U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/26/94 - 10/27/94 ** EVENT NUMBERS ** 27940 27949 27950 27951 27952 27953 27954 27955 27956 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27940 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/23/94 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 19:45 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/23/94 | +------------------------------------------------+EVENT TIME: 19:15[EDT]| |NRC NOTIFIED BY: HARMON |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRISTENSEN 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 +------------------------------------------------------------------------------+ | POTENTIAL FOR EXCESSIVE BYPASS OF WATER FROM CONTAINMENT SUMP TO AUXILIARY | | BUILDING UNDER ACCIDENT CONDITIONS. | | | | PLANT TESTING AND AN ENGINEERING EVALUATION PERFORMED BY THE LICENSEE HAVE | | DETERMINED THAT EXCESSIVE CONTAINMENT SUMP INVENTORY LOSS TO THE AUXILIARY | | BUILDING COULD OCCUR DURING CERTAIN ACCIDENT CONDITIONS. SPECIFICALLY, A | | 1 1/2" RELIEF VALVE IN A LOW-PRESSURE PORTION OF PIPING FOR THE [EMERGENCY | | CORE COOLING SYSTEM] COULD LIFT DUE TO OVER PRESSURIZATION DURING | | POSTULATED ACCIDENT CONDITIONS. SPECIFICALLY, IF ONE OF TWO [CONTAINMENT | | SPRAY] PUMPS DID NOT START DURING AN ACCIDENT, THE SUCTION PIPING, | | INCLUDING THE NaOH ADDITION SUBSYSTEM, FOR THAT TRAIN WOULD BECOME | | PRESSURIZED DUE TO REACTOR COOLANT SYSTEM AND CONTAINMENT BACK PRESSURE, | | CAUSING THE RELIEF VALVE ON THE [ECCS SUCTION HEADER] FOR THAT TRAIN TO TO | | LIFT. THE RELIEF VALVES (ONE PER TRAIN) FOR THE [ECCS SUCTION HEADER] ARE | | LOCATED IN PENETRATION ROOMS IN THE PLANT AUXILIARY BUILDING. | | | | THE LICENSEE HAS ISOLATED [ONE] OF THE NaOH ADDITION SUBSYSTEMS, AND HAS | | ENTERED 72 HOUR TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION | | 3.6.2.2 DUE TO THE INOPERABILITY OF THE NaOH ADDITION SUBSYSTEM. THE | | LICENSEE IS INVESTIGATING SEVERAL OPTIONS, INCLUDING GAGGING THE RELIEF | | VALVES OR DEVELOPING INSTRUCTIONS TO CLOSE THE ISOLATION VALVES FOR THE | | NaOH ADDITION SUBSYSTEM ON AN IDLE ECCS TRAIN DURING AN ACCIDENT. THE RI | | HAS BEEN INFORMED. | | | | *** UPDATE 1406 10/24/94 FROM CHALOT BY STRANSKY *** | | | | THE LICENSEE CORRECTED THE TEXT OF THE ABOVE EVENT DESCRIPTION. CHANGES TO | | THE EVENT DESCRIPTION HAVE BEEN DENOTED BY THE USE OF [ ]. RI INFORMED. | | INFORMED | | | | *** UPDATE AT 0923 ON 10/26/93 FROM SNYDER TO HUFFMAN *** | | RECENTLY, THE LICENSEE ENTERED A 72 HOUR LCO WHEN THE NaOH ADDITION | | SUBSYSTEM (FOR IODINE REMOVAL) WAS PARTIALLY DISABLED TO PREVENT A | | POTENTIAL CONTAINMENT BYPASS MECHANISM. IT WAS DETERMINED THAT WITH ONE | | TRAIN OF CONTAINMENT SPRAY (CS) OPERATING AND THE OTHER CS TRAIN SHUTDOWN, | | THE SHUTDOWN ECCS SUCTION HEADER COULD BE PRESSURIZED VIA RECIRCULATION | | PIPING FROM THE RUNNING CS TRAIN THROUGH CROSS CONNECT PIPING IN THE NaOH | | ADDITION SUBSYSTEM TO THE SUCTION SIDE OF THE SHUTDOWN CS TRAIN. IF | | CONTAINMENT SUMP LEVELS AND PRESSURES ARE SUFFICIENTLY HIGH, THE ECCS | | SUCTION HEADER ON THE SHUTDOWN TRAIN COULD BE OVER PRESSURIZED AND LIFT A | | SAFETY RELIEF VALVE RESULTING IN CONTAINMENT COOLANT INVENTORY BEING | | BYPASSED INTO THE AUX BUILDING. | | | | AT 0543 TODAY, THE PARTIALLY DISABLED NaOH ADDITION SUBSYSTEM WAS RESTORED | | TO SERVICE AND THE ECCS SUCTION HEADER SAFETY RELIEF VALVES GAGGED. THIS | | ALLOWED THE