U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/07/98 - 08/10/98 ** EVENT NUMBERS ** 34613 34614 34615 34616 34617 34618 34619 34620 34621 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34613 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 08/07/98 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 05:52 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 08/07/98 | +------------------------------------------------+EVENT TIME: 03:20[EDT]| |NRC NOTIFIED BY: DOUGLAS BAUDER |LAST UPDATE DATE: 08/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM MOSLAK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE MAIN STEAM SAFETY VALVES DISCOVERED TO HAVE EXCESSIVE INITIAL LIFT | | SETPOINTS | | | | WHILE PERFORMING MAIN STEAM SAFETY VALVE TESTING, THREE OF SIXTEEN MAIN | | STEAM SAFETY VALVES TESTED HAD INITIAL LIFT PRESSURES IN EXCESS OF THE | | LIMIT ALLOWED BY PLANT TECHNICAL SPECIFICATIONS. THE PRESSURE LIMIT OF | | TECHNICAL SPECIFICATION 3.7.1.1 IS 995 PSIG. THE VALVES AND THEIR AS-FOUND | | INITIAL LIFT PRESSURES ARE AS FOLLOWS: | | | | VALVE LIFT PRESSURE | | 2-RV-4001 1007 PSIG | | 2-RV-4000 1015 PSIG | | 2-RV-3992 1001 PSIG | | | | THESE VALVES WERE READJUSTED AND RETESTED TWICE SATISFACTORILY. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34614 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 08/07/98 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 10:12 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/07/98 | +------------------------------------------------+EVENT TIME: 09:40[EDT]| |NRC NOTIFIED BY: J. BURGESS |LAST UPDATE DATE: 08/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE ERNSTES RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO ICE ACCUMULATION IN ICE | | BED FLOW CHANNELS | | | | ON 8/5/98, DURING THE PERFORMANCE OF A TECHNICAL SPECIFICATION (TS) | | SURVEILLANCE ON THE ICE CONDENSER ICE BED FLOW CHANNELS, SEVERAL FLOW | | CHANNELS WERE DISCOVERED TO BE BLOCKED BY A BUILDUP OF ICE GREATER THAN | | 0.38 INCHES THICK. THE LICENSEE DECLARED THE ICE BED INOPERABLE AND ENTERED | | TS ACTION STATEMENT 3.6.5.1, WHICH REQUIRES THE ICE CONDENSER BED TO | | RESTORED TO OPERABLE STATUS WITHIN 48 HOURS. | | | | DUE TO DIFFICULTIES IN CLEARING SOME OF THE FLOW CHANNELS WITHIN THE LCO | | TIME CONSTRAINTS, THE LICENSEE COMMENCED A UNIT SHUTDOWN IN ACCORDANCE WITH | | THE TSs. THE LICENSEE REPORTED THAT THE UNIT WILL BE REQUIRED TO BE IN HOT | | STANDBY WITHIN 6 HOURS. THE LICENSEE INTENDS TO REMAIN IN MODE 3 UNTIL THE | | ICE BED IS DECLARED OPERABLE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34615 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/07/98 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/07/98 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: MARI JAWORSKY |LAST UPDATE DATE: 08/07/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM MOSLAK RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 10CFR21 REPORT - DEFECTIVE GAS TURBINE GENERATOR TACHOMETER TRANSDUCER | | | | MILLSTONE UNIT 1 USES ONE DIESEL GENERATOR AND ONE GAS TURBINE GENERATOR | | (GTG) FOR DEDICATED EMERGENCY POWER TO VITAL AC BUSES DURING AN EVENT. | | | | THE GTG IS A GE LM-1500 GENERATOR THAT UTILIZES TACHOMETER TRANSDUCERS | | (TTs) TO PROVIDE THE GOVERNOR WITH THE SPEED SIGNALS FROM THE GTG AND THE | | DIESEL GENERATOR. ONE OF THESE TTs THAT WAS ACCEPTED FROM