U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/23/94 - 06/24/94 ** EVENT NUMBERS ** 27298 27308 27381 27436 27437 27438 27439 27440 27441 27442 27443 27444 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/25/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:03 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 17:50[EDT]| |NRC NOTIFIED BY: RICHARD BONNER |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AC RELAYS WERE DISCOVERED IN THE DC STARTING CIRCUIT FOR THE TWO MOTOR | | DRIVEN AUXILIARY FEEDWATER PUMPS. | | | | THE LICENSEE DISCOVERED DURING A DESIGN REVIEW THAT THE AUTOMATIC STARTING | | CIRCUIT FOR THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS HAD AC RELAYS IN IT. | | THE STARTING CIRCUIT IS A DC CIRCUIT. THE RELAYS ARE NORMALLY ENERGIZED | | AND WHEN THEY ARE DEENERGIZED THEY INITIATE AUXILIARY FEEDWATER. THE AC | | RELAYS WERE INSTALLED AS PART OF A POST TMI BACKFIT AND HAVE BEEN IN THE | | SYSTEM FOR SEVERAL YEARS. | | | | THE POTENTIAL PROBLEM WITH THE AC RELAYS IN THE DC STARTING CIRCUITRY IS AN | | INADVERTENT START OF THE MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS. THE | | TURBINE DRIVEN AUXILIARY FEEDWATER PUMP IS NOT AFFECTED BY THE PROBLEM | | BECAUSE IT DOES NOT HAVE AN AUTOMATIC START FEATURE. THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE PROBLEM AND WILL CORRECT THE PROBLEM PRIOR | | TO CHANGING MODES. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS ALSO INFORMED | | STATE AND LOCAL AUTHORITIES OF THE PROBLEM. | | | | **** RETRACTED AT 0954 EDT ON 06/23/94 BY BATES TAKEN BY ANDREWS **** | | RETRACTION OF THIS REPORT IS BEING MADE BASED ON REVIEW OF THE IMPACT OF | | THE RELAYS USED IN THE CONTROL CIRCUITS THAT INTITIATE AUXILIARY FEEDWATER. | | THE ISSUE CONCERNED THE USE OF AC RELAYS IN DC CIRCUIT. THIS | | MISAPPLICATION IS NOT REPORTABLE UNDER ANY OF THE 10 CFR 50.72 AND 10 CFR | | 50.73 CRITERIA. THIS CONDITION ALONE DOES NOT PREVENT FULFILLMENT OF A | | SAFETY FUNCTION AND HAD THIS EVENT BEEN FOUND WHILE THE PLANT WERE | | OPERATING, WOULD NOT HAVE RESULTED IN THE PRINCIPLE SAFETY BARRIERS BEING | | SERIOUSLY DEGRADED. THIS IS BASED ON ANTICIPATED FAILURE, SATISFACTORY | | OPERATION OF THE RELAYS INCLUDING SURVEILLANCE TESTING, AND OVERALL CIRCUIT | | DESIGN. ALSO, THIS EVENT DOES NOT POSE A 10 CFR 21 CONCERN | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | HOO NOTIFIED R1DO (ROGGE). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27308 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 05/26/94 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 22:50 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 19:37[EDT]| |NRC NOTIFIED BY: D.W. BAIN |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS ESF ACTUATION DURING INSTRUMENT CALIBRATION DUE TO PRESSURE | | SPIKING. | | | | "EVENT: WHILE PERFORMING A REFUELING FREQUENCY CHANNEL CALIBRATION ON | | FEEDWATER PRESSURE INSTRUMENTATION, A PRESSURE SPIKE ON THE INSTRUMENTATION | | REFERENCE LEG RESULTED IN A SPURIOUS ACTUATION OF LOW LEVEL II LEVEL | | INSTRUMENTATION. THE FOLLOWING ISOLATIONS OCCURRED: | | | | 1. REACTOR BUILDING VENTILATION ISOLATION. | | 2. REACTOR WATER CLEANUP OUTBOARD