U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/26/94 - 05/27/94 ** EVENT NUMBERS ** 27244 27295 27297 27301 27302 27303 27304 27305 27306 27307 27308 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 05/13/94 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 03:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/13/94 | +------------------------------------------------+EVENT TIME: 02:51[EDT]| |NRC NOTIFIED BY: SMITH |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAD A TRIP OF THE CONTAINMENT GASEOUS RADIATION MONITOR, WHICH | | CAUSED A CONTAINMENT VENTILATION ISOLATION. | | | | WHILE ATTEMPTING TO DRAIN COLD LEG ACCUMULATORS TO THE REACTOR COOLANT | | DRAIN TANK (RCDT), THE DRAIN VALVES WERE OPENED PRIOR TO THE RCDT's PUMPS | | BEING STARTED. THIS CAUSED THE TANK TO FILL UP, WHICH CAUSED APPROXIMATELY | | FIVE GALLONS OF WATER TO COME OUT OF THE DRAIN TANK VENT. THE CONTAMINATED | | WATER CAUSED THE CONTAINMENT BUILDING GAS MONITOR TO REACH THE "TRIP 2" | | SETPOINT. THIS EVENT CAUSED THE "B" TRAIN CONTAINMENT PURGE VALVES TO | | CLOSE, THE REACTOR BUILDING EVACUATION ALARM TO SOUND AND OCCURRED DURING | | CORE ALTERATIONS. THERE WAS A FUEL ASSEMBLY IN THE MANIPULATOR CRANE AT | | THE TIME, AND IT WAS PLACED IN THE UPENDER, SET DOWN AND SENT TO THE POOL. | | THE EVACUATION WAS THEN COMPLETED. | | | | THE WATER THAT CAME OUT THE VENT AND ONTO THE FLOOR HAS RAISED THE | | BACKGROUND COUNT RATE, AND WILL BE CLEANED UP. THE SETPOINT FOR THE RAD | | MONITOR WILL NOW BE ADJUSTED BASED ON THE NEW BACKGROUND, AND THEN CORE | | ALTERATIONS WILL BE RESUMED. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | | | | * * * UPDATE 1716EDT 5/26/94 FROM RYBCZYK TO S.SANDIN * * * | | THE LICENSEE IS RETRACTING THIS EVENT AFTER FURTHER REVIEW DETERMINED THAT | | THIS WAS NOT AN ESF ACTUATION. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. NOTIFIED R2DO(PEEBLES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/25/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 13:14[CDT]| |NRC NOTIFIED BY: DAVE KUSER |LAST UPDATE DATE: 05/27/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNING EO | |NLCO TECH SPEC LCO A/S |BOB CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH EMERGENCY DIESEL GENERATORS BEING | | DECLARED INOPERABLE. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON MAY 25, 1994 AT 1:14 PM A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED | | WHEN BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE | | SURVEILLANCE TEST CONDUCTED EACH REFUELING OUTAGE NOT VERIFYING THE LOAD | | SHEDDING OF ALL LOADS ON THE CRITICAL 480 VOLT BUS. PROPER LOAD SHEDDING | | OF ALL 4160 VOLT LOADS IS VERIFIED DURING THE SEQUENTIAL LOADING TEST. THE | | PRINCIPAL 480 VOLT LOADS NOT VERIFIED TO BE SHED INCLUDE STATION AIR | | COMPRESSORS AND THE CRD PUMPS. THESE COMPONENTS ARE TRANSFERRED TO ANOTHER | | BUS DURING THE SURVEILLANCE TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE | | CRITICAL 480 VOLT BUS ARE SMALL. | | | | IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS IN SECTION 3.5.F.2, | | A LOAD REDUCTION TO 25 PERCENT POWER WAS INITIATED. AN ENGINEERING | | EVALUATION