EITEL | | MANUFACTURING COMPANY, CAPISTRANO BEACH, CA, (BERKELEY MODEL #466-120) | | WAS LATER DETERMINED TO HAVE THE FINGER SPRING WASHER INSTALLED IN THE | | INCORRECT ORIENTATION IN THE TT RESULTING IN AN IMPROPER FIT OF THE | | BEARINGS. BEARING FAILURE WOULD INCREASE VIBRATION IN THE TT ASSEMBLY | | POSSIBLY RESULTING IN EARLY FAILURE OF THE WINDINGS, OR SEIZURE AND | | BREAKAGE OF THE SHAFT. EITHER FAILURE WOULD RESULT IN A LOSS OF SPEED | | SIGNAL TO THE GOVERNOR. | | | | THIS TT PROVIDES AN OVERSPEED SIGNAL TO THE GOVERNOR. A TRIP IS INITIATED | | IF THE SIGNAL IS LOST. IN THE EVENT THAT THE GTG IS OPERATING IN AN | | EMERGENCY, WITH AN ACCIDENT SIGNAL PRESENT, THE TRIP IS BYPASSED. | | | | THESE TTs ARE PRODUCED COMMERCIALLY AND ARE DEDICATED FOR THIS SAFETY | | RELATED APPLICATION BY MILLSTONE. THE TT WITH THE DEFECT WAS ACCEPTED | | AND INSTALLED IN ID LOCATION TG-25-5. | | | | THE DEFECTIVE TT INSTALLED IN LOCATION TG-25-5 IS COUPLED TOGETHER ON THE | | SAME DRIVE MECHANISM WITH A TT OF THE SAME DESIGN INSTALLED IN LOCATION | | TG-25-1. THE SIGNAL FROM THE TT INSTALLED IN LOCATION TG-25-1 PROVIDES | | THE FEEDBACK TO THE GOVERNOR FOR SPEED CONTROL OF THE ELECTRIC GENERATOR. | | WITHOUT THIS SPEED SIGNAL, THE GOVERNOR CANNOT CONTROL THE FREQUENCY OF | | THE GENERATOR WHICH WOULD PREVENT SYNCHRONIZATION TO THE VITAL AC BUSES. | | FAILURE OF THE TT INSTALLED IN LOCATION TG-25-5 COULD HAVE CAUSED THE | | FAILURE OF THE TT INSTALLED IN LOCATION TG-25-1, RENDERING THE GTG | | UNAVAILABLE TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. IN THIS SITUATION, | | THE GTG WOULD NOT BE ABLE TO PERFORM ITS SAFETY FUNCTION. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THIS CONDITION AND IS DETERMINING | | CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34616 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 08/07/98 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 16:32 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 08/07/98 | +------------------------------------------------+EVENT TIME: 15:15[CDT]| |NRC NOTIFIED BY: RICK PEARSON |LAST UPDATE DATE: 08/07/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 32 SAFETY RELATED MOTOR OPERATED VALVES(MOVs) COULD BE DAMAGED BY A | | FIRE-INDUCED HOT SHORT - | | | | AS PART OF THE PRAIRIE ISLAND FIRE PROTECTION SELF-ASSESSMENT, THE LICENSEE | | PERFORMED A REVIEW OF NRC INFORMATION NOTICE 92-18. | | | | THE LICENSEE PERFORMED A CALCULATION TO DETERMINE THE VALVE AND OPERATOR | | THRUST AND TORQUE VALUES THAT COULD OCCUR DURING A HOT SHORT THAT BYPASSES | | THE LIMIT SWITCHES OR TORQUE SWITCHES. THE CALCULATION ADDRESSED | | 46 APPENDIX R-RELATED MOVs WITH LIMITORQUE OPERATORS AND FOUND THAT 32 OF | | THESE VALVES COULD BE PHYSICALLY DAMAGED BY A FIRE INDUCED HOT SHORT. | | | | AFFECTED SYSTEMS INCLUDE THE RESIDUAL HEAT REMOVAL, COMPONENT COOLING | | WATER, SAFETY INJECTION, REACTOR COOLANT, AND AUXILIARY FEEDWATER SYSTEMS. | | | | THE LICENSEE HAS ESTABLISHED HOURLY ROVING FIRE WATCHES IN PLANT AREAS THAT | | COULD AFFECT THE ABOVE VALVES AND THEIR ELECTRICAL CABLES PENDING FURTHER | | EVALUATION OF THIS ISSUE. | | | | NONE OF THESE VALVES HAVE BEEN DECLARED INOPERABLE AND THIS ISSUE HAS NO | | ADVERSE IMPACT ON PRESENT PLANT OPERATIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34617 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING, INC. |NOTIFICATION