U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/09/95 - 01/10/95 ** EVENT NUMBERS ** 28198 28221 28224 28225 28226 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 12/30/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 15:21 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 12/30/94 | +------------------------------------------------+EVENT TIME: 14:59[EST]| |NRC NOTIFIED BY: JOE BERGIN |LAST UPDATE DATE: 01/09/95 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENCLOSURE BUILDING FILTRATION SYSTEM CHARCOAL BEDS FAILED SURVEILLANCE. | | | | THE ENCLOSURE BED FILTRATION SYSTEMS ARE ALIGNED TO THE AUXILIARY EXHAUST | | SYSTEM FOR CONTROL OF RAD RELEASES FROM THE SPENT FUEL POOL. THIS | | FILTRATION SYSTEM HAS CHARCOAL BEDS FOR IODINE ADSORPTION PURPOSES. RESULTS | | FROM SURVEILLANCE TESTING OF THE REMOVAL EFFICIENCY OF THE CHARCOAL FOR | | BOTH FILTRATION TRAINS WERE BELOW TECHNICAL SPECIFICATIONS. ONE TRAIN | | TESTED AT 83% WHILE THE OTHER TRAIN TESTED AT 82%. MINIMUM TECH SPEC | | REQUIRED REMOVAL EFFICIENCY IS 95%. | | | | THE CHARCOAL IN ONE TRAIN HAS BEEN REPLACED WITH NEW CHARCOAL, HOWEVER, THE | | TRAIN DOES NOT CURRENTLY HAVE EMERGENCY BACKUP POWER CAPABILITY DUE TO THE | | MAINTENANCE OUTAGE WORK IN PROGRESS AND CAN NOT BE CONSIDERED OPERABLE. THE | | OTHER FILTRATION TRAIN WILL HAVE THE CHARCOAL REPLACED WHEN WORK SCHEDULING | | PERMITS. NO FUEL MOVEMENT WILL TAKE PLACE UNTIL THE FILTRATION TRAINS ARE | | DECLARED OPERABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | | | | *** UPDATE FROM LICENSEE:RESETOR TO NRC:HUFFMAN AT 1500 ON 1/9/95 *** | | | | THE LICENSEE REPORTS THAT A CHARCOAL SAMPLE FROM ONE OF THE CONTROL ROOM | | VENTILATION SYSTEM TRAINS HAD AN IODINE REMOVAL EFFICIENCY OF ONLY 92%. | | THIS IS LESS THAN THE TECH SPEC MINIMUM REQUIRED 95% EFFICIENCY AND | | REPRESENTS A SYSTEM DEGRADATION SIMILAR TO THE ABOVE REPORTED CONDITION FOR | | THE ENCLOSURE BUILDING VENTILATION SYSTEM. THE RESULTS FOR OPPOSITE CONTROL | | ROOM VENTILATION TRAIN IS NOT YET AVAILABLE. | | | | THE UNIT IS CURRENTLY DEFUELED AND THE CONTROL ROOM VENTILATION SYSTEM IS | | NOT REQUIRED TO BE OPERABLE. THE CHARCOAL FILTER WILL BE REPLACED BEFORE | | REFUELING COMMENCES. | | | | THE LICENSEE PLANS TO CONTINUE INVESTIGATING THE CAUSE OF THE FILTER | | DEGRADATIONS. THE DETERIORATION OF CHARCOAL FILTER BED EFFICIENCIES SINCE | | THE LAST SURVEILLANCE FOR THESE INDEPENDENT VENTILATION SYSTEMS IS UNUSUAL. | | | | THE NRC RESIDENT INSPECTOR, R1DO(SHANBAKY), STATE AND LOCAL AUTHORITIES | | HAVE BEEN INFORMED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28221 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/08/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 04:32 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/08/95 | +------------------------------------------------+EVENT TIME: 02:35[CST]| |NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 01/09/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THE COMPROMISE OF SAFEGUARDS INFORMATION. | | COMPENSATORY MEASURES WERE TAKEN. SEE HOO LOG FOR DETAILS. THE RI WILL BE | | NOTIFIED. | | | | ***UPDATE AT 10:19 BY BUSH TO GOULD*** THE LICENSEE DETERMINED THAT THIS | | EVENT SHOULD NOT HAVE BEEN REPORTED SINCE THE LOCK WAS PHYSICALLY LOCKED | | PRIOR TO THE CLERKS SECURITY CHECK. DURING THE CHECK, THE CLERK | | INADVERTENTLY BROKE THE LOCK WHEN SHE JERKED ON IT, BUT THE CABINET WAS NOT | | UNATTENDED UNTIL A NEW LOCK WAS INSTALLED. THE LICENSEE IS THEREFORE | | RETRACTING THIS EVENT. THE RI WAS INFORMED. | | | | REG 4 (STETKA) INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 01/09/95 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 14:50 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 01/09/95 | +------------------------------------------------+EVENT TIME: 14:25[EST]| |NRC NOTIFIED BY: ED BURCHFIELD |LAST UPDATE DATE: 01/09/95 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR BLOWDOWN OF BOTH STEAM GENERATORS THROUGH A SINGLE COMMON | | HEADER STEAM LINE BREAK. | | | | THE LICENSEE HAS