U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/23/94 - 11/25/94 ** EVENT NUMBERS ** 27955 27993 28060 28061 28062 28063 28064 28065 28066 28067 28068 28069 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27955 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/26/94 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 20:58 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 18:12[EDT]| |NRC NOTIFIED BY: HOLDAM |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SOLENOID VALVES FOR 2 PORVs NOT INCLUDED IN THE UNIT 3 EQ PROGRAM - | | | | WITH UNIT 3 IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE SINCE | | FEBRUARY 1993, LICENSEE DISCOVERED THAT THE SOLENOID VALVES FOR TWO | | POWER OPERATED RELIEF VALVES (PORVs) ARE NOT INCLUDED IN THE UNIT 3 | | ENVIRONMENTAL QUALIFICATION (EQ) PROGRAM. | | | | THIS CONDITION POTENTIALLY COULD HAVE RENDERED BOTH PORVs INOPERABLE AND | | UNABLE TO PERFORM THEIR OVER PRESSURIZATION SYSTEM PROTECTION FUNCTION | | AND COULD HAVE POTENTIALLY PLACED UNIT 3 IN A CONDITION THAT ALONE COULD | | HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF SYSTEMS (PORVs) | | NEEDED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. | | | | LICENSEE WILL INCLUDE THESE VALVES IN THE UNIT 3 EQ PROGRAM AND WILL | | REVIEW THE UNIT 3 EQ PROGRAM. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 11/23/94 1435EDT FROM:PARKS BY:SCARFO * * * | | THE LICENSEE IS RETRACTING THIS EVENT ON THE BASIS THAT THE SOLENOID VALVES | | ARE NUCLEAR GRADE AND ENVIRONMENTALLY-QUALIFIED BY ASCO FOR MORE THAN | | THIRTY YEARS. THE SOLENIODS WILL BE ADDED TO THE EQ PARTS LIST AND | | INCLUDED IN THE EQ TEST PROGRAM. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. R1DO(RULAND) NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27993 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/04/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 15:09 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/04/94 | +------------------------------------------------+EVENT TIME: 14:52[EST]| |NRC NOTIFIED BY: STEVE BRINKMAN |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO FSAR COMMITMENTS ARE NOT BEING MET | | | | 1) THE FSAR TAKES CREDIT FOR THE MANUAL TERMINATION OF AUXILIARY FEED | | WATER (AFW) WITHIN 10 MINUTES FOLLOWING CERTAIN ACCIDENTS. NO | | CORRESPONDING PROCEDURE EXISTS WITHIN THE EMERGENCY OPERATING PROCEDURES TO | | IMPLEMENT MANUAL TERMINATION OF AFW. | | | | 2) THE FSAR IDENTIFIES MINIMUM AND MAXIMUM TIMES FOR THE AUTO INITIATION | | OF AFW IN CERTAIN CIRCUMSTANCES. NO SURVEILLANCE PROCEDURE EXISTS WHICH | | VERIFIES THE MINIMUM ACTUATION TIME. | | | | THE LICENSEE IS CURRENTLY IN A REFUELING OUTAGE SCHEDULED TO END IN THE | | BEGINNING OF DECEMBER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 11/23/94 1412EDT FROM:STRONG BY:SCARFO * * * | | THE LICENSEE IS RETRACTING THIS EVENT ON THE BASIS THAT AN INVESTIGATION | | INTO THE IMPLEMENTATION OF THE FSAR ASSUMPTIONS HAS FOUND THAT ALL | | ASSUMPTIONS ARE BEING MET AND NO REPORT WAS NECESSARY. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. R1DO(RULAND) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/23/94 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 01:25 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/22/94 | +------------------------------------------------+EVENT TIME: 21:37[EST]| |NRC NOTIFIED BY: PHIL ROGERS |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE 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 +------------------------------------------------------------------------------+ | INVALID PRESSURE SIGNAL CAUSES SIAS (SAFETY INJECTION ACTUATION SIGNAL) | | | | AN INVALID HIGH PRESSURE SIGNAL ON PRESSURIZER CHANNELS C & D OCCURRED | | DURING FILLING OF THE REACTOR COOLANT SYSTEM. THE HIGH PRESSURE SIGNAL | | CLEARED THE SIAS BLOCK, ALLOWING THE ACTUAL PRESSURE OF 72 PSIG ON CHANNELS | | A & B TO INITIATE THE SIAS AND CONTAINMENT ISOLATION SIGNAL. THE HIGH | | PRESSURE SAFETY INJECTION (HPSI) PUMPS WERE RACKED OUT AND THEREFORE DIDN'T | | START. THE LOW PRESSURE SAFETY INJECTION (LPSI) PUMPS WERE ALREADY RUNNING | | FOR DECAY HEAT REMOVAL. BOTH EDG's STARTED. | | | | THE B EDG LOADED ON TO ITS BUS ABOUT 20 MINUTES AFTER THE SIAS OCCURRED. | | THE EDG LOADED ON TO THE BUS WHEN THE TIE BREAKER SUPPLYING THE BUS OPENED | | FOR UNKNOWN REASONS. THE CAUSE OF THE HIGH PRESSURIZER PRESSURE SIGNAL AND | | THE REASON FOR THE TIE BREAKER OPENING ARE UNDER INVESTIGATION. ALL SYSTEMS | | HAVE BEEN RESTORED TO THEIR STATUS PRIOR TO THE SIAS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 11/23/94 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 02:53 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/23/94 | +------------------------------------------------+EVENT TIME: 01:55[EST]| |NRC NOTIFIED BY: GREGORY SASSON |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE | | | | "AT 0155 EST ON 11/23/94 THE UNIT 1 HPCI SYSTEM WAS DECLARED INOPERABLE. | | THE SYSTEM WAS DECLARED INOPERABLE AS A RESULT OF FAILURE TO MEET SEISMIC | | SUPPORT REQUIREMENTS ON THE STEAM SUPPLY LINE. A STATION EMPLOYEE REPORTED | | THE FAILURE OF A VERTICAL TRAPEZE STRUT ON THE HPCI STEAM SUPPLY LINE AT | | 1600 ON 11/22/94. STATION ENGINEERING IMMEDIATELY CONDUCTED A REVIEW OF | | THE HPCI SYSTEM DESIGN REQUIREMENTS AND DETERMINED THAT THE STEAM LINE NO | | LONGER WAS SEISMICALLY QUALIFIED. THIS DETERMINATION WAS MADE AT 0155 EST | | ON 11/23/94. THE TIME OF INOPERABILITY WILL BE CONSIDERED AS 1600 ON | | 11/22/94 FOR LCO TRACKING PURPOSES. THE HPCI SYSTEM IS CURRENTLY | | CONSIDERED INOPERABLE BUT AVAILABLE." | | | | ALL OTHER ECCS SYSTEMS ARE CURRENTLY OPERABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/23/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 08:16 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/23/94 | +------------------------------------------------+EVENT TIME: 03:27[CST]| |NRC NOTIFIED BY: DORWICK |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY (HPCS) INOPERABLE DURING MAINTENANCE | | | | WHILE HANGING AN OUT OF SERVICE (OOS) ON THE 1B DIESEL GENERATOR TO INSPECT | | DC CONTROL COMPONENTS, THE DIVISION 3 DC BUS WAS DEENERGIZED. THIS | | RESULTED IN THE HPCS PUMP'S CONTROL LOGIC BECOMING DEENERGIZED, AND MADE | | THE HPCS PUMP INOPERABLE. THE AUTHOR OF THE OOS REALIZED THAT THIS WOULD | | BE THE CASE BUT THE NEW ELECTRONIC OUT OF SERVICE PROGRAM DID NOT REFLECT | | THIS CLEARLY. | | | | THE CONTROL ROOM IMMEDIATELY REALIZED THAT THE HPCS PUMP WAS MADE | | INOPERABLE. IT TOOK ABOUT THREE HOURS TO RESTORE THE HPCS PUMP TO AN | | OPERABLE STATUS. MOST OF THE DELAY WAS ASSOCIATED WITH MANIPULATING THE | | NEW OOS SYSTEM. | | | | SUBSEQUENTLY THE OOS WAS REWRITTEN AND THE DIV 3 BUS WAS REENERGIZED. THIS | | ALLOWED THE HPCS PUMP TO REMAIN OPERABLE WHILE THE 1B DG WAS OOS FOR | | INSPECTION. ALL OTHER ECCS SYSTEMS AND EDGs WERE OPERABLE THROUGHOUT THE | | EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/23/94 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:54 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/23/94 | +------------------------------------------------+EVENT TIME: 13:15[EST]| |NRC NOTIFIED BY: COLOMB |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |NINF INFORMATION ONLY |PAPIERELLO EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 66 POWER OPERATION | 66 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A PACKAGE OF SAFETY RELIEF VALVE (SRV) PARTS EXCEEDED INCOMING RADIOLOGICAL | | INSPECTION LIMITS OF 49CFR173.422(d). | | | | A PACKAGE CONTAINING RECONDITIONED SRV PARTS FROM WYLE LABORATORIES | | REGISTERED 0.8 mREM/HR ON AN INCOMING INSPECTION AT THE PLANT, EXCEEDING | | THE 49CFR173.22(d) LIMIT OF 0.5 mREM/HR. THE DOSE MEASUREMENT WAS | | CONDUCTED ON A GEIGER-MUELLER COUNTER. THE PACKAGE WAS IMPOUNDED IN A | | SECURED AREA AND REMAINS UNOPENED. NO PERSONNEL EXPOSURES OCCURRED. AN | | INVESTIGATION IS BEING CONDUCTED. | | | | WYLE LABORATORIES AND ROBERTS EXPRESS (THE CARRIER) HAVE BEEN NOTIFIED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 11/23/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:11 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/23/94 | +------------------------------------------------+EVENT TIME: 17:30[CST]| |NRC NOTIFIED BY: STERN |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ENGINEERING EVALUATION DETERMINED THAT AN EMERGENCY DIESEL GENERATOR | | (EDG) COOLING WATER PUMP MAY NOT PERFORM ITS SAFETY FUNCTION DURING/AFTER A | | SEISMIC EVENT. | | | | DURING MAINTENANCE OF THE "1/2" EDG COOLING WATER PUMP BEDPLATE, A | | TECHNICIAN NOTICED THAT A HANGER ON THE SUCTION OF THE COOLING WATER PUMP | | WAS IMPROPERLY ENGAGED. AN ENGINEERING EVALUATION DETERMINED THAT THE | | LOADING ON THE PUMP SUCTION NOZZLE DURING A SEISMIC EVENT WOULD EXCEED THE | | DESIGN CAPACITY OF THE HANGER. IN SUCH AN INSTANCE, THE COOLING WATER PUMP | | MAY NOT PERFORM ITS SAFETY FUNCTION. THE EDG COOLING WATER PUMP PROVIDES | | COOLING WATER TO THE EDG AND THE ECCS ROOM COOLERS. THE LENGTH OF TIME | | THIS CONDITION HAS EXISTED IS UNKNOWN. MAINTENANCE WORK CONTINUES ON THE | | "1/2" EDG. NO TECHNICAL SPECIFICATION ACTION STATEMENT HAS BEEN ENTERED | | DUE TO THE MODE OF OPERATION. | | | | THE HANGER WILL BE REPAIRED PRIOR TO RESTART. THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/23/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 21:49 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 11/23/94 | +------------------------------------------------+EVENT TIME: 17:00[PST]| |NRC NOTIFIED BY: POCHE |LAST UPDATE DATE: 11/23/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TECHNICAL SPECIFICATION (T/S)-REQUIRED SHUTDOWN SHOULD HAVE BEEN | | INITIATED WHEN BOTH TRAINS OF THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM | | WERE INOPERABLE DURING ACCEPTANCE TESTING. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "FOLLOWING SURVEILLANCE TESTING PERFORMED ON 11/21/94, CONTROL ROOM | | EMERGENCY FILTRATION SYSTEM TRAIN "B" WAS DECLARED INOPERABLE WHEN IT DID | | NOT MEET ACCEPTANCE CRITERIA FOR CONTROL ROOM PRESSURIZATION. FOLLOWING | | INVESTIGATION AND CORRECTIVE MAINTENANCE TO REDUCE LEAKAGE THROUGH A | | SUSPECT AIR HANDLER DOOR SEAL, EMERGENCY FILTRATION TRAIN "B" WAS RETESTED | | ON 11/22/94 AND AGAIN DID NOT SATISFY ACCEPTANCE CRITERIA FOR CONTROL ROOM | | PRESSURIZATION. ON THE MORNING OF 11/23/94, FOLLOW-UP INVESTIGATION | | IDENTIFIED UNCAPPED CABLE PENETRATIONS ENTERING THE CONTROL ROOM. | | SUBSEQUENTLY, THE PENETRATIONS WERE TEMPORARILY SEALED AND THE EMERGENCY | | FILTRATION SYSTEM WAS RETESTED WITH SATISFACTORILY RESULTS. | | | | IT HAS BEEN DETERMINED THAT THE CABLE PENETRATIONS WERE OPENED ON THE | | AFTERNOON OF 11/22/94, AND THEREFORE DID NOT CONTRIBUTE TO THE INITIAL | | FAILURE OF EMERGENCY FILTRATION SYSTEM TRAIN "B" ON 11/21/94. A FOLLOW UP | | OPERABILITY ASSESSMENT WAS INITIATED TO DETERMINE OPERABILITY STATUS FOR | | THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM DURING THIS EVENT. THIS | | ASSESSMENT, WHICH WAS COMPLETED AFTER THE SATISFACTORY EMERGENCY FILTRATION | | SYSTEM RETEST, DETERMINED THAT BOTH CONTROL ROOM EMERGENCY FILTRATION | | TRAINS WERE INOPERABLE FROM THE TIME THAT PENETRATIONS WERE OPENED IN THE | | CONTROL ROOM, UNTIL THE PENETRATIONS WERE TEMPORARILY SEALED AND THE | | EMERGENCY FILTRATION SYSTEM WAS SATISFACTORILY RETESTED. CONSEQUENTLY, | | T.S. 3.0.3 SHOULD HAVE BEEN ENTERED. AN IN-DEPTH INVESTIGATION OF THIS | | EVENT IS IN PROGRESS." END OF TEXT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/24/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 02:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/24/94 | +------------------------------------------------+EVENT TIME: 01:40[EST]| |NRC NOTIFIED BY: RCHARD KRAMER |LAST UPDATE DATE: 11/24/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |MARTIN VIRGILIO EO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOE LOUZONIS FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 80 POWER OPERATION | 70 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED BASED ON TECH SPEC REQUIRED SHUTDOWN | | | | TECH SPEC 3.6.E.2 REQUIRES THE PLANT TO BE SHUTDOWN AND PRESSURE REDUCED TO | | LESS THAN 90 PSIG WITHIN 24 HOURS WHENEVER ONE SAFETY RELIEF VALVE IS | | DECLARED INOPERABLE. THE PLANT HAS DETERMINED ONE SRV TO BE INOPERABLE | | BASED ON A SLOW HEAT UP OF THE TORUS WATER (ABOUT 4-5 DEGREES F PER DAY). | | CURRENT TORUS TEMPERATURE IS 71 DEGREES F. | | | | THE LICENSEE'S CONCERN IS AN INCREASE IN THE LIFT PRESSURE OF THE SRV | | CAUSED BY AN INCREASE IN THE BACK PRESSURE ACTING ON THE SRV. THE | | LICENSEE'S EMERGENCY PLAN REQUIRES THE DECLARATION OF AN UNUSUAL EVENT | | WHENEVER A SHUTDOWN IS REQUIRED BY TECH SPECS. | | | | THE LICENSEE INTENDS TO SHUTDOWN THE PLANT AND PROCEED TO COLD SHUTDOWN TO | | MAKE REPAIRS TO THE SRV. THE SPECIFIC SRV INVOLVED HAS NOT BEEN | | DETERMINED, BUT IS BELIEVED TO BE THE E SRV BASED ON THE TEMPERATURE | | SENSORS IN THE TORUS. THE UNUSUAL EVENT CAN BE TERMINATED WHEN THE UNIT IS | | SHUTDOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS THE APPROPRIATE | | STATE AND LOCAL OFFICIALS. A PRESS RELEASE IS PLANNED. | | | | * * * UPDATE AT 1805 EST 11/24/94 BY KNOLL TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT WAS TERMINATED WHEN REACTOR PRESSURE WAS REDUCED BELOW 90 | | PSIG AND THE LCO WAS EXITED. RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/24/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:03 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/24/94 | +------------------------------------------------+EVENT TIME: 09:30[EST]| |NRC NOTIFIED BY: BRYAN CROKE |LAST UPDATE DATE: 11/24/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID MCGUIRE 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF COMMUNICATION CAPABILITY | | | | THE LICENSEE REPORTED THE LOSS OF THE NUCLEAR ALERT SYSTEM PHONE LINK TO | | THE STATE OF NEW HAMPSHIRE. THE IS A MICROWAVE PHONE SYSTEM. A BACKUP | | LAND LINE IS AVAILABLE AND HAS BEEN TESTED. THE STATES OF VERMONT AND | | MASSACHUSETTS WERE ALSO NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28068 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/24/94 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 17:19 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/24/94 | +------------------------------------------------+EVENT TIME: 14:12[EST]| |NRC NOTIFIED BY: HARMON |LAST UPDATE DATE: 11/24/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McGUIRE 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 +------------------------------------------------------------------------------+ | SAFETY INJECTION ACTUATION SIGNAL AND CONTAINMENT ISOLATION SIGNAL | | GENERATED DURING TESTING. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "B TRAIN SAFETY INJECTION ACTUATION SIGNAL (SIAS) WITH CONCURRENT B TRAIN | | CONTAINMENT ISOLATION SIGNAL (CIS) OCCURRED DURING TIME RESPONSE TESTING | | WHICH WAS BEING PERFORMED BY INSTRUMENT AND CONTROL (I&C) PERSONNEL. | | | | A TRAIN SIAS WAS IN BLOCK. | | | | THE B TRAIN SIAS AND CIS COMPONENTS ACTUATED AS EXPECTED FOR EXISTING | | SHUTDOWN PLANT CONDITIONS. | | | | BISTABLES ARE REQUIRED TO BE PULLED FOR TESTING PER I&C TEST PROCEDURE. | | APPARENT CAUSE OF SPURIOUS/INADVERTENT ACTUATION WAS ONE BISTABLE MODULE | | WAS NOT PULLED OUT FAR ENOUGH AWAY FROM ITS ASSOCIATED CIRCUIT BOARD. IT | | INADVERTENTLY MADE CONTACT AND A SPURIOUS SIGNAL WAS GENERATED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28069 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/24/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 22:30 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/24/94 | +------------------------------------------------+EVENT TIME: 21:30[CST]| |NRC NOTIFIED BY: SPIELER |LAST UPDATE DATE: 11/24/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HILAND RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE DECLARED THE HIGH PRESSURE CORE SPRAY SYSTEM INOPERABLE DUE TO | | INOPERABILITY OF THE ASSOCIATED EMERGENCY DIESEL GENERATOR. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 2130 THE 72 HOUR TIME CLOCK FOR THE 1B DIESEL GENERATOR (DG) EXPIRED. | | IN ACCORDANCE WITH OUR TECHNICAL SPECIFICATIONS WE DECLARED THE UNIT 1 HIGH | | PRESSURE CORE SPRAY SYSTEM (HPCS) INOPERABLE AND ENTERED THE 14 DAY TIME | | CLOCK FOR THAT SYSTEM. THE 1B DG WILL REMAIN INOPERABLE UNTIL FURTHER | | TESTING IS COMPLETED FOR OPERABILITY. ALL OTHER EMERGENCY CORE COOLING | | SYSTEMS AND DGs ARE OPERABLE AT THIS TIME." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+