DATE: 08/07/98 | | CITY: REGION: 4 |NOTIFICATION TIME: 16:58 [ET]| | COUNTY: JOHNSON STATE: WY |EVENT DATE: 08/06/98 | |LICENSE#: SUA-134 AGREEMENT: N |EVENT TIME: 12:00[MDT]| | DOCKET: |LAST UPDATE DATE: 08/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM JOHNSON RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+JOE HOLONICH NMSS | |NRC NOTIFIED BY: JOHN VASELIN | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -GROUND WATER MONITOR WELL AT URANIUM LEACH MINE PLACED IN EXCURSION STATUS | | | | AT 1200 MDT ON 08/06/98, SITE PERSONNEL PLACED GROUND WATER MONITOR WELL | | #MW-89, AT THE COGEMA MINING, INC, CHRISTENSEN IN-SITU URANIUM LEACH | | MINE IN JOHNSON COUNTY, WY, IN EXCURSION STATUS. THIS WAS DONE AFTER | | DETERMINING THAT THE LEVELS OF CHLORIDES AND ALKALINITY IN A SAMPLE OF | | THE WELL WATER WERE ABOVE THE UPPER CONTROL LIMITS. THE CONDUCTIVITY | | LEVEL OF THE SAMPLE REMAINED BELOW THE UPPER CONTROL LIMIT. | | | | AT 1100 MDT ON 08/07/98, SITE PERSONNEL ANALYZED A SECOND SAMPLE OF THE | | WELL WATER (VERIFICATION SAMPLE) AND DETERMINED THAT THE CHLORIDE LEVEL | | OF THE SAMPLE WAS 14.4 MILLIGRAMS PER LITER (UPPER CONTROL LIMIT IS | | 13.6 MILLIGRAMS PER LITER) AND THE ALKALINITY LEVEL OF THE SAMPLE WAS | | 121.9 MILLIGRAMS PER LITER (UPPER CONTROL LIMIT IS 121.0 MILLIGRAMS PER | | LITER). | | | | THE LICENSEE PLANS TO PUMP MORE WATER FROM THE AREA OF THE MONITOR WELL | | IN ORDER TO DECREASE THE CHLORIDE AND ALKALINITY LEVELS. | | | | THERE WERE NO SPILLS OR RADIOLOGICAL RELEASES ASSOCIATED WITH THIS EVENT. | | | | THE LICENSEE NOTIFIED THE WYOMING DEPARTMENT OF ENVIRONMENTAL QUALITY AND | | PLANS TO SUBMIT A WRITTEN REPORT OF THIS EVENT TO THE NRC WITHIN 7 DAYS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 34618 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTERN PENNSYLVANIA HOSPITAL |NOTIFICATION DATE: 08/07/98 | | CITY: PITTSBURGH REGION: 1 |NOTIFICATION TIME: 17:03 [ET]| | COUNTY: ALLEGHENY STATE: PA |EVENT DATE: 07/28/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM MOSLAK RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MILE PACILIO, RAD SAF OFF | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - OVEREXPOSURE OF A 4 YEAR OLD CHILD DUE TO BREAST FEEDING BY HIS MOTHER - | | | | ON 07/28/98, A 43 YEAR OLD FEMALE PATIENT REPORTED TO WESTERN PENNSYLVANIA | | HOSPITAL TO BE EVALUATED FOR THYROID ABLATION THERAPY. DURING CONSULTATION | | WITH HOSPITAL PERSONNEL, THE PATIENT DENIED BREAST FEEDING HER 4 YEAR OLD | | SON. THE PATIENT CLEARLY HAD THE ABILITY TO SPEAK AND UNDERSTAND THE | | ENGLISH LANGUAGE. A HOSPITAL RADIATION TECHNOLOGIST ADMINISTERED A 3.02 | | MILLICURIE CAPSULE OF I-131 TO THE PATIENT IN PREPARATION FOR A WHOLE BODY | | SCAN SCHEDULED ON 07/31/98. | | | | ON 07/31/98, THE PATIENT RETURNED TO THE HOSPITAL FOR A WHOLE BODY SCAN. | | THE PATIENT WAS COUNSELLED BY THE ATTENDING HOSPITAL PHYSICIAN AND A | | MEMBER OF THE HOSPITAL RADIATION SAFETY OFFICE CONCERNING THE PRECAUTIONS | | SURROUNDING THE IMPENDING ABLATION THERAPY SCHEDULED FOR 08/04/98. AFTER | | THIS COUNSELLING, THE PATIENT ADMITTED TO BREAST FEEDING HER SON DURING | | THE PREVIOUS THREE DAYS, STATING THAT SHE HAD BEEN TOO EMBARRASSED TO | | DISCLOSE THIS DURING HER PREVIOUS HOSPITAL VISIT. THREE HOSPITAL EMPLOYEES | | TOLD THE PATIENT TO IMMEDIATELY DISCONTINUE BREAST FEEDING HER SON. | | | | ON 