Event Notification Report for April 23, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/22/1999 - 04/23/1999 ** EVENT NUMBERS ** 35600 35611 35612 35617 35618 35619 35620 35621 35622 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35600 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/17/1999| | UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 11:58[EDT]| | RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/17/1999| +------------------------------------------------+EVENT TIME: 09:59[CDT]| | NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 04/23/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |JOHN JACOBSON R3 | |10 CFR SECTION: | | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 N Y 99 Power Operation |99 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF A PRIMARY CONTAINMENT AIR SAMPLE RETURN ISOLATION VALVE TO MEET | | MAXIMUM INSERVICE TEST STROKE-TIME REQUIREMENTS | | | | While performing quarterly valve stroke-time testing on Unit 3, a primary | | containment air sample return isolation valve exceeded its specified maximum | | stroke-time limit. The sample return line was isolated in accordance with | | Technical Specification 3.7.D for primary containment isolation valves, and | | this action satisfied the 4-hour limiting condition for operation action | | statement requirements. The second in-line primary containment isolation | | system valve remains operable. | | | | The licensee stated that no other valves failed to meet the maximum | | stroke-time limits. The licensee also stated that, during a test that was | | performed last month, the valve in question was identified as being in the | | 'Alert' time range for inservice test timing requirements and that it was | | being tested per the required increased testing frequency. Corrective | | actions are being initiated, and troubleshooting activities are in | | progress. | | | | The licensee plans to notify the NRC resident inspector. | | | | *** UPDATE ON 4/23/99 @ 0443 BY GADBOIS TO GOULD *** RETRACTION | | | | UPON FURTHER REVIEW, IT WAS DETERMINED THAT THIS EVENT DID NOT CONSTITUTE A | | REPORTABLE CONDITION SINCE THE PENETRATION HAD A OPERABLE REDUNDANT VALVE | | WHICH COULD HAVE ISOLATED THE CONTAINMENT PENETRATION. THEREFORE, THEY ARE | | RETRACTING THIS EVENT. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | | | | THE REG 3 RDO(LEACH) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35611 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/20/1999| | UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 19:21[EDT]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/20/1999| +------------------------------------------------+EVENT TIME: 18:32[EDT]| | NRC NOTIFIED BY: RAY McKINLEY |LAST UPDATE DATE: 04/22/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 | |10 CFR SECTION: |CURT COWGILL R1 | |ACCS 50.72(b)(1)(iv) ECCS INJECTION |R. BLOUGH/D. FLOREK R1 | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |ART BURRITT SRI | |AESF 50.72(b)(2)(ii) ESF ACTUATION |WILLIAM BATEMAN NRR | | |CHARLES MILLER IRO | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 A/R Y 100 Power Operation |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AUTO REACTOR SCRAM FROM 100% POWER DUE TO LOSS OF MAIN FEEDWATER; ECCS | | INJECTION - | | | | AT 1832 ON 04/20/99, WITH UNIT 1 AT 100% POWER, ALL EIGHT CONDENSATE SYSTEM | | DEEP BED DEMINERALIZER OUTLET MOTOR OPERATED VALVES FAILED CLOSED POSSIBLY | | DUE TO A COMPUTER MALFUNCTION. THE DEMINERALIZER BYPASS VALVES TRIPPED DUE | | TO THERMAL OVERLOADS AND FAILED TO OPEN, CAUSING ALL THREE STEAM DRIVEN MAIN | | FEEDWATER PUMPS TO TRIP. THE REACTOR