U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/02/97 - 04/03/97 ** EVENT NUMBERS ** 32066 32067 32068 32069 32070 32071 32072 32073 32074 32075 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/02/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 10:55 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 10:45[EST]| |NRC NOTIFIED BY: JOHN LIJOI |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARKLEY RDO | |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 Y 100 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO EMERGENCY DIESEL GENERATORS INOPERABLE. TECH SPEC REQUIRED SHUTDOWN. | | | | AFTER OPERATING THE #21 EMERGENCY DIESEL GENERATOR (EDG) TO PROVE | | OPERABILITY, IT WAS SHUTDOWN AT 0935. AT 0945, A TROUBLE ALARM WAS | | RECEIVED ON THE #21 EDG. AN INVESTIGATION REVEALED A DC CONTROL POWER LAMP | | WAS EXTINGUISHED. THIS RESULTED IN THE #21 EDG BEING INOPERABLE. THE #23 | | EDG IS OUT OF SERVICE FOR PLANNED MAINTENANCE AND THE #22 EDG 22 OPERABLE. | | PLANT SHUTDOWN WAS INITIATED AT 1044 IN ACCORDANCE WITH TS 3.0.1. | | | | FURTHER INVESTIGATION SHOWED THAT JACKET WATER PRESSURE SWITCH #3 WAS | | INOPERABLE. THIS SWITCH IS BEING REPLACED. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/02/97 | |UNIT: [1] [2] [3] STATE: CT |NOTIFICATION TIME: 13:28 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: D BERARDI |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTRACTOR SUPERVISOR DUTIES TESTED POSITIVE FOR ALCOHOL. | | | | | | A CONTRACTOR SUPERVISOR TESTED POSITIVE FOR ALCOHOL DURING A FOR-CAUSE | | TEST. THE CONTRACT PERSON DID NOT PERFORM ANY WORK ON VITAL EQUIPMENT. HIS | | ACCESS TO THE PROTECTED AREA HAS BEEN REVOKED. THE LICENSEE NOTIFIED THE | | STATE OF CONNECTICUT OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32068 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 04/02/97 | | CITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION TIME: 13:33 [ET]| | COUNTY: CITRUS STATE: FL |EVENT DATE: 04/02/97 | |LICENSE#: 1157-1 AGREEMENT: Y |EVENT TIME: 09:30[EST]| | DOCKET: |LAST UPDATE DATE: 04/02/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MEL SHYMLOCK RDO | | |FRED COMBS (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CHARLIE ADAMS | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SEVENTEEN PEOPLE WERE POTENTIALLY EXPOSED TO A 50 mCi Cs-137 SOURCE WHILE | | CLEANING A FEEDER CHUTE. | | | | THE STATE OF FLORIDA BUREAU OF RADIATION CONTROL WAS NOTIFIED OF THE | | FOLLOWING EVENT AT 0930 EST ON 04/02/97: | | | | THE EVENT OCCURRED AT THE CRYSTAL RIVER UNITS #4 AND #5 COAL FIRE PLANTS | | EITHER EARLY THIS MORNING OR YESTERDAY. SEVENTEEN PEOPLE WERE CLEANING A | | COAL FEEDER CHUTE AND IT WAS NOT KNOWN AT THE TIME IF THE SHUTTER ON A | | 50 mCi CS-137 SOURCE USED TO MEASURE THE AMOUNT OF COAL GOING UP THE CHUTE | | TO BE FED INTO THE HOPPER WAS CLOSED. THE STATE OF FLORIDA CALCULATED THAT | | THE WORST CASE TOTAL EXPOSURE TO EACH PERSON CLEANING THE FEEDER CHUTE | | WOULD HAVE BEEN 175 mRem (5 HOURS AT 35 mRem/hr). THE STATE OF FLORIDA | | BUREAU OF RADIATION CONTROL IS INVESTIGATING THIS EVENT. STATE OF FLORIDA | | ORIGINAL ITEM NUMBER IS #FL-97-034. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32069 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NC DIVISION OF RAD PROTECTION |NOTIFICATION DATE: 04/02/97 | | CITY: ROCKY MOUNT REGION: 2 |NOTIFICATION TIME: 15:04 [ET]| | COUNTY: EDGECOMBE STATE: NC |EVENT DATE: 04/02/97 | |LICENSE#: 064-0969-1 AGREEMENT: Y |EVENT TIME: 10:30[EST]| | DOCKET: |LAST UPDATE DATE: 04/02/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MILT SHYMLOCK RDO | | |FRED COMBS (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: GRANT MILLS | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DOWN SWITCH FAILURE AT AN INDUSTRIAL IRRADIATOR OWNED BY ABBOTT LABS. NO | | PERSONNEL WERE EXPOSED TO RADIATION. | | | | THE STATE OF NORTH CAROLINA DIVISION OF RADIATION PROTECTION WAS NOTIFIED | | OF THE FOLLOWING EVENT AT 1030 EST ON 04/02/97: | | | | A DOWN SWITCH FAILURE LASTING GREATER THAN 3 HOURS OCCURRED THIS MORNING AT | | ABBOTT LABS INDUSTRIAL IRRADIATOR LOCATED IN ROCKY MOUNT, NORTH CAROLINA. | | ABBOTT LABS REPORTED THAT DURING THE ABNORMAL ENTRY TO INVESTIGATE THE DOWN | | SWITCH FAILURE, IT WAS DISCOVERED THAT THE SOURCES IN THE IRRADIATOR WERE | | IN THEIR SHIELDED POSITION. THE PROBLEM WAS CAUSED BY A "STUCK ACTUATOR | | SPRING ASSEMBLY." THE ASSEMBLY IN QUESTION IS BEING REPLACED AND THE SAFETY | | CHECKS ARE TO BE PERFORMED PRIOR TO RESTART (PLANNED FOR THIS AFTERNOON). | | NORDION HAS BEEN INFORMED BY THE ABBOTT LABS OF THIS SITUATION. ABBOTT LABS | | WILL FILE A WRITTEN REPORT WITH THE NORTH CAROLINA AGENCY WITHIN | | 30 DAYS OF THIS EVENT. THE STATE OF NORTH CAROLINA DIVISION OF RADIATION | | PROTECTION IS INVESTIGATING THIS EVENT. THE STATE OF NORTH CAROLINA | | ORIGINAL ITEM NUMBER IS NC-97-11. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32070 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/02/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 15:21 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 15:10[EST]| |NRC NOTIFIED BY: BERGIN |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICH BARKLEY RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UPDATED FINAL SAFETY ANALYSIS REPORT LIMITS FOR RADIOACTIVITY RELEASED TO | | THE AUXILIARY BUILDING COULD BE EXCEEDED. | | | | THE LICENSEE DISCOVERED THAT 19 OF THE 23 AIR OPERATED CONTAINMENT | | ISOLATION VALVES TESTED ON 03/12/97 WOULD NOT HAVE CLOSED AGAINST FULL | | SYSTEM PRESSURE (2250 psia). THREE OF THE VALVES THAT FAILED THE TEST ARE | | LOCATED IN THE LETDOWN LINE FROM THE REACTOR COOLANT SYSTEM AND ANOTHER | | THREE VALVES THAT FAILED THE TEST ARE REACTOR COOLANT PUMP SEAL BLEED-OFF | | LINE ISOLATION VALVES. THESE 6 VALVES WOULD FAIL UNDER FULL SYSTEM PRESSURE | | AND WOULD RESULT IN A RELEASE OF RADIOACTIVITY TO THE AUXILIARY BUILDING | | GREATER THAN THE ALLOWED LIMIT SPECIFIED BY THE UPDATED FINAL SAFETY | | ANALYSIS REPORT. THE OTHER 13 VALVES THAT FAILED THE TEST ARE LOCATED IN | | MANY DIFFERENT SYSTEMS. ALL 19 FAILED VALVES WILL BE REPAIRED PRIOR TO | | PLANT STARTUP. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THIS EVENT REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32071 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/02/97 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 16:20 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHYMLOCK 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 Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BUILDING COOLING UNITS MAY NOT HAVE RESTARTED DURING A LOSS OF | | COOLANT ACCIDENT/LOSS OF OFFSITE POWER DUE TO POTENTIALLY UNDER-RATED | | PRIMARY CONTROL POWER FUSES. | | | | DURING A LOSS OF COOLANT ACCIDENT CONCURRENT WITH A LOSS OF OFFSITE POWER | | (LOCA/LOOP), THE REACTOR BUILDING COOLING UNITS (RBCUs) ARE REQUIRED TO | | RESTART AND PROVIDE REACTOR BUILDING HEAT REMOVAL. DURING A LOCA/LOOP, | | POWER IS INITIALLY LOST TO THE RBCUs UNTIL THE EMERGENCY POWER SOURCE CAN | | BE ALIGNED TO THE AFFECTED UNIT. UPON RESTORATION OF POWER TO THE AFFECTED | | UNIT, THE RBCUs ARE RESTARTED BY AN ENGINEERING SAFEGUARDS (ES) SIGNAL. | | DURING THIS RESTART, A SIGNAL FROM THE RBCU CONTROL CIRCUIT CLOSES CONTACTS | | IN THE MAIN POWER SUPPLY PATH TO THE RBCU MOTORS TO SUPPLY POWER TO THE | | MOTORS. THE RBCU CONTROL CIRCUIT RECEIVES POWER FROM A CONTROL POWER | | TRANSFORMER THAT HAS FUSES ON THE PRIMARY (POWER) AND SECONDARY (CONTROL) | | SIDES. | | | | ON APRIL 2, 1997, AT 1300 EST, FOR UNIT 3, IT WAS CONSERVATIVELY DETERMINED | | THAT THESE PRIMARY SIDE CONTROL FUSES WERE POTENTIALLY UNDER-RATED AND MAY | | NOT HAVE PERMITTED THE RBCUs TO START DURING A LOCA/LOOP UPON RECEIPT OF AN | | ES SIGNAL. THE POTENTIALLY UNDER-RATED FUSES WERE REPLACED WITH FUSES OF A | | HIGHER RATING ON JUNE 21, 1995. THEREFORE, THE POTENTIAL RBCU INOPERABILITY | | EXISTED ON UNIT 3 PRIOR TO JUNE 21, 1995. THE ORIGINAL FUSES (8 AMPS) ON | | THE PRIMARY SIDE WERE THE ONES SPECIFIED BY THE MANUFACTURER AND IN | | ACCORDANCE WITH SYSTEM DRAWINGS. THE NEW FUSES INSTALLED WERE 15 AMPS AND | | THE MANUFACTURER SAID THAT IT WAS ACCEPTABLE TO INSTALL THE HIGHER RATED | | FUSES. THE 8 AND 15 AMP FUSES ARE INSTANTANEOUS FUSES. | | | | THIS EVENT WAS CONSERVATIVELY REPORTED BY THE LICENSEE BASED ON A | | PRELIMINARY ENGINEERING ASSESSMENT. A DETAILED ANALYSIS IS IN PROGRESS TO | | DETERMINE WHETHER THE UNIT 3 RBCUs COULD HAVE PERFORMED THEIR INTENDED | | SAFETY FUNCTION DURING A LOCA/LOOP. UNIT 1 AND 2 ARE NOT AFFECTED BY THIS | | FUSE ISSUE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32072 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/02/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 19:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 17:40[EST]| |NRC NOTIFIED BY: GORLEY |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHYMLOCK RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 "B" EMERGENCY DIESEL GENERATOR AUTOMATICALLY STARTED UNEXPECTEDLY WHEN | | ITS LOGIC POWER WAS RESTORED BEFORE ENERGIZING ITS 4.16 KV BUS. | | | | THE "B" EMERGENCY DIESEL GENERATOR (SWING) AUTOSTARTED WHEN ITS LOGIC POWER | | FOR UNDERVOLTAGE WAS RESTORED TO THE "2F" 4.16 KV BUS PRIOR TO ENERGIZING | | THE BUS. THE "2F" BUS HAD BEEN DEENERGIZED FOR NORMAL MAINTENANCE (CLEANING | | AND INSPECTION) ACTIVITIES. THE PROCEDURE FOR RESTORING THE "2F" BUS TO | | SERVICE DID NOT SPECIFY ENERGIZING THE BUS PRIOR TO RESTORING THE LOGIC | | POWER TO THE BUS. | | | | THE "B" EMERGENCY DIESEL GENERATOR WAS PROPERLY SECURED AFTER IT HAD | | UNEXPECTEDLY AUTOSTARTED. THE LICENSEE WILL CORRECT THE PROCEDURE TO | | PREVENT THIS TYPE OF EVENT FROM OCCURRING AGAIN IN THE FUTURE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32073 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/02/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 20:41 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 18:30[EST]| |NRC NOTIFIED BY: KIEL |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RON GARDNER 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POWER AND CONTROL CABLES NOT PROTECTED FROM HIGH ENERGY LINE BREAKS | | | | EMERGENCY EQUIPMENT COOLING WATER VALVES (DIVISION 1 PRIMARY CONTAINMENT | | INBOARD RETURN ISOLATION VALVE, #P44-F616 AND DIVISION 2 PRIMARY | | CONTAINMENT INBOARD RETURN ISOLATION VALVE, #P44-F615) HAVE BEEN DETERMINED | | TO HAVE POWER AND CONTROL CABLES WHICH COULD BE AFFECTED BY JET | | IMPINGEMENT. THE CABLES ARE IN THE IMPINGEMENT CONE FOR A HIGH ENERGY LINE | | BREAK. THE UPDATED FINAL SAFETY ANALYSIS REPORT SECTION 3.6 STATES THAT ESF | | SYSTEMS WILL BE PROTECTED FROM HIGH ENERGY LINE BREAKS. THEREFORE, THE | | DESIGN OF THE CABLING FOR #P44-F616 AND #P44-F615 ARE OUTSIDE THEIR DESIGN | | BASIS. A TEAM WILL BE ASSEMBLED