U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/11/95 - 04/12/95 ** EVENT NUMBERS ** 28632 28662 28663 28664 28665 28666 28667 28668 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28632 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/04/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 12:26 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/02/95 | +------------------------------------------------+EVENT TIME: 05:18[CST]| |NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 04/11/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT SYSTEM (SBGT) STARTED ON A HIGH RADIATION SIGNAL | | | | THE LICENSEE DETERMINED ON 1000 ON 4/4/95 THAT THE SBGT SYSTEM STARTED ON | | AN INVALID HIGH RAD SIGNAL FROM THE ANNULUS RADIATION MONITOR RMS*RE11B. | | THE EVENT OCCURRED AT 0518 ON 4/2/95. | | | | THE DELAY IN REPORTING OCCURRED BECAUSE THE PLANT ORIGINALLY THOUGHT THE | | CAUSE OF THE SBGT ACTUATION WAS A LOW FLOW SIGNAL IN THE ANNULUS PRESSURE | | CONTROL SYSTEM. THE LICENSEE TERMED THE LOW FLOW SIGNAL AS A 'NON-ESF | | SIGNAL' AND CONCLUDED THAT THE EVENT WAS NOT REPORTABLE. | | | | UPON REVIEWING THIS EVENT ON 4/4/95, WITH THE KNOWLEDGE THAT THE CAUSE OF | | THE START WAS THE FAILURE OF A RAD MONITOR, THE LICENSEE CONCLUDED THAT THE | | EVENT WAS REPORTABLE. THE RADIATION MONITOR SIGNAL WAS TERMED AN 'ESF | | SIGNAL'. THE CHANGE IS BASED ON THE DIFFERENCE IN CLASSIFICATION BETWEEN | | THE SIGNALS THOUGHT TO HAVE CAUSED THE ACTUATION. | | | | THE RADIATION MONITOR IN QUESTION IS CURRENTLY BEING REPAIRED. | | | | BOTH RESIDENT INSPECTORS ARE ON TRAVEL. THE LICENSEE WILL INFORM OTHER | | REGIONAL INSPECTORS CURRENTLY ON SITE. | | | | *** UPDATE DATE\TIME 4/11/95 @ 1443 EDT FROM LICENSEE (CLARK) BY McGINTY*** | | | | THE LICENSEE'S INVESTIGATION DETERMINED THAT THIS NOTIFICATION WAS NOT | | REQUIRED FOR THE FOLLOWING REASONS: | | | | THE 1992 REVISION TO 10CFR50.72 AND 50.73 CHANGED CERTAIN INVALID ESF | | ACTUATIONS TO 'NOT REPORTABLE'. GUIDANCE ASSOCIATED WITH THE REVISION | | (FEDERAL REGISTER 57FR41378 AND NUREG-1022, REV. 1, DRAFT 2) CLARIFIES THIS | | CHANGE TO THE REPORTABILITY CRITERIA. IN PARTICULAR, INVALID ACTUATIONS OF | | THE REACTOR BUILDING VENTILATION SYSTEM (OR EQUIVALENT) ARE NOT REPORTABLE | | AS ESF ACTUATIONS. BECAUSE THE STANDBY GAS TREATMENT SYSTEM FUNCTIONS AS A | | SUBSYSTEM OF THE OVERALL REACTOR BUILDING VENTILATION SYSTEM, INVALID | | ACTUATIONS OF STANDBY GAS TREATMENT SYSTEM IN THESE CIRCUMSTANCES ARE NOT | | REPORTABLE. | | | | IN THIS CASE, AN INVALID ANNULUS HIGH RADIATION SIGNAL WAS GENERATED BY | | FAILURE OF THE CENTRAL PROCESSING UNIT ASSOCIATED WITH THE ANNULUS | | RADIATION MONITOR. BECAUSE THE REACTOR BUILDING VENTILATION (INCLUDING | | STANDBY GAS TREATMENT SYSTEM) ACTUATED IN RESPONSE TO AN INVALID SIGNAL, | | THIS EVENT IS NOT REPORTABLE UNDER 10CFR50.72(b)(2)(ii). | | | | THE LICENSEE DISCUSSED THIS RETRACTION WITH THE NRC SENIOR RESIDENT | | INSPECTOR. THE HOO NOTIFIED THE R4DO (JOHNSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28662 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/11/95 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 04:07 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/95 | +------------------------------------------------+EVENT TIME: 00:40[CDT]| |NRC NOTIFIED BY: DAVID SCHUSSLER |LAST UPDATE DATE: 04/11/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLAYTON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING LOSS OF OFFSITE POWER (LOOP)/LOSS OF COOLANT ACCIDENT (LOCA) TESTING | | THE 'A' EMERGENCY DIESEL GENERATOR (EDG) FAILED TO LOAD ONTO THE EMERGENCY | | BUS. | | | | THE EDG STARTED DURING THE TEST BUT DID NOT LOAD ONTO THE BUS. THE LICENSEE | | IS CONTINUING TO INVESTIGATE THE PROBLEM. AT THIS TIME THE CAUSE OF THE | | PROBLEM APPEARS TO BE BAD CONTACTS IN THE EDG UNDERVOLTAGE CIRCUIT THAT | | SENSES IF THE EMERGENCY BUS IS DEENERGIZED BEFORE IT ALLOWS THE EDG OUTPUT | | BREAKER TO CLOSE. THE TEST WAS LAST SUCCESSFULLY PERFORMED ON THE 'A' EDG | | DURING THE LAST REFUELING OUTAGE. THE 'B' EDG LOOP/LOCA TEST WAS | | SUCCESSFULLY COMPLETED YESTERDAY. THE LICENSEE IS NOT CURRENTLY IN ANY | | TECHNICAL SPECIFICATION ACTION STATEMENT DUE TO THIS PROBLEM. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28663 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/11/95 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 09:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/95 | +------------------------------------------------+EVENT TIME: 09:03[EDT]| |NRC NOTIFIED BY: HARRIS |LAST UPDATE DATE: 04/11/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HOSEY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT SUMP SWAPOVER VALVES FOUND DECLUTCHED DURING CONTAINMENT | | WALKDOWNS. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "A ONE-HOUR PHONE CALL FOR UNIT 1 PER 50.72(b)(1)(ii)(B) AND A FOUR-HOUR | | PHONE CALL FOR UNIT 2 PER 50.72(b)(2)(i) IS BEING MADE AS A RESULT OF THE | | DISCOVERY OF ONE TRAIN OF CONTAINMENT SUMP SWAPOVER VALVES BEING | | INOPERABLE. THE VALVES WERE FOUND IN A DECLUTCHED STATE. UNIT 1 FCV 63-73 | | (B TRAIN) AND UNIT 2 FCV 63-72 (A TRAIN) WERE DISCOVERED IN A DECLUTCHED | | STATE DURING WALKDOWN OF AN EMERGENCY INSTRUCTION. WHILE THE EXACT | | DURATION THESE VALVES WERE IN THE DECLUTCHED POSITION IS NOT KNOWN, IT IS | | ASSUMED THAT SOME [AT] TIME DURING EACH UNITS OPERATION, THE OPPOSITE TRAIN | | OF ECCS EQUIPMENT WAS INOPERABLE FOR MAINTENANCE OR OTHER REASONS. WITH | | BOTH TRAINS OF ECCS INOPERABLE, THE PLANT IS PLACED OUTSIDE DESIGN BASIS." | | | | THE LICENSEE DISCOVERED THE DECLUTCHED VALVES DURING WALKDOWNS TO VERIFY | | NEW EMERGENCY OPERATING PROCEDURES. THE MOTOR OPERATORS FOR THESE VALVES | | ARE MADE BY LIMITORQUE, BUT ARE OF A SPECIAL-USE DESIGN, AND WOULD NOT HAVE | | AUTOMATICALLY REENGAGED HAD THE VALVES BEEN GIVEN AN ELECTRICAL SIGNAL TO | | REPOSITION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28664 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MICHIGAN STATE UNIVERSITY |NOTIFICATION DATE: 04/11/95 | | CITY: REGION: 3 |NOTIFICATION TIME: 11:28 [ET]| | COUNTY: STATE: MI |EVENT DATE: 04/07/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/11/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CLAYTON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ERICKSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE REPORTED LOSS OF 250ęCi P-32 FROM MICHIGAN STATE UNIVERSITY | | LABORATORY. | | | | ON 3/31/95, A 250ęCi SHIPMENT OF P-32 WAS RECEIVED BY A UNIVERSITY | | LABORATORY. THE LICENSEE DISCOVERED THAT THE SOURCE WAS MISSING ON 4/7/95, | | AND HAS UNSUCCESSFULLY SEARCHED FOR THE SOURCE. THE LICENSEE BELIEVES THAT | | THE SOURCE MAY HAVE BEEN DISCARDED WITH TRASH AND TAKEN TO A LANDFILL. THE | | LICENSEE REPORTED THAT A MAJOR CLEANING OF THE LABORATORY OCCURRED ON THE | | DAY OF RECEIPT OF THE SHIPMENT, AND THAT THE SHIPMENT MAY HAVE BEEN | | INADVERTENTLY MIXED IN WITH OTHER TRASH AND TAKEN TO THE LANDFILL. THE | | LICENSEE DOES NOT BELIEVE THAT THE SOURCE MAY HAVE BEEN STOLEN. | | | | THE LICENSEE HAS CONTACTED NRC REGION III (SRENIAWSKI). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28665 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/11/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:38 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/95 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: CROKE |LAST UPDATE DATE: 04/11/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SAFETY RELIEF VALVE SOLENOID VALVE WAS FOUND TO HAVE A DEFECTIVE WELD ON | | A MOUNTING STRUT. | | | | VERMONT YANKEE HAS FOUR SAFETY RELIEF VALVES (SRV) THAT ARE FOR BOTH | | OVER-PRESSURE PROTECTION AND THE ADS (AUTOMATIC DEPRESSURIZATION SYSTEM) | | FUNCTION. ONE OF THE SOLENOID VALVES (SD-2-71A) THAT FEEDS THE "71A" SRV | | IS CONNECTED BY A BRACKET TO A UNI-STRUT. THE UNI-STRUT FILLET WELD TO AN | | I-BEAM WAS FOUND TO BE BROKEN DURING A SEISMIC QUALIFICATION INSPECTION OF | | THE SAFE SHUTDOWN EQUIPMENT LIST. | | | | IF A SEISMIC EVENT WERE TO HAVE OCCURRED DURING OPERATION, THE LICENSEE | | COULD NOT CONCLUSIVELY DEFINE THAT THE "71A" SRV WOULD OPERATE IN THE ADS | | FUNCTION. VERMONT YANKEE WOULD ENTER A 7 DAY LCO IF THE ADS FUNCTION OF | | THE "71A" VALVE WERE TO BECOME INOPERABLE DURING OPERATION. WITH THE PLANT | | IN THE REFUELING OUTAGE, THE LICENSEE HAS NOT HAD TO ENTER AN LCO FOR THE | | CONDITION. THE LICENSEE BELIEVES THAT THE WELD WAS PROBABLY BROKEN DURING | | THE MOST RECENT RUN CYCLE. THE LICENSEE ALSO WILL INSPECT THE WELDS FOR | | THE OTHER THREE SRV's. THE LICENSEE WILL BE REPAIRING THE WELD. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28666 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/11/95 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 23:26 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/11/95 | +------------------------------------------------+EVENT TIME: 20:51[CDT]| |NRC NOTIFIED BY: BARNES |LAST UPDATE DATE: 04/11/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 HAD A TURBINE TRIP AND RX SCRAM CAUSED BY AN OPERATOR PUTTING | | JUMPERS ON THE WRONG LINK DURING THE PERFORMANCE OF A WARM-UP PROCEDURE TO | | RESTORE THE REACTOR WATER CLEANUP (RWCU) SYSTEM TO SERVICE. | | | | WHEN THE OPERATOR PLACED THE JUMPERS ON THE WRONG TERMINALS, THIS CAUSED | | THE FEEDWATER CONTROL SYSTEM TO MALFUNCTION AND RAISE RX VESSEL WATER | | LEVEL. THE TURBINE TRIPPED (CAUSING THE RX SCRAM) AND THE FEEDWATER PUMPS | | TRIPPED ON THE HIGH RX VESSEL WATER LEVEL CONDITION. ALL RODS FULLY | | INSERTED. | | | | FOLLOWING THE FEEDPUMP TRIP, THE UNIT TOOK A GROUP 2 ISOLATION AND A RCIC | | AUTO-START ON LOW REACTOR VESSEL WATER LEVEL. HPCI ALSO STARTED AND | | INJECTED FOR ABOUT ONE SECOND BEFORE BEING ISOLATED. THE UNIT IS STABLE IN | | HOT SHUTDOWN, STEAMING TO THE MAIN CONDENSER AND MAINTAINING LEVEL WITH | | RCIC. ALL OF THE ECCS's AND EDG's ARE OPERABLE. THE LICENSEE IS EVALUATING | | MAINTENANCE ITEMS TO DETERMINE A POTENTIAL RESTART DATE. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28667 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 04/11/95 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 23:31 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 04/11/95 | +------------------------------------------------+EVENT TIME: 23:00[EDT]| |NRC NOTIFIED BY: GRANT |LAST UPDATE DATE: 04/11/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BRIAN SHERON EO | | |WRIGHT FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED AN UNUSUAL EVENT BASED ON REACTOR COOLANT SYSTEM | | LEAKAGE GREATER THAN 10 gpm. THE UNUSUAL EVENT WAS TERMINATED AT 2333 EDT, | | BASED ON THE LEAKAGE BEING STOPPED. | | | | THE LICENSEE WAS PERFORMING SURVEILLANCE TEST "OST-254" (ANNUAL OPERATIONAL | | PRESSURE TEST) ON RHR SYSTEM TRAIN "A". THE LICENSEE OPENED VALVE | | "HCV-142" (OFF OF CVCS SYSTEM UPSTREAM OF THE NON-REGENERATIVE HEAT | | EXCHANGER) TO FILL AND PRESSURIZE RHR LOOP "A" AND IMMEDIATELY RECEIVED A | | VCT "MAKEUP" INDICATION. THE LICENSEE CLOSED "HCV-142" UPON THE INDICATION | | OF THE LEAKAGE, BUT THIS DID NOT STOP THE LEAKAGE (THE VALVE INDICATES | | CLOSED). THE LICENSEE THEN MANUALLY SHUT VALVE "CVC-205B" (IMMEDIATELY | | UPSTREAM OF "HCV-142"), WHICH ISOLATED THE LEAK. THE LICENSEE IS | | INVESTIGATING WHERE THE LEAKAGE WENT TO, HOWEVER, AT THIS TIME THEY BELIEVE | | THE WATER WENT TO THE RWST (RWST LEVEL INCREASED 0.1%). | | | | RHR TRAIN "A" WAS AT ATMOSPHERIC PRESSURE WHEN THE VALVE WAS OPENED TO FILL | | AND PRESSURIZE THE SYSTEM, WHICH WAS TO BE OPERATIONALLY TESTED AT ABOUT | | 350 psig. THE LICENSEE HAD PREVIOUSLY REMOVED RHR TRAIN "A" FROM SERVICE | | FOR THE PERFORMANCE OF THE TEST, HAVING ENTERED A 24 HOUR LCO (RHR TRAIN | | "A" REMAINS OUT OF SERVICE FOR THE INVESTIGATION). ALL OTHER ECCS's AND | | EDG's ARE OPERABLE, INCLUDING RHR TRAIN "B". | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 2333 EDT, BASED ON THE LEAKAGE | | BEING STOPPED. THE UNIT REMAINS AT 100% POWER, AND THE LICENSEE WILL BE | | INVESTIGATING THE CAUSE OF THE LEAKAGE. THE LICENSEE INFORMED THE RESIDENT | | INSPECTOR, AND STATE AND LOCAL AUTHORITIES OF THE UNUSUAL EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28668 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/12/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 01:47 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/11/95 | +------------------------------------------------+EVENT TIME: 21:13[CDT]| |NRC NOTIFIED BY: JOHN REIS |LAST UPDATE DATE: 04/12/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 +------------------------------------------------------------------------------+ | ESF ACTUATION DUE TO ERROR DURING TESTING | | | | AN ESF ACTUATION OCCURRED WHEN VENT VALVE 2B21-N413B WAS OPENED WITH THE | | INSTRUMENT STOP VALVE OPEN AT THE SAME TIME. A PRESSURE SPIKE RESULTED AND | | CAUSED THE ASSOCIATED ESF ACTUATIONS. THESE VALVES ARE ASSOCIATED WITH A | | PRESSURE TRANSMITTER USED FOR GENERATING A REFERENCE LEG SIGNAL IN THE | | REACTOR PRESSURE VESSEL LEVEL SYSTEM. AS SOON AS THE SPIKE OCCURRED, THE | | VENT VALVE WAS CLOSED. THE INSTRUMENT STOP VALVE WAS THOUGHT TO HAVE BEEN | | CLOSED WHEN THE VENT VALVE WAS OPENED. THESE VALVES WERE MANIPULATED IN | | THE PERFORMANCE OF SURVEILLANCE LIS-NB-418B, A FUNCTIONAL TEST OF THE LPCI | | INJECTION VALVE OPEN PERMISSIVE. | | | | THE FOLLOWING SIGNALS WERE RECEIVED. | | | | CHANNEL "B" RPS 1/2 SCRAM | | CHANNEL "B" PCIS GROUPS 1-7, 10 PARTIAL TRIPS | | RCIC LOW LEVEL INITIATION & HI LEVEL VALVE CLOSURE | | CHANNEL B ARI AND ATWS RPT | | CHANNEL B ADS LOW LEVEL PERMISSIVE | | DIVISION 2 ECCS INITIATION | | | | THE DIV 2 ECCS INITIATION CONSISTED OF THE 2A D/G STARTING & THE 2C RHR | | INJECTION VALVE 2E12-F042C OPENING. THE 2B RHR INJECTION VALVE DID NOT | | OPEN BECAUSE OF A 500 lb. INJECTION LINE INTERLOCK. THIS INTERLOCK CAME | | FROM PRESSURE SWITCH 2E12-N413B BEING PRESSURIZED BY THE INSTRUMENT | | SURVEILLANCE. BOTH THE B & C RHR PUMPS WERE IN PULL TO LOCK AND DID NOT | | START. | | | | AT THE TIME OF THE EVENT, RCIC WAS ISOLATED & DIVISION 2 ECCS WAS NOT | | REQUIRED. THERE WAS NO INJECTION INTO THE RPV. THE UNIT WAS IN REFUEL AND | | FLOODED UP. ALL SIGNALS HAVE BEEN RESET AND THE EDG HAS BEEN SECURED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+