ISOLATION. | | | | AS REPORTED ON MAY 21, 1994, THE OUTBOARD ISOLATION DAMPERS FOR THE REACTOR | | BUILDING DID NOT AUTOMATICALLY CLOSE DUE TO A RELAY IN THE LOGIC WITH STUCK | | CONTACTS. THE DAMPERS WERE MANUALLY CLOSED IMMEDIATELY. REPAIR ACTIVITIES | | FOR THE DEFECTIVE RELAY ARE ONGOING. IN ADDITION, THE STANDBY GAS TREATMENT | | SYSTEM, WHICH NORMALLY WOULD HAVE AUTOMATICALLY INITIATED, WAS REMOVED FROM | | SERVICE FOR PLANNED OUTAGE ACTIVITIES." | | | | "INITIAL SAFETY SIGNIFICANCE EVALUATION: MINIMAL. ALL SYSTEMS FUNCTIONED AS | | REQUIRED EXCEPT FOR STANDBY GAS TREATMENT WHICH WAS REMOVED FROM SERVICE AS | | NOTED ABOVE." | | | | "CORRECTIVE ACTION(S): RESET THE SPURIOUS ISOLATIONS AND RESTARTED SYSTEMS | | AS REQUIRED TO SUPPORT PLANT ACTIVITIES. THE SPURIOUS ACTUATION WILL BE | | ADDRESSED THROUGH THE PLANT'S CORRECTIVE ACTION PROGRAM." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * UPDATE DATE/TIME:6/23/94 @ 1404 EDT *FROM LICENSEE:McGOWAN BY:McGINTY* | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON BEING AN INVALID ACTUATION | | INVOLVING SYSTEMS THAT ARE EXEMPTED FROM REPORTABILITY IN 10 CFR 50.72. THE | | LICENSEE INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE R2DO | | (SHYMLOCK). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27381 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/10/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 11:10 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/10/94 | +------------------------------------------------+EVENT TIME: 10:40[EDT]| |NRC NOTIFIED BY: STRONG |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT AN UNANALYZED CONDITION EXIST ASSOCIATED | | WITH THE PRIMARY PRESSURE BOUNDARY. | | | | THIS WAS DISCOVERED WHEN THEY REALIZED THAT THEY HAD SOME NON QA BALL SEALS | | (WHICH WERE INSTALLED IN 1990, QA PAPER WORK CANNOT BE FOUND) ON THE | | CONTROL ELEMENT DRIVE ASSEMBLY. PRIOR TO A RECENT MODIFICATION, WHEN THEY | | INSTALLED A VERSAVENT ASSEMBLY (DURING REFUEL OUTAGE IN 1992), THEY HAD A | | SEATING ARRANGEMENT WITH THE BALL SEALS AND A THREADED VENT PLUG TORQUED ON | | TO THE BALL PROVIDING A SEALING PATH WITH A CAP AT THE TOP AND BOTH | | TOGETHER PROVIDED QA CATEGORY 1 SEALS FOR BOUNDARIES. WHEN THEY INSTALLED | | THE VERSAVENT ASSEMBLY, HOWEVER, THEY REMOVED THE CAP. SINCE THE VERSAVENT | | ASSEMBLY DOES NOT PROVIDE CODE BOUNDARY ISOLATION DUE TO ITS DESIGN | | CONFIGURATION (IT HAS AN "O" RING WHICH PREVENTS IT FROM BEING A CODE | | ISOLATION) THEY MAY HAVE CREATED A CONDITION WITH THE COMBINATION OF BOTH | | THE NON QA BALL SEALS AND A NON QA VERSAVENT ASSEMBLY, THAT COULD | | POTENTIALLY RESULT IN NOT HAVING A QA CATEGORY 1 PRESSURE BOUNDARY FOR THE | | RCS. THEY ARE FURTHER INVESTIGATING THIS CONDITION AND WILL CORRECT PRIOR | | TO RESTART. THE RI AND STATE AND LOCAL AGENCIES WERE NOTIFIED. | | | | **** RETRACTED AT 0924 EDT ON 06/23/94 BY BATES TAKEN BY ANDREWS **** | | THIS REPORT WAS MADE AS A CONSERVATIVE MEASURE BASED ON THE DISCOVERY THAT | | NON-QA BALL SEATS WERE INSTALLED ON THE CEDM VENT ASSEMBLIES. THIS WAS | | THOUGHT TO BE AN UNANALYZED CONDITION WHICH WAS ASSOCIATED WITH THE PRIMARY | | PRESSURE BOUNDARY. SUBSEQUENT INVESTIGATION