U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/22/98 - 09/23/98 ** EVENT NUMBERS ** 34811 34818 34819 34820 34821 34822 34823 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34811 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/20/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:45 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/19/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:20[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/22/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 0707001 |JOSEPHINE PICCONE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SAFETY SYSTEM WAS DISCOVERED TO BE DISABLED. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PADUCAH: | | | | "ON 09/19/98 AT 1620 CDT, AN OPERATOR PERFORMING ROUTINE CHECKS DISCOVERED | | A SAFETY SYSTEM THAT HAD BEEN DISABLED. THE ENRICHMENT CASCADE EQUIPMENT | | USES A REFRIGERATION CYCLE TO REMOVE HEAT FROM THE PROCESS. THE | | REFRIGERANT SIDE OF THE SYSTEM HAS A RUPTURE DISC INSTALLED TO PREVENT | | OVERPRESSURIZATION AND POTENTIAL RUPTURE OF THE PRESSURE BOUNDARY. THERE | | IS AN ISOLATION VALVE BETWEEN THE SYSTEM AND THE RUPTURE DISC. BOTH THE | | RUPTURE DISC AND THE IN-LINE VALVE ARE CONTROLLED AS 'Q' SAFETY SYSTEM | | COMPONENTS. THE VALVE IS REQUIRED BY THE TSR TO BE SEALED IN THE OPEN | | POSITION WHEN THE EQUIPMENT IS IN SPECIFIC OPERATING MODES. THE CHECK | | BEING PERFORMED BY THE OPERATOR WAS A PRE-START INSPECTION. WHEN HE | | DISCOVERED THE VALVE SEAL WIRE BROKEN AND THE VALVE CLOSED, HE OPENED THE | | VALVE AND SEALED IT IN THE OPEN POSITION. HE THEN CHECKED THE REMAINING | | VALVES IN THE FACILITY AND DISCOVERED TWO MORE WITH THE SEAL WIRES BROKEN | | AND THE VALVES CLOSED. HE IMMEDIATELY OPENED THESE VALVES AND SEALED THEM | | IN THE OPEN POSITION. THE LATTER TWO VALVES WERE REQUIRED TO BE OPEN | | BECAUSE THEY WERE REQUIRED BY THE TSR TO PROVIDE OVERPRESSURE PROTECTION TO | | THE EQUIPMENT SERVED. THE APPROPRIATE COMPENSATORY ACTIONS WERE TAKEN. | | ADDITIONAL COMPENSATORY ACTIONS INCLUDED A WALKDOWN OF ALL SIMILAR SYSTEMS | | IN THE PLANT. NO OTHER DISCREPANCIES WERE FOUND." | | | | THE VALVES WERE LAST CHECKED ON 08/18/98 AS A QUARTERLY INSPECTION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY PADUCAH PERSONNEL. | | | | * * *RETRACTED AT 1625 EDT ON 09/22/98 BY J.M. UNDERWOOD TO F.E. JONES* * * | | | | FURTHER REVIEW OF THE SUBJECT EVENT BY NUCLEAR REGULATORY AFFAIRS AND THE | | PLANT SHIFT SUPERINTENDENT HAS CONCLUDED THAT THE SUBJECT RUPTURE DISC | | OVERPRESSURE RELIEF SYSTEM (SETPOINT 285 PSIA) SERVES AS A BACK-UP FOR THE | | CELL COOLANT HIGH PRESSURE TRIP CIRCUIT COMMONLY REFERRED TO AS A MELETRON. | | THE MELETRON AND AN ASSOCIATED RELAY TIED INTO THE SYSTEM COOLANT VAPOR | | LINE WILL SHUTDOWN THE CELL AT 222 PSIA AND PRECLUDE FURTHER PRESSURE RISE. | | SINCE THE MELETRON PROVIDES THE SAME SAFETY FUNCTION AS THE DISABLED | | RUPTURE DISC RELIEF DEVICE, CELL OVERPRESSURE PROTECTION WAS MAINTAINED. | | THUS, THE REPORTING CRITERION WERE NOT MET, AND THE EVENT NOTIFICATION IS | | RETRACTED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY PADUCAH PERSONNEL. THE NRC | | HEADQUARTERS OPERATIONS OFFICER NOTIFIED THE R3DO (JAMES CREED), NMSS EO | | (JOSEPHINE PICCONE), AND AEOD IRD (FRANK CONGEL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34818 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/22/98 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 12:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/22/98 | +------------------------------------------------+EVENT TIME: 09:32[CDT]| |NRC NOTIFIED BY: WILLIAM C. VALAGURA |LAST UPDATE DATE: 09/22/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO MAINTENANCE ACTIVITY | | | | THE REACTOR AUTOMATICALLY TRIPPED DUE TO LOW WATER LEVEL IN STEAM GENERATOR | | (SG) #2A. ALL EQUIPMENT PERFORMED AS EXPECTED, AND ALL CONTROL RODS FULLY | | INSERTED INTO THE CORE. THE LOW LEVEL WAS DUE TO CLOSURE OF THE MAIN | | FEEDWATER LEVEL CONTROL VALVE (LCV) CAUSED BY AN IMPROPERLY INSTALLED | | JUMPER DURING MAINTENANCE ACTIVITY. THE JUMPER WAS INSTALLED DURING | | MAINTENANCE ACTIVITY ASSOCIATED WITH THE #2A SG LOW POWER FEEDWATER LCV. | | THE JUMPER SHOULD HAVE BEEN INSTALLED ON THE PROCESS CARD FOR THE LOW POWER | | FEEDWATER LCV, BUT WAS INSTALLED ON THE MAIN FEEDWATER LCV PROCESS CARD | | RESULTING IN THE MAIN FEEDWATER LCV CLOSING WHILE UNIT 2 WAS AT 100% POWER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34819 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 09/22/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 13:12 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 09/21/98 | | FABRICATION & SCRAP RECOVERY |EVENT TIME: 11:00[PDT]| | COMMERICAL LWR FUEL |LAST UPDATE DATE: 09/22/98 | | CITY: RICHLAND REGION: 4 +-----------------------------+ | COUNTY: BENTON STATE: WA |PERSON ORGANIZATION| |LICENSE#: SNM-1227 AGREEMENT: Y |ELMO COLLINS RDO | | DOCKET: 07001257 |FRED COMBS, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: LOREN MAAS | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT - LOSS OF CRITICALITY CONTROL | | | | DURING THE DISASSEMBLY OF THE PLANT'S PERMANENTLY SHUTDOWN AMMONIUM | | DIURANATE (ADU) CONVERSION LINE-1, WORKERS STACKED SECTIONS OF DUCTWORK | | WITH VISIBLE ACCUMULATIONS OF SOLIDS. A CRITICALITY SAFETY SPECIALIST | | NOTED THIS CONDITION WHILE PERFORMING A ROUTINE WALK-THROUGH. PLANT | | OPERATING PERSONNEL REMOVED THE VISIBLE SOLIDS FROM THE DUCTWORK, SAMPLED | | THEM, AND PLACED THEM INTO AUTHORIZED STORAGE WITHIN 4 HOURS OF DISCOVERY. | | ANALYSIS DETERMINED THAT THERE WAS A TOTAL OF LESS THAN 9.2 KG OF LOW | | ENRICHED URANIUM (LESS THAN 5.0 WEIGHT %). | | | | FURTHER INVESTIGATION REVEALED THAT PERSONNEL HAD COMPLETED ALL REQUIRED | | ROUTINE AND PRE-JOB EQUIPMENT SURVEILLANCES. HOWEVER, CONTRARY TO | | CRITICALITY SAFETY REQUIREMENTS, THE DISASSEMBLY CREW DID NOT HAVE A | | PROCESS OPERATOR REMOVE VISIBLE SOLIDS FROM THE DUCTWORK PRIOR TO PLACING | | IT IN AN ACCUMULATION AREA. | | | | THIS WAS A LOSS OF MASS AND GEOMETRY CONTROL WHILE MODERATION CONTROL WAS | | MAINTAINED. IT WAS DETERMINED THAT THE MASS WAS LESS THAN 26% OF THE | | MINIMUM CRITICAL MASS. | | | | DISASSEMBLY ACTIVITIES WERE PLACED ON HOLD AND WILL NOT RESTART UNTIL A | | THOROUGH REVIEW OF THE EVENT IS COMPLETE