U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/25/95 - 01/26/95 ** EVENT NUMBERS ** 28274 28275 28276 28277 28278 28279 28280 28281 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28274 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 01/25/95 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 13:16 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/25/95 | +------------------------------------------------+EVENT TIME: 10:43[EST]| |NRC NOTIFIED BY: HEALY |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESSURIZER OVERPRESSURE PROTECTION (POP) ACTUATED WHEN REACTOR COOLANT | | PUMP (RCP) "21" WAS SECURED. | | | | UPON SECURING THE ONLY OPERATING RCP, THE PRESSURIZER OVERPRESSURE | | PROTECTION SYSTEM ACTUATED. POP SENSED AN APPARENT PRESSURE INCREASE (OR | | SPIKE) WHEN RCP "21" WAS SECURED. REACTOR COOLANT SYSTEM TEMPERATURE WAS | | 180øF AT A PRESSURE OF 350psig WHEN THE PRESSURIZER OVERPRESSURE PROTECTION | | SYSTEM ACTUATED. THE SETPOINT FOR THE PRESSURIZER OVERPRESSURE PROTECTION | | SYSTEM (RELIEF VALVES ON PRESSURIZER OPERATED RELIEF VALVES PR-1 & PR-2) IS | | 375psig. BOTH PRESSURIZER OVERPRESSURE PROTECTION RELIEF VALVES WERE OPEN | | FOR ABOUT 20 TO 30 SECONDS. REACTOR SYSTEM PRESSURE IS BEING MAINTAINED BY | | A BUBBLE IN THE PRESSURIZER AND THE POP RELIEF VALVES ARE LOCATED IN THE | | STEAM SPACE OF THE PRESSURIZER. LICENSEE DID NOT SEE ANY CHANGE IN | | PRESSURIZER LEVEL OR ANY INCREASE IN THE PRESSURIZER RELIEF TANK (PRT) | | LEVEL. WIDE RANGE REACTOR COOLANT PRESSURE INDICATION INCREASED FROM | | 350psig TO 368psig AFTER RCP "21" WAS SECURED. THE RESIDUAL HEAT REMOVAL | | PUMP WAS OPERATING BEFORE AND AFTER RCP "21" WAS SECURED (THIS SHOULD NOT | | HAVE CAUSED RCS TO INCREASE IN PRESSURE RIGHT AFTER RCP "21" WAS SECURED). | | LICENSEE WILL PERFORM A FUNCTIONAL CHECK OF BOTH PRESSURIZER OVERPRESSURE | | PROTECTION CHANNELS TO CHECK RELIEF VALVE SETPOINTS. | | | | LICENSEE WILL NOTIFY THEIR RESIDENT INSPECTOR OF THIS EVENT. LOWER | | ALLOWAYS CREEK TOWNSHIP WAS NOTIFIED BY LICENSEE OF THIS EVENT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28275 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/25/95 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 13:21 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/20/95 | +------------------------------------------------+EVENT TIME: 10:30[CST]| |NRC NOTIFIED BY: M RINZEL |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFIED GOVERNMENT AGENCY (WISCONSIN DEPARTMENT OF NATURAL RESOURCES) OF | | EXCEEDING POLLUTION LIMITS. | | | | THE LICENSEE NOTIFIED THE WISCONSIN DEPARTMENT OF NATURAL RESOURCES THAT | | THEY HAD EXCEEDED THE WISCONSIN POLLUTION DISCHARGE ELIMINATION SYSTEM | | (WPDES) LIMIT OF 100ppm MAXIMUM DAILY TOTAL SUSPENDED SOLIDS FOR THE | | RETENTION POND. A TWENTY FOUR HOUR COMPOSITE SAMPLE SHOWED THAT TOTAL | | SUSPENDED SOLIDS WAS 126ppm. THE LICENSEE CLEANED THE SAMPLER | | (CONTINUOUSLY SAMPLES THE RETENTION POND) AND ALL SAMPLES TAKEN SINCE THEN | | HAVE BEEN WITHIN THE SPECIFICATION LIMIT OF 100ppm. