U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/19/95 - 05/22/95 ** EVENT NUMBERS ** 28780 28832 28833 28834 28835 28836 28837 28838 28839 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28780 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/09/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 21:35 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/09/95 | +------------------------------------------------+EVENT TIME: 19:23[CDT]| |NRC NOTIFIED BY: MOTSEGOOD |LAST UPDATE DATE: 05/19/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CREED 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DIVISION 3 EMERGENCY DIESEL GENERATOR LOADED TO BUS DUE TO THE LOSS OF A | | 345 kV OFFSITE POWER LINE. | | | | THE DIVISION 3 EMERGENCY DIESEL GENERATOR (EDG) AUTOMATICALLY STARTED AND | | LOADED TO ITS ASSOCIATED EMERGENCY 4160V BUS WHEN POWER TO THE BUS WAS | | MOMENTARILY INTERRUPTED DUE TO SEVERE WEATHER. THE LICENSEE REPORTED THAT | | THE 345 kV BROKAW DISTRIBUTION LINE WAS LOST, CAUSING A MOMENTARY | | UNDERVOLTAGE CONDITION TO THE RESERVE AUXILIARY TRANSFORMER. THE EMERGENCY | | RESERVE AUXILIARY TRANSFORMER (ERAT) DID NOT PICK UP LOAD AS EXPECTED, AND | | THE EDG AUTOMATICALLY STARTED AND LOADED DUE TO BUS UNDERVOLTAGE. THE EDG | | CONTINUES TO SUPPLY POWER TO THE BUS AT THIS TIME. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE FAILURE OF THE BUS | | TO TRANSFER FROM THE RAT TO THE ERAT. THE LICENSEE HAS TWO REMAINING 345 | | KV LINES AVAILABLE AS A SOURCE OF OFFSITE POWER. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE 1029 5/19/95 BY NADEN TAKEN BY STRANSKY * * * | | | | LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE STATED THAT THE | | EMERGENCY DIESEL GENERATORS ARE NOT CONSIDERED TO BE ENGINEERED SAFETY | | FEATURES (AS DESCRIBED IN THE PLANT USAR) AND, THEREFORE, THE AUTOMATIC | | START OF AN EMERGENCY DIESEL GENERATOR IS NOT CONSIDERED TO BE AN ESF | | ACTUATION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED | | R3DO(LANKSBURY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28832 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 05/19/95 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 11:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/19/95 | +------------------------------------------------+EVENT TIME: 11:15[EDT]| |NRC NOTIFIED BY: ROGER WEST |LAST UPDATE DATE: 05/19/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |AL CHAFFEE EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |CHARLIE SHULL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED AND TECHNICAL SPECIFICATION SHUTDOWN COMMENCED DUE | | TO A FAILURE TO MEET A SURVEILLANCE REQUIREMENT. | | | | DURING A REVIEW OF PAST IN-SERVICE INSPECTION EXAMINATIONS, THE LICENSEE | | DETERMINED THAT THE ULTRASONIC EXAMINATION TECHNIQUE USED TO INSPECT | | REACTOR COOLANT SYSTEM BRANCH CONNECTION WELDS WAS INADEQUATE TO MEET ASME | | CODE SECTION XI REQUIREMENTS. THE LICENSEE ALSO DETERMINED THAT THE | | SURVEILLANCE REQUIREMENTS OF TECHNICAL SPECIFICATION 4.0.5 HAD NOT BEEN | | SATISFIED AND THAT THE ECCS SYSTEMS ASSOCIATED WITH THE AFFECTED WELDS WERE | | INOPERABLE. BASED ON THE INOPERABILITY OF THE ECCS SYSTEMS (BOTH TRAINS | | FOR BOTH UNITS), BOTH UNITS ENTERED TECHNICAL SPECIFICATION 3.0.3 AT 10:25, | | AND POWER REDUCTIONS FOR UNITS 1 AND 2 WERE COMMENCED AT 11:18 AND 11:15, | | RESPECTIVELY. THERE