U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/21/94 - 04/22/94 ** EVENT NUMBERS ** 27059 27131 27132 27133 27134 27135 27136 27137 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/08/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 12:00 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 07:58[CDT]| |NRC NOTIFIED BY: SCHUSSLER |LAST UPDATE DATE: 04/21/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 12 HR LCO ACTION STATEMENT TO BE IN HOT S/D DUE TO | | THEIR INABILITY TO COMPLETE MAINTENANCE WORK ON A CST LEVEL SWITCH WITHIN | | THE REQUIRED 24 HR TIME PERIOD. | | | | THIS OCCURRED WHEN THEY WERE PERFORMING MAINTENANCE ON A LEVEL SWITCH ON | | THE CONDENSATE STORAGE TANK WHICH CONTROLS THE SUCTION SOURCE FOR THE HPCI | | AND RCIC SYSTEMS. THEY WERE UNABLE TO COMPLETE THE MAINTENANCE ON THIS | | SWITCH WITHIN THE 24 HR PERIOD(ENDING AT 07:58CDT) DUE TO UNANTICIPATED | | PROBLEMS WITH REPAIRING OF THE SWITCH(A COVER PLATE HAD TO BE | | MANUFACTURED). THE SWITCH WAS FINALLY REPAIRED BY 10:47 AND THE LCO ACTION | | STATEMENT WAS EXITED. THE RI WAS INFORMED. | | | | * * * UPDATE 04/21/94 1158EST FROM:SUEPER BY:SCARFO * * * | | THIS EVENT IS BEING RETRACTED ON THE BASIS THAT SUFFICIENT ADMINISTRATIVE | | CONTROLS WERE IN PLACE TO ENSURE THAT THE SAFETY FUNCTION OF THE HPCI AND | | RCIC SYSTEMS WOULD BE COMPLETED IF PLANT CONDITIONS WARRANTED THEIR | | ACTUATIONS. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED THE LICENSEE: | | "ON APRIL 8 AT AROUND 1105, THE DUANE ARNOLD ENERGY CENTER NOTIFIED THE NRC | | OF A REPORTABLE CONDITION BASED ON THE FAILURE TO COMPLETE POST-MAINTENANCE | | TESTING ON A CONDENSATE STORAGE TANK (CST) LEVEL ELEMENT, LE5219, WITHIN | | THE ALLOWED OUT OF SERVICE TIME (24 HOURS). AS A RESULT, BOTH THE HIGH | | PRESSURE COOLANT INJECTION (HPCI) AND REACTOR CORE INJECTION COOLING (RCIC) | | SYSTEMS WERE DECLARED INOPERABLE AND A 12 HOUR LIMITING CONDITION OF | | OPERATION (LCO) WAS ENTERED. PER NUREG 1022, INOPERABILITY OF A SINGLE | | TRAIN SAFETY SYSTEM SUCH AS HPCI IS CONSIDERED A FOUR-HOUR REPORTABLE | | CONDITION UNDER 10CFR50.72(b)(2)(iii). | | | | AS PART OF THE MAINTENANCE AND SUBSEQUENT POST-MAINTENANCE TESTING THAT WAS | | PERFORMED ON LE5219, THE HPCI AND RCIC PUMP SUCTION AUTOMATIC SWAP FUNCTION | | WAS DISABLED. THIS FEATURE CHANGES THE PUMP SUCTION PATH FROM THE CST TO | | THE SUPPRESSION POOL ON CST LOW LEVEL. HOWEVER, THE ABILITY OF HPCI AND | | RCIC TO AUTOMATICALLY INITIATE AND INJECT WAS NOT AFFECTED. ALSO, WITH THE | | EXCEPTION OF SEVERAL HOURS WITHIN THE ALLOWED OUT OF SERVICE WINDOW AND A | | FEW MINUTES IN THE LCO WHEN THE INSTRUMENT WAS BEING CALIBRATED, THE CST | | LOW LEVEL ALARM FUNCTION REMAINED OPERABLE. THE ANNUNCIATOR RESPONSE | | PROCEDURE FOR CST LOW LEVEL DIRECTS THE CONTROL ROOM OPERATOR TO COMPLETE | | THE PUMP SUCTION SWAP IF IT FAILS TO OCCUR AUTOMATICALLY. AT ALL TIMES, | | THE CONTROL ROOM CST LEVEL INDICATION REMAINED OPERABLE. | | | | DRAFT 2 OF NUREG 1022 REV. 1 STATES THAT THE INTENT OF THE CRITERIA FOR | | REPORTING UNDER 10 CFR 50.72(b)(2)(iii) AND 10 CFR 50.72(a)(2)(v) "...IS TO | | CAPTURE THOSE EVENTS WHERE THERE WOULD HAVE BEEN A FAILURE OF A SAFETY | | SYSTEM TO PROPERLY COMPLETE A SAFETY FUNCTION..." FURTHERMORE, IT GOES ON | | TO STATE THAT "REASONABLE OPERATOR ACTIONS TO CORRECT MINOR PROBLEMS MAY BE | | CONSIDERED..." SIMILAR WORDING ALSO APPEARS IN THE ORIGINAL NUREG 