HAS DETERMINED THAT THE BALL | | SEAT IS CONSIDERED A GASKET WITHIN THE ASSEMBLY AND STEM WHICH COMPRESSES | | THE BALL SERVES AS THE ASME PRESSURE RETAINING COMPONENT. ON THIS BASIS, | | NO UNANALYZED CONDITION OR PRESSURE BOUNDARY DEGREDATION EXISTS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | HOO NOTIFIED R1DO (ROGGE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27436 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 07:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 05:07[CDT]| |NRC NOTIFIED BY: CLARENCE BUSH |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS WESTERMAN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING REMOVAL OF TEMPORARY PROCEDURE TP-94-0010 "SHUTDOWN COOLING | | RELIABILITY DURING REFUEL OUTAGES," SHORTING OF THE TEST LEAD OCCURRED. | | THIS RESULTED IN AN ISOLATION AND SUBSEQUENT TRIP OF RESIDUAL HEAT REMOVAL | | PUMP "A." RESIDUAL HEAT REMOVAL PUMP "A" WAS ALIGNED TO THE SHUTDOWN | | COOLING ALIGNMENT. THE SHORTING OF THE TEST LEADS CAUSED FUSE "1B21-H67A" | | TO BLOW INITIATING THE ISOLATION OF RESIDUAL HEAT REMOVAL PUMP "A." | | | | THE PUMP WAS OUT OF SERVICE FROM 0507 CST UNTIL 0525 CST FOR A TOTAL TIME | | OF 18 MINUTES. COOLANT TEMPERATURE AT THE START OF THE EVENT WAS 108.9 | | DEGREES F. COOLANT TEMPERATURE WHEN THE SYSTEM WAS RESTORED WAS 110.7 | | DEGREES F. THE TOTAL INCREASE OF COOLANT TEMPERATURE WAS 1.8 DEGREES F. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN PERFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27437 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 10:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: MUTZ |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARTIN FARBER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF CRIMINAL ACT INVOLVING INDIVIDUAL GRANTED ACCESS. SEE HOO LOG | | FOR DETAILS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27438 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 11:02 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: MABEN |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 2 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE MAINE DEPARTMENT OF ENVIRONMENTAL PROTECTION AND | | THE STATE NUCLEAR SAFETY ENGINEER ABOUT A SMALL KEROSENE OIL SPILL (10 TO | | 20 GALLONS) FROM THE HEATING OIL TANK FOR THE SPARE GENERATOR BUILDING. THE | | OIL SPILLED ON GRAVEL AND TO GROUND. IT IS BEING CLEANED UP BY THE HAZMAT | | TEAM. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27439 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 11:12 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 09:50[CDT]| |NRC NOTIFIED BY: DAVE HODEL |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARTIN FARBER RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DRYWELL LEAK DETECTION SYSTEMS OUTSIDE OF TECHNICAL SPECIFICATIONS. | | | | THE DRYWELL ATMOSPHERIC PARTICULATE MONITOR IS BEING REMOVED FROM SERVICE | | TO REPLACE FILTER PAPER. THIS MONITOR IS PART OF THE REACTOR COOLANT | | LEAKAGE DETECTION SYSTEM. THE OTHER LEAKAGE DETECTION SYSTEM IS THE DRYWELL | | SUMP FLOW MONITORING SYSTEM WHICH IS CURRENTLY CONSIDERED INOPERABLE AND | | ALREADY IN A 30 DAY LCO CONDITION. | | | | WITH BOTH SYSTEMS OUT OF SERVICE, THE LICENSEE IS REQUIRED TO BE IN HOT | | SHUTDOWN IN 12 HOURS. THEY DO NOT EXPECT THE PAPER CHANGE-OUT TO LAST MORE | | THAN TWO HOURS AND DO NOT ANTICIPATE HAVING TO SHUTDOWN OR REDUCE POWER. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27440 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 12:01 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 11:05[EDT]| |NRC NOTIFIED BY: BENESOLE |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - THE ELECTRICAL POWER SYSTEM FOR OCONEE IS PRESENTLY VULNERABLE TO | | A SINGLE FAILURE DUE TO RELIANCE ON A NON-SAFETY RELATED SYSTEM - | | | | WHILE PERFORMING MAINTENANCE ACTIVITIES, LICENSEE DISCOVERED THAT IF THE | | AIR PRESSURE WHICH OPERATES THE AIR OPERATED CIRCUIT BREAKERS IN THE | | KEOWEE ELECTRICAL TIES TO THE OCONEE EMERGENCY POWER PATH (#ACB-1,2,3,4) | | BECOMES LOW, A RELAY WILL LOCK OUT THE KEOWEE MAIN TRANSFORMER FROM THE | | OCONEE OVERHEAD EMERGENCY POWER PATH. PORTIONS OF THE AIR SUPPLY TO THESE | | BREAKERS IS NON-SAFETY RELATED. | | | | AT 1515 ON 06/22/94, LICENSEE DECLARED THE OCONEE OVERHEAD EMERGENCY POWER | | PATH INOPERABLE AND ENTERED TECH SPEC LCO A/S 3.7.2.A.1 WHICH REQUIRES | | THE LICENSEE TO RESTORE THE OCONEE OVERHEAD EMERGENCY POWER PATH TO | | OPERABILITY STATUS WITHIN 72 HOURS OR TO SHUT ALL THREE UNITS DOWN. | | | | LICENSEE IS PERFORMING A TEMPORARY PLANT MODIFICATION TO DISABLE THIS | | PROTECTIVE FEATURE. | | | | AT 1105 ON 06/23/94, LICENSEE COMPLETED THE OPERABILITY EVALUATION | | INCLUDING THE 10CFR50.59 SAFETY EVALUATION AND DETERMINED THAT THIS EVENT | | IS REPORTABLE TO THE NRC. | | | | LICENSEE WILL SUBMIT AN LER OF THIS EVENT TO THE NRC. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27441 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/23/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 12:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/22/94 | +------------------------------------------------+EVENT TIME: 16:10[CDT]| |NRC NOTIFIED BY: PINZON |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS WESTERMAN RDO | |NLTR LICENSEE 24 HR REPORT | | |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SECONDARY ACCIDENT MONITORING CONTAINMENT SUMP INDICATOR INOP FOR 3 MONTHS | | | | AT 0530 (CDT) ON 06/21/94, LICENSEE DISCOVERED THAT 1 OF 2 WATER LEVEL | | INDICATORS (1 CHANNEL) ON THE SECONDARY ACCIDENT MONITORING CONTAINMENT | | SUMP WAS INDICATING LOW. THE OTHER SECONDARY SUMP INDICATOR AND THE 2 | | PRIMARY SUMP LEVEL INDICATORS WERE INDICATING NORMAL LEVEL. | | | | LICENSEE DECLARED THE INDICATOR INOPERABLE AND ENTERED TECH SPEC LCO A/S | | 3.3.3.6 WHICH REQUIRES THE INOPERABLE LEVEL INDICATOR CHANNEL TO BE | | RESTORED TO OPERABLE STATUS WITHIN 7 DAYS OR TO PLACE UNIT 2 IN AT LEAST | | HOT SHUTDOWN MODE WITHIN THE NEXT 12 HOURS. | | | | AT 1200 (CDT) ON 06/21/94, LICENSEE DETERMINED THAT THE CAUSE OF THE LOW | | READING WAS THE CIRCUIT BREAKER FOR THE SECONDARY LEVEL INDICATOR WAS IN | | THE OPEN POSITION. | | | | AT 2245 (CDT) ON 06/21/94, LICENSEE COMPLETED SURVEILLANCE TESTS ON THIS | | BREAKER, CLOSED THE BREAKER, DECLARED THE LEVEL INDICATOR OPERABLE, AND | | EXITED THE A/S. | | | | AT 1610 (CDT) ON 