OF THE CONDITION IS ONGOING. A FOLLOW-UP NOTIFICATION WILL BE | | MADE WHEN SUCH INFORMATION IS AVAILABLE." END OF TEXT. | | | | THE LICENSEE IS REDUCING POWER AT 100 MW(e) PER HOUR. THE LICENSEE | | CONSIDERS THE EDGS AVAILABLE. ALL ECCS AND RCIC ARE OPERABLE. THE WEATHER | | IN THE AREA IS CALM WITH NO FORECAST OF RAIN. THE PROBLEM WAS DISCOVERED | | DURING REVIEW OF UNDERVOLTAGE TESTING. THE LAST REFUELING OUTAGE ENDED IN | | JULY OF 1993. THE LICENSEE IS INVESTIGATING CORRECTIVE ACTIONS AND IS | | PURSUING ENFORCEMENT DISCRETION WITH THE NRC TO STOP THE POWER DESCENSION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS INFORMED LOCAL AND | | STATE OFFICIALS IN ACCORDANCE WITH THEIR EMERGENCY PLAN. | | | | * * * UPDATE 5/25/94 @ 22:40 FROM CAUL TAKEN BY SEBROSKY * * * | | THE REACTOR IS CURRENTLY AT 24% POWER AND THE LICENSEE PLANS TO SCRAM THE | | THE PLANT AT 22:00 CT PER THEIR NORMAL SHUTDOWN PROCEDURES. THE SHUTDOWN | | IS BEING DONE DUE TO BOTH EDGS BEING DECLARED INOPERABLE. THE LICENSEE | | WILL EXIT THE UNUSUAL EVENT WHEN THE PLANT REACHES COLD SHUTDOWN | | CONDITIONS. COLD SHUTDOWN IS EXPECTED TO BE REACHED SOMETIME TOMORROW | | MORNING. THE LICENSEE HAS BEEN IN CONTACT WITH REGION 4 OFFICIALS | | CONCERNING THE SHUTDOWN AND HAS INFORMED THE RESIDENT INSPECTOR. | | | | HOO NOTIFIED R4DO(POWERS) AND EO(). | | | | * * * UPDATE 5/27/94 @ 0106 FROM HITZEL TAKEN BY WEAVER * * * | | THE PLANT REACHED COLD SHUTDOWN AT 2357 CDT ON 5/26/94. THIS SATISFIES THE | | TECHNICAL SPECIFICATION ACTION STATEMENT FOR HAVING BOTH EMERGENCY DIESELS | | INOPERABLE. CONTRARY TO THE LAST UPDATE, THE UNUSUAL EVENT WILL NOT BE | | TERMINATED UNTIL AT LEAST ONE EDG IS MADE OPERABLE AS REQUIRED BY THEIR | | EMERGENCY PROCEDURES. NO TIME ESTIMATE WAS AVAILABLE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL GOVERNMENTS. | | | | HOO NOTIFIED R4 RDO (POWERS) AND EO ( ). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27297 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 05/25/94 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 15:34 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 13:15[EDT]| |NRC NOTIFIED BY: RADISHOFSKI |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "TESTING OF THE EMERGENCY SWITCHGEAR ROOM COOLING SYSTEMS HAS UNCOVERED A | | WIRING INADEQUACY WHICH RENDERS EACH SYSTEM'S AUTOMATIC START FUNCTION | | INOPERABLE. A RELAY IN EACH SYSTEM'S AUTOMATIC START CIRCUITRY HAS NOT | | BEEN INCORPORATED INTO THE LOGIC AS IS DIRECTED BY PLANT DRAWINGS. AS A | | RESULT, A COOLING FAN TRIP ON A LOSS OF OFFSITE POWER COULD POTENTIALLY | | FAIL TO RESET AUTOMATICALLY. THE NATURE OF THE WIRING DEFICIENCY IS SUCH | | THAT THE PROBLEM DOES NOT ROUTINELY MANIFEST ITSELF UNDER AUTOMATIC SYSTEM | | START CONDITIONS. THE SWITCHGEAR COOLED BY THE REDUNDANT SYSTEMS IS | | CRITICAL TO THE OPERATION OF ENGINEERED SAFEGUARD SYSTEMS NECESSARY TO | | MITIGATE THE CONSEQUENCES OF AN ACCIDENT AT SUSQUEHANNA. EMERGENCY | | SWITCHGEAR ROOM COOLING CAN STILL BE ESTABLISHED THROUGH MANUAL SYSTEM | | START." | | END OF TEXT. | | | | THIS CONDITION WAS DISCOVERED DURING AN 18-MONTH SURVEILLANCE PERFORMED | | DURING