U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/27/97 - 05/28/97 ** EVENT NUMBERS ** 32237 32393 32394 32395 32396 32397 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32237 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 04/29/97 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 10:40 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/29/97 | +------------------------------------------------+EVENT TIME: 07:43[EDT]| |NRC NOTIFIED BY: BILL WEBSTER |LAST UPDATE DATE: 05/27/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL REACTOR TRIP FROM 1% DUE TO A ROD CONTROL SYSTEM URGENT FAILURE - | | | | AT 1226 ON 04/28/97, WHILE STARTING UNIT 1 UP FROM A REFUELING OUTAGE, | | THE REACTOR WAS CRITICAL AT 1E-7 AMPS ON THE INTERMEDIATE RANGE NUCLEAR | | INSTRUMENTATION DETECTORS (LESS THAN 1% POWER) FOR THE PERFORMANCE OF LOW | | POWER CORE PHYSICS TESTING. | | | | AT 0046 ON 04/29/97, A ROD CONTROL SYSTEM URGENT FAILURE ALARM WAS RECEIVED | | WHILE MOVING THE ROD CONTROL SELECTOR SWITCH IN SUPPORT OF THE TESTING. | | LICENSEE TROUBLESHOOTING OF THE ROD CONTROL SYSTEM PROBLEM WAS UNSUCCESSFUL | | IN DETERMINING THE CAUSE. | | | | AT 0743 ON 04/29/97, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR | | FROM A POWER LEVEL OF 1E-7 AMPS. ALL CONTROL RODS INSERTED COMPLETELY. | | UNIT 1 IS STABLE IN MODE 3 (HOT SHUTDOWN) AT 547øF. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTION AND INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 1032 ON 05/27/97 FROM ROSENBERGER TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE FOLLOWING IS THE TEXT OF A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "FURTHER REVIEW OF THIS EVENT BY STATION MANAGEMENT HAS DETERMINED THAT | | THIS MANUAL REACTOR TRIP WAS A PLANNED EVOLUTION, NOT REQUIRED BY ANY | | TECHNICAL SPECIFICATIONS, NORMAL OR EMERGENCY PROCEDURES, NOR EXISTING | | CONDITIONS. THE TRIP WAS PERFORMED TO ALLOW TROUBLESHOOTING AND REPAIRS | | TO THE ROD CONTROL SYSTEM TO CONTINUE. THEREFORE, THIS EVENT IS CONSIDERED | | A PLANNED AND NORMAL SHUTDOWN OF THE REACTOR, AND IS NOT REPORTABLE. THE | | REFERENCED 4 HOUR, NON-EMERGENCY REPORT OF 04/29/97 IS HEREBY WITHDRAWN." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R2DO TOM DECKER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32393 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 05/27/97 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 07:21 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 05/27/97 | +------------------------------------------------+EVENT TIME: 00:34[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 05/27/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTO REACTOR TRIP FROM 100% POWER OCCURRED ON A LOW DEPARTURE FROM NUCLEATE | | BOILING RATIO RESULTING FROM THE LOSS OF TWO REACTOR COOLANT PUMPS (RCPs). | | | | AT 2342 MST ON 05/26/97, PRIOR TO THE TRIP, VOLTAGE INDICATION BEGAN TO | | DECREASE ON THE 13.8 KV NON-CLASS 1E BUS #NAN-S01. ACTUAL VOLTAGE WAS | | NOT DECREASING. AMONG OTHER LOADS, BUS #NAN-S01 POWERS TWO OF THE FOUR | | RCPs. WHEN THE INDICATED VOLTAGE DROPPED TO 10.1 KV, THE NORMAL