSING THE MAIN TURBINE | | CONTROL VALVES TO OPEN AND REACTOR PRESSURE TO STEADILY DECREASE AT A VERY | | SLOW RATE. THE LICENSEE AGAIN BEGAN TO REDUCE REACTOR POWER AT 2103 IN | | ORDER TO REMOVE THIS PRESSURE REGULATOR FROM SERVICE, PLACE THE REDUNDANT | | TRAIN IN SERVICE, AND LIMIT THE EFFECTS OF ANY TRANSIENTS THAT MIGHT BE | | RECEIVED. THE POWER REDUCTION WAS CEASED AT 2126 WITH REACTOR POWER AT | | 76%, AND XENON CAUSED POWER TO FURTHER DECREASE TO 73.5%. THE LICENSEE | | DISABLED THE 'B' MAIN TURBINE PRESSURE REGULATOR AT 2323. THE 'A' MAIN | | TURBINE PRESSURE REGULATOR WAS PLACED IN SERVICE, AND POWER ASCENSION WAS | | COMMENCED AT 2330. REACTOR POWER WAS GREATER THAN 80% AT 2342. | | | | SUBSEQUENT REVIEW (ON 08/04/97) DETERMINED THAT UNIT 1 WAS OUTSIDE ITS | | DESIGN BASIS BETWEEN 2323 AND 2342 ON 08/03/97, BECAUSE THERE WAS NO BACKUP | | PRESSURE REGULATOR AVAILABLE WITH THE REACTOR BELOW 80% THERMAL POWER. THIS | | WAS BASED UPON A REVIEW OF THE UNIT 2 FINAL SAFETY ANALYSIS REPORT (FSAR) | | WHICH IMPLIED THAT UNIT 2 WOULD BE OUTSIDE ITS DESIGN BASIS IF A BACKUP | | PRESSURE REGULATOR WAS NOT AVAILABLE WHEN THE REACTOR WAS BELOW 80% THERMAL | | POWER. THIS ITEM IS NOT REFERENCED IN THE UNIT 1 FSAR. HOWEVER, THE | | LICENSEE DECIDED THAT THE SAME CONDITIONS THAT APPLY TO UNIT 2 SHOULD APPLY | | TO UNIT 1 AS WELL. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1320 ON 08/12/97, FROM ANDERSON TAKEN BY WEAVER * * * | | | | THE LICENSEE HAS RETRACTED THIS EVENT NOTIFICATION. THE RETRACTION IS | | BASED ON AN ANALYSIS DONE BY GENERAL ELECTRIC WHICH CONCLUDED THAT THE | | PLANT WAS NOT IN FACT OUTSIDE OF ITS DESIGN BASIS. THEREFORE, NO | | 10CFR50.72 NOTIFICATION WAS REQUIRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO INFORMED THE | | R2DO (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32733 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/06/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:06 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/06/97 | +------------------------------------------------+EVENT TIME: 19:45[EDT]| |NRC NOTIFIED BY: DENIS CORNAX |LAST UPDATE DATE: 08/12/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO QUESTIONABLE PRESSURIZER | | SAFETY VALVE SETTINGS | | | | AT 1945, THE LICENSEE COMMENCED A TECHNICAL SPECIFICATION 3.0.1 REQUIRED | | SHUTDOWN DUE TO THE FACT THAT ONE OR MORE PRESSURIZER SAFETY VALVE SETTINGS | | MAY BE OUTSIDE THE ñ1% ALLOWABLE LIMIT. THE PRESSURIZER SAFETY VALVES ARE | | SET IN ACCORDANCE WITH SECTION XI CODE REQUIREMENTS USING MEASURED AMBIENT | | TEMPERATURE. READINGS TAKEN TODAY CONFIRM THAT THE VALVE BODY/BONNET | | TEMPERATURES ARE SIGNIFICANTLY DIFFERENT THAN THE AMBIENT TEMPERATURES USED | | TO SET THE VALVES. THEREFORE, ONE OR MORE VALVES MAY HAVE SETPOINTS LOWER | | THAN 2,485 PSIG ñ1% ALLOWABLE PER THE TECHNICAL SPECIFICATIONS. (UNIT 2 | | NORMALLY OPERATES WITH THE BLOCK VALVES CLOSED. THEY HAVE AN AUTOMATIC | | OPEN SIGNAL.) | | | | THE LICENSEE PLANS TO PLACE UNIT 2 IN COLD SHUTDOWN AND DEPRESSURIZE UNIT 2 | | IN ORDER TO PERMIT THE VALVES TO BE RESET ACCORDING TO THE RECENT | | TEMPERATURE READINGS. THIS ISSUE AFFECTS UNIT 2 ONLY BECAUSE UNIT 3 IS | | CURRENTLY IN COLD SHUTDOWN AS PART OF A REFUELING OUTAGE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0340 ON 08/07/97, FROM MIKE RUH ENTERED BY JOLLIFFE * * * | | | | AT 0200 ON 08/07/97, UNIT 2 ENTERED MODE 4 (HOT SHUTDOWN). THE LICENSEE | | WILL BE RESETTING THE THREE PRESSURIZER SAFETY VALVES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO (RICH CONTE). | | | | * * * UPDATE AT 2244 ON 08/12/97, FROM SANTINI TAKEN BY WEAVER * * * | | | | THE LICENSEE REPORTED THE FOLLOWING RESULTS OF TESTING CONDUCTED BY WYLE | | LABS ON THE PRESSURIZER SAFETY VALVES: | | | | VALVE LIFT PRESSURE | | PCV-464 2,564 PSIG | | PCV-466 2,512 PSIG | | PCV-468 2,434 PSIG | | | | PCV-464 WAS DISCOVERED TO HAVE DEFECTIVE INTERNAL COMPONENTS, AND THE VALVE | | HAS BEEN REPLACED. THE OTHER TWO VALVES TESTED SATISFACTORILY SUBSEQUENT | | TO THE ORIGINAL TEST. THESE TWO VALVES HAVE BEEN REINSTALLED IN THE PLANT. | | | | THE PLANT IS IN COLD SHUTDOWN MAKING PREPARATIONS TO HEAT UP. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, AND THE HOO NOTIFIED THE | | R1DO (GRAY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32747 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: THERMO NUTECH |NOTIFICATION DATE: 08/12/97 | | CITY: ALBUQUERQUE REGION: 4 |NOTIFICATION TIME: 00:01 [ET]| | COUNTY: STATE: NM |EVENT DATE: 08/08/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[MDT]| | DOCKET: |LAST UPDATE DATE: 08/12/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOSEPH TAPIA RDO | | |JOHN GREEVES EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JERRIE MOORE (NM RAD) | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE NOTIFICATION FROM THE NEW MEXICO RADON PROGRAM | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE NEW MEXICO | | RADON PROGRAM: | | | | "AN INDIVIDUAL'S QUARTERLY TLD SHOWS EXPOSURES OF 2 REM (WHOLE BODY) AND | | 5 REM (EXTREMITY). THIS INDIVIDUAL COULD NOT ACCOUNT FOR THESE READINGS AS | | HE HANDLED SOURCES OF CS-137 [FROM] 1 TO 10 æCi. HE CAN NOT ACCOUNT FOR | | THIS TYPE OF EXPOSURE NOR CAN THE [RADIATION SAFETY OFFICER (RSO)] FIND THE | | PROBLEM. FURTHER INVESTIGATION IS IN PROGRESS. A FACILITY INSPECTION WAS | | DONE ON 7/3/97, AND THE EVENT WAS DISCUSSED WITH THE RSO AND FACILITY | | MANAGER. AT THAT TIME THEY SAID THEY THOUGHT IT WAS NOT A TRUE EXPOSURE | | BUT COULD NOT ACCOUNT FOR THE READING." | | | | REPORT 'NM-07-05' WAS RECEIVED VIA FACSIMILE FROM THE NEW MEXICO RADON | | PROGRAM LOCATED AT 4131 MONTGOMERY BLVD NE, ALBUQUERQUE, NM 87109. THE | | FACSIMILE COVER SHEET STATED, "EVENTS FOR LAST QUARTER, 3/97 TO 6/97." | | | | (REFER TO THE HOO LOG FOR TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32748 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 08/12/97 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 11:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/11/97 | +------------------------------------------------+EVENT TIME: 17:15[CDT]| |NRC NOTIFIED BY: KENNETH J. TAPLETT |LAST UPDATE DATE: 08/12/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 REPORT REGARDING A VIOLATION OF A LICENSE CONDITION - FAILURE TO | | PERFORM TECHNICAL SPECIFICATION REQUIRED SURVEILLANCE | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "TECHNICAL SPECIFICATION SURVEILLANCE 4.3.2.1.2.c, 'CONTAINMENT SPRAY | | ACTUATION RELAYS SLAVE RELAY TEST,' WAS NOT PERFORMED FOR CONTAINMENT SPRAY | | PUMP 1A ON A QUARTERLY BASIS FOR THE PERIOD FROM OCTOBER 31, 1996, TO APRIL | | 15, 1997. DURING A REVIEW OF NRC GENERIC LETTER 96-01, 'TESTING OF | | SAFETY-RELATED LOGIC CIRCUITS,' A DETERMINATION WAS MADE THAT THE | | ASSOCIATED ACTUATION DEVICE, WHICH IS THE BREAKER FOR CONTAINMENT SPRAY | | PUMP 1A, HAD NOT BEEN TESTED TO CHECK CONTINUITY. CONTAINMENT SPRAY PUMP | | 1A CURRENTLY MEETS ALL SURVEILLANCE REQUIREMENTS, AND THE PUMP IS OPERABLE. | | THIS EVENT IS REPORTABLE PURSUANT TO 10 CFR 50.73(a)(2)(i)(B)." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32749 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 08/12/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 16:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/12/97 | +------------------------------------------------+EVENT TIME: 14:08[CDT]| |NRC NOTIFIED BY: JOHN CARLSON |LAST UPDATE DATE: 08/12/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POLAR CRANE USED DURING POWER OPERATIONS - NOT ALLOWED BY UFSAR | | | | THE LICENSEE HAS DETERMINED THAT USE OF THE POLAR CRANE DURING CONDITIONS | | OTHER THAN COLD SHUTDOWN IS NOT ALLOWED. SINCE THE POLAR CRANE HAS BEEN | | USED DURING CYCLE SEVEN ON SEVERAL OCCASIONS, THE LICENSEE IS REPORTING | | THIS AS AN UNANALYZED CONDITION. | | | | THIS ISSUE STEMS FROM THE FACT THAT THE POLAR CRANE IS POWERED BY A | | 480-VOLT SAFETY-RELATED ELECTRICAL BUS. HOWEVER, THE ELECTRICAL PROTECTIVE | | DEVICES ASSOCIATED WITH THE POLAR CRANE ARE NOT SUFFICIENT TO ENSURE THE | | VIABILITY OF THE SAFETY-RELATED POWER SUPPLY IN CASE OF A FAULT ON THE | | POLAR CRANE. THE LICENSEE HAS ELECTRICALLY ISOLATED THE POLAR CRANE | | PENDING RESOLUTION OF THIS ISSUE. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32750 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 08/12/97 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 17:17 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 08/12/97 | +------------------------------------------------+EVENT TIME: 16:00[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 08/12/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT SUPPRESSION POOL BYPASSED DURING CERTAIN INERTING OPERATIONS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE PERFORMING A REVIEW OF INDUSTRY REPORTABLE EVENTS, A VALVE ALIGNMENT | | WAS IDENTIFIED WHICH WOULD CREATE A SUPPRESSION CHAMBER BYPASS PATH AND | | REDUCE THE PRESSURE SUPPRESSION FUNCTION OF THE SUPPRESSION POOL. THIS | | VALVE ALIGNMENT OCCURS WHEN INERTING OR DE-INERTING THE DRYWELL AND | | SUPPRESSION CHAMBER SIMULTANEOUSLY DURING PLANT STARTUP AND SHUTDOWN. A | | SUBSEQUENT ANALYSIS OF THE DESIGN BASIS [LOSS OF COOLANT ACCIDENT] SHOWED | | THAT PEAK CONTAINMENT PRESSURE COULD EXCEED THE MAXIMUM DESIGN PRESSURE OF | | 62 PSIG WHILE IN THIS CONFIGURATION. ADMINISTRATIVE CONTROLS ARE | | IMPLEMENTED TO PROHIBIT OPERATION IN THIS CONFIGURATION." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32751 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/12/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 19:42 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/12/97 | +------------------------------------------------+EVENT TIME: 18:58[EDT]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 08/12/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - SPILL OF RADIOACTIVE WATER | | | | THE LICENSEE REPORTED A SPILL OF RADIOACTIVE WATER TO THE CONNECTICUT | | DEPARTMENT OF ENVIRONMENTAL PROTECTION. A REACTOR COOLANT PUMP STORAGE | | CONTAINER WAS BEING REMOVED FROM A FLAT BED TRUCK WHEN APPROXIMATELY ONE | | QUART OF CONTAMINATED WATER SPILLED ONTO THE ASPHALT. THE SPILL OCCURRED | | IN A RADIOLOGICALLY CONTROLLED AREA AND HAS BEEN CLEANED UP. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+