08/03/98, THE PATIENT AND HER SON RETURNED TO THE HOSPITAL IN ORDER TO | | HAVE ANY UPTAKE BY HER SON ASSESSED. A BIOASSAY OF THE CHILD'S THYROID | | GLAND DETERMINED THAT IT HAD A BURDEN OF 2.7 MICROCURIES OF I-131, WHICH | | EQUATES TO AN ORGAN DOSE OF 184 RADS (TEDE = 5.5 RADS). DURING SUBSEQUENT | | CONVERSATIONS WITH THE PATIENT, SHE REVEALED THAT SHE HAD CONTINUED | | TO BREAST FEED HER SON OVER THE WEEKEND, INCLUDING IMMEDIATELY BEFORE | | REPORTING TO THE HOSPITAL FOR THE BIOASSAY. | | | | HOSPITAL PERSONNEL SUSPENDED ADMINISTERING ANY ADDITIONAL I-131 TO THE | | PATIENT AND ARE CONTINUING TO FOLLOW THE CONDITION OF THE PATIENT AND | | THE CHILD. THE HOSPITAL NUCLEAR PHYSICIAN NOTIFIED THE CHILD'S PHYSICIAN | | WHO IS COORDINATING FOLLOWUP CARE, INCLUDING ASSESSMENT BY A PEDIATRIC | | ENDOCRINOLOGIST AND PROTECTION BY THE LOCAL CHILD YOUTH SERVICES. | | THE HOSPITAL NUCLEAR PHYSICIAN ALSO NOTIFIED THE PATIENT'S ATTENDING | | PHYSICIAN AND SURGEON CONCERNING THIS INCIDENT IN ORDER TO COORDINATE | | THE PROTECTION OR TREATMENT ALTERNATIVES FOR THIS PATIENT. | | | | HOSPITAL PERSONNEL DO NOT PLAN TO ISSUE A PRESS RELEASE REGARDING THIS | | INCIDENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34619 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 08/07/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 19:07 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 08/07/98 | +------------------------------------------------+EVENT TIME: 15:50[PDT]| |NRC NOTIFIED BY: BRIAN GARDES |LAST UPDATE DATE: 08/07/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |BRUCE BOGER, NRR EO | |NLCO TECH SPEC LCO A/S |HOWARD WONG REG4 | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 70 POWER OPERATION | 70 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN FROM 70% POWER DUE TO INOPERABLE EDG - | | | | AT 1045 PDT ON 08/04/98, THE LICENSEE DECLARED ONE OF THREE EMERGENCY | | DIESEL GENERATORS (#2 EDG) INOPERABLE DUE TO VOLTAGE REGULATION PROBLEMS. | | TECH SPEC 3.8.1.B.4 REQUIRES THE LICENSEE TO RESTORE #2 EDG TO OPERABLE | | STATUS WITHIN 72 HOURS. LICENSEE TROUBLESHOOTING AND REPAIRS HAVE BEEN | | UNABLE TO RESTORE #2 EDG TO OPERABLE STATUS. | | | | AT 1045 PDT ON 08/07/98, THE LICENSEE ENTERED TECH SPEC 3.8.1.F WHICH | | REQUIRES THE PLANT TO BE IN CONDITION 3 (HOT SHUTDOWN) WITHIN 12 HOURS. | | | | AT 1550 PDT ON 08/07/98, THE LICENSEE COMMENCED A NORMAL PLANT SHUTDOWN | | FROM 70% POWER DUE TO AN INOPERABLE EDG. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR AND ISSUE A PRESS | | RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34620 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CROW BUTTE RESOURCES, INC. |NOTIFICATION DATE: 08/07/98 | | CITY: CRAWFORD REGION: 4 |NOTIFICATION TIME: 19:53 [ET]| | COUNTY: STATE: NE |EVENT DATE: 08/07/98 | |LICENSE#: SUA-1534 AGREEMENT: Y |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 08/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM JOHNSON RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+JOE HOLONICH NMSS | |NRC NOTIFIED BY: LELAND HUFFMAN |FEMA, DOE, USDA, HHS FAX | |HQ OPS OFFICER: DICK JOLLIFFE |EPA, DOT (NRC) FAX | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - RADIOLOGICAL LIQUID RELEASE FROM AN IN-SITU URANIUM LEACH MINE - | | | | AT 1200 MDT ON 08/07/98, SITE PERSONNEL OBSERVED INJECTION WELL #I-710 | | AT THE CROW BUTTE