THE NIGHT SHIFT. THE EMERGENCY SWITCHGEAR ROOM COOLING SYSTEMS WERE | | DECLARED INOPERABLE AND TECHNICAL SPECIFICATION ACTION STATEMENTS 3.8.3.1 | | AND 3.8.3.2 WERE ENTERED. AN INVESTIGATION INTO THE CORRECT STATUS OF THE | | RELAY CONTACTS (CONNECTED TO THE LOGIC OR DISCONNECTED VIA AN APPROVED | | PLANT MODIFICATION) HAS BEGUN. CORRECTIVE ACTIONS WILL BE PURSUED PENDING | | COMPLETION OF THIS INVESTIGATION. THE SYSTEM REMAINS FULLY OPERABLE, IT IS | | JUST THE AUTOMATIC ACTUATION SIGNAL THAT IS DISABLED DUE TO THE WIRING | | DEFICIENCY. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27301 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 05/26/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 05:09 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 00:40[CDT]| |NRC NOTIFIED BY: MATT POHL |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION FOR A ONE GALLON HYDRAZINE SPILL | | | | AT 0040 CDT A SECURITY GUARD REPORTED A STRONG AMMONIA ODOR IN THE VICINITY | | OF THE SECONDARY CHEMISTRY AMERZINE (I.E. HYDRAZINE) STORAGE TOTES. AN | | OPERATOR WAS DISPATCHED AND DISCOVERED THE AMERZINE SPILL. FURTHER | | INVESTIGATION REVEALED A LOOSE SWAGE-LOCK FITTING ON THE SUCTION OF THE | | AMERZINE TRANSFER PUMP. | | | | THE SPILLED LIQUID IS ISOLATED BY A BERM AND ROPED OFF TO PREVENT PERSONNEL | | ENTRY INTO THE AREA. THE SPILL WILL BE CLEANED UP WHEN HAZMAT PERSONNEL | | ARRIVE IN THE MORNING. NO PLANT EQUIPMENT OTHER THAN THE STORAGE TOTES ARE | | INACCESSIBLE BECAUSE OF THIS SPILL. NOTIFICATION WILL BE MADE TO THE | | NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY DURING NORMAL BUSINESS HOURS | | TODAY. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27302 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 05/26/94 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 11:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 10:20[CDT]| |NRC NOTIFIED BY: BRUCE BUTLER |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 NON-LICENSED SUPERVISOR WAS CONFIRMED POSITIVE FOR A RANDOM DRUG TEST | | (ALCOHOL). THE LICENSEE HAS SUSPENDED UNESCORTED ACCESS AND REFERRED HIM TO | | THE EMPLOYEE ASSISTANCE PROGRAM. A WORK REVIEW WILL BE PERFORMED. SEE HOO | | LOG FOR DETAILS. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27303 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/26/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 13:31 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 09:44[CDT]| |NRC NOTIFIED BY: DAVE KUSER |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SHUTDOWN COOLING ISOLATION DURING FLUSHES DUE TO SPURIOUS ACTUATION OF | | REACTOR RECIRCULATION PUMP LOW SUCTION PRESSURE TO RHR INTERLOCK PRESSURE | | SWITCH. | | | | "AT 9:44 AM, WITH THE PLANT SHUTDOWN AND THE RESIDUAL HEAT REMOVAL (RHR) | | SYSTEM BEING FLUSHED AND HEATED IN ACCORDANCE WITH SECTION 8.1 OF OPERATING | | PROCEDURE 2.2.69.2 IN PREPARATION FOR PLACING IT IN THE SHUTDOWN COOLING | | MODE OF OPERATION, AN UNEXPECTED CLOSURE OF RHR SHUTDOWN COOLING SUPPLY | | ISOLATION VALVES RHR-MOV-M017 AND 18 OCCURRED. THESE PRIMARY CONTAINMENT | | ISOLATION VALVES ARE THE SUCTION VALVES FROM THE REACTOR