U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/28/97 - 08/29/97 ** EVENT NUMBERS ** 32708 32832 32833 32834 32835 32836 32837 32838 32839 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32708 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/31/97 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 22:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/31/97 | +------------------------------------------------+EVENT TIME: 21:02[EDT]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 08/28/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED AUTOMATIC START OF THE TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP | | | | A PLANT OPERATOR CLEARED TAGS ON THE '23' AUXILIARY FEEDWATER (AFW) PUMP | | AND RESET THE TRIP VALVE AND OVERSPEED DEVICE FOR THE PUMP. THE PUMP THEN | | AUTOMATICALLY STARTED ABOUT FOUR TO FIVE MINUTES LATER WITHOUT A VALID | | ACTUATION SIGNAL. THE CAUSE OF THE AUTOMATIC START IS UNKNOWN, BUT IT WILL | | BE INVESTIGATED. | | | | THE AFW PUMP DID NOT INJECT WATER INTO THE STEAM GENERATORS. PUMP | | DISCHARGE WAS DIRECTED THROUGH A RECIRCULATION LINE BACK TO THE AFW TANK. | | STEAM GENERATOR LEVELS ARE BEING MAINTAINED BY THE MOTOR-DRIVEN AFW PUMPS. | | THE LICENSEE PLANS TO REMAIN IN MODE 4 UNTIL REPAIRS ARE COMPLETE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1655 ON 08/28/97 BY STEVE SAUER ENTERED BY JOLLIFFE * * * | | | | THE '23' AFW PUMP STARTED WHEN THE PUMP WAS BEING RETURNED FROM MAINTENANCE | | ACTIVITIES IMMEDIATELY AFTER THE EQUIPMENT OPERATOR HAD RESET THE TRIP | | VALVE ('2MS52') DUE TO THE '2MS132' GOVERNOR VALVE BEING OPEN. WHEN THE | | OPERATOR RESET THE '2MS52' VALVE, THE '23' AFW PUMP STARTED BUT THIS WAS | | NOT IMMEDIATELY RECOGNIZED BY THE OPERATOR DUE TO THE NOISE OF THE OTHER | | RUNNING PUMPS IN THE AREA AND THE LOW STEAM PRESSURE (<100 PSIG) ON THE | | MAIN STEAM HEADER FEEDING THE AFW PUMP TURBINE. THERE WERE NO VALID ESF | | SIGNALS PRESENT THAT WOULD HAVE STARTED THE PUMP. THE REASON FOR THE | | '2MS132' VALVE BEING IN THE OPEN POSITION IS STILL UNDER INVESTIGATION. | | | | SINCE THE START OF THE '23' AFW PUMP DID NOT OCCUR AS THE RESULT OF AN ESF | | SIGNAL, THE LICENSEE DESIRES TO RETRACT THIS EVENT REPORT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO JIM LINVILLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32832 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 08/28/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 00:23 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 08/27/97 | +------------------------------------------------+EVENT TIME: 20:25[CDT]| |NRC NOTIFIED BY: SALGADO |LAST UPDATE DATE: 08/28/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAS DECLARED THE 2/3 EMERGENCY DIESEL GENERATOR (EDG) INOPERABLE. | | | | DURING THE PERFORMANCE OF DIESEL GENERATOR SURVEILLANCE, DOS 6600-01, TO | | RETURN THE 2/3 EDG TO OPERABLE STATUS, THE EDG TRIPPED DUE TO A LOW ENGINE | | WATER PRESSURE SIGNAL. THE TRIP WAS SUBSEQUENTLY RESET LOCALLY BY AN | | OPERATOR, BUT THE EDG RESTARTED DUE TO THE CONTROL SWITCH REMAINING IN THE | | START POSITION. IT TRIPPED AGAIN ON THE LOW ENGINE WATER PRESSURE SIGNAL | | AND THIS TIME THE CONTROL SWITCH WAS PLACED TO THE STOP POSITION. THE | | CAUSE OF THE LOW ENGINE WATER PRESSURE TRIP IS CURRENTLY BEING | | INVESTIGATED. THEY ARE IN A 7 DAY LCO ACTION STATEMENT AND THE 2/3 EDG IS | | STILL INOPERABLE. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32833 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/28/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 04:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/28/97 | +------------------------------------------------+EVENT TIME: 04:00[EDT]| |NRC NOTIFIED BY: WISNIEWSKI |LAST UPDATE DATE: 08/28/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |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 +------------------------------------------------------------------------------+ | TWO RECIRC SYSTEM PRIMARY CONTAINMENT ISOLATION SAMPLE VALVES INOPERABLE. | | | | DURING A SURVEILLANCE TEST OF TWO IN-SERIES RECIRC SYSTEM SAMPLE VALVES | | (#RV-39 & 40) (PRIMARY CONTAINMENT ISOLATION VALVES), THE LICENSEE | | DETERMINED THAT THE VALVES FAILED TO ISOLATE FLOW AS WAS INDICATED AT THE | | CHEMISTRY SAMPLE SINK. THE LICENSEE DECLARED THESE VALVES INOPERABLE AND | | ENTERED TS LCO ACTION STATEMENT 3.7.D.3 TO BE IN COLD SHUTDOWN CONDITION | | WITHIN 24 HOURS. THE LICENSEE IS INVESTIGATING THE PROBLEM. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND WILL NOTIFY STATE | | OFFICIALS. | | | | * * * UPDATE AT 1745 BY DENNIS MAY ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE REPAIRED AND SHUT SAMPLE VALVE #RV-39, DECLARED IT OPERABLE, | | AND EXITED TS LCO A/S 3.7.D.3. THE LICENSEE IS INCREASING POWER FROM 70%. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED R1DO JIM LINVILLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32834 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DEPARTMENT OF ARMY (ACALA) |NOTIFICATION DATE: 08/28/97 | | CITY: FAYETTEVILLE REGION: 2 |NOTIFICATION TIME: 09:15 [ET]| | COUNTY: HOKE STATE: NC |EVENT DATE: 08/28/97 | |LICENSE#: 12-00722-13 AGREEMENT: Y |EVENT TIME: 08:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/28/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MIKE JORDAN, R3 RDO | | |Dr. COOL, NMSS EO | +------------------------------------------------+PAUL FREDRICKSON, R2 RDO | |NRC NOTIFIED BY: JEFF HAVENNER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING AN INVENTORY CHECK AT FORT BRAGG, NC., THE LICENSEE DISCOVERED THAT | | A CHEMICAL DETECTOR CONTAINING 250 MICROCURIES OF AMERICIUM-241 HAS BEEN | | MISSING SINCE 1995 OR 1996. | | | | THE DEPARTMENT OF ARMY (ACALA), ROCK ISLAND, IL, WAS NOTIFIED BY FORT BRAGG | | THAT DURING AN INVENTORY CHECK, THE LICENSEE DISCOVERED THAT A CHEMICAL | | DETECTOR (#M43A1) CONTAINING 250 MICROCURIES OF AMERICIUM-241 HAS BEEN | | MISSING SINCE 1995 OR 1996. THE SOURCE WAS MANUFACTURED BY NUCLEAR | | RADIATION DEVELOPMENTS, GRAND ISLAND, NY, IN 1984 OR 1985. THE DETECTOR | | WAS MADE BY BRUNSWICK COMPANY, DeLAND, FL. (THE COMPANY HAS CHANGED | | ITS NAME BUT THE CALLER DID NOT KNOW THE PRESENT NAME OF THE COMPANY). | | THE CALLER DID NOT KNOW THE SERIAL NUMBER OF THE DETECTOR OR THE SERIAL | | NUMBER OF THE SOURCE. | | | | (REFER TO THE HOO LOG BOOK FOR CONTACT TELEPHONE NUMBERS) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32835 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 08/28/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 12:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/28/97 | +------------------------------------------------+EVENT TIME: 10:50[CDT]| |NRC NOTIFIED BY: CURT BASNER |LAST UPDATE DATE: 08/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -ECC SYSTEMS POTENTIALLY INOPERABLE IN THE PAST DUE TO CROSS-TIE OF DC | | BUSES | | | | IN MARCH, 1997, THE LICENSEE IDENTIFIED THAT A DC BUS WOULD BE MADE | | INOPERABLE WHEN CROSS-TYING TO THE OPPOSITE UNIT'S DC BUS DUE TO THE | | POSSIBLE LACK OF CAPABILITY OF THE OPPOSITE UNIT'S BATTERY TO HANDLE TWO | | BUSES AND THAT THE CROSS-TIE SWITCH MAY BE UNABLE TO HANDLE THE AMPERAGE. | | | | THIS NOTIFICATION IS BEING MADE TO DOCUMENT THAT PLANT EVOLUTIONS IN THE | | PAST MAY HAVE PLACED THE DC BUSES IN THE ABOVE CONFIGURATION CONCURRENT | | WITH THE REQUIRED REDUNDANT EQUIPMENT BEING INOPERABLE. POTENTIALLY, | | THIS CONDITION COULD HAVE RENDERED MULTIPLE EMERGENCY CORE COOLING SYSTEM | | TRAINS INOPERABLE AND THE LICENSEE WOULD NOT HAVE RECOGNIZED THIS | | CONDITION. | | | | SUBSEQUENT TO IDENTIFYING THIS CONDITION, NEITHER UNIT 1 NOR UNIT 2 HAVE | | BEEN ABOVE MODE 5 AND EMERGENCY CORE COOLING SYSTEMS HAVE NOT BEEN REQUIRED | | TO BE OPERABLE. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE PLANS TO SUBMIT A LICENSEE EVENT REPORT REGARDING THIS EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32836 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/28/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:11 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/28/97 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 08/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 80 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTROL AREA CHILLED WATER SYSTEM CHILLERS COULD BE INOP DURING WINTER - | | | | WHILE REVIEWING PLANT SYSTEM DESIGNS, THE LICENSEE IDENTIFIED A CONDITION | | ASSOCIATED WITH THE SAFETY RELATED CONTROL AREA CHILLED WATER SYSTEM | | CHILLER UNITS THAT COULD HAVE PREVENTED THE FULFILLMENT OF A SAFETY | | FUNCTION NECESSARY TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. THE | | CHILLED WATER SYSTEM FUNCTIONS TO MAINTAIN DESIGN AIR TEMPERATURES IN THE | | CONTROL ROOM AND OTHER AREAS IN THE AUXILIARY BUILDING. | | | | IN THE EVENT OF AN ACCIDENT RESULTING IN A LOSS OF INSTRUMENT AIR, THE | | SAFETY RELATED CONTROL AREA CHILLED WATER SYSTEM CHILLER UNITS WOULD | | RECEIVE FULL FLOW FROM THE SAFETY AUXILIARY COOLING (SAC) SYSTEM SINCE THE | | CHILLER CONDENSER PRESSURE CONTROL VALVE FAILS OPEN. WHEN THE PRESSURE | | CONTROL VALVE FAILS OPEN, MAXIMUM COOLING IS PROVIDED TO THE CONDENSER | | WHICH CAN RESULT IN A LOW EVAPORATOR PRESSURE TRIP IF COOLING WATER | | TEMPERATURE IS EXCESSIVELY LOW. BASED ON INFORMATION PROVIDED BY THE | | CHILLER MANUFACTURER, THERE IS REASONABLE ASSURANCE OF CHILLER OPERABILITY | | UNDER THIS CONDITION WHEN THE SAC SYSTEM TEMPERATURE IS AT LEAST 55øF. | | HOWEVER, DURING THE WINTER MONTHS, SAC SYSTEM TEMPERATURES ARE EXPECTED TO | | BE LESS THAN 55øF AS THEY ARE COOLED BY DELAWARE RIVER WATER. | | | | THE LICENSEE HAS REASONABLE ASSURANCE OF CONTINUED CHILLER OPERABILITY | | SINCE THE CURRENT DELAWARE RIVER WATER TEMPERATURE IS STABLE AT 76øF AND | | NOT EXPECTED TO REACH 55øF UNTIL EARLY-TO-MID NOVEMBER, 1997. UNDER ALL | | CONDITIONS, SAC SYSTEM TEMPERATURES WILL BE EQUAL TO OR GREATER THAN RIVER | | WATER TEMPERATURE. ALL EMERGENCY CORE COOLING SYSTEMS AND SAFETY RELATED | | SYSTEMS ARE OPERATIONAL. THE LICENSEE NOTIFIED LOCAL OFFICIALS AND THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32837 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: TRU-TEC COMPANY |NOTIFICATION DATE: 08/28/97 | | CITY: NEW CASTLE REGION: 1 |NOTIFICATION TIME: 14:09 [ET]| | COUNTY: STATE: DE |EVENT DATE: 08/28/97 | |LICENSE#: 07-28386-01 AGREEMENT: N |EVENT TIME: 13:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/28/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES LINVILLE, R1 RDO | | |DON COOL, NMSS EO | +------------------------------------------------+PAUL FREDRICKSON, R2 RDO | |NRC NOTIFIED BY: NORMAN LANIER |JEFF SHACKELFORD, R4 RDO | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - THREE RADIOACTIVE CESIUM-137 SOURCES MISSING - | | | | TRU-TEC COMPANY EMPLOYEES SHIPPED A CONTAINER CONTAINING THREE RADIOACTIVE | | CESIUM-137 SOURCES (1 MILLICURIE, 18 MILLICURIES, & 100 MILLICURIES) BY | | FEDERAL EXPRESS TRUCK AND PLANE FROM NEW CASTLE, DE, TO WILMINGTON, NC. | | WHEN THE CONTAINER WAS RECEIVED BY TRU-TEC EMPLOYEES IN WILMINGTON, NC, | | THE LOCK ON THE CONTAINER WAS MISSING AND THE THREE SOURCES WERE MISSING. | | | | THE TRU-TEC REPRESENTATIVE NOTIFIED THE NATIONAL RESPONSE CENTER | | (INCIDENT