WERE NO INDICATIONS OF ANY PHYSICAL PROBLEMS WITH THE | | WELDS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE STATE, AND THE | | COUNTY. AT THE TIME OF THE LICENSEE'S NOTIFICATION, THE LICENSEE WAS | | UNSURE OF WHETHER OR NOT A PRESS RELEASE WOULD BE MADE. | | | | ** UPDATE DATE\TIME:5/19/95 @ 1341 *FROM LICENSEE:WEST BY:McGINTY ** | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AND EXITED T/S 3.0.3 AT 1310 EDT. | | SUBSEQUENT REVIEW REVEALED THAT THE DETERMINATION TO ENTER T/S 3.0.3 WAS | | OVERLY CONSERVATIVE. OTHER MEANS EXIST TO RESOLVE THE NON-CONFORMANCE. | | | | THE LICENSEE WILL BE SUBMITTING A CODE RELIEF REQUEST EARLY NEXT WEEK. THE | | POWER DECREASE WAS STOPPED AT 97.5% FOR UNIT 1, AND 98% FOR UNIT 2. THE | | UNIT'S ARE NOT IN ANY SIGNIFICANT T/S ACTION STATEMENTS AT THIS TIME, AND | | THE ECCS SYSTEMS FOR BOTH UNITS ARE OPERABLE. THE LICENSEE HAS INFORMED | | THE RESIDENT INSPECTOR, STATE AND LOCAL AUTHORITIES, AND WILL NOT BE | | ISSUING A PRESS RELEASE. HOO NOTIFIED THE R3DO (LANKSBURY), EO (CHAFFEE) | | AND FEMA (SHULL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28833 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/19/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 12:15 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/19/95 | +------------------------------------------------+EVENT TIME: 11:57[EDT]| |NRC NOTIFIED BY: BONNER |LAST UPDATE DATE: 05/19/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLUMBERG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THE HYDROGEN ANALYZERS MAY NOT PROVIDE | | ACCURATE SAMPLE RESULTS DURING A LOCA. | | | | THE LICENSEE WAS PERFORMING A DESIGN BASIS DOCUMENTATION PACKAGE REVIEW FOR | | UNIT 2, WHEN THEY CAME ACROSS A DISCREPANCY IDENTIFIED IN 1984 AND A | | LETTER TO THE NRC REGARDING THE ISSUE. THE REVIEW OF THE ACTUAL SYSTEM | | DESIGN DOES NOT AGREE WITH WHAT WAS STATED IN THE LETTER TO THE NRC. | | SPECIFICALLY, THE CONTAINMENT AUXILIARY CIRCULATION FANS ARE NOT QUALIFIED | | FOR POST-LOCA OPERATION. THE SAMPLE POINTS FOR THE HYDROGEN ANALYZERS ARE | | CURRENTLY CONNECTED TO THE DUCTWORK ASSOCIATED WITH THE CONTAINMENT | | AUXILIARY CIRCULATION FANS. | | | | DURING A LOCA, ATMOSPHERIC MIXING IN CONTAINMENT IS PROVIDED BY THE | | POST-INCIDENT RECIRCULATION FANS. IF THE CONTAINMENT AUXILIARY CIRCULATION | | FANS ARE NOT OPERATING, THE SAMPLE TAKEN FROM THE DUCT MIGHT NOT BE | | REPRESENTATIVE OF THE CONTAINMENT ATMOSPHERE. | | | | THE LICENSEE WILL BE FURTHER INVESTIGATING TO DETERMINE CORRECTIVE ACTIONS. | | THE LICENSEE INFORMED THE STATE AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28834 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ELI LILLY & CO. |NOTIFICATION DATE: 05/19/95 | | CITY: INDIANAPOLIS REGION: 3 |NOTIFICATION TIME: 14:11 [ET]| | COUNTY: STATE: IN |EVENT DATE: 05/15/95 | |LICENSE#: 13-01133-02 AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/19/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROGER LANKSBURY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: HAMPTON | | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE OPERATIONS CENTER OF THE LOSS OF A SHIPMENT | | CONTAINING 45.6 æCi OF IODINE-125. | | | | THE SHIPMENT WAS REPORTED LOST BY THE COURIER (WORLD COURIER) ON MAY 15th. | | THE SHIPMENT WAS BEING SHIPPED FROM ELI LILLY, LOCATED IN INDIANAPOLIS, | | INDIANA, TO