1022 AND | | IT'S SUPPLEMENTS. | | | | THE DUANE ARNOLD ENERGY CENTER STILL CONSIDERS HPCI AND RCIC TO HAVE BEEN | | TECHNICALLY INOPERABLE DURING THE 12 HOUR LCO DISCUSSED ABOVE. HOWEVER, | | GIVEN THE FACT THAT BOTH HPCI AND RCIC WERE CAPABLE OF AUTOMATICALLY | | INITIATING AND INJECTING AND THAT EXISTING PLANT PROCEDURES WOULD HAVE | | DIRECTED THE CONTROL ROOM OPERATORS TO COMPLETE THE SUCTION SWAP ON LOW CST | | LEVEL, THE DAEC NO LONGER REGARDS THIS SPECIFIC CONDITION AS REPORTABLE | | ACCORDING TO THE GUIDANCE GIVEN IN NUREG 1022." | | END OF TEXT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R3DO(WRIGHT) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27131 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/21/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 10:00 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/20/94 | +------------------------------------------------+EVENT TIME: 16:23[EDT]| |NRC NOTIFIED BY: WILLIAM STRONG |LAST UPDATE DATE: 04/21/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |AL CHAFFEE EO | |NLCO TECH SPEC LCO A/S |CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LATE NOTIFICATION OF AN UNUSUAL EVENT. REACTOR COOLANT SYSTEM LEAK RATE IN | | EXCESS OF TECH SPEC LIMIT. | | | | A RCS LEAK RATE INDICATION OF APPROXIMATELY 8 GPM, WHICH IS IN EXCESS OF | | THE TECH SPEC LIMIT (1 GPM UNIDENTIFIED/ 10 GPM IDENTIFIED), WAS OBSERVED. | | THE LEAKAGE WAS IDENTIFIED TO BE IN THE CHEMICAL VOLUME CONTROL SYSTEM | | (CVCS). THE LEAK WAS DETERMINED TO BE SEAT LEAKAGE FROM THE THREE-WAY | | DIVERTER VALVE, "2LTR7.1", BETWEEN THE VCT AND THE DE-GAS SYSTEM. THE LEAK | | WAS ISOLATED AT 1930 EDT ON 4/20/94 AND THE TECH SPEC LCO WAS EXITED. | | THE LICENSEE DETERMINED AT 0930 EDT ON 4/21/94 THAT THIS WAS REPORTABLE, | | CLASSIFIED IT AS AN UNUSUAL EVENT AND TERMINATED IT AT THAT TIME. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL GOVERNMENT | | AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27132 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/21/94 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/21/94 | +------------------------------------------------+EVENT TIME: 10:35[EDT]| |NRC NOTIFIED BY: BAIN |LAST UPDATE DATE: 04/21/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |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 +------------------------------------------------------------------------------+ | TWO REACTOR WATER CLEANUP ISOLATION VALVES FAILED A LOCAL LEAK RATE TEST | | (LLRT). | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "LOCAL LEAK RATE TESTING (LLRT) WAS BEING PERFORMED ON 2-G31-F001, REACTOR | | WATER CLEANUP INLET INBOARD ISOLATION VALVE, AND 2-G31-F004, REACTOR WATER | | CLEANUP INLET OUTBOARD ISOLATION VALVE. THIS TESTING WAS REQUIRED BY AN | | INTERNAL ACTION ITEM (INITIATED DUE TO PREVIOUS REPAIRS TO THESE VALVES | | DURING AN APRIL, 1993, OUTAGE) WHICH REQUIRED REPEATABILITY TESTING. THE | | SUBJECT VALVES HAD SATISFACTORILY PASSED THE AS-FOUND LLRTs DURING THE | | CURRENT OUTAGE. HOWEVER, THE SUBSEQUENT REPEATABILITY LLRTs OF THE SUBJECT | | VALVES DISCOVERED THAT THE LEAKAGE PAST THE VALVES EXCEEDED THE MAXIMUM | | ALLOWABLE TECHNICAL SPECIFICATION LEAKAGE. NEITHER VALVE COULD HOLD THE | | LLRT TEST PRESSURE. NO MAINTENANCE HAD BEEN PERFORMED BETWEEN THE AS-FOUND | | AND REPEATABILITY LLRTs ON EACH VALVE. | | | | THE SAFETY SIGNIFICANCE OF THIS EVENT IS MINIMAL BECAUSE THE