U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/27/94 - 12/28/94 ** EVENT NUMBERS ** 28184 28186 28187 28188 28189 28190 28191 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 12/26/94 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 02:42 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 12/26/94 | +------------------------------------------------+EVENT TIME: 01:41[EST]| |NRC NOTIFIED BY: ADAMS |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAKE 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR TRIP FROM 100% POWER DUE TO LOW STEAM | | GENERATOR LEVEL | | | | WITH THE UNIT OPERATING AT 100% POWER, THE "3C" MAIN FEEDWATER CONTROL | | VALVE FAILED CLOSED FOR UNKNOWN REASONS. OPERATORS WERE UNABLE TO MANUALLY | | REOPEN THE VALVE, AND AN AUTOMATIC TURBINE/REACTOR TRIP OCCURRED DUE TO | | STEAM/FEEDWATER FLOW MISMATCH COINCIDENT WITH LOW STEAM GENERATOR LEVEL IN | | THE "3C" STEAM GENERATOR. ALL RODS FULLY INSERTED FOLLOWING THE TRIP, AND | | ALL OTHER SYSTEMS FUNCTIONED AS REQUIRED. THE AUXILIARY FEEDWATER SYSTEM | | AUTOMATICALLY STARTED, AND WAS USED TO MAINTAIN STEAM GENERATOR LEVELS | | FOLLOWING THE TRIP. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FEEDWATER CONTROL VALVE | | FAILURE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1428 ON 12/27/94 BY KNORE ENTERED BY HOO JOLLIFFE * * * | | | | DURING AN INVESTIGATION INTO THE CAUSE OF THE MAIN FEEDWATER CONTROL VALVE | | CLOSURE, LICENSEE HAS DETERMINED THAT A LOOSE SCREW TERMINATION ON THE | | ELECTRICAL CURRENT-TO-PNEUMATIC (I/P) TRANSMITTER MAY HAVE RESULTED IN | | AN INTERMITTENT OPEN CIRCUIT IN THE CONTROL LOOP TO THE MAIN FEEDWATER | | CONTROL VALVE. WITH THIS OPEN CIRCUIT, THE VALVE FAILED CLOSED REGARDLESS | | OF THE CONTROLLER POSITION (i.e., MANUAL OR AUTOMATIC) IN THE CONTROL ROOM. | | THE TRANSMITTER TERMINAL BLOCK IS LOOSELY RIVETED TO A MOUNTING PLATE. | | THIS CONFIGURATION MAY HAVE CONTRIBUTED TO VIBRATION INDUCED LOOSENING OF | | THE SCREW. | | | | LICENSEE HAS REPLACED THE 'C' MAIN FEEDWATER CONTROL VALVE TRANSMITTER | | MODULE WITH A NEW MODEL. LICENSEE HAS EITHER REPLACED OR INSPECTED THE | | 'A' AND 'B' VALVE TRANSMITTER MODULES FOR SIMILAR CONDITIONS. | | | | LICENSEE INTENDS TO MONITOR THE NEW MODULES WHILE UNIT 3 IS AT REDUCED | | POWER. IF NO ANOMALIES IN TRANSMITTER OPERATION OCCUR, LICENSEE WILL | | RETURN UNIT 3 TO FULL POWER. | | | | LICENSEE INTENDS TO SUBMIT AN LER ON THIS EVENT TO THE NRC. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R2DO STEVE VIAS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28186 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 12/27/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:23 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 10:20[EST]| |NRC NOTIFIED BY: WOOKEY |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KINNEMAN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION SYSTEM WAS OUTSIDE DESIGN BASIS DUE TO FAILURE OF | | INLET SUPPLY DAMPER TO FULLY CLOSE | | | | ON 12/10/94, THE LICENSEE PERFORMED A TEST OF THE CONTROL ROOM VENTILATION | | SYSTEM. DURING THE TEST, THE INLET SUPPLY DAMPER FAILED TO COMPLETELY | | CLOSE. THE DAMPER WAS SUBSEQUENTLY EXERCISED SATISFACTORILY AND DECLARED | | OPERABLE ON 12/12/94. THE LICENSEE ATTRIBUTED THE FAILURE OF THE DAMPER TO | | MECHANICAL BINDING. AN ENGINEERING EVALUATION COMPLETED ON 12/27/94 | | DETERMINED THAT, WITH THE DAMPER UNABLE TO COMPLETELY CLOSE, THE UNIT | | EXCEEDED ITS DESIGN BASIS FOR CONTROL ROOM VENTILATION INLEAKAGE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 12/27/94 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 13:05 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 