LICENSEE TO EXIT THE 72 HOUR LCO DISCUSSED ABOVE. LICENSEE | | ENGINEERING STAFF PERFORMED A 10CFR50.59 SAFETY EVALUATION WHICH CONCLUDED | | THAT IT WOULD BE ACCEPTABLE TO DISABLE THE ECCS SUCTION HEADER RELIEF | | VALVES. THIS WOULD ELIMINATE THE POTENTIAL CONTAINMENT BYPASS ROUTE. | | | | FURTHER EVALUATION OF ALTERNATE LONG TERM SOLUTIONS WILL BE CONSIDERED | | DURING THE UPCOMING REFUELING OUTAGE. R2DO(LANDIS) INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27949 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 10/26/94 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 04:30 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 01:26[CDT]| |NRC NOTIFIED BY: STEVE KUCZYNSKI |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |L. ROBERT GREGER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A N 0 REFUELING | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT SCRAM SIGNAL DURING SURVEILLANCE TESTING. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE REPORTING THIS EVENT: | | "AT 01:26 WITH UNIT 3 IN THE REFUEL MODE, A FULL REACTOR SCRAM SIGNAL WAS | | RECEIVED ON LOW REACTOR WATER LEVEL. THIS IN TURN RESULTED IN GROUP II AND | | GROUP III ISOLATION SIGNALS WITH REACTOR BUILDING VENTILATION ISOLATION AND | | THE START OF THE STANDBY GAS TREATMENT SYSTEM. | | | | THE INSTRUMENT MAINTENANCE DEPARTMENT WAS PERFORMING A SURVEILLANCE ON | | REACTOR HIGH PRESSURE SWITCHES AT THE TIME OF THE FULL SCRAM. THE REACTOR | | HIGH PRESSURE SCRAM SWITCHES ARE LOCATED IN CLOSE PROXIMITY TO THE REACTOR | | LOW LEVEL SCRAM AND ISOLATION SWITCHES. ROOT CAUSE DETERMINATION IS IN | | PROGRESS. | | | | ALL SYSTEMS RESPONDED AS EXPECTED AS A RESULT OF THE FULL SCRAM SIGNAL. | | ACTUAL WATER LEVEL DID NOT DECREASE DURING THIS EVENT." | | | | THE LICENSEE STATED THAT SHUTDOWN COOLING WAS ISOLATED FOR APPROXIMATELY 14 | | MINUTES WITH NO DETECTABLE INCREASE IN WATER TEMPERATURE WHEN IT WAS | | RESTORED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27950 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 10/26/94 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 13:55 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 10:49[CDT]| |NRC NOTIFIED BY: BISTODEAU |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |L. ROBERT GREGER 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 +------------------------------------------------------------------------------+ | DURING THE MEASUREMENT OF HPCI VIBRATION LEVELS PER A SURVEILLANCE, THE | | AUTOMATIC HPCI SUCTION SWAPOVER ON +2" TORUS LEVEL OCCURRED. | | | | HPCI WAS BEING OPERATED FOR A SURVEILLANCE TO MEASURE VIBRATION LEVELS. A | | PROBLEM WITH A TACHOMETER RESULTED IN HPCI BEING RUN FOR LONGER THAN IS | | NORMALLY EXPECTED FOR THIS PARTICULAR SURVEILLANCE. THE TEST LINEUP DRAWS | | A SUCTION FROM THE CONDENSATE STORAGE TANK (CST), AND DISCHARGES BACK TO | | THE CST. THE STEAM EXHAUST FOR THE HPCI TURBINE IS DIRECTED TO THE TORUS, | | WHICH CAUSED AN INCREASE IN BOTH TORUS TEMPERATURE AND LEVEL DURING THE | | TEST. | | | | AN OPERATOR HAD ALREADY CUT IN ANOTHER LOOP OF RHR TORUS COOLING (ONE LOOP | | WAS ALREADY IN SERVICE) AND WAS INITIATING THE PROCESS OF TORUS LEVEL | | REDUCTION BY CLOSING A BREAKER AND OPENING THE DRAIN VALVE TO RAD-WASTE, | | WHEN THE SWAPOVER OCCURRED. | | | | SINCE THE SUCTION VALVE LOGIC IS PART OF THE HPCI SYSTEM, THIS EVENT IS | | BEING REPORTED AS AN ESF ACTUATION. THE LICENSEE WILL INFORM THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27951 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/26/94 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 11:00[CDT]| |NRC NOTIFIED BY: RINZEL |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |L. ROBERT GREGER 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 +------------------------------------------------------------------------------+ | PROBLEM WITH THE CALIBRATED RANGES OF THE T-hot AND T-cold RTD's FOUND. | | | | DURING ACCIDENT ANALYSIS EVALUATIONS THAT WESTINGHOUSE IS PERFORMING IN | | SUPPORT OF THE POTENTIAL UNIT 2 REACTOR COOLANT SYSTEM FLOW RATE CHANGES | | (DUE TO STEAM GENERATOR TUBE PLUGGING), A SEPARATE PROBLEM WAS DISCOVERED. | | THE PROBLEM RELATES TO THE OVER-POWER DELTA T (OPdT) SETPOINTS. THE | | CURRENT CALIBRATED RANGES OF THE T-hot AND T-cold RTD's ARE NOT WHAT IS | | ASSUMED IN THE ACCIDENT ANALYSIS. THE RESULT IS THE OPdT FUNCTION DOES NOT | | PROVIDE ADEQUATE PROTECTION UNDER A SLOW REACTIVITY ADDITION (ROD | | WITHDRAWAL) TRANSIENT INITIATED FROM ABOUT 10% POWER TO A POWER LEVEL OF | | ABOUT 90%. THE CONDITION IS MOST LIMITING AT BEGINNING OF LIFE. | | | | THE CONDITION APPLIES TO BOTH UNITS, HOWEVER, UNIT 2 IS IN A REFUELING | | OUTAGE AT THIS TIME. UNIT 1 IS CURRENTLY AT 100% POWER, AND THEREFORE | | COMPLETE PROTECTION IS IN PLACE AT THAT POWER LEVEL. THE LICENSEE STAFF IS | | PURSUING A JUSTIFICATION FOR CONTINUED OPERATION AND FURTHER DETAILED | | EVALUATIONS WITH WESTINGHOUSE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27952 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT SAINT VRAIN REGION: 4 |NOTIFICATION DATE: 10/26/94 | |UNIT: [1] [ ] [ ] STATE: CO |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] GA (GENERAL ATOMIC) |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 12:50[MDT]| |NRC NOTIFIED BY: HAK |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE COLORADO STATE DEPARTMENT OF HEALTH THAT THE 9.0 pH | | LEVEL OF LIQUID WASTE DISCHARGED TO THE PLANT'S FARM POND WAS IN VIOLATION | | OF THE STATE EPA pH LIMIT OF 9.5. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27953 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/26/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:07 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 14:10[CDT]| |NRC NOTIFIED BY: TANDERUP |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOSS OF ONSITE ANNOUNCING SYSTEM FOR UNKNOWN REASONS - | | | | AT 1410 (CDT), A MAJOR PORTION OF THE PLANT'S ONSITE ANNOUNCING SYSTEM | | WAS LOST FOR UNKNOWN REASONS. | | | | AT 1412 (CDT), THE SYSTEM WAS RESTORED TO SERVICE BY TRANSFERRING THE | | SYSTEM TO ITS ALTERNATE POWER SUPPLY. | | | | AT 1417 (CDT), THE SYSTEM WAS LOST AGAIN. | | | | LICENSEE IS INVESTIGATING THE CAUSE AND WILL MAKE REPAIRS AS NECESSARY. | | | | THIS LOSS OF ONSITE COMMUNICATIONS AFFECTS THE LICENSEE'S ACCOUNTABILITY | | SYSTEM FOR THEIR EMERGENCY PLAN. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2110 BY SMALLFOOT ENTERED BY HOO JOLLIFFE * * * | | | | LICENSEE REPLACED 2 BLOWN POWER SUPPLY ELECTRICAL FUSES AND AT 1623 (CDT) | | RESTORED THE SYSTEM TO SERVICE. LICENSEE IS CONTINUING TO INVESTIGATE THE | | CAUSE OF THE BLOWN FUSES. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R4DO COLLINS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27954 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/26/94 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 17:33 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 14:26[EDT]| |NRC NOTIFIED BY: HURCHALLA |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |JOHN ZWOLINSKI EO | |ANLI 50.72(b)(1)(iii) LIGHTNING | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - Rx TRIP DUE TO MAIN TURBINE TRIP DUE TO LIGHTNING STRIKING TRANSFORMER - | | | | AT 1426, UNIT 1 AUTO TRIPPED FROM 100% POWER DUE TO THE MAIN TURBINE | | TRIPPING DUE TO A MAIN GENERATOR LOCKOUT CAUSED BY LIGHTNING STRIKING | | A SINGLE PHASE TRANSFORMER IN BAY #1 OF THE SWITCHYARD OUTSIDE THE | | PLANT PROTECTED AREA. | | | | SWITCHYARD BAY #1 SUPPORTS POWER TRANSMISSION FROM THE UNIT 1 MAIN | | GENERATOR. THE LIGHTNING STRIKE IGNITED 10 GALLONS OF OIL ON THE SINGLE | | PHASE TRANSFORMER. LICENSEE SUMMONED OFFSITE FIRE FIGHTING SUPPORT. | | | | AS THE FIRE WAS CONTROLLED AND NOT CONSIDERED A HAZARD TO OTHER SWITCHYARD | | COMPONENTS, LICENSEE ALLOWED THE OIL TO BURN OFF RATHER THAN TO RISK DAMAGE | | DUE TO FIRE FIGHTING EFFORTS. THE FIRE LASTED LONGER THAN 10 MINUTES. | | | | ALL CONTROL RODS INSERTED COMPLETELY. THE MAIN STEAM SAFETY VALVES LIFTED | | AND IMMEDIATELY RESEATED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | | | UNIT 1 IS STABLE IN MODE 3 (HOT STANDBY). | | | | LICENSEE HAS DECIDED NOT TO RESTART UNIT 1 AT THIS TIME BUT TO BEGIN THEIR | | 40 DAY REFUELING OUTAGE INSTEAD. | | | | THIS EVENT HAD NO EFFECT ON UNIT 2 WHICH IS AT 100% POWER NOR THE | | AVAILABILITY OF OFFSITE POWER TO UNITS 1 OR 2. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27955 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/26/94 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 20:58 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 18:12[EDT]| |NRC NOTIFIED BY: HOLDAM |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SOLENOID VALVES FOR 2 PORVs NOT INCLUDED IN THE UNIT 3 EQ PROGRAM - | | | | WITH UNIT 3 IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE SINCE | | FEBRUARY 1993, LICENSEE DISCOVERED THAT THE SOLENOID VALVES FOR TWO | | POWER OPERATED RELIEF VALVES (PORVs) ARE NOT INCLUDED IN THE UNIT 3 | | ENVIRONMENTAL QUALIFICATION (EQ) PROGRAM. | | | | THIS CONDITION POTENTIALLY COULD HAVE RENDERED BOTH PORVs INOPERABLE AND | | UNABLE TO PERFORM THEIR OVER PRESSURIZATION SYSTEM PROTECTION FUNCTION | | AND COULD HAVE POTENTIALLY PLACED UNIT 3 IN A CONDITION THAT ALONE COULD | | HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF SYSTEMS (PORVs) | | NEEDED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. | | | | LICENSEE WILL INCLUDE THESE VALVES IN THE UNIT 3 EQ PROGRAM AND WILL | | REVIEW THE UNIT 3 EQ PROGRAM. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27956 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/26/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 21:05 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 16:40[EDT]| |NRC NOTIFIED BY: GAUZZA |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 7 CONTAINMENT ISOLATION VALVES NOT INCLUDED IN UNIT 2 LLRT PROGRAM - | | | | WITH UNIT 2 IN MODE 6 (REFUELING) IN A REFUELING OUTAGE SINCE 09/30/94, | | LICENSEE DISCOVERED DURING LOCAL LEAK RATE TESTING (LLRT) THAT 7 RUPTURE | | DISK OR CHECK VALVES (CONTAINMENT ISOLATION VALVES) ARE NOT INCLUDED IN | | THE UNIT 2 LLRT PROGRAM. | | | | LICENSEE WILL EVALUATE THESE VALVES FOR INCLUSION IN THE UNIT 2 LLRT | | PROGRAM. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+