SUPPLY | | BREAKER TRIPPED OPEN, AS EXPECTED, FOR AN UNDERVOLTAGE CONDITION, AND THE | | TWO REACTOR COOLANT PUMPS LOST POWER. THE APPARENT CAUSE OF THE DECREASING | | VOLTAGE INDICATION IS UNDER INVESTIGATION AND MAY BE ATTRIBUTED TO A FAULTY | | POTENTIAL TRANSFORMER CIRCUIT. THERE WAS NO GRID DISTURBANCE. | | | | ALL RODS FULLY INSERTED INTO THE CORE. ALL SAFETY SYSTEMS FUNCTIONED | | AS REQUIRED. NO OTHER ENGINEERED SAFETY FEATURE ACTUATIONS OCCURRED | | (AUXILIARY FEEDWATER SYSTEM WAS NOT ACTUATED) AND NONE WERE REQUIRED. | | THE CONTROL ROOM SUPERVISOR DETERMINED THAT IT WAS AN UNCOMPLICATED | | REACTOR TRIP. THE STEAM DUMP BYPASS CONTROL SYSTEM IS OPERATING PROPERLY | | AND MAINTAINING THE REACTOR COOLANT SYSTEM AT A Tave NO LOAD CONDITION. | | UNIT 1 IS CURRENTLY STABLE IN MODE 3 (HOT STANDBY). THE EVENT DID NOT | | RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER OR RESULT IN ANY | | RELEASES OF RADIOACTIVE MATERIALS. | | | | THE LICENSEE DID NOT NOTICE THE VOLTAGE DECREASING ON BUS #NAN-S01 UNTIL | | 0014 MST ON 05/27/97. THE LICENSEE EMERGENCY RESPONSE FACILITY DATA | | ACQUISITION AND DISPLAY SYSTEM INDICATED THAT THE VOLTAGE ON BUS #NAN-S01 | | STARTED TO DECREASE AT 2342 MST ON 05/26/97. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32394 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/27/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 12:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/27/97 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: EDDIE JONES |LAST UPDATE DATE: 05/27/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK HOSEY 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 Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SEVERAL "B" TRAIN ESF EQUIPMENT STARTED UNEXPECTEDLY DURING DIESEL | | GENERATOR SEQUENCER "B" TIMER CALIBRATION TESTING. | | | | THE DIESEL GENERATOR SEQUENCER TIMER CALIBRATION TEST IS PERFORMED YEARLY | | AND THIS IS THE FIRST TIME THIS TEST PROCEDURE HAS BEEN USED SINCE IT WAS | | REVISED. | | | | SEVERAL ESF EQUIPMENT ACTUATED UNEXPECTEDLY DURING THE PERFORMANCE OF THE | | "B" TRAIN DIESEL GENERATOR SEQUENCER TIMER CALIBRATION TEST. THERE WAS NO | | INJECTION TO THE REACTOR COOLANT SYSTEM SINCE NONE OF THE SAFETY INJECTION | | VALVES RECEIVED AN AUTO OPEN SIGNAL. THE TURBINE DRIVEN AUXILIARY | | FEEDWATER PUMP STARTED AND INJECTED TO THE STEAM GENERATORS (DID NOT AFFECT | | THE REACTOR SIDE OF THE PLANT), "1B" NUCLEAR DECAY PUMP (RHR) AUTO STARTED, | | "1B1" AND "1B2" COMPONENT COOLING WATER PUMPS AUTO STARTED, "1BNV" AND | | "1BNI" HIGH PRESSURE AND INTERMEDIATE PRESSURE INJECTION PUMPS AUTO | | STARTED, "1BUCYC" STANDBY CONTROL ROOM CHILLER SAFETY ALIGNED BUT DID NOT | | START, AND THE STEAM GENERATOR BLOWDOWN ISOLATION VALVES ISOLATED. | | | | THE DIESEL GENERATOR ASSOCIATED WITH THE SEQUENCER THAT WAS BEING TESTED | | DID NOT START BECAUSE IT WAS TAGGED OUT OF SERVICE PER THE SEQUENCER TIMER | | CALIBRATION TEST. THE LICENSEE IS GOING THROUGH THE DIESEL GENERATOR | | SEQUENCER TIMER CALIBRATION TEST PROCEDURE TO FIND OUT IF THE PROCEDURE HAS | | ANY ERRORS. | | | | THE LICENSEE