09:30[EST]| |NRC NOTIFIED BY: DONALD HART |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STEAM GENERATOR BLOWDOWN RELEASE EXCEEDED VPDES RELEASE LIMIT FOR TSS - | | | | AT 0530 ON 12/27/94, LICENSEE OBTAINED A SAMPLE OF THE UNIT 1 STEAM | | GENERATOR BLOWDOWN RELEASED FROM THE PLANT FOLLOWING COMPLETION OF A | | SCHEDULED MAINTENANCE OUTAGE. THE SAMPLE CONTAINED 257.7 MG/LITER OF TOTAL | | SUSPENDED SOLIDS (TSS) AND VISIBLE SOLIDS AND MAGNETITE BUT NO DETECTABLE | | RADIOACTIVITY. THE BLOWDOWN RELEASE HAD BEEN STOPPED AT 0503. | | | | AT 0930 ON 12/27/94, LICENSEE NOTIFIED THE VIRGINIA STATE DEPARTMENT | | OF ENVIRONMENTAL QUALITY (WATER) THAT THE RELEASE EXCEEDED THE VIRGINIA | | POLLUTION DISCHARGE ELIMINATION SYSTEM (VPDES) TSS RELEASE LIMIT OF | | 100 MG/LITER. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28188 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/27/94 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 13:30 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 11:20[CST]| |NRC NOTIFIED BY: WELCH |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ELECTRICAL RELAYS IN BOTH ATWS LOGIC TRAINS FAILED DURING A TEST - | | | | DURING A REFUELING OUTAGE, LICENSEE WAS PERFORMING A TECH SPEC SURVEILLANCE | | TEST OF THE ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) SYSTEM FROM 03/11/94 | | TO 06/20/94. | | | | ON 03/11/94 DURING THE TEST, THE ATWS TIME DELAY RELAY #K101C FAILED TO | | TRIP AND THE ATWS TIME DELAY RELAY #K101D FAILED TO TRIP WITHIN THE | | REQUIRED TECH SPEC TIME TOLERANCE. | | | | THESE RELAYS PROVIDE A TRIP SIGNAL TO THE RECIRCULATION MOTOR-GENERATOR SET | | FIELD BREAKERS UPON RECEIPT OF A LOW-LOW REACTOR VESSEL WATER LEVEL SIGNAL. | | | | FAILURE OF THESE RELAYS RENDERED BOTH ATWS LOGIC TRAINS 'A' & 'B' INCAPABLE | | OF INITIATING THE RECIRCULATION M-G SET FIELD BREAKER TRIPS. | | | | LICENSEE REPLACED BOTH RELAYS AND BOTH TESTED SATISFACTORILY TO WITHIN | | THE REQUIRED TOLERANCES PRIOR TO THE STARTUP OF UNIT 3 FROM THE REFUELING | | OUTAGE. | | | | AT 1120 (CST) ON 12/27/94, LICENSEE DISCOVERED THAT THIS EVENT HAD NOT | | BEEN REPORTED TO THE NRC. | | | | LICENSEE IS INVESTIGATING THE REASON FOR THEIR FAILURE TO REPORT THIS | | MULTIPLE FAILURES OF REDUNDANT TRAINS OF A SAFETY RELATED SYSTEM EVENT | | TO THE NRC AT THE TIME OF OCCURRENCE ON 03/11/94. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28189 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 12/27/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 16:07 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 12:15[PST]| |NRC NOTIFIED BY: POCHE |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -HIGH CONTROL ROOM EMERGENCY FILTRATION SYSTEM HUMIDITY SENSORS SETPOINTS- | | | | AT 1215 (PST), LICENSEE DETERMINED THAT THE SETPOINTS FOR BOTH TRAINS OF | | THE CONTROL ROOM EMERGENCY FILTRATION (CREF) SYSTEM HUMIDITY SENSORS ARE | | NOT ADEQUATE TO ENSURE PERFORMANCE OF THE SYSTEM'S CARBON FILTERS UNDER | | ALL CONDITIONS. THE INSTALLED HUMIDITY SENSORS HAVE A NONADJUSTABLE | | SETPOINT OF 70 +/-7% RELATIVE HUMIDITY. IN ORDER TO ENSURE CARBON FILTER | | PERFORMANCE ASSUMED IN THE DESIGN BASIS, IT IS NECESSARY THAT THE RELATIVE | | HUMIDITY NOT EXCEED 70%. | | | | BETWEEN 1215 AND 1220 (PST), LICENSEE ENTERED TECH SPEC LCO A/S 3.0.3 | | TO INSTALL ELECTRICAL JUMPERS THAT WILL RESULT IN ENERGIZATION OF THE CREF | | SYSTEM HEATERS WHEN THE SYSTEM IS UTILIZED IN THE EMERGENCY MODE OF | | OPERATION. THIS CONFIGURATION HAS BEEN ANALYZED AND FOUND TO BE | | ACCEPTABLE PROVIDED OUTSIDE AIR TEMPERATURE REMAINS BELOW 80 DEGREES F | | (WHICH IT SHOULD FOR SEVERAL MONTHS). | | | | LICENSEE