VESSEL WATER LEVEL DROPPED FROM A | | NORMAL LEVEL OF +35 INCHES TO +12.5 INCHES, CAUSING THE REACTOR TO | | AUTOMATICALLY SCRAM FROM 100% POWER DUE TO LOW REACTOR VESSEL WATER LEVEL. | | ALL CONTROL RODS INSERTED COMPLETELY; HOWEVER, ROD #30-39 INSERTED SLOWLY. | | NO SAFETY/RELIEF VALVES LIFTED. STEAM IS BEING DUMPED TO THE MAIN | | CONDENSER. | | | | REACTOR VESSEL WATER LEVEL FURTHER DROPPED TO -38 INCHES, CAUSING THE HIGH | | PRESSURE COOLANT INJECTION (HPCI) AND THE REACTOR CORE ISOLATION COOLING | | (RCIC) SYSTEMS TO ACTUATE AND INJECT INTO THE REACTOR VESSEL. THE REDUNDANT | | REACTIVITY CONTROL SYSTEM INITIATED TO TRIP THE CIRCUIT BREAKERS FOR THE | | REACTOR RECIRCULATION PUMPS. PRIMARY CONTAINMENT ISOLATION SYSTEM GROUPS | | 1B, 2A, 2B, 2C, 3, 6A, 6B, 6C, 7B, AND 8B ISOLATED. THE DIVISION 'A' | | ATWS/RPT CIRCUIT BREAKER FOR THE 'A' RECIRC MOTOR GENERATOR SET FAILED TO | | TRIP, AS REQUIRED. SMOKE WAS OBSERVED TO BE COMING FROM THE BREAKER. THE | | BREAKER WAS MANUALLY TRIPPED FROM THE CONTROL ROOM AND THE SMOKING STOPPED. | | THE 'A' AND 'B' RECIRC MOTOR GENERATOR SET DRIVE MOTOR CIRCUIT BREAKERS ALSO | | FAILED TO TRIP ON THE 13 kV BUS FAST TRANSFER. THE BREAKERS WERE MANUALLY | | TRIPPED. | | | | REACTOR VESSEL WATER LEVEL DROPPED TO A LOW LEVEL OF -75 INCHES ABOUT 40 | | SECONDS INTO THE EVENT (TOP OF ACTIVE FUEL IS -161 INCHES). THE HPCI AND | | RCIC SYSTEMS RECOVERED REACTOR VESSEL WATER LEVEL TO +25 INCHES, AT WHICH | | TIME CONTROL ROOM OPERATORS MANUALLY SECURED THE HPCI SYSTEM. THE RCIC | | SYSTEM IS MAINTAINING REACTOR VESSEL WATER LEVEL AT +25 INCHES WITH REACTOR | | PRESSURE AT 875 PSIG AT AN INJECTION RATE OF 300 GPM. | | | | PLANT OPERATORS ENCOUNTERED A PROBLEM WITH THE AUXILIARY STEAM SYSTEM AND | | THE MECHANICAL VACUUM PUMP. THEY MANUALLY CLOSED THE MAIN STEAM ISOLATION | | VALVES. THEY ARE CONTROLLING REACTOR VESSEL WATER LEVEL WITH THE RCIC | | SYSTEM AND REACTOR COOLANT SYSTEM PRESSURE WITH THE HPCI SYSTEM. | | | | UNIT 1 IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN) AND COOLING DOWN | | TO COLD SHUTDOWN. PRIMARY CONTAINMENT PARAMETERS ARE NORMAL. THERE WAS NO | | RELEASE OF RADIOACTIVE MATERIAL. RELEASE RATES ARE NORMAL. THIS EVENT HAD | | NO IMPACT ON UNIT 2 WHICH IS IN OPERATIONAL CONDITION 5 IN A REFUELING | | OUTAGE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND IS INVESTIGATING THIS | | EVENT. THEY PLAN TO ISSUE A PRESS RELEASE. | | | | *** UPDATE ON 4/21/99 @ 0418 BY HUNTER TO GOULD *** | | | | THE REACTOR IS IN OPCON 3 AT 350 PSIG CONTINUING TO COLD SHUTDOWN. | | CONDENSER VACUUM IS BEING REESTABLISHED IN ORDER TO RE-OPEN THE MSIVs AND | | SECURE HPCI FROM PRESSURE CONTROL MODE. FEEDWATER SYSTEM IS BEING | | REPRESSURIZED TO REESTABLISH NORMAL FEED AND SECURE RCIC FROM LEVEL CONTROL | | MODE. | | | | ALSO THE "1A" AND "1B" MG SET DRIVE MOTOR BREAKERS DID NOT TRIP DURING THE | | TRANSIENT SINCE PLANT LOADS WERE PREVIOUSLY TRANSFERRED BY A REACTOR | | OPERATOR PRIOR TO THE TURBINE TRIP. THE BREAKERS, THEREFORE, OPERATED AS | | DESIGNED. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | THE REG 1 RDO(SHANBAKY) WAS NOTIFIED. | | | | *** UPDATE ON 4/22/99 @ 0220 BY HUNTER TO GOULD *** | | | | THE UNIT IS IN COLD SHUTDOWN AS OF 2214 ON 4/21/99. RESOLUTION OF | | EQUIPMENT PROBLEMS WHICH RESULTED IN THE SHUTDOWN ARE IN PROGRESS. | | ACTIVITIES ARE ALSO IN PROGRESS FOR PLANT STARTUP. | | | | ALL CONTROL RODS INCLUDING 30-39 WENT FULL IN WITHIN THE REQUIRED TECHNICAL | | SPECIFICATION TIME. ROD 30-39 POSITION INDICATION WAS LOST FOR | | APPROXIMATELY TWO MINUTES AFTER THE SCRAM, THEN THE "00" FULL IN POSITION | | INDICATION BECAME AVAILABLE AND REMAINED AVAILABLE THROUGHOUT THE SHUTDOWN. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. THE REG 1 RDO(SHANBAKY) WAS | | INFORMED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35612 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MA DEPT OF PUBLIC HEALTH RCP |NOTIFICATION DATE: 04/21/1999| |LICENSEE: AEA TECHNOLOGIES QSA, INC |NOTIFICATION TIME: 15:00[EDT]| | CITY: BURLINGTON REGION: 1 |EVENT DATE: 04/21/1999| | COUNTY: STATE: MA |EVENT TIME: 14:00[EDT]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/22/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MOHAMED SHANBAKY R1 | | |FREDERICK COMBS NMSS | +------------------------------------------------+JOSEPH GIITTER IRO | | NRC NOTIFIED BY: KEN TRAEGDE |DONNA MARIE PEREZ IP | | HQ OPS OFFICER: DICK JOLLIFFE |LEN WERT R2 | +------------------------------------------------+DALE POWERS R4 | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NOCM COMM ASST BRIEF | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SHIPMENT OF 8 Ir-192 SOURCES (866 CURIES TOTAL) FROM BURLINGTON, MA, | | OVERDUE IN MEXICO - | | | | AT 1500 EDT ON 04/21/99, KEN TRAEGDE OF THE MA DEPARTMENT OF PUBLIC HEALTH | | RADIATION CONTROL PROGRAM (RCP) LOCATED IN BOSTON, MA, REPORTED THAT ON | | 04/16/99, AEA TECHNOLOGY QSA, INC., LOCATED IN BURLINGTON, MA, SHIPPED A | | MODEL #855 SOURCE CHANGER LOADED WITH 8 Ir-192 SOURCES (TOTALING 866 CURIES) | | VIA FEDERAL EXPRESS TO VICONT S.A. DE C.V. LOCATED IN TOLUCA, MEXICO. THE | | UNDAMAGED PACKAGE HAD A TRANSPORT INDEX OF 1.4 (NORMAL READINGS OF 1.4 mR/HR | | AT 1 METER AND 55 mR/HR AT THE SURFACE) AT THE TIME OF SHIPMENT. | | | | THE SHIPMENT WAS SCHEDULED TO ARRIVE IN MEXICO ON 04/17/99. AS OF 1400 EDT | | ON 04/21/99, THE RECIPIENT (VICONT S.A. DE C.V.) HAD RECEIVED THE SHIPPING | | PAPERS BUT NOT THE CONTAINER. THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED | | A FULL SEARCH FOR THE PACKAGE. THE FEDERAL EXPRESS HAZARDS MATERIAL | | INVESTIGATION TEAM HAS CONDUCTED A PHYSICAL SEARCH OF EXPRESS DEPOTS IN | | BOSTON, MEMPHIS, LOS ANGELES, AND MEXICO. | | | | THE LICENSE NUMBERS ARE: SU-1485, 12-8361, 52-0243, 54-0237, AND 58-0242. | | | | CONTACT THE NRC OPERATIONS OFFICER FOR APPLICABLE TELEPHONE NUMBERS. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER | | (GAUTHIER); REPORT NUMBER 481132. | | | | *********************************** UPDATE AT 1345 ON 04/22/99 BY JONES | | *********************************** | | | | The NRC entered the Monitoring Phase of Normal Mode at 1345 on 04/22/99. | | The NRC operations officer notified, the R1DO (Shanbaky), Region 1 (Miller), | | IRO (Congel and Giitter), NMSS (Paperiello), RCT (Weinstein), PAO (Gagner), | | EDO's office (name unknown), and Chairman's office (Holian). The RCT | | notified FEMA (Dan Rishe), DOE (Thomas Yates), EPA (Ms. Reddy), USDA (Bob | | Conley), HHS/CDC (James Raab), and DOT (Rick Boyle). | | | | | | | | *********************************** UPDATE AT 1600 ON 04/22/99 BY JONES | | *********************************** | | | | A Commissioner's Assistants Briefing was conducted at 1600 on 04/22/99. The | | following notifications were made (* office did not participate): IRO (Joe | | Giitter, Erick Weinstein), Chairman Jackson (Dan Gillen), Commissioner Dicus | | (Joel Lubenau), Commissioner Diaz (Patrick Castleman), Commissioner | | McGaffigan (Janet Schlueter), Commissioner Merrifield (JohnThoma), EDO (*), | | DEDE (*), NMSS (Don Cool, Carl Paperiello), NMSS EO (Fred Combs), R1DO | | (Mohamed Shanbaky), PAO (Joe Gilland), CAO (Thomas Madden), SECY (Andrew | | Bates), SP (Paul Lohaus), IP (Ron Hauber), R1 (Felicia Hinson, Jim Wiggins, | | etc), and R2 (Doug Collins, Chuck Hosey, Rich Woodruff). The briefer was | | Fred Combs of NMSS. | | | | 1610 Played back tape of briefing for EDO (Dan Martin) and DEDE (Jocelyn | | Mitchell). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35617 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/22/1999| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 03:00[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 04/22/1999| +------------------------------------------------+EVENT TIME: 01:31[CDT]| | NRC NOTIFIED BY: PFEFFER |LAST UPDATE DATE: 04/22/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MELVYN LEACH R3 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF 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 Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM ON LOW REACTOR WATER LEVEL. | | | | THE PLANT HAD A REACTOR SCRAM FROM 100% POWER DUE TO A LOW REACTOR WATER | | LEVEL. CAUSE OF THE LOW REACTOR WASTER LEVEL IS UNKNOWN AND BEING | | INVESTIGATED. ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED, AND NO | | SAFETY RELIEF VALVES LIFTED. PLANT DID HAVE GROUP 2 AND GROUP 3 ISOLATIONS. | | THE GROUP 3 ISOLATION HAS BEEN RESET, AND PRESENTLY THEY ARE IN PROGRESS | | OF RESETTING THE GROUP 2 ISOLATION. THE MAIN CONDENSER IS THE HEAT SINK. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35618 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/22/1999| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 06:32[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 04/22/1999| +------------------------------------------------+EVENT TIME: 01:45[CDT]| | NRC NOTIFIED BY: WELLER |LAST UPDATE DATE: 04/22/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MELVYN LEACH R3 | |10 CFR SECTION: | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Hot Shutdown |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED HPCI INOPERABLE AND ENTERED AN LCO ACTION STATEMENT. | | | | THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0145 TO 0236 DUE TO MOISTURE IN | | THE TURBINE STEAM INLET LINE. A HPCI TURBINE INLET HIGH DRAIN POT LEVEL | | ANNUNCIATION WAS RECEIVED AT 0145. RCIC WAS VERIFIED OPERABLE. THE | | STEAMLINE MANUAL DRAIN VALVE WAS OPENED AND THE DRAIN LINE ANNUNCIATOR | | CLEARED AT 0236. HPCI WAS DECLARED OPERABLE AND PLACED IN STANDBY. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35619 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 04/22/1999| | UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 14:36[EDT]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/21/1999| +------------------------------------------------+EVENT TIME: [EDT]| | NRC NOTIFIED BY: BRUCE MONTGOMERY |LAST UPDATE DATE: 04/22/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 N 0 Refueling |0 Refueling | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - VOLUNTARY FITNESS-FOR-DUTY REPORT - | | | | A licensed operator was determined to be just below the limit by random | | test. The employee's access to the plant was terminated. Refer to the HOO | | Log for additional details. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 35620 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: U.S. ARMY (ACALA) |NOTIFICATION DATE: 04/22/1999| |LICENSEE: U.S. ARMY (ACALA) |NOTIFICATION TIME: 17:22[EDT]| | CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 04/22/1999| | COUNTY: STATE: IL |EVENT TIME: [CDT]| |LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 04/22/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MOHAMED SHANBAKY R1 | | |MELVYN LEACH R3 | +------------------------------------------------+FREDERICK COMBS NMSS | | NRC NOTIFIED BY: GAVIN ZIGLER | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DAMAGED VIAL CONTAINING 0.8 CURIES OF TRITIUM | | | | During repair activities at Fort Drum, New York, in the arms room, an M224 | | range indicator was apparently damaged. The illuminator was checked working | | prior to the maintenance and noted not to be working later. The contained | | vial of tritium, 0.8 Ci, used in the illuminator is assumed to be broken. | | The device has been double bagged and the area secured until the results of | | surveys are obtained. Survey results were sent off site as lab facilities | | are not available on site. Investigation of the event is ongoing, and no | | further information is available at this time. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35621 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/22/1999| | UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 19:02[EDT]| | RXTYPE: [3] B&W-L-LP |EVENT DATE: 04/22/1999| +------------------------------------------------+EVENT TIME: 18:08[EDT]| | NRC NOTIFIED BY: BILL BANDHAUGER |LAST UPDATE DATE: 04/22/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LEN WERT R2 | |10 CFR SECTION: | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |3 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE OVERLOAD OF ESF TRANSFORMER IN AN ABNORMAL OPERATING PROCEDURE | | FOUND | | | | While investigating a previous LER concerned with backfeed the following was | | discovered: | | | | "During a scenario involving a Loss of Off-Site Power resulting from a loss | | of the BEST and Startup transformers, the Crystal River Unit 3 abnormal | | operating procedures could have caused an overload of the safety-related | | Engineered Safeguards 4160V to 480V transformer. Assuming a single failure | | of the 'B' side diesel generator, power could have been unavailable to both | | trains of 480V Engineered safeguards loads. | | | | "This condition is considered reportable per 10 CFR 50.72(b)(l)(ii)(B) and | | 10 CFR 50.73(a)(2)(ii)(B) as a condition outside of the design basis of the | | plant. | | | | "Loads have been identified which can be administratively maintained off | | during this scenario to avoid the overload condition, and therefore, the | | transformer is operable." | | | | This is under investigation, and further actions will be forthcoming. | | | | The licensee intends to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35622 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/23/1999| | UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 04:33[EDT]| | RXTYPE: [1] GE-3 |EVENT DATE: 04/23/1999| +------------------------------------------------+EVENT TIME: 02:14[CDT]| | NRC NOTIFIED BY: WELLER |LAST UPDATE DATE: 04/23/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MELVYN LEACH R3 | |10 CFR SECTION: | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Hot Shutdown |0 Hot Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE AND PLANT ENTERED LCO ACTION STATEMENT | | | | THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0214 TO 0220 DUE TO MOISTURE IN | | THE TURBINE STEAM INLET LINE. A 14-DAY LCO ACTION STATEMENT WAS ENTERED, | | AND RCIC WAS VERIFIED OPERABLE. HPCI TURBINE INLET HIGH DRAIN POT LEVEL | | ANNUNCIATION WAS RECEIVED DUE TO STROKING MO-2036 (TURBINE STEAM SUPPLY | | VALVE) AS PART OF THE REACTOR SHUTDOWN PROCEDURE AT REACTOR PRESSURE OF 500 | | PSIG. THE STEAM LINE MANUAL DRAIN VALVE WAS OPENED, AND THE ANNUNCIATOR | | CLEARED AT 0220. HPCI DECLARED OPERABLE AND IN STANDBY. THE 14-DAY LCO | | ACTION STATEMENT WAS ALSO EXITED AT 0220. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+
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