U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/30/97 - 05/01/97 ** EVENT NUMBERS ** 31879 32243 32244 32245 32246 32247 32248 32249 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31879 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ENERTECH |NOTIFICATION DATE: 03/03/97 | | CITY: BREA REGION: 4 |NOTIFICATION TIME: 16:45 [ET]| | COUNTY: STATE: CA |EVENT DATE: 03/03/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PST]| | DOCKET: |LAST UPDATE DATE: 04/30/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE, RVIB NRR | |NRC NOTIFIED BY: JOHN DEKLEINE | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION REGARDING HIGH FAILURE RATES OF BW/IP (FORMERLY | | BORG-WARNER) PRESSURE SWITCHES INSTALLED ON BW/IP ELECTRO-HYDRAULIC | | ACTUATORS USED IN THE GAS TREATMENT, SERVICE WATER, AND HEATING AND | | VENTILATION SYSTEMS AT NINE MILE POINT UNIT 2 (REFER TO EVENT #31822 FOR | | ADDITIONAL INFORMATION.) | | | | ON FEBRUARY 20, 1997, NINE MILE POINT UNIT 2 MADE A NOTIFICATION TO THE NRC | | REGARDING THE EXISTENCE OF A DEVIATION OR NON-CONFORMANCE CONDITION IN A | | BASIC COMPONENT THAT WAS REPORTABLE UNDER 10 CFR PART 21 GUIDELINES. THE | | BASIC COMPONENT WAS IDENTIFIED AS A SAFETY-RELATED PRESSURE SWITCH SUPPLIED | | BY BW/IP THAT MAY BE IN ONE OF FIVE PART NUMBERS, AND THE REPORT CITED A | | HIGH FAILURE RATE OF THESE PRESSURE SWITCHES. | | | | ENERTECH AND BW/IP ARE CURRENTLY INVESTIGATING THIS ISSUE. ENERTECH IS | | ALERTING ALL POTENTIALLY AFFECTED CUSTOMERS OF A REPORTED SAFETY-RELATED | | BASIC COMPONENT THAT IS CURRENTLY BEING INVESTIGATED BY NINE MILE POINT | | UNIT 2 UNDER 10 CFR PART 21 GUIDELINES. SINCE ENERTECH WAS NOT PART OF THE | | NINE MILE POINT EVALUATION PROCESS, ENERTECH HAS ALSO REQUESTED HARDWARE | | AND DOCUMENTATION FROM NINE MILE POINT PERSONNEL FOR BW/IP EVALUATION OF | | THE STATED SITUATION. ADDITIONALLY, ENERTECH REQUESTED FEEDBACK FROM | | POTENTIALLY AFFECTED CUSTOMERS. | | | | (REFER TO THE HOO LOG FOR CONTACT NAMES AND TELEPHONE NUMBERS.) | | | | * * * 1934 APRIL 30, 1997, UPDATE FROM DEKLEINE RECEIVED BY TROCINE * * * | | | | A FACSIMILE RECEIVED FROM ENERTECH REPORTED THAT ALL KNOWN USERS OF THE | | PRESSURE SWITCHES IN QUESTION HAD BEEN NOTIFIED AND THAT A MORE ADVANCED | | PRESSURE SWITCH HAD BEEN SUGGESTED TO THE AFFECTED NUCLEAR POWER | | FACILITIES. THE FACSIMILE ALSO STATED THAT ENERTECH WAS WAITING FOR | | ADDITIONAL INFORMATION FROM NINE MILE POINT UNIT 2 BEFORE ADDITIONAL ACTION | | OR STATUS FROM ENERTECH COULD/WOULD OCCUR. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (DOLCE) AND NRR RVIB (HODGE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32243 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/30/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 04:36 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 02:30[EDT]| |NRC NOTIFIED BY: COLEMAN |LAST UPDATE DATE: 04/30/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE. | | | | THE LICENSEE HAS DECLARED THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM | | INOPERABLE DUE TO AN INTERMITTENT GROUND ON THE ASSOCIATED DC ELECTRICAL | | BUS. AFTER PERFORMING A MONTHLY SURVEILLANCE TEST ON THE HPCI SYSTEM, A | | GROUND OCCURRED ON THE 'B' STATION SERVICE BATTERY BUS WHEN THE HPCI | | AUXILIARY OIL PUMP WAS STOPPED. THE BREAKER FOR THE PUMP WAS OPENED, AND | | THE GROUND CLEARED. HOWEVER, MAINTENANCE TECHNICIANS WERE UNABLE TO FIND | | ANY PROBLEM WITH THE PUMP MOTOR, AND WHEN THE BREAKER WAS RECLOSED, THE | | GROUND DID NOT RECUR. THE LICENSEE THEN REPEATED THE HPCI SURVEILLANCE, AND | | THE GROUND AGAIN OCCURRED WHEN THE AUXILIARY OIL PUMP WAS STOPPED. THE | | LICENSEE IS CONTINUING TO INVESTIGATE THE PROBLEM. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 04/30/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 07:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 05:24[EDT]| |NRC NOTIFIED BY: KEN DOVER |LAST UPDATE DATE: 04/30/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING AN EVOLUTION, THE STEAM DUMPS ISOLATED DUE TO LOW REACTOR COOLANT | | SYSTEM TEMPERATURE. | | | | WHILE DRAINING MOISTURE FROM THE 2B FEEDWATER PUMP TURBINE, STEAM PRESSURE | | AND REACTOR COOLANT SYSTEM TEMPERATURE BEGAN TO DECREASE AS EXPECTED. WHEN | | THE DRAINS ON THE 2B FEEDWATER PUMP WERE RETURNED TO "AUTO," TWO OUT OF THE | | FIVE VALVES DID NOT CLOSE. THE SWITCH USED FOR THESE DRAINS IS AN | | "AUTO/CLOSE" SWITCH. DRAIN VALVES 2SP-23 AND 2SP-33 DID NOT CLOSE WHEN THE | | SWITCH WAS PLACED BACK IN "AUTO". THIS RESULTED IN REACTOR COOLANT SYSTEM | | TEMPERATURE DECREASING TO 547.6øF. REACTOR PROTECTION SYSTEM TRIP SIGNAL | | P-12 ACTUATED WHEN THE TWO-OUT-OF-FOUR LOOP LOW-LOW Tave LOGIC WAS | | SATISFIED. THE P-12 ACTUATION CAUSED THE STEAM DUMPS TO ISOLATE. | | | | THE DRAIN VALVES ON THE 2B FEEDWATER PUMP WERE MANUALLY ISOLATED, AND A | | WORK REQUEST HAS BEEN ISSUED TO INVESTIGATE/REPAIR THE PROBLEM. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32245 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/30/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:32 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 12:00[CDT]| |NRC NOTIFIED BY: DAVE THRONE |LAST UPDATE DATE: 04/30/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SIMULTANEOUS OPENING OF TORUS AND DRYWELL PURGE VALVES DURING OPERATION | | COULD HAVE BYPASSED THE PRESSURE SUPPRESSION FUNCTION OF SUPPRESSION POOL. | | | | ON 04/14/97, THE DRESDEN SITE RECEIVED A PROBLEM IDENTIFICATION FORM (PIF) | | FROM LaSALLE STATION. ONE ISSUE RAISED IN THE PIF INVOLVED THE | | SIMULTANEOUS OPENING OF TORUS AND DRYWELL PURGE VALVES, THEREBY POSSIBLY | | BYPASSING THE PRESSURE SUPPRESSION FUNCTION OF THE SUPPRESSION POOL. THE | | SHIFT MANAGER REVIEWED THE PIF FOR REPORTABILITY AND MADE THE DETERMINATION | | THAT MORE INFORMATION WAS REQUIRED. ENGINEERING AND REGULATORY ASSURANCE | | WERE REQUESTED TO ASSIST ON THE REPORTABILITY DETERMINATION. | | | | THIS UNDESIRABLE LINEUP (AND UNANALYZED CONDITION) WAS ESTABLISHED IN THE | | PAST AT DRESDEN TO EQUALIZE THE DRYWELL AND TORUS PRESSURES WHILE | | PERFORMING ROUTINE VACUUM BREAKER TESTING. SINCE IMPLEMENTATION OF THE | | UPGRADED TECHNICAL SPECIFICATIONS IN JANUARY 1997, DRESDEN HAS ESTABLISHED | | THIS LINEUP FOUR TIMES ON UNIT 2 AND THREE TIMES ON UNIT 3. CORRECTIVE | | ACTION TO PREVENT RECURRENCE OF THIS UNDESIRED VALVE LINEUP IS ALREADY IN | | PLACE. THE PRESSURE EQUALIZATION PROCESS WILL NOW BE ACCOMPLISHED UTILIZING | | THE PUMP-BACK AIR COMPRESSOR