REDUCED POWER FROM 100% TO 97% TO REDUCE CONTAINMENT | | TEMPERATURE WHICH IS UNRELATED TO THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32395 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNKNOWN |NOTIFICATION DATE: 05/27/97 | | CITY: SAGINAW REGION: 3 |NOTIFICATION TIME: 11:52 [ET]| | COUNTY: SAGINAW STATE: MI |EVENT DATE: 05/27/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/27/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | |DON COOL, NMSS EO | +------------------------------------------------+RICHARD BARRETT, IRD AEOD | |NRC NOTIFIED BY: PETTY OFFICER FLETCHER |JAMES CAMERON REG3 | |HQ OPS OFFICER: LEIGH TROCINE |FLETCHER, NAT RES CT EPA | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINER WITH A RADIOACTIVE MATERIALS LABEL FOUND IN THE BASEMENT OF A | | RESIDENCE IN SAGINAW, MICHIGAN. | | | | AT 1152 ON MAY 27, 1997, THE NATIONAL RESPONSE CENTER FORWARDED A CALL FROM | | A CONCERNED MEMBER OF THE PUBLIC TO THE NRC OPERATIONS CENTER. THE | | INDIVIDUAL RECENTLY PURCHASED A HOME IN SAGINAW, MICHIGAN, AND WHILE | | CLEANING OUT THE BASEMENT OF THE HOME HE FOUND A SMALL BLUE CAN WITH A | | RADIOACTIVE MATERIALS LABEL ON IT. THE INDIVIDUAL OPENED THE CAN BEFORE | | NOTICING THE LABEL WHICH STATED, "RADIOACTIVE MATERIAL - DO NOT OPEN." | | THE BLUE CAN CONTAINED A METAL CYLINDER WITH A HOLE IN THE MIDDLE, AND | | THERE WAS A SHAFT WITH A CAP ON IT INSIDE THE HOLE. THE INDIVIDUAL | | RECLOSED THE CONTAINER AND PLACED THE MATERIAL OUTSIDE THE HOME IN A SHED. | | THE INDIVIDUAL WAS WEARING GLOVES AT THE TIME. | | | | NRC REGION 3 (CAMERON) STATED THAT AN NRC REGION 3 INSPECTOR WILL BE IN | | SAGINAW THIS AFTERNOON PERFORMING AN INSPECTION AT ANOTHER SITE. NRC | | REGION 3 (CAMERON) PLANS TO CALL THE INDIVIDUAL AND INFORM HIM THAT AN NRC | | INSPECTOR WILL COME BY TO PERFORM A SURVEY OF THE MATERIAL. | | | | THE NATIONAL RESPONSE CENTER NOTIFIED THE CENTERS FOR DISEASE CONTROL, | | DEPARTMENT OF ENERGY, ENVIRONMENTAL PROTECTION AGENCY (EPA) OFFICE OF AIR | | AND RADIATION, EPA REGION V, NATIONAL OCEANIC AND ATMOSPHERIC | | ADMINISTRATION, AND DEPARTMENT OF NATURAL RESOURCES. AT 1311, EPA REGION V | | (JENSEN) CALLED THE NRC OPERATIONS CENTER FOR ADDITIONAL INFORMATION AND | | FOR AN NRC REGION 3 CONTACT NAME AND TELEPHONE NUMBER. | | | | (REFER TO THE HOO LOG FOR THE INDIVIDUAL'S NAME, TELEPHONE NUMBER, AND | | ADDRESS AND FOR AN EPA REGION V CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32396 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SENECA ARMY DEPOT ACTIVITY |NOTIFICATION DATE: 05/27/97 | | CITY: ROMULUS REGION: 1 |NOTIFICATION TIME: 15:40 [ET]| | COUNTY: STATE: NY |EVENT DATE: 05/27/97 | |LICENSE#: SUC-1275 AGREEMENT: Y |EVENT TIME: 15:30[EDT]| | DOCKET: |LAST UPDATE DATE: 05/27/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON, REG 3 RDO | | | | +------------------------------------------------+ROBERT BORES, REG 1 RD0 | |NRC NOTIFIED BY: MICHAEL R. LEWIS | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAD1 20.2202(a)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IMMEDIATE NOTIFICATION OF A FILM BADGE EXPOSURE