IS DETERMINING PERMANENT CORRECTIVE ACTIONS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28190 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/27/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:15 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 14:20[CST]| |NRC NOTIFIED BY: RUSTIC |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 40 POWER OPERATION | 40 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SCOTT COUNTY EMERGENCY SIRENS INOPERABLE FOR LONGER THAN ONE HOUR - | | | | AT 1420 (CST), SCOTT COUNTY, IOWA OFFICIALS NOTIFIED LICENSEE THAT THE | | SCOTT COUNTY EMERGENCY SIRENS BECAME INOPERABLE AT 1400 (CST) FOR UNKNOWN | | REASONS. COUNTY CONTRACTORS ARE REPAIRING THE SIRENS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1824 (CST) BY RUSTIC ENTERED BY HOO JOLLIFFE * * * | | | | AT 1650 (CST), SCOTT COUNTY CONTRACTORS REPLACED A BATTERY IN A SIREN | | SYSTEM ENCODER AND DECLARED THE SIRENS OPERABLE. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R3DO JOHN MADERA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28191 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/27/94 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 12/27/94 | +------------------------------------------------+EVENT TIME: 16:45[EST]| |NRC NOTIFIED BY: DAVE NIX |LAST UPDATE DATE: 12/27/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STEVEN VIAS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ALL 3 UNITS IN SHUTDOWN LCO DUE TO INOPERABLE Rx BUILDING SPRAY SYSTEMS - | | | | LICENSEE WAS REVIEWING THE PLANT ABNORMAL PROCEDURE FOR THE LOSS OF LOW | | PRESSURE INJECTION FOR EACH UNIT. LICENSEE DETERMINED THAT DURING A | | POSTULATED LOSS OF COOLANT ACCIDENT IN WHICH A SINGLE FAILURE DISABLES | | 1 OF THE 2 REACTOR BUILDING EMERGENCY SUMP LINES, THIS PROCEDURE INSTRUCTS | | THE CONTROL ROOM OPERATORS TO STOP BOTH REACTOR BUILDING SPRAY PUMPS PRIOR | | TO SWAPPING THE SUCTION PATH FROM THE BORATED WATER STORAGE TANK TO THE | | REACTOR BUILDING EMERGENCY SUMP. | | | | THIS CONDITION IS BEYOND THE DESIGN BASIS ASSUMPTIONS OUTLINED IN THE | | MAXIMUM HYPOTHETICAL ACCIDENT (MHA) PER THE NRC SAFETY EVALUATION REPORT | | (SER) FOR THE OCONEE NUCLEAR STATION UPDATED FINAL SAFETY ANALYSIS REPORT. | | THIS SER REQUIRES OPERABILITY OF THE REACTOR BUILDING SPRAY SYSTEM TO | | MITIGATE THE CONSEQUENCES OF AN MHA. | | | | AT 1645, LICENSEE DECLARED ALL 3 REACTOR BUILDING SPRAY SYSTEMS INOPERABLE | | AND ENTERED TECH SPEC LCO A/S 3.0 WHICH REQUIRES ALL 3 UNITS TO BE PLACED | | IN HOT SHUTDOWN MODE WITHIN 12 HOURS. LICENSEE ADMINISTRATIVELY IS NOT | | REQUIRED TO BEGIN ACTUAL POWER REDUCTION FOR THE FIRST 6 HOURS. | | | | LICENSEE INTENDS TO REVISE THE ABNORMAL PROCEDURE FOR EACH UNIT SUCH THAT | | UPON FAILURE OF THE SUCTION LINE FROM THE REACTOR BUILDING EMERGENCY SUMP | | TO THE LOW PRESSURE INJECTION/REACTOR BUILDING SPRAY PUMPS, THE CONTROL | | ROOM OPERATORS WILL BE INSTRUCTED TO STOP 1 LOW PRESSURE INJECTION PUMP | | WHICH WILL LEAVE 1 LOW PRESSURE INJECTION PUMP AND 1 REACTOR BUILDING SPRAY | | PUMP RUNNING. THIS LINEUP WILL MEET ALL DESIGN BASIS ASSUMPTIONS SPECIFIED | | IN THE MHA. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2232 BY OWENS ENTERED BY HOO JOLLIFFE * * * | | | | AT 2225, LICENSEE REVISED ALL 3 ABNORMAL PROCEDURES AND EXITED TECH SPEC | | LCO A/S 3.0. | | | | ALL 3 UNITS REMAINED AT 100% POWER THROUGHOUT THIS EVENT. | | | | LICENSEE PREPARED A SAFETY EVALUATION OF THIS CONDITION IN ACCORDANCE WITH | | 10CFR50.59. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R2DO STEVE VIAS. | +------------------------------------------------------------------------------+