URANIUM PROJECT, CRAWFORD, NE, AND NOTED NO FAILURE. | | | | AT 1510 MDT ON 08/07/98, SITE PERSONNEL DISCOVERED A LEAK IN A 2 INCH UNION | | AT THE WELL HEAD OF INJECTION WELL #I-710 AND IMMEDIATELY ISOLATED THE | | LEAK. THE RELEASED MINING INJECTION SOLUTION HAD BREACHED A DIVERSION BERM | | AND ENTERED SQUAW CREEK WHICH RUNS THROUGH THE PERMIT AREA. | | | | SITE PERSONNEL DETERMINED THE FLOW RATE OF THE SPILL TO BE APPROXIMATELY | | 54 GPM. THEY ESTIMATED THE MAXIMUM RELEASE FROM THE WELL TO BE | | 10,260 GALLONS, EVEN THOUGH THEY BELIEVE THAT THE ACTUAL VOLUME OF THE | | RELEASE MAY BE MUCH LESS, IN THE RANGE OF 600 GALLONS. THEY PLAN TO | | REVIEW OPERATING RECORDS TO DETERMINE THE EXACT TIME OF THE FAILURE. | | | | BASED UPON THE AVERAGE RADIUM CONCENTRATION OF THE MINING INJECTION | | SOLUTION (BARREN LIXIVIANT) AT 1000 PICOCURIES PER LITER AND THE MAXIMUM | | RELEASED VOLUME, SITE PERSONNEL ESTIMATED THAT THE MAXIMUM RELEASE OF | | RADIUM-226 WOULD BE 38.8 MICROCURIES. | | | | SITE PERSONNEL OBTAINED WATER SAMPLES FROM SQUAW CREEK UPSTREAM AND | | DOWNSTREAM OF THE CREEK ENTRY POINT AND PLAN TO HAVE THESE SAMPLES | | ANALYZED FOR THE PRESENCE OF RADIUM-226 AND NATURAL URANIUM. | | | | SITE PERSONNEL HAVE TEMPORARILY REPAIRED THE WELL HEAD AND THE DIVERSION | | BERM PROTECTING SQUAW CREEK IN THE PERMIT AREA AND THEY EXPECT NO IMPACT | | TO DOWNSTREAM WATER USERS. THE NEAREST DOWNSTREAM IMPOUNDMENT USED FOR | | LIVESTOCK WATERING CONTAINS 65.2 MILLION GALLONS. WITH NO DILUTION OR | | ABSORPTION IN THE WELL FIELD, MAXIMUM IMPACT THE THE WATER IN THE | | IMPOUNDMENT WOULD BE AN INCREASE OF 0.16 PICOCURIES PER LITER. | | | | THE LICENSEE PLANS TO SUBMIT FURTHER INFORMATION TO THE NRC IN A WRITTEN | | REPORT WITHIN 7 DAYS IN ACCORDANCE WITH THEIR LICENSE CONDITION 12.4. | | | | THE LICENSEE' ASSESSMENT OF RISK OF THIS EVENT IS THAT NO ADVERSE IMPACT ON | | PEOPLE, LIVESTOCK, WILDLIFE, OR THE ENVIRONMENT DOWNSTREAM OF THE POINT OF | | RADIOLOGICAL RELEASE IS ANTICIPATED. | | | | NRC REPRESENTATIVES AGREE WITH THE LICENSEE'S ASSESSMENT OF RISK OF THIS | | EVENT AND THAT NO RESPONSE TO THIS EVENT FROM FEDERAL AGENCIES IS REQUIRED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34621 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 08/08/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 18:57 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 08/08/98 | +------------------------------------------------+EVENT TIME: 12:16[PDT]| |NRC NOTIFIED BY: BRIAN GARDES |LAST UPDATE DATE: 08/08/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK WHILE PLANT IS SHUTDOWN - | | | | AT 1216 PDT ON 08/08/98, WITH THE PLANT IN CONDITION 3 (HOT SHUTDOWN) AND | | COOLING DOWN TO CONDITION 4 (COLD SHUTDOWN), PLANT PERSONNEL DISCOVERED A | | REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK ON THE INSTRUMENT SENSING | | LINE FOR THE 'B' REACTOR RECIRCULATION LOOP FLOW INSIDE PRIMARY | | CONTAINMENT. | | | | THE LICENSEE ENTERED TECH SPEC 3.4.5.C WHICH REQUIRES THE PLANT TO BE IN | | CONDITION 4 WITHIN 36 HOURS DUE TO THE REACTOR COOLANT SYSTEM PRESSURE | | BOUNDARY LEAK. THE LAST UNIDENTIFIED DRYWELL LEAK RATE TEST RESULTS WERE | | 0.56 GPM ON 1015 PDT ON 08/07/98. | | | | THE LICENSEE PLANS TO ENTER THE PRIMARY CONTAINMENT AND REPAIR THE LEAK | | AFTER THE PLANT ENTERS CONDITION 4. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+