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28276 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 01/25/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/25/95 | +------------------------------------------------+EVENT TIME: 01:00[EST]| |NRC NOTIFIED BY: MIKE QUINN |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO 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 +------------------------------------------------------------------------------+ | BALL FLOAT VALVE DID NOT PREVENT WATER FROM ENTERING EMERGENCY DIESEL | | GENERATOR (EDG) ROOM "A" WHEN SERVICE WATER CAUSED EDG "B" ROOM WATER LEVEL | | TO INCREASE TO 1 - 1.5". | | | | AFTER COMPLETING PLANNED PREVENTIVE MAINTENANCE ON EDG "B", A RESTORATION | | ERROR (PERSONNEL/PROCEDURAL) CAUSED APPROXIMATELY 200 GALLONS OF SERVICE | | WATER TO BE SPRAYED ON TOP OF EDG "B" AND OTHER ELECTRICAL EQUIPMENT IN THE | | ROOM BEFORE THE SERVICE WATER COULD BE SECURED. DRAIN LINE IN EDG "B" ROOM | | AND EDG "A" ROOM FLOW INTO A COMMON DISCHARGE HEADER. THE HEADER HAS A | | MANUAL ISOLATION VALVE WHICH IS CLOSED AT ALL TIMES IN ORDER TO PREVENT | | DISCHARGING DIESEL OIL FROM THE EDG ROOMS TO THE RIVER AND TO PREVENT RIVER | | FLOOD WATERS FROM BACKING UP INTO THE EDG ROOMS. THE DRAIN LINES IN EDG | | "A" ROOM AND EDG "B" ROOM EACH HAVE A BALL FLOAT TO PREVENT WATER FROM | | ENTERING THE ROOMS. ONE OR TWO MINUTES AFTER OPENING THE SERVICE WATER | | VALVE A FINAL CHECK OF EDG "B" ROOM WAS MADE AT WHICH TIME THE SERVICE | | WATER SPRAYING ON TOP OF EDG "B" WAS DISCOVERED. SERVICE WATER WAS SECURED | | WITHIN TWO MINUTES AFTER DISCOVERING IT SPRAYING ON TOP OF EDG "B". | | MAXIMUM WATER LEVEL IN THE EDG "B" ROOM WAS BETWEEN 1" TO 1.5" IN DEPTH. | | WHEN THE LICENSEE ENTERED EDG "A" ROOM THEY FOUND WATER COMING INTO THE | | ROOM THROUGH ITS FLOOR DRAIN. THE BALL FLOAT IN THE DRAIN LINE SHOULD HAVE | | PREVENTED WATER FROM ENTERING EDG "A" ROOM (NOT MUCH WATER CAME INTO THE | | ROOM). LICENSEE IS INVESTIGATING THIS PROBLEM. THE COMMON HEADER MANUAL | | DRAIN ISOLATION VALVE WAS OPENED AND EDG "B" ROOM WAS DRAINED. ALL | | EQUIPMENT IN EDG "B" ROOM HAS BEEN DRIED AND ELECTRICAL EQUIPMENT WHICH GOT | | WET IN EDG "B" HAVE BEEN MEGGERED (ELECTRIC MOTOR, OUTPUT LINES FROM THE | | EDG, etc.). THE LICENSEE SAID THAT EDG "B" SHOULD BE RESTORED TO SERVICE | | LATER THIS AFTERNOON. THE LICENSEE SAID THAT EDG "B" HAS BEEN IN TECH SPEC | | 3.8.1.1 (72 HOUR LCO ACTION STATEMENT) SINCE 0345EST 01/24/95. EDG "A" IS | | FULLY OPERABLE. LICENSEE SAID THAT THE SPRAYING DOWN OF EDG "B" WAS NOT A | | REPORTABLE EVENT. LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS | | EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28277 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/25/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/25/95 | +------------------------------------------------+EVENT TIME: 14:20[CST]| |NRC NOTIFIED BY: M BERRENS |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY YANDELL RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BORAFLEX NEUTRON ABSORBING PANEL IN SPENT FUEL POOL REGION 1 STORAGE RACKS | | EXCEEDS ITS ASSUMED DESIGN BASIS ANALYSIS. | | | | LICENSEE COMPLETED REPORTABILITY REVIEW AT 1420CST TODAY OF A TEST | | CONDUCTED IN AUGUST OF 1994 AND DETERMINED THAT A CONDITION EXISTS IN THEIR | | SPENT FUEL POOL REGION 1 (HIGHER ACTIVATED SPENT FUEL IS STORED IN THIS | | REGION) STORAGE RACKS. BLACKNESS TESTING (A NEUTRON SOURCE IS PLACED IN A | | CERTAIN AREA OF THE SPENT FUEL POOL TO DETERMINE BORON CONCENTRATION) OF | | THE SPENT FUEL POOL WAS CONDUCTED IN AUGUST 1994 (UNIT 2 SPENT FUEL RACKS | | WERE NOT TESTED). BASED ON PRELIMINARY RESULTS OF THIS TEST, THERE EXISTS | | DEGRADATION OF THE BORAFLEX NEUTRON ABSORBING PANEL (PANEL BOLTED BETWEEN | | FUEL RACKS MADE OUT OF NEUTRON ABSORBING MATERIAL) WHICH EXCEEDS THAT | | ASSUMED IN THE DESIGN BASIS ANALYSIS. THIS DEGRADATION EXISTS IN AT LEAST | | ONE STORAGE CELL (HOLDS ONE FUEL ASSEMBLY) IN THE REGION 1 RACK. | | A JUSTIFICATION FOR CONTINUED OPERATION HAS BEEN IN PLACE SINCE AUGUST 1994 | | BASED UPON THE LICENSEE MAINTAINING THE SPENT FUEL POOL WATERBORNE BORON | | CONCENTRATION ò 2500ppm. THIS LEVEL WAS CHOSEN TO BOUND A COMPLETE LOSS OF | | BORAFLEX IN THE RACKS PLUS THE ACCIDENT CONDITION ASSUMED IN THE DESIGN | | BASIS. RESULTS OF THE UNIT 1 EVALUATION WILL BE USED TO SEE WHAT | | CORRECTIVE ACTIONS (IF ANY) NEED TO BE TAKEN ON UNIT 2 SPENT FUEL POOL | | BORAFLEX PANELS. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR INTERNATIONAL CORP. |NOTIFICATION DATE: 01/25/95 | | CITY: SOUTHFIELD REGION: 3 |NOTIFICATION TIME: 17:01 [ET]| | COUNTY: STATE: MI |EVENT DATE: 01/25/95 | |LICENSE#: 21-17189-01MD AGREEMENT: N |EVENT TIME: 15:25[EST]| | DOCKET: |LAST UPDATE DATE: 01/25/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | |BOB PIERSON EO | +------------------------------------------------+ | |NRC NOTIFIED BY: D PELLICCIARINI | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBE 30.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST POWER TO FUME HOODS FOR APPROXIMATELY ONE HOUR. | | | | LICENSEE HAD A PARTIAL POWER OUTAGE AT THEIR SYNCOR INTERNATIONAL | | CORPORATION OFFICE LOCATED AT 21681 MELROSE AVE., SOUTHFIELD, MI. THIS | | PARTIAL OUTAGE CAUSED POWER TO BE LOST TO A FUME HOOD FOR APPROXIMATELY ONE | | HOUR. LICENSEE IS REQUIRED PER THEIR LICENSE TO HAVE FUME HOODS POWERED AT | | ALL TIMES TO PREVENT AIRBORNE CONTAMINATION INSIDE THEIR FACILITY. AT THE | | TIME OF THE POWER OUTAGE LICENSEE HAD 107 mCi OF XENON-133 AND 635.5 mCi OF | | IODINE-131 UNDER THE FUME HOOD. A NEARBY AIRBORNE SAMPLER NEVER LOST POWER | | AND AIRBORNE CONCENTRATION WAS 3.6E-12æCi/ml DURING THE POWER OUTAGE. | | CALLER CALLED FROM SYNCOR INTERNATIONAL CORP. HEADQUARTERS LOCATED AT 20001 | | PRAIRIE ST., CHATSWORTH, CA. | | | | REGION 3 WAS NOTIFIED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28279 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 01/25/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:41 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/25/95 | +------------------------------------------------+EVENT TIME: 18:27[EST]| |NRC NOTIFIED BY: MIKE QUINN |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH ENERGY LINE BREAK BARRIER VIOLATED | | | | IN OCTOBER 1994 A HEATER, USED TO HEAT CONTROL ROOM AIR, WAS REMOVED FROM | | VENTILATING DUCTING, LEAVING A HOLE ONE FOOT IN WIDTH AND 2.5 FEET IN | | HEIGHT BETWEEN THE CONTROL ROOM (CR) AND CONTROL ROOM VENTILATION FAN ROOM | | (CRVFR). AN OPERATOR, AFTER READING ABOUT HIGH ENERGY LINE BARRIER | | REQUIREMENTS, DISCOVERED THIS HOLE ON 01/24/95 AT 1230 EST. SHEET METAL | | WAS FABRICATED AND INSTALLED OVER THE HOLE BY 1650EST ON 01/24/95. | | | | DURING THE TIME PERIOD FROM 10/94 UNTIL 01/25/95 AT 1650 EST LICENSEE SAID | | THAT THEY HAD VIOLATED THE HIGH ENERGY LINE BREAK BARRIER CRITERIA BECAUSE | | IF A STEAM LINE RUPTURE HAD OCCURRED IN THE TURBINE HALL, THE STEAM MIGHT | | HAVE ENTERED THE CR (MAKING CR UNINHABITABLE). THE STEAM WOULD HAVE TO | | TRAVEL BETWEEN 50 FEET AND 60 FEET TO GET TO THE CRVFR THEN ENTER THE CR | | VIA THE HOLE. THE STEAM WOULD HAVE TO GO FROM THE TURBINE HALL THROUGH 2 | | DOUBLE DOORS (DOORS NOT TAKEN INTO ACCOUNT IN THEIR ACCIDENT ANALYSIS FOR A | | HIGH ENERGY LINE BREAK), DOWN