SYSTEM. THE PROCEDURES HAVE BEEN REVISED, AND | | CAUTIONS CONCERNING THE BYPASS FLOW PATH HAVE BEEN ADDED. OPERATOR | | TRAINING ON THE NEW PROCEDURES IS CURRENTLY IN PROGRESS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/30/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 16:33[CDT]| |NRC NOTIFIED BY: BILL ARENS |LAST UPDATE DATE: 04/30/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT A MALFUNCTION OF DIFFERENTIAL PRESSURE SWITCHES DUE TO | | TORNADO GENERATED MISSILES COULD INADVERTENTLY ISOLATE SERVICE WATER FLOW | | TO THE DIESEL BUILDING | | | | AN NRC INSPECTION AT FARLEY NUCLEAR PLANT QUESTIONED THE LACK OF EXTERNAL | | MISSILE DESIGN CONSIDERATIONS TO PROTECT CERTAIN COMPONENTS FROM DESIGN | | BASIS TORNADOS. AS A FOLLOWUP, SOUTHERN NUCLEAR COMPANY PERFORMED A | | WALKDOWN AT FARLEY TO IDENTIFY ADDITIONAL POTENTIAL TARGETS FOR TORNADO | | GENERATED MISSILES AND INSURE THAT THE FINAL SAFETY ANALYSIS (FSAR) | | COMMITMENT WAS MET. FSAR SECTION 3.5.4 STATES THAT CATEGORY I EQUIPMENT AND | | PIPING OUTSIDE THE CONTAINMENT ARE EITHER HOUSED IN CATEGORY I STRUCTURES | | OR BURIED UNDERGROUND. THIS EVALUATION IS CONTINUING; HOWEVER, THE WALKDOWN | | IDENTIFIED FOUR CATEGORY I SERVICE WATER DIFFERENTIAL PRESSURE SWITCHES | | LOCATED ON THE OUTSIDE OF THE DIESEL GENERATOR BUILDING THAT ARE VULNERABLE | | TO TORNADO MISSILES. THESE SWITCHES PROVIDE CLOSURE SIGNALS TO DIESEL | | GENERATOR BUILDING SERVICE WATER ISOLATION VALVES IN THE EVENT OF FLOW | | GREATER THAN 7,000 GALLONS PER MINUTE. IN THE EVENT OF A TORNADO GENERATED | | MISSILE CAUSING DAMAGE TO THESE SWITCHES, A MALFUNCTION OF THESE SWITCHES | | COULD INADVERTENTLY ISOLATE SERVICE WATER FLOW TO THE DIESEL GENERATOR | | BUILDING. THE LICENSEE HAS ATTRIBUTED THIS CONDITION TO A DESIGN ERROR. | | | | A PROBABLE RISK ASSESSMENT CALCULATION SHOWED THAT THE IMPACT FREQUENCY FOR | | THE EXPOSED SWITCHES, CONDUIT, AND TUBING CONNECTIONS IS VERY LOW (ON THE | | ORDER OF E-9 PER YEAR). THUS, THE RISK THESE FOUR SWITCHES FACE FROM A | | MISSILE HAZARD IS JUDGED TO BE INSIGNIFICANT. EACH DIESEL GENERATOR HAS | | SERVICE WATER SOURCES FROM BOTH UNITS THAT CAN BE PLACED IN SERVICE EITHER | | REMOTELY FROM THE CONTROL ROOM OR LOCALLY IN THE DIESEL GENERATOR BUILDING. | | | | THE LICENSEE PLANS TO TAG THE FOUR SERVICE WATER MOTOR OPERATED VALVES IN | | THE OPEN POSITION AND REMOVE THE ELECTRICAL POWER FROM THE OPERATORS. THE | | LICENSEE ALSO PLANS TO PLACE CAUTION TAGS IN THE CONTROL ROOM TO ALERT | | OPERATORS THAT ELECTRICAL POWER HAS BEEN REMOVED FROM THESE MOTOR OPERATED | | VALVES TO FAIL THE VALVES IN THE OPEN POSITION. IN ADDITION, THE LICENSEE | | PLANS TO ISSUE DESIGN CHANGES TO REMOVE THE DIFFERENTIAL PRESSURE SWITCHES. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32247 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/01/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 02:02 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 21:58[CDT]| |NRC NOTIFIED BY: MILLIFF |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL 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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO CLOSURE OF FEED REG VALVE. | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE UNIT FROM 100% POWER IN | | ANTICIPATION OF AN AUTOMATIC TRIP DUE TO LOW STEAM GENERATOR (SG) WATER | | LEVEL. ALL CONTROL RODS INSERTED PROPERLY FOLLOWING THE TRIP, AND ALL | | SYSTEMS FUNCTIONED AS EXPECTED. THE AUXILIARY FEEDWATER SYSTEM | | AUTOMATICALLY STARTED AND SUPPLIED WATER TO THE STEAM GENERATORS. | | | | THE LICENSEE REPORTED THAT LEVEL IN THE 'D' SG BEGAN DECREASING WHEN THE | | MAIN FEEDWATER REGULATING VALVE FOR THAT SG CLOSED FOR UNKNOWN REASONS. | | OPERATORS WERE UNABLE TO GET THE VALVE TO RESPOND TO EITHER AUTOMATIC OR | | MANUAL CONTROLS. WHEN THE WATER LEVEL IN THE 'D' SG DECREASED TO 35%, | | OPERATORS MANUALLY TRIPPED THE UNIT IN ANTICIPATION OF AN AUTOMATIC TRIP AT | | 33% LEVEL. THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FEED REG VALVE | | MALFUNCTION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32248 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 03:08[EDT]| |NRC NOTIFIED BY: GOETCHIUS |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOLCE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY INJECTION DUE TO STUCK OPEN MSSV DURING TESTING. | | | | WHILE TESTING THE MAIN STEAM SAFETY VALVES (MSSVs) AS PART OF REFUELING | | OUTAGE ACTIVITIES, ONE MSSV STUCK OPEN, THEN SUBSEQUENTLY RESEATED, CAUSING | | A SAFETY INJECTION SIGNAL DUE TO STEAM GENERATOR DIFFERENTIAL PRESSURE. | | NEITHER REACTOR COOLANT SYSTEM (RCS) PRESSURE NOR TEMPERATURE DECREASED | | SIGNIFICANTLY DUE TO THE STUCK MSSV, AND NO INJECTION OF WATER TO THE RCS | | OCCURRED. (THIS IS AN INTERMEDIATE HEAD SAFETY INJECTION PLANT.) | | | | OPERATORS ENTERED EMERGENCY OPERATING PROCEDURE 'E0' IN RESPONSE TO THE | | EVENT. THE LICENSEE REPORTED THAT ALL SYSTEMS FUNCTIONED AS EXPECTED, | | EXCEPT THAT THE '25' FAN COOLER UNIT AND '23' AUXILIARY BOILER FEED PUMP | | DID NOT AUTOMATICALLY START IN RESPONSE TO THE ESFAS SIGNAL. THIS EQUIPMENT | | WAS MANUALLY STARTED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 0529 EDT 5/1/97 FROM GOETCHIUS TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS ENTERED TECHNICAL SPECIFICATION 3.0.3. THE '25' FAN COOLER | | UNIT HAS BEEN DECLARED INOPERABLE (BUT REMAINS AVAILABLE), AND THE | | EMERGENCY DIESEL GENERATOR FOR THE OTHER ESFAS TRAIN IS CURRENTLY OUT OF | | SERVICE FOR MAINTENANCE. THE LICENSEE HAS 30 HOURS TO EITHER DECLARE THE | | FAN COOLER UNIT OPERABLE OR TO REDUCE RCS TEMPERATURE TO <350øF IN ORDER TO | | COMPLY WITH THE TECHNICAL SPECIFICATION. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED. NOTIFIED R1DO (DOLCE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32249 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/01/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/01/97 | +------------------------------------------------+EVENT TIME: 02:20[EDT]| |NRC NOTIFIED BY: GOETCHIUS |LAST UPDATE DATE: 05/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DOLCE 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS STEAM GENERATOR BLOWDOWN ISOLATION | | | | AT 0220 EDT, STEAM GENERATOR BLOWDOWN ISOLATION RADIATION MONITOR 'R49' | | SPIKED, CAUSING A STEAM GENERATOR BLOWDOWN ISOLATION. OPERATORS CONFIRMED | | THAT THE RADIATION MONITOR SPIKE WAS SPURIOUS, AND THEN RESET THE | | ISOLATION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+