COOLANT SYSTEM TO | | THE RHR SYSTEM AND AUTOMATICALLY CLOSE IF REACTOR PRESSURE IS GREATER THAN | | 72.5 PSIG (TECH SPEC SETPOINT PER TABLE 3.2.A IS LESS THAN OR EQUAL TO 75 | | PSIG) OR UPON A GROUP 2 ISOLATION CAUSED BY DRYWELL HIGH PRESSURE OR LOW | | REACTOR WATER LEVEL." | | | | "AT THE TIME, THE SUCTION VALVE TO RHR PUMP "B" HAD BEEN OPENED AND THE | | SUCTION VALVE TO RHR PUMP "D" WAS BEING OPENED. REACTOR COOLANT PRESSURE | | WAS APPROXIMATELY 40 PSIG AND TEMPERATURE WAS APPROXIMATELY 290 DEGREES | | FAHRENHEIT. A REACTOR WATER LEVEL DECREASE OF APPROXIMATELY 5 INCHES, FROM | | THE 50 INCHES NARROW RANGE TO 45 INCHES, WAS NOTED. NORMAL WATER LEVEL | | DURING PLANT OPERATION IS 35 INCHES NARROW RANGE." | | | | "AN INVESTIGATION INTO THE UNEXPECTED TRIP WAS INITIATED IMMEDIATELY, AND | | PRELIMINARY INDICATIONS ARE THAT THE TRIP OCCURRED DUE TO THE SPURIOUS | | ACTUATION OF ONE OR BOTH OF THE REACTOR RECIRCULATION PUMP LOW SUCTION | | PRESSURE TO RHR INTERLOCK PRESSURE SWITCHES. DURING RECOVERY FROM THIS | | ISOLATION, SEVERAL ADDITIONAL ISOLATIONS DUE TO SPURIOUS PRESSURE SPIKES | | OCCURRED. RECOVERY ACTIONS ARE CONTINUING." | | | | "A SIMILAR UNEXPECTED CLOSURE OF THE SUCTION VALVES HAD PREVIOUSLY OCCURRED | | ON MARCH 17, 1994. AT THAT TIME, THE RHR SYSTEM HAD ALREADY BEEN PLACED IN | | SHUTDOWN COOLING AND BULK REACTOR COOLANT TEMPERATURE WAS APPROXIMATELY 175 | | DEGREES FAHRENHEIT. AS SPECIFIED IN THE ASSOCIATED LER, (94-005), THE NSSS | | VENDOR INDICATED THAT VOID FORMATION IS NOT UNEXPECTED AT THIS TEMPERATURE. | | CORRECTIVE ACTIONS TO PREVENT RECURRENCE FROM THAT EVENT HAVE NOT YET BEEN | | COMPLETED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOONOTE: SEE EVENT #26953 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27304 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 05/26/94 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 14:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: HARDIN |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF CRIMINAL HISTORY OF CONTRACTOR GRANTED ACCESS. IMMEDIATE | | COMPENSATORY MEASURES TAKEN ON DISCOVERY. SEE HOO LOG FOR DETAILS. THE | | LICENSEE INFORMED THE NRC REGION 2 OFFICE AND THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27305 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/26/94 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 16:00 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 00:00[PDT]| |NRC NOTIFIED BY: BRUCE R. HUGO |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IS MAKING A PART 21 NOTIFICATION. | | | | SUBJECT: WNP-2, OPERATING LICENSE NPF-21 | | 10 CFR PART 21 REPORT | | AUTOMATIC SWITCH COMPANY (ASCO) REPLACEMENT SOLENOID PILOT VALVE | | DIAPHRAGMS SUPPLIED BY GENERAL ELECTRIC NUCLEAR ENERGY | | | | SUPPLIER: GENERAL ELECTRIC (GE) NUCLEAR ENERGY | | 175 CURTNER AVENUE | | SAN JOSE, CA 95125 | | | | "SCRAM SOLENOID PILOT VALVE (SSPV) DIAPHRAGMS SUPPLIED TO WNP-2 BY GE | | NUCLEAR ENERGY HAVE SHOWN A DECREASED SERVICE LIFE COMPARED WITH PREVIOUS | | EXPERIENCE. DIAPHRAGMS REMOVED FROM SERVICE FOLLOWING THE MARCH 26, 1994, | | FAILURE OF A CONTROL ROD TO SCRAM HAD SIGNIFICANT DEGRADATION