A HALLWAY, THEN THROUGH 2 MORE DOUBLE DOORS | | (THESE DOORS ARE NOT TAKEN INTO ACCOUNT IN THEIR ACCIDENT ANALYSIS FOR A | | HIGH ENERGY LINE BREAK) TO GET INTO CRVFR. THEN THE STEAM WOULD ENTER THE | | CR VIA THE HOLE. THESE DOUBLE DOORS ARE CLOSED AT ALL TIMES DURING POWER | | OPERATION. LICENSEE IS WAITING FOR THE HEATING FAN TO BE REINSTALLED. | | LICENSEE NOTIFIED STATE AND LOCAL AUTHORITIES OF THIS EVENT. THE NRC | | RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/25/95 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 22:09 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/25/95 | +------------------------------------------------+EVENT TIME: 17:21[CST]| |NRC NOTIFIED BY: G TURNER,jr. |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM DECLARED INOPERABLE WHEN RCIC | | STEAM SUPPLY INBOARD ISOLATION VALVE ISOLATED DURING SURVEILLANCE TESTING. | | | | DURING PERFORMANCE OF SURVEILLANCE STP-207-5253 (RCIC/RHR SYSTEM ISOLATION, | | RHR EQUIPMENT AREA AMBIENT TEMPERATURE HIGH CHANNEL CALIBRATION, LOGIC | | SYSTEM FUNCTIONAL TESTING) A SPURIOUS SIGNAL CAUSED CLOSURE OF E51-MOV-F063 | | (RCIC STEAM SUPPLY INBOARD ISOLATION VALVE) AND A RCIC SYSTEM ISOLATION. | | THE LICENSEE DECLARED RCIC INOPERABLE AND ENTERED TECH SPEC 3.3.2 | | (INSTRUMENTATION) & TECH SPEC 3.7.3 (HAVE 14 DAYS TO RESTORE RCIC TO | | SERVICE). LICENSEE IS INVESTIGATING THIS EVENT. | | | | THE SURVEILLANCE TEST PROCEDURE WAS COMPLETED WITHOUT ANY FURTHER PROBLEMS | | AND AT 2133 CST, RCIC WAS DECLARED OPERABLE AND RETURNED TO ITS NORMAL | | STANDBY STATUS. THE LICENSEE COULD NOT FIND OUT WHAT CAUSED THE SPURIOUS | | ISOLATION SIGNAL. DURING THE TIME PERIOD RCIC WAS DECLARED INOPERABLE, ALL | | EMERGENCY CORE COOLING SYSTEMS (HPCS, LPCS AND LPCI) WERE FULLY OPERABLE. | | | | RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/25/95 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 23:38 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/25/95 | +------------------------------------------------+EVENT TIME: 22:20[CST]| |NRC NOTIFIED BY: THOMAS OSELAND |LAST UPDATE DATE: 01/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRAVERSING INCORE PROBES (TIPs) PURGE AND BALL VALVE WILL REOPEN IF A GROUP | | II ISOLATION SIGNAL IS RESET WITH THE TIP CONTROL SWITCHES IN THE OPEN | | POSITION. | | | | | | UNIT 1 & 2 TIP PURGE AND BALL VALVES WILL REOPEN IF A GROUP II (TIP, RHR IF | | RUNNING, & PRIMARY CONTAINMENT ISOLATION) ISOLATION SIGNAL IS RESET WITH | | THE TIP CONTROL SWITCH IN THE OPEN POSITION. THE GROUP II ISOLATION SIGNAL | | INITIATORS ARE LOW REACTOR VESSEL WATER LEVEL OR HIGH DRYWELL PRESSURE. THE | | QUAD CITIES UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) SECTION 7.3.2.2 | | STATES THAT "GROUP I (MAIN STEAM ISOLATION VALVE ISOLATION), GROUP II, | | GROUP III (REACTOR WATER CLEANUP ISOLATION), & GROUP IV (HIGH PRESSURE CORE | | INJECTION ISOLATION) VALVES, AS DESCRIBED IN TABLE 6.2-7 WILL NOT | | AUTOMATICALLY OPEN WHEN THE ISOLATION IS RESET." THE LICENSEE HAS | | DETERMINED THAT THE EXISTING CONDITION IS OUTSIDE THE PLANT DESIGN BASIS AS | | DESCRIBED IN UFSAR 7.3.2.2. AN INVESTIGATION IS CONTINUING TO SEE IF ANY | | OTHER GROUP I, GROUP II, GROUP III, OR GROUP IV VALVES ARE AFFECTED. TIPs | | ARE NORMALLY OUT OF SERVICE WITH THEIR CONTROL SWITCHES IN THE CLOSED | | POSITION. TIPs CAN STILL BE USED. LICENSEE IS STILL INVESTIGATING THIS | | EVENT. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+