OF 61 REM BY THE SENECA | | ARMY DEPOT ACTIVITY INSTALLATION LOCATED IN ROMULUS, NEW YORK | | | | AT 1530 EST ON MAY 27, 1997, THE SENECA ARMY DEPOT ACTIVITY INSTALLATION | | LOCATED IN ROMULUS, NEW YORK, WAS NOTIFIED BY THE SAVANNA ARMY DEPOT | | ACTIVITY INSTALLATION OF A THERMOLUMINESCENT DOSIMETER (TLD) WHICH | | INDICATED EXPOSURE TO GAMMA RADIATION OF 61 REM SHALLOW (7 MG PER SQUARE CM | | DEPTH) AND 61 REM DEEP (1,000 MG PER SQUARE CM DEPTH) DOSE EQUIVALENTS. | | THE TLD WAS LISTED AS WHOLE BODY FOR THE WEARING PERIOD OF OCTOBER 25, 1992 | | TO JANUARY 23, 1993. | | | | THE TLD WAS DISCOVERED AT THE SAVANNA ARMY DEPOT ACTIVITY INSTALLATION ON | | THE MORNING OF APRIL 28, 1997. THE TLD WAS LOCATED ON THE 30-MM | | DEMILITARIZATION LINE INSIDE A CNU-TYPE CONTAINER WHICH HELD APPROXIMATELY | | 575 AIR FORCE 30-MM DEPLETED URANIUM CARTRIDGES. IT IS CURRENTLY BELIEVED | | THAT THE TLD FELL INTO THE CONTAINER AT THE SENECA ARMY DEPOT ACTIVITY | | INSTALLATION DURING THE WEARING PERIOD REFERENCED ABOVE AND THAT THE | | CONTAINER WAS TRANSPORTED TO THE SAVANNA ARMY DEPOT ACTIVITY INSTALLATION, | | WHERE IT HAS SPENT THE REMAINING YEARS IN STORAGE. | | | | (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER AND ADDRESS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32397 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/27/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 16:59 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/27/97 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: SCOTT DAVIS |LAST UPDATE DATE: 05/27/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED AUTOMATIC SWAP OF THE HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM | | SUCTION FROM THE CONDENSATE STORAGE TANK (CST) TO THE SUPPRESSION POOL | | DURING SURVEILLANCE TESTING | | | | AT 2219 ON MAY 16, 1997, THE HPCS SYSTEM AUTOMATICALLY SWAPPED SUCTION FROM | | THE CST TO THE SUPPRESSION POOL DURING PERFORMANCE TESTING. AT THE TIME, | | THE HPCS SYSTEM WAS ALIGNED TO TAKE A SUCTION FROM THE CST AND RETURN WATER | | TO THE CST. THE TRANSMITTERS WERE ISOLATED, AND THE LICENSEE BELIEVES THAT | | A TEMPERATURE CHANGE IN THE ISOLATED INSTRUMENT LINES CAUSED A FALSE HIGH | | SUPPRESSION POOL LEVEL SIGNAL WHICH IN TURN CAUSED THE HPCS PUMP SUCTION TO | | AUTOMATICALLY SWAP OVER TO THE SUPPRESSION POOL. (THE SUPPRESSION POOL | | LEVEL DID NOT ACTUALLY CHANGE.) THE CST VALVES RECEIVED CLOSE SIGNALS WHEN | | THE SWAP OCCURRED, AND THE PUMP WENT TO MINIMUM FLOW SUPPRESSION POOL TO | | SUPPRESSION POOL. OPERATORS RECOGNIZED THE SITUATION AND SHUT THE SYSTEM | | DOWN. THERE WAS NO CORE SPRAY INJECTED INTO THE REACTOR VESSEL. | | | | A SIMILAR EVENT (#11337) OCCURRED IN 1988. THE LICENSEE SUBSEQUENTLY | | DETERMINED THAT THE PREVIOUS EVENT WAS NOT REPORTABLE BECAUSE IT WAS NOT | | CONSIDERED TO BE AN ENGINEERED SAFETY FEATURE ACTUATION, AND THIS | | DETERMINATION WAS PROCEDURALIZED IN 1988. THE LICENSEE'S REGULATORY | | AFFAIRS DEPARTMENT REVIEWED THE MAY 16, 1997 EVENT AND DETERMINED IT TO BE | | REPORTABLE AT 1600 ON MAY 27, 1997. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+