CONSISTING OF | | HARDENING, SET, AND CRACKING. THIS DEGRADATION HAS RESULTED IN INCREASED | | SCRAM TIME FROM SOME CONTROL RODS. AN UNUSUAL COMBINATION OF SSPV PRESSURE | | AND EXHAUST DIAPHRAGM DEGRADATION CAUSED THE FAILURE OF ONE CONTROL ROD TO | | SCRAM." | | | | "DIAPHRAGMS WITH SIGNIFICANT DEGRADATION HAD BEEN IN SERVICE BETWEEN 3.6 | | AND 4 YEARS. THE SUPPLIER RECOMMENDS A MAXIMUM 4 YEAR SERVICE LIFE. | | ANALYSIS OF THE DIAPHRAGMS INDICATES A DIFFERENCE IN THE COMPOSITION OF THE | | BUNA-N MATERIAL (e.g., VARIABILITY IN FILLER, ACRYLONITRILE, AND | | PLASTICIZER CONTENT) COMPARED WITH DIAPHRAGMS REMOVED IN 1990. THIS | | COMPOSITION DIFFERENCE MAY HAVE CHANGED THE AGING CHARACTERISTICS OF THE | | BUNA-N MATERIAL; DIAPHRAGMS REMOVED IN 1990 HAD LESS DEGRADATION AFTER UP | | TO 6.6 YEARS IN SERVICE THAN THOSE REMOVED IN 1994 WITH UP TO 4 YEARS IN | | SERVICE. THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOES NOT BELIEVE THAT | | DIAPHRAGM SHELF LIFE WAS A FACTOR IN THE DEGRADATION." | | | | "THE SSPV DIAPHRAGMS HAVE BEEN REPLACED FOR ALL CONTROL RODS. WNP-2 IS | | REEVALUATING THE ALLOWABLE SERVICE LIFE OF THE DIAPHRAGMS." | | | | THE LICENSEE WILL PROVIDE A WRITTEN REPORT AS A REVISION TO AN EXISTING | | WNP-2 LICENSEE EVENT REPORT (LER 94-005). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27306 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/26/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:28 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 17:33[CDT]| |NRC NOTIFIED BY: YURKOVICH |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOSE CALVO EO | | |BELCHER FEMA | | |BROCKMAN IRB | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 DECLARED AN UNUSUAL EVENT DUE TO SUSPECTED PRESSURIZER POWER | | OPERATED RELIEF VALVE (PORV) LEAKAGE > 25 GPM. | | | | AT 1657CDT, OPERATORS OBSERVED A DECREASE IN PRESSURIZER AND VOLUME CONTROL | | TANK LEVEL INDICATIONS AND AN INCREASE IN THE PRESSURIZER RELIEF TANK LEVEL | | AND TEMPERATURE INDICATIONS. AN UNUSUAL EVENT WAS DECLARED AT 1733CDT AND | | THE UNIT 2 EMERGENCY PROCEDURE FOR EXCESSIVE PRIMARY PLANT LEAKAGE ENTERED. | | THE INITIAL LEAKAGE WAS ESTIMATED AT 75 GPM. OPERATORS SUSPECTING THAT ONE | | OF THE PORVs WAS LEAKING, SHUT THE ASSOCIATED BLOCK VALVE. AN INSPECTION | | INSIDE CONTAINMENT IS UNDERWAY TO CONFIRM THAT THE RCS LEAK HAS BEEN | | ISOLATED. THE CURRENT PRESSURIZER LEVEL IS 30% AND STABLE WITH THE RCS AT | | NOP/NOT. THE LOWEST PRESSURIZER LEVEL RECORDED WAS 23%. ALL SAFETY-RELATED | | EQUIPMENT IS AVAILABLE. THE LICENSEE WILL MAINTAIN UNIT 2 IN MODE 3 WHILE | | INVESTIGATING THE SOURCE OF THE RCS LEAKAGE. THE LICENSEE INFORMED THE | | ILLINOIS DEPT. OF NUCLEAR SAFETY, ILLINOIS EMERGENCY MANAGEMENT AGENCY AND | | WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 2035EDT 5/26/94 FROM YURKOVICH TO S.SANDIN * * * | | AN INSPECTION INSIDE CONTAINMENT VERIFIED THAT THE RCS LEAKAGE WAS NOT FROM | | THE PORV AS PREVIOUSLY REPORTED. THE CURRENT LEAKAGE IS ESTIMATED AT 58 | | GPM. THE LICENSEE IS CONTINUING EFFORTS TO IDENTIFY AND ISOLATE THE SOURCE | | OF THE RCS LEAKAGE TO THE PRT COLLECTION HEADER. THE LICENSEE HAS