THE UNIVERSITY OF PLYMOUTH, LOCATED IN PLYMOUTH IN THE UK. | | | | THE LICENSEE SUSPECTS THAT THE PACKAGE HAS NOT LEFT THE COUNTRY, AND MAY | | HAVE BEEN LOST IN NEW YORK CITY. ANOTHER PACKAGE SHIPPED ON THE SAME DAY | | VIA THE SAME COURIER WAS RECEIVED AT THE OVERSEAS DESTINATION (CAMBRIDGE, | | ENGLAND). THE COURIER HAS EXPRESSED CONFIDENCE THAT THE PACKAGE WILL BE | | LOCATED. | | | | THE I-125 WAS IN A SOLID FORM, SHIPPED ON DRY ICE. THE LICENSEE STATED | | THAT THE POTENTIAL HAZARD IS CONSIDERED MINIMAL, AND PRIMARILY AN INGESTION | | CONCERN. THE PACKAGE CONSISTS OF ABOUT 60 NANOGRAMS OF MATERIAL IN A | | PLASTIC VIAL, WRAPPED IN LEAD FOIL AND SEALED WITH A SPILL PILLOW IN | | ZIPLOCK BAGS. THE ZIPLOCK BAGS ARE PLACED IN A BOX AND THEN IN A STYROFOAM | | COOLER WITH DRY ICE AND PACKAGED IN AN OUTER CARDBOARD BOX. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28835 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 05/19/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 15:02 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 05/19/95 | +------------------------------------------------+EVENT TIME: 14:30[EDT]| |NRC NOTIFIED BY: BANDHAUER |LAST UPDATE DATE: 05/19/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE RDO | |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 +------------------------------------------------------------------------------+ | REACTOR COOLANT PUMP LUBE OIL COLLECTION TANK SYSTEM MAY NOT COLLECT ALL | | LEAKAGE. | | | | THE REACTOR COOLANT PUMP (RCP) LUBE OIL COLLECTION TANK SYSTEM (LOCTS) MAY | | NOT BE DESIGNED TO COLLECT ALL LEAKAGE OF OIL DUE TO A RECENTLY REPLACED | | TRANSMITTER WHICH PENETRATES THE RCP LUBE OIL SYSTEM. THE PENETRATION MAY | | ALLOW LEAKAGE AT POINTS NOT DESIGNED TO BE COLLECTED BY THE LOCTS. THE | | TOTAL AMOUNT OF OIL LEAKED FROM THE RCP LUBE OIL SYSTEMS INTO THE REACTOR | | BUILDING IS ESTIMATED TO BE LESS THAN 100 GALLONS SINCE THE REFUELING | | OUTAGE COMPLETED IN 6/94 (ABOUT 11 MONTHS). | | | | PAST LEAKAGE AND FUTURE EXPECTED LEAKAGE (UNTIL THE NEXT REFUELING OUTAGE) | | IS CONSIDERED INSIGNIFICANT TO THE FIRE HAZARD ANALYSIS AND ECCS | | OPERABILITY. THE SUPPORTING ANALYSIS WAS PREVIOUSLY REPORTED BY FP&L IN | | RESPONSE TO NRC INSPECTION REPORT 50-302/90-29. THE ANALYSIS SHOWS THE | | CAPABILITY TO WITHSTAND A FIRE IN THE REACTOR BUILDING GIVEN A LEAK OF UP | | TO 800 GALLONS OF OIL IN THE REACTOR BUILDING. | | | | BASED ON LUBE OIL INVENTORY ANALYSIS, SOME OIL IS BEING LEAKED INTO THE | | REACTOR BUILDING WITHOUT BEING COLLECTED BY THE LOCTS. THE EXACT SOURCE OF | | THE OIL AND ITS DISPOSITION IS NOT KNOWN AT THIS TIME (CANNOT ENTER THE | | REACTOR BUILDING TO LOOK FOR IT). THE NEW PENETRATION IS A POTENTIAL | | SOURCE OF THE LOST LUBE OIL, BECAUSE IT IS NOT DESIGNED TO BE LEAK TIGHT. | | | | THE LICENSEE WILL BE FURTHER EVALUATING THE PROBLEM FOR CORRECTIVE ACTION. | | THE LICENSEE HAS NOT DECLARED ANY SYSTEMS INOPERABLE AS A RESULT OF THIS | | EVENT NOTIFICATION. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28836 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/19/95 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 20:07 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/19/95 | +------------------------------------------------+EVENT TIME: 19:55[EDT]| |NRC NOTIFIED BY: WALKER |LAST UPDATE DATE: 05/19/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE REACTOR PLANT CHILL WATER SYSTEM VALVES FAILED LOCAL LEAK RATE TEST. | | | | LOCAL LEAK RATE TESTING (LLRT) IDENTIFIED EXCESSIVE LEAKAGE THROUGH VALVES | | CTV-91A, CTV-38A & RV-105A OF THE REACTOR PLANT CHILL WATER SYSTEM. THE | | CTV-91A VALVE MEASURED LEAK RATE WAS 52,900 SCCM, AND THE COMBINED LEAKAGE | | OF CTV-38A & RV-105A WAS 52,800 SCCM. THE MAXIMUM ALLOWABLE LEAKAGE IS | | 1000 SCCM. THIS LEAKAGE, IN COMBINATION WITH THE TOTAL BYPASS LEAKAGE | | FLOW, EXCEEDS THE 0.6La LIMIT IN THE TECHNICAL SPECIFICATIONS. | | | | THE TEST WAS PERFORMED ON 5/2/95, AND THE VALVES (TWO CONTAINMENT ISOLATION | | VALVES AND A RELIEF VALVE) WERE REPAIRED AND TESTED SATISFACTORILY ON | | 5/9/95. THE CALLER HAD JUST RECEIVED THE INCIDENT REPORT FORM (95-028) | | TODAY, AT WHICH TIME THE REPORTABILITY WAS DETERMINED. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL AUTHORITIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28837 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 05/19/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 21:59 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/19/95 | +------------------------------------------------+EVENT TIME: 18:04[EDT]| |NRC NOTIFIED BY: SCHALL |LAST UPDATE DATE: 05/19/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE RDO | |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 | M/R Y 25 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DUE TO LOSS OF CONDENSER VACUUM DURING UNIT STARTUP. | | | | UNIT 1 WAS STARTING UP FOLLOWING A REFUELING OUTAGE WHEN OPERATORS MANUALLY | | SCRAMMED THE REACTOR DUE TO DECREASING CONDENSER VACUUM. ALL RODS INSERTED | | AS REQUIRED. THE TURBINE WAS NOT ONLINE DURING THIS EVENT, AND THE LOWEST | | WATER LEVEL SEEN WAS APPROXIMATELY +140". | | | | PRIOR TO THE MANUAL SCRAM, THE UNIT WAS RECEIVING MAIN CONDENSER | | CIRCULATING WATER INTAKE PUMP (CWIP) SCREEN HIGH DIFFERENTIAL PRESSURE | | TRIPS. UPON PUMP RESTART, THE PUMP WOULD RUN FOR APPROXIMATELY 30 SECONDS | | PRIOR TO TRIPPING AGAIN. DURING THIS TIME FRAME, CONDENSATE AND FEEDWATER | | PRESSURE REDUCED TO APPROXIMATELY 20 PSIG DUE TO APPARENT FLASHING IN THE | | HOTWELLS. | | | | REACTOR CORE ISOLATION COOLING (RCIC) WAS INITIALLY STARTED FOR REACTOR | | VESSEL LEVEL CONTROL UNTIL CONDENSATE AND FEEDWATER COULD BE LINED UP FOR | | INJECTION. RCIC EXPERIENCED OSCILLATIONS IN THE AUTOMATIC MODE, AND WAS | | THEREFORE TRANSFERRED TO MANUAL, WHERE IT RESPONDED AS EXPECTED. DUE TO | | THE OSCILLATIONS IN RCIC AUTOMATIC OPERATION, VESSEL LEVEL INCREASED | | RAPIDLY, AND RCIC TRIPPED ON HIGH LEVEL SHORTLY AFTER BEING TRANSFERRED TO | | MANUAL. THE HIGHEST LEVEL REACHED WAS APPROXIMATELY +212". | | | | TO HELP CONTROL REACTOR PRESSURE, THE MAIN STEAM LINE (MSL) DRAIN VALVES | | WERE CLOSED. THE MAIN STEAM ISOLATION VALVES (MSIVs) WERE ALSO | | SUBSEQUENTLY CLOSED TO MAINTAIN PRESSURE AND REDUCE THE COOLDOWN RATE. THE | | MSL DRAINS WERE THEN RE-OPENED FOR PRESSURE CONTROL. LEVEL CONTROL WAS | | ESTABLISHED WITH CONDENSATE AND FEEDWATER THROUGH THE STARTUP LEVEL CONTROL | | VALVE. | | | | PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2, 6 & 8 ISOLATION SIGNALS WERE | | RECEIVED (AT +162.5" REACTOR VESSEL LEVEL), AND WERE VERIFIED. THE GROUP 2 | | VALVES WERE VERIFIED TO HAVE CLOSED. MOST OF THE GROUP 6 VALVES WERE | | ALREADY CLOSED, AND THOSE THAT