AND FURTHER TRAINING IS CONDUCTED | | IN ALL SAFETY REQUIREMENTS ASSOCIATED WITH THE JOB. RESTART IS ESTIMATED | | BY 09/24/98. | | | | SIEMENS HAS NOTIFIED NRC REGION 4 AND HEADQUARTERS FUEL CYCLE PERSONNEL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34820 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/22/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:16 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/21/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:30[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/22/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT, LOSS OF CRITICALITY CONTROL | | | | PLANT PERSONNEL DETERMINED THAT A NUCLEAR CRITICALITY SAFETY APPROVAL | | (NCSA) WAS DEFICIENT IN THAT IT FAILED TO ANALYZE A CREDIBLE SCENARIO AND, | | THEREFORE, FAILED TO ESTABLISH THE CONTROLS NECESSARY TO MEET THE DOUBLE | | CONTINGENCY PRINCIPLE. CONTROL #2 REQUIRES THAT ONLY 'TRACE AMOUNTS' | | (UNDEFINED) OF URANIUM-BEARING MATERIAL MAY BE PRESENT IN THE PROCESS | | EQUIPMENT (CONVERTERS) MOVED INTO THE X-700 CONVERTER DISASSEMBLY/REPAIR | | AREA. THE EVALUATION FURTHER STATES THAT EQUIPMENT WITH SIGNIFICANT | | ACCUMULATIONS OF URANIUM MATERIAL WOULD BE CLEANED IN THE X-705 | | DECONTAMINATION FACILITY PRIOR TO TRANSFER. ESTIMATED ENRICHMENT CAN REACH | | 100 WEIGHT % UO2F2. ADDITIONALLY, NONDESTRUCTIVE EXAMINATION OF CONVERTERS | | IN THE X-700 CONVERTER AREA INDICATE THAT MORE THAN TRACE AMOUNTS OF | | URANIUM-BEARING MATERIALS ARE PRESENT IN THEM. THESE CONVERTERS WERE | | STAGED IN THE AREA PRIOR TO THE NCSA FOR THE AREA. | | | | THE NCSA PRESENTLY DOES NOT BOUND THE CONDITIONS PRESENT. THE NCSA IS | | BEING UPDATED TO INCLUDE MULTIPLE CONVERTERS AND MORE THAN TRACE AMOUNTS OF | | URANIUM-BEARING MATERIALS BEING PRESENT. THERE HAS BEEN AN ADMINISTRATIVE | | HOLD PLACED ON DISASSEMBLY AND REPAIR OF CONVERTERS IN THE X-700 AREA. | | CRITICALITY PERSONNEL HAVE DETERMINED THE PRESENT SAFETY OF THE CONDITION | | IN THE X-700 BUILDING AND NOTE THAT MODERATION CONTROLS HAVE ALWAYS BEEN | | MET. | | | | PORTSMOUTH PERSONNEL INFORMED THE NRC RESIDENT INSPECTOR AND PLAN TO INFORM | | THE ONSITE DEPARTMENT OF ENERGY REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 34821 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: HORIZON HOSPITAL SYSTEM |NOTIFICATION DATE: 09/22/98 | | CITY: GREENVILLE REGION: 1 |NOTIFICATION TIME: 15:06 [ET]| | COUNTY: MERCER STATE: PA |EVENT DATE: 09/18/98 | |LICENSE#: 370606402 AGREEMENT: N |EVENT TIME: 16:00[EDT]| | DOCKET: |LAST UPDATE DATE: 09/22/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MOHAMED SHANBAKY RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: ANDREW BUKUVITZ | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PERSONNEL OVEREXPOSURE | | | | A NUCLEAR MEDICAL TECHNICIAN'S BADGE (FOR THE TIME PERIOD OF JULY 18 | | THROUGH AUGUST 21) INDICATES A WHOLE BODY DOSE OF 11.1 REM. THE TECHNICIAN | | IS ONE OF SIX TECHNICIANS WHO PREPARE NUCLEAR MEDICINES AND NONE OF THE | | OTHER TECHNICIANS' BADGES INDICATED MORE THAN NORMAL EXPOSURES. THE | | TECHNICIAN WORKS MAINLY WITH TECHNICIUM-99 WITH AN ENERGY LEVEL OF ABOUT | | 