06/22/94, LICENSEE DETERMINED BY REVIEWING INFORMATION | | FROM THE EMERGENCY RESPONSE FACILITY DATA ACQUISITION DISPLAY SYSTEM | | THAT THIS CIRCUIT BREAKER HAD BEEN OPENED SOMETIME BETWEEN 03/16/94 | | AND 03/24/94. THUS, THE A/S HAD NOT BEEN MET FOR APPROXIMATELY 3 MONTHS. | | THIS CONDITION IS IN VIOLATION OF THE LICENSEE'S PLANT OPERATING LICENSEE | | (24 HOUR REPORT). | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27442 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 17:22 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 14:50[EDT]| |NRC NOTIFIED BY: KANTNER |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A LICENSED PLANT EMPLOYEE TESTED POSITIVE FOR ILLEGAL DRUGS DURING A RANDOM | | DRUG TEST. THE EMPLOYEE'S UNESCORTED ACCESS TO THE PLANT HAS BEEN REVOKED. | | SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27443 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [2] [ ] STATE: AR |NOTIFICATION TIME: 19:40 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 18:00[CDT]| |NRC NOTIFIED BY: THOMPSON |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS WESTERMAN RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE LOST THE SAFETY PARAMETER DISPLAY SYSTEM TO THE EMERGENCY | | OPERATIONS FACILITY AND COMMUNICATIONS FROM THE METEOROLOGY TOWER DURING | | A LOCAL THUNDERSTORM. | | | | LICENSEE IS MAKING REPAIRS. | | | | LICENSEE WILL NOTIFY THE STATE AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27444 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 06/23/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 20:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/23/94 | +------------------------------------------------+EVENT TIME: 17:15[CDT]| |NRC NOTIFIED BY: REEVES |LAST UPDATE DATE: 06/23/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS WESTERMAN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -CONTROL ROOM EMERGENCY BYPASS FILTRATION SYS INOP PER TS REF REQUIREMENT- | | | | WHILE RESEARCHING DESIGN INFORMATION ASSOCIATED WITH CONTROL ROOM | | PRESSURIZATION REQUIREMENTS, LICENSEE DISCOVERED A REFERENCE IN THE USAR | | THAT INDICATED THAT THE CONTROL ROOM WOULD BE MAINTAINED AT A POSITIVE | | DESIGN PRESSURE OF 0.25 INCHES WATER GAUGE DURING ALL PLANT OPERATING | | CONDITIONS. | | | | THIS INFORMATION WAS CONTAINED IN AN AMENDMENT TO THE FSAR ASSOCIATED WITH | | CONTROL ROOM HABITABILITY REQUIREMENTS UNDER RELEASED STEAM CONDITIONS | | THAT HAD BEEN SUBMITTED TO THE NRC IN 1973. THIS NUMERICAL VALUE IS NOT | | SPECIFIED IN THE USAR. | | | | LICENSEE DECLARED THE CONTROL ROOM EMERGENCY BYPASS FILTRATION SYSTEM | | INOPERABLE SINCE THIS SYSTEM WILL NOT MAINTAIN CONTROL ROOM OVERPRESSURE | | AT THIS VALUE. TECH SPEC LCO A/S 3.12.A.4 REQUIRES THE PLANT TO BE PLACED | | IN COLD SHUTDOWN CONDITION (PRESENT PLANT CONDITION) WITHIN 24 HOURS WITH | | THIS SYSTEM INOPERABLE. | | | | LICENSEE IS RESEARCHING DESIGN INFORMATION REGARDING CONTROL ROOM | | PRESSURIZATION REQUIREMENTS, INCLUDING THE BASIS AND DESIGN REQUIREMENT | | FOR THIS VALUE. | | | | LICENSEE WILL RESOLVE THIS ISSUE PRIOR TO PLANT STARTUP PRESENTLY SCHEDULED | | FOR 06/30/94. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+