RECENTLY DETERMINED THAT THERE IS A POSSIBILITY THAT BOTH | | STEAM GENERATORS ON ANY OF THE THREE UNITS COULD BLOW DOWN FROM A STEAM | | LINE BREAK ON CERTAIN STEAM LINES COMMON TO THE GENERATORS. THE COMMON | | STEAM HEADERS INVOLVE AUXILIARY STEAM AND THE STEAM SUPPLY LINES TO THE | | TURBINE DRIVEN EMERGENCY FEEDWATER PUMPS (TDEFWP). | | | | IMMEDIATE CORRECTIVE ACTIONS HAVE BEEN TAKEN TO CLOSE ONE OF THE TWO STEAM | | SUPPLY VALVES FROM THE STEAM GENERATORS TO THE COMMON STEAM HEADERS (AUX | | STEAM AND TDEFWP). THIS ACTION ELIMINATES THE POTENTIAL BLOWDOWN OF BOTH | | STEAM GENERATORS FROM A SINGLE LINE BREAK. | | | | THIS CONDITION IS CURRENTLY CONSIDERED AN UNREVIEWED SAFETY QUESTION BY THE | | LICENSEE. A CONFERENCE CALL TOOK PLACE TODAY BETWEEN REPRESENTATIVES FROM | | THE NRC REGION II, NRR, THE NRC RESIDENT INSPECTOR AND THE LICENSEE | | CONCERNING THIS ISSUE. LONG TERM CORRECTIVE ACTIONS AND ANALYSIS ARE STILL | | IN PROGRESS. | | | | THE LICENSEE STATES THAT ISOLATING A STEAM SOURCE TO THE TURBINE DRIVEN | | EMERGENCY FEEDWATER PUMP DOES NOT PLACE THEM INTO ANY TECH SPEC OPERABILITY | | CONDITIONS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28225 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/09/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 20:09 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/09/95 | +------------------------------------------------+EVENT TIME: 19:33[EST]| |NRC NOTIFIED BY: JOHN RESETOR |LAST UPDATE DATE: 01/09/95 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL NON-CONSERVATISMS IN THE CONTAINMENT PURGE RADIONUCLIDE RELEASE | | RATE LIMITS. | | | | THE LICENSEE HAS DETERMINED THAT THE PROCEDURE FOR CONTAINMENT PURGING HAS | | A MAXIMUM ALLOWABLE INSTANTANEOUS RELEASE LIMIT FOR PARTICULATES AND | | IODINES (NON-NOBLE GASES) WHICH MAY BE NON-CONSERVATIVE. RADIOLOGICAL | | RELEASE RATE CALCULATIONS BASED ON THE LIMITS IN THE PROCEDURES MAY RESULT | | IN EXCEEDING LIMITS PRESCRIBED IN THE RADIOACTIVE EFFLUENT MONITORING | | MANUAL. | | | | THE ERRORS WERE DISCOVERED DURING AN INTERNAL RADIATION ASSESSMENT AUDIT. | | THE PROCEDURE LIMITS WILL BE REVISED. RECORDS FOR RELEASES DURING THE LAST | | SIX MONTHS HAVE BEEN REVIEWED AND SHOW THAT NO LIMITS WERE ACTUALLY | | EXCEEDED. | | | | HOW THE ERRONEOUS LIMITS WERE DETERMINED IS STILL UNDER INVESTIGATION. | | | | THE NRC RESIDENT, STATE AND LOCAL AUTHORITIES HAVE BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28226 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/09/95 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 21:48 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/09/95 | +------------------------------------------------+EVENT TIME: 18:32[CST]| |NRC NOTIFIED BY: BOB SCOTT |LAST UPDATE DATE: 01/09/95 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 89 POWER OPERATION | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM DUE TO TURBINE TRIP. | | | | WHILE CUTTING OUT THE HIGH PRESSURE FEEDWATER HEATERS EXTRACTION STEAM AND | | DRAINS, A HI-HI MOISTURE SEPARATOR LEVEL TURBINE TRIP WAS RECEIVED. THE | | TURBINE TRIP CAUSED A REACTOR TRIP ON TURBINE STOP VALVE CLOSURE. ALL RODS | | FULLY INSERTED. THERE WERE NO COMPLICATIONS DURING THE SCRAM TRANSIENT AND | | ALL SYSTEMS FUNCTIONED AS REQUIRED. NO SAFETY RELIEF VALVES LIFTED AND | | DECAY HEAT IS BEING REMOVED VIA THE REACTOR WATER CLEANUP SYSTEM HEAT | | EXCHANGER. | | | | THE LOWEST REACTOR WATER LEVEL DURING THE TRANSIENT HAS NOT YET BEEN | | DETERMINED BUT THE WATER LEVEL DID REMAIN ABOVE THE ECCS INITIATION | | SETPOINTS. GROUP II AND III ISOLATIONS (CONTAINMENT ISOLATION VALVES; RWCU; | | SHUTDOWN COOLING VALVES) OCCURRED AS EXPECTED. THE STANDBY GAS TREATMENT | | SYSTEM ALSO INITIATED AS REQUIRED. | | | | THE CAUSE OF THE HIGH LEVEL IN THE MOISTURE SEPARATOR REHEATER IS STILL | | UNDER INVESTIGATION. | | | | THE LICENSEE IS CURRENTLY UNCERTAIN ABOUT AN ESTIMATED RESTART DATE. THEY | | MAY REMAIN SHUTDOWN FOR A SEVERAL DAY MINI-MAINTENANCE OUTAGE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+