140.5 KEV. THE BADGE IS A LUXEL DOSIMETER FROM LANDAUER AND IS PROCESSED BY | | THEM. THE PROCESSING OF THE BADGE, REPEATED TO INSURE CORRECT READING, | | INDICATED A LOW ENERGY EXPOSURE OF ABOUT 100 KEV. THE TECHNICIAN WILL BE | | REMOVED FROM DUTIES WITH POSSIBILITY OF FURTHER EXPOSURE AND AN | | INVESTIGATION IS BEING CONDUCTED. | | | | NRC REGION 1 DNMS (IHOR CZERWINSKYJ) WAS NOTIFIED BY THE LICENSEE'S PHYSICS | | CONSULTANT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34822 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 09/22/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 15:41 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/22/98 | +------------------------------------------------+EVENT TIME: 12:20[CDT]| |NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 09/22/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED CONDITION THAT COULD LEAD TO FAILURE OF RHR SYSTEM | | | | DURING AN IMPACT ASSESSMENT FOR SINGLE LOOP OPERATION, THE SEISMIC REVIEWER | | OBSERVED THAT THE SEISMIC ANALYSIS FOR THE REACTOR RECIRCULATION (RR) | | SYSTEM SUCTION VALVES WAS ONLY FOR THE OPEN POSITION. THE CLOSED POSITION | | MAY BE NECESSARY FOR LOOP ISOLATION. SINGLE LOOP OPERATION IS ALLOWED IN | | MODES 1 AND 2 (SECTION 3.4.1 OF TECHNICAL SPECIFICATIONS). | | SINCE THE CLOSED POSITION IS POSSIBLE DURING OPERATION AND SINCE THE DESIGN | | REQUIREMENTS MANDATE THAT THE VALVE BE ANALYZED, THIS IS AN UNANALYZED | | CONDITION AND FAILURE OF THIS VALVE IS BEING CONSIDERED. | | | | THE RESIDUAL HEAT REMOVAL (RHR) SYSTEM SUCTION IS FROM THE RR SYSTEM | | SUCTION LINE PRIOR TO THE RR SUCTION ISOLATION VALVE. SINCE THE SEISMIC | | FAILURE OF THE RR SUCTION VALVES COULD RESULT IN LOSS OF RHR CAPABILITY, | | THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10 CFR 50.72. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34823 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/22/98 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 21:54 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/22/98 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: JAMES CROSSMAN |LAST UPDATE DATE: 09/22/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ZEILER 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 +------------------------------------------------------------------------------+ | INADVERTENT SAFETY INJECTION SIGNAL GENERATED DURING TESTING | | | | DURING THE SETUP FOR PERFORMANCE OF SOLID STATE TRAIN 'A' SLAVE RELAY | | TESTING, A TRAIN 'A' SAFETY INJECTION SIGNAL WAS INADVERTENTLY GENERATED. | | THE CORE IS OFF-LOADED, AND MOST OF THE EMERGENCY CORE COOLING SYSTEMS | | (ECCS) ARE TAGGED OUT-OF-SERVICE. THE '1H' EMERGENCY DIESEL GENERATOR | | AUTOMATICALLY STARTED, A PHASE 'A' CONTAINMENT ISOLATION OCCURRED, AND TWO | | SERVICE WATER SYSTEM SPRAY MOTOR-OPERATED VALVES OPENED. NO INJECTION | | OCCURRED DUE TO ECCSs BEING OUT-OF-SERVICE. THE CAUSE OF THE SIGNAL WAS | | THE PERFORMANCE OF TEST STEPS BEING PERFORMED OUT-OF-SEQUENCE DUE TO A | | COMMUNICATION ERROR. THE SIGNAL HAS BEEN RESET, AND ALL EQUIPMENT RETURNED | | TO THEIR PROPER CONDITION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+