REPORT #401301) WHO NOTIFIED THE NRC OPERATIONS OFFICER, | | EPA REGION IV AND THE STATE OF NORTH CAROLINA. | | | | SEE HOO LOG FOR CONTACT TELEPHONE NUMBERS. | | | | * * * UPDATE AT 1516 BY TRU-TEC NORMAN LANIER ENTERED BY JOLLIFFE * * * | | | | FEDERAL EXPRESS LOCATED THE MISSING SOURCES IN THEIR FACILITY IN | | MEMPHIS, TN. | | | | THE OPERATIONS NOTIFIED THE ABOVE INDIVIDUALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32838 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DEFENSE DISTRIBUTION DEPOT |NOTIFICATION DATE: 08/28/97 | | CITY: LETTERKENNY REGION: 1 |NOTIFICATION TIME: 16:16 [ET]| | COUNTY: STATE: PA |EVENT DATE: 08/27/97 | |LICENSE#: 37-30062-01 AGREEMENT: N |EVENT TIME: 10:30[EDT]| | DOCKET: |LAST UPDATE DATE: 08/28/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES LINVILLE RDO | | |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM LINVILLE, R1DO | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SEVEN 3-CURIE TRITIUM SOURCES MISSING AND PRESUMED TO BE STOLEN - | | | | ALLEN HILSMEIER, RADIATION SAFETY OFFICER, DEFENSE DISTRIBUTION DEPOT, | | REPORTED TO NRC REGION 1 THAT SEVEN 3-CURIE TRITIUM SOURCES WERE MISSING | | FROM THEIR FACILITY IN LETTERKINNEY, PA. MR HILSMEIER INTERVIEWED ALL | | EMPLOYEES WHO COULD HAVE BEEN INVOLVED EXCEPT ONE WHO RECENTLY RESIGNED. | | MR HILSMEIER WAS CONVINCED THAT THE SOURCES WERE STOLEN, NOT LOST OR | | MISPLACED DURING A SHIFT BY AN EMPLOYEE. THE LICENSEE HAS INITIATED ITS | | OWN CRIMINAL INVESTIGATION. THE LICENSEE HAS SWIPED ALL WORKING AREAS WITH | | NO EVIDENCE OF CONTAMINATION AND IS PERFORMING A PHYSICAL INVENTORY OF ALL | | RADIOACTIVE SOURCES. | | | | * * * UPDATE AT 1702 BY GLORIA WRIGHT ENTERED BY JOLLIFFE * * * | | | | GLORIA WRIGHT, DEPUTY COMMANDER, DEFENSE DISTRIBUTION DEPOT, REPORTED THE | | SAME EVENT TO THE NRC OPERATIONS OFFICER. | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO JIM LINVILLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32839 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/28/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/28/97 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 08/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN 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 92 POWER OPERATION | 92 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AVAILABLE WATER VOLUME IN RWST NOT ADEQUATE IN MODES 5 AND 6 - | | | | DURING THE ONGOING NRC AE DESIGN INSPECTION, NRC INSPECTORS ASKED A | | QUESTION ABOUT THE REACTOR COOLANT MAKEUP REQUIRED AFTER A 10CFR50, | | APPENDIX R FIRE. TO RESPOND TO THE QUESTION, THE LICENSEE REVIEWED | | TWO ASSOCIATED DESIGN CALCULATIONS. THE MORE RESTRICTIVE CALCULATION | | WAS DETERMINED TO BE THE CALCULATION OF RECORD TO MEET THE REQUIREMENT. | | THIS CALCULATION REQUIRES 87,000 GALLONS OF WATER TO BE AVAILABLE IN THE | | REFUELING WATER STORAGE TANK (RWST). THE VALUE OF 87,000 GALLONS WAS | | APPROVED ON 02/20/90. DURING MODES 1 THROUGH 4, PLANT PROCEDURES | | ADEQUATELY ENSURE THAT THIS REQUIREMENT IS MET. DURING MODES 5 AND 6, | | PLANT PROCEDURES ARE NOT ADEQUATE TO ENSURE THAT THIS REQUIREMENT IS MET. | | THE PLANT HAS BEEN IN MODES 5 AND 6 MANY TIMES SINCE THIS REQUIREMENT | | BECAME EFFECTIVE ON 02/20/90. BASED ON THIS, THE PLANT HAS BEEN IN AN | | UNANALYZED CONDITION SEVERAL TIMES SINCE 02/20/90. | | | | CURRENTLY BOTH UNITS ARE IN MODE 1. THE LICENSEE IS REVIEWING PLANT | | OPERATING PROCEDURES TO DETERMINE IMPACT AND WILL IMPLEMENT PROCEDURE | | CHANCES AS NEEDED PRIOR TO EITHER UNIT ENTERING MODES 5 OR 6. THE LICENSEE | | IS CONTINUING TO EVALUATE THE SUBJECT CALCULATIONS AND PLANS TO SUBMIT A | | LICENSEE EVENT REPORT TO THE NRC ON THIS SUBJECT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+