WERE OPEN WERE VERIFIED TO HAVE CLOSED. THE | | GROUP 8 VALVES WERE ALREADY CLOSED, SO NO VALVE MOTION OCCURRED. | | | | THE LICENSEE WILL INVESTIGATE PROBLEMS WITH RCIC OPERATION IN AUTOMATIC | | MODE PRIOR TO STARTUP. IN ADDITION, THE REASON FOR THE CWIP SCREEN HIGH | | D/P TRIPS AND THE CONDENSATE AND FEEDWATER PRESSURE REDUCTION WILL BE | | UNDERSTOOD AND ANY NECESSARY CORRECTIVE ACTIONS TAKEN. WITH THE EXCEPTION | | OF PROBLEMS ENCOUNTERED WITH THE OPERATION OF RCIC IN AUTOMATIC, ALL | | SYSTEMS RESPONDED AS EXPECTED AFTER THE MANUAL SCRAM. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 28838 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ST. JOHNS |NOTIFICATION DATE: 05/20/95 | | CITY: MAPLEWOOD, MN REGION: 3 |NOTIFICATION TIME: 12:56 [ET]| | COUNTY: RAMSEY STATE: MN |EVENT DATE: 05/20/95 | |LICENSE#: 22-24441-01 AGREEMENT: N |EVENT TIME: 11:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/20/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PATRICK HILAND RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: CLAUDIA ROBERTO | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ST. JOHNS HOSPITAL RECEIVED A PACKAGE WITH CONTAMINATION ON ITS SURFACE | | | | THE PACKAGE HAD APPROXIMATELY 6,800 DPM OF ACTIVITY PER 100 cmý ON ITS | | SURFACE. THE PACKAGE CONTAINS Tc-99m AND IS LOCATED IN THE HOSPITAL'S HOT | | LAB. NO CONTAMINATION WAS FOUND OTHER THAN ON THE PACKAGE. | | | | THE PACKAGE WAS PACKAGED AND SHIPPED BY MALLINCKRODT PHARMACY OF ST. PAUL, | | MINNESOTA. THE LICENSEE INTENDS TO LEAVE THE PACKAGE IN THE HOT LAB TO | | ALLOW THE Tc-99 TO DECAY. | | | | CONTACT PHONE NUMBERS ARE AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28839 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 05/21/95 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 15:51 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/21/95 | +------------------------------------------------+EVENT TIME: 12:23[EDT]| |NRC NOTIFIED BY: JAMES HELM |LAST UPDATE DATE: 05/21/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL TRIP FROM 100% WHEN 4 CONTROL RODS DROPPED INTO THE CORE | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED UNIT 2 FROM 100% POWER AFTER ALL 4 | | CONTROL BANK 'A' GROUP 2 CONTROL RODS DROPPED INTO THE CORE FOR UNKNOWN | | REASONS. | | | | FOLLOWING THE REACTOR TRIP, THE MAIN TURBINE TRIPPED, AS EXPECTED, AND ALL | | CONTROL RODS INSERTED INTO THE CORE. HOWEVER, THE ROD BOTTOM LIGHT IN THE | | INDIVIDUAL ROD POSITION INDICATOR FOR CONTROL ROD #M-10 WAS SLOW TO | | ILLUMINATE FOLLOWING THE TRIP (THIS IS A NORMAL CONDITION FOR SURRY UNIT | | 2). | | | | THE AUXILIARY FEEDWATER SYSTEM ACTUATED, AS EXPECTED, AND STEAM IS BEING | | DUMPED TO THE MAIN CONDENSER. | | | | NO PRIMARY OR SECONDARY SAFETY OR POWER OPERATED RELIEF VALVES LIFTED | | DURING THIS EVENT. HOWEVER, THE 'C' MAIN STEAM POWER OPERATED RELIEF | | VALVE LIFTED AND RESEATED APPROXIMATELY 27 MINUTES AFTER THE TRIP WHILE | | STABILIZING RCS TEMPERATURE. | | | | UNIT 2 IS STABLE IN MODE 4 (HOT SHUTDOWN). | | | | NO ROD CONTROL SYSTEM TESTING OR MAINTENANCE ACTIVITIES WERE BEING | | CONDUCTED AT THE TIME THE CONTROL RODS DROPPED INTO THE CORE AND LICENSEE | | IS INVESTIGATING THE CAUSE. | | | | UNIT 1 IS AT 100% POWER AND WAS UNAFFECTED BY THIS EVENT. | | | | LICENSEE INFORMED THE BACKUP NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+