PLANT IS IN A | | SHUTDOWN CONDITION AND THE VALVE HAD PASSED THE AS-FOUND LLRTs. AN | | ASSESSMENT OF THE SAFETY CONSEQUENCES OF THE SUBJECT PROBLEM IF IT HAD | | OCCURRED DURING PLANT OPERATION WILL BE IDENTIFIED IN THE FOLLOWING LER | | REQUIRED BY 10CFR50.73. | | | | CORRECTIVE MAINTENANCE WILL BE PERFORMED ON 2-G31-F001 AND 2-G31-F004, AND | | ANY OTHER VALVES WHICH MAY FAIL THE TECHNICAL SPECIFICATION LEAKAGE RATE | | REQUIREMENTS." | | END OF TEXT. | | | | AN INVESTIGATION INTO THE CAUSE OF THE LLRT FAILURE IS UNDERWAY. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27133 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/21/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/94 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: DORAZIO |LAST UPDATE DATE: 04/21/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOTH EMERGENCY DIESEL GENERATORS (EDGs) WERE DECLARED INOPERABLE WHEN THEY | | FAILED A LOAD-REJECT SURVEILLANCE TEST. | | | | DURING THE EDG LOAD-REJECT SURVEILLANCE TEST PERFORMED ON EDG "1A", THE | | OUTPUT VOLTAGE OF 4795 VOLTS EXCEEDED THE ACCEPTANCE LEVEL OF 4784 VOLTS. | | AN ANALYSIS OF THE RESULTS OF THE SAME SURVEILLANCE TEST PERFORMED ON EDG | | "1B" ON 03/29/94 DETERMINED THAT A SIMILAR CONDITION OCCURRED. BOTH EDGs | | WERE DECLARED INOPERABLE AND TECHNICAL SPECIFICATION (T/S) ACTION STATEMENT | | 3.8.1.2 WAS ENTERED (IMMEDIATE SUSPENSION OF CORE ALTERATIONS AND MODE | | CHANGES). | | | | BOTH TESTS WERE PERFORMED AT THE MIDPOINT OF THE KILO-VAR RANGE SPECIFIED | | IN THE SURVEILLANCE PROCEDURE (2664KVAR 25KVAR). THE LICENSEE BELIEVES | | THAT THE OUTPUT VOLTAGE WILL BE REDUCED IF THE TEST IS PERFORMED AT A LOWER | | KVAR LEVEL. THE TEST PROCEDURE WILL BE REVISED TO SPECIFY THAT THE TEST BE | | PERFORMED AT THE MINIMUM KVAR LEVEL OF 2664KVAR. THIS REVISION IS | | COMPLETED AND A RE-TEST OF THE EDGs WILL BE PERFORMED SHORTLY. DURING THE | | TIME WHEN THE EDGs WERE INOPERABLE (BUT BEFORE THE LICENSEE HAD DETERMINED | | THAT THEY WERE), CORE ALTERATIONS WERE PERFORMED AND A MODE CHANGE FROM | | REFUELING TO COLD SHUTDOWN WAS COMPLETED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 04/22/94 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 01:20 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/21/94 | +------------------------------------------------+EVENT TIME: 22:25[EDT]| |NRC NOTIFIED BY: MIKE NEMCEK |LAST UPDATE DATE: 04/22/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENGINEERED SAFETY FEATURES ACTUATION, BALANCE OF PLANT (BOP) ISOLATION, DUE | | TO HUMAN ERROR. | | | | SEVEN BOP ISOLATION VALVES HAD BEEN OPENED AND DEENERGIZED. WHEN THE | | DIVISION 2 13.8KV BUS, "EH12", WAS REENERGIZED THE 120 VAC INSTRUMENTATION | | BUS FED BY "EH12" DID NOT REENERGIZED BECAUSE REQUIRED FUSES HAD NOT BEEN | | REPLACED. PROCEDURAL PAPER WORK HAD BEEN SIGNED OFF INDICATING THAT THE | | FUSES HAD BEEN REPLACED. WHEN THE SEVEN BOP ISOLATION VALVES WERE | | REENERGIZED THEY CLOSED BECAUSE OF THE DEENERGIZED 120 VAC INSTRUMENTATION | | BUS. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/22/94 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 02:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/22/94 | +------------------------------------------------+EVENT TIME: 00:15[CDT]| |NRC NOTIFIED BY: TRAVIS BROUGHTON |LAST UPDATE DATE: 04/22/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 | A/R N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RPS ACTUATION DUE TO A NOISE SPIKE ON A SOURCE RANGE NUCLEAR | | INSTRUMENTATION CHANNEL. | | | | WHILE PERFORMING SOLID STATE PROTECTION (SSPS) CHANNEL "B" TESTING WITH | | SHUTDOWN BANKS WITHDRAWN, SOURCE RANGE CHANNEL "N-32" SPIKED HIGH | | GENERATING A TRIP SIGNAL ON TRAIN "A". THE CAUSE OF THE SPIKE IS BEING | | INVESTIGATED BECAUSE "N-32" SHOULD HAVE BEEN DEENERGIZED DURING THIS PHASE | | OF THE TEST. ALL RODS FULLY INSERTED. THE RCS HAD PREVIOUSLY BEEN BORATED | | TO COLD SHUTDOWN CONDITIONS. THE LICENSEE ELECTED TO INVOKE 10CFR50.54X BY | | NOT OPENING REACTOR TRIP BREAKER "B" AS REQUIRED BY EOP 0 STEP 1, TO ALLOW | | SSPS TO REMAIN UNCHANGED TO FACILITATE TROUBLE SHOOTING. THE FEEDWATER | | PREHEATER BYPASS VALVES WERE OPEN AND CLOSED ON THE REACTOR TRIP DUE TO P4. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27136 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/22/94 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 04:56 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/22/94 | +------------------------------------------------+EVENT TIME: 02:19[EDT]| |NRC NOTIFIED BY: GLEN LONG |LAST UPDATE DATE: 04/22/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ISOLATION OF THE REACTOR WATER CLEANUP (RWCU) SYSTEM AND SECONDARY | | CONTAINMENT AND INITIATION OF STANDBY GAS TREATMENT SYSTEM (SBGTS) DUE TO | | REFERENCE LEG PERTURBATION. | | | | THE FOLLOWING IS THE TEXT OF A LICENSEE FAX: | | "WHILE PERFORMING A VALVE LINE UP ON AN INSTRUMENT RACK FOR REACTOR WATER | | LEVEL AND PRESSURE INSTRUMENTS A DIVISION 1 RWCU ISOLATION, SECONDARY | | CONTAINMENT ISOLATION AND A SBGTS INITIATION OCCURRED. | | | | "DURING A HANDS ON VERIFICATION OF AN INSTRUMENT VALVE, THE AUXILIARY | | OPERATOR ATTEMPTED TO MOVE THE VALVE IN THE CLOSED DIRECTION PER PROCEDURE. | | THIS APPARENTLY CREATED A PERTURBATION IN THE REFERENCE LEG AND CAUSED A | | MOMENTARY FALSE LOW LEVEL 2 (112 INCHES) SIGNAL WHICH RESULTED IN THE ABOVE | | ACTUATIONS. | | | | "VERIFIED THE SIGNAL TO BE FALSE USING MULTIPLE INDICATIONS, RESET THE | | ACTUATIONS AND RETURNED RWCU, SBGTS AND THE REACTOR BUILDING VENTILATION | | SYSTEM TO NORMAL OPERATION. FOLLOW UP INVESTIGATION WILL BE IN ACCORDANCE | | WITH THE PLANT'S CORRECTIVE ACTION PROGRAM." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27137 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/22/94 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 05:39 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/22/94 | +------------------------------------------------+EVENT TIME: 03:45[EDT]| |NRC NOTIFIED BY: GREGORY COLLINS |LAST UPDATE DATE: 04/22/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ISOLATION OF THE DRYWELL H2/O2 ANALYZER DUE TO A BLOWN FUSE. | | | | THE FOLLOWING IS THE TEXT OF A LICENSEE FAX: | | "AT 0345 HOURS ON 04/22/94, A U/2 INADVERTENT ESF ACTUATION OCCURRED WHEN | | FUSE C71A-F32A IN FUSE PANEL 20C609 BLEW, CAUSING A 6C ISOLATION. VALVES | | SV-57-233, 283, & 291 CLOSED ISOLATING 20S206 DRYWELL H2/02 ANALYZER. ALSO | | AS A RESULT, U/2 RECEIVED AN A-1 HALF SCRAM. NO TESTING WAS IN PROGRESS AT | | THIS TIME. THE BLOWN FUSE WAS FOUND APPROXIMATELY 0410 HOURS. ALL | | EXPECTED ACTIONS DID OCCUR. I&C TECHNICIANS ARE INVESTIGATING TO PIN POINT | | THE CAUSE." | | | | THE FUSE WAS REPLACED. A BAD CARD FOR HIGH DRYWELL PRESSURE WAS FOUND. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+