INSERTED | | ALL SHUTDOWN BANKS AND IS MAKING PREPARATIONS TO COOLDOWN, IF NECESSARY. | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(MADERA), | | EO(CALVO), IRB(BROCKMAN) AND AEOD(JORDAN). | | | | * * * UPDATE 2127EDT 5/26/94 FROM YURKOVICH TO S.SANDIN * * * | | THE SOURCE OF THE RCS LEAKAGE HAS BEEN IDENTIFIED AS THE 1/2 INCH | | "2-RC-8003C" VALVE LEAK OFF LINE FROM RC LOOP "2C" BYPASS LINE. OPERATORS | | CLOSED THE BREAKER FOR THE MOV AND OPENED THE VALVE FROM THE CONTROL BOARD. | | INSIDE CONTAINMENT, THE VALVE WAS MANUALLY BACKSEATED WHICH ISOLATED THE | | RCS LEAK. THIS WAS CONFIRMED BY AN INCREASING PRESSURIZER LEVEL. PRT | | PRESSURE WAS MAINTAINED BETWEEN 30 AND 50 PSIG (RUPTURE DISK RELIEVES AT | | 100 PSIG) DURING THIS EVENT. MAINTENANCE IS CURRENTLY EVALUATING WHETHER | | REPAIRS CAN BE PERFORMED IN THE CURRENT MODE. THE LICENSEE ANTICIPATES | | TERMINATING THE UNUSUAL EVENT SHORTLY. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. NOTIFIED R3D0(MADERA) AND EO(CALVO). | | | | * * * UPDATE 2234EDT 5/26/94 FROM YURKOVICH TO S.SANDIN * * * | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 2058CDT BASED UPON THE RCS | | LEAK BEING ISOLATED AND THE PLANT STABILIZED. A MEETING IS IN PROGRESS TO | | DETERMINE IF THE UNIT WILL REMAIN IN MODE 3 FOR REPAIRS. THE LICENSEE | | INFORMED OUTSIDE STATE AGENCIES AND THE NRC RESIDENT INSPECTOR. NOTIFIED | | R3DO(MADERA), EO(CALVO) AND FEMA(WITSBERGER). | | | | HOONOTE: BRAIDWOOD HAS IMPLEMENTED THE NUMARC EALs EFFECTIVE DEC 1993 WHICH | | DOES NOT RECOMMEND AN ALERT DECLARATION AT 50 GPM RCS LEAKAGE (NUREG-0654). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27307 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 05/26/94 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 22:32 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 05/26/94 | +------------------------------------------------+EVENT TIME: 21:33[EDT]| |NRC NOTIFIED BY: MORRISON |LAST UPDATE DATE: 05/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THE SPENT FUEL PIT CRANE WAS STORED IN A POSITION | | CONTRARY TO THE FSAR. | | | | "UNLOADED SPENT FUEL CRANE WAS MOVED FROM ITS NORMAL STORAGE POSITION TO | | ANOTHER AREA TO ALLOW SCAFFOLDING TO BE BUILT AROUND IT FOR PAINTING. THIS | | MOVE OCCURRED ON MARCH 24, 1994. THE POSITION IT WAS MOVED TO IS OVER THE | | SPENT FUEL PIT. TODAY, AS A SUBSEQUENT REVIEW OF THE POSITION, IT WAS NOTED | | THAT THE FSAR STATES THAT THE NORMAL PARKED POSITION OF THE CRANE SHALL NOT | | BE OVER THE SPENT FUEL PIT. THIS IS A CONDITION CURRENTLY CONSIDERED | | OUTSIDE THE DESIGN BASIS. WE ARE CONTINUING TO REVIEW THE DESIGN BASIS AND | | FOLLOWUP INFORMATION WILL BE FORTHCOMING. IMMEDIATE ACTIONS HAVE STARTED TO | | REMOVE THE SCAFFOLDING TO ALLOW THE RETURN OF THE SPENT FUEL PIT CRANE TO | | ITS NORMAL POSITION (NOT OVER THE SPENT FUEL PIT)." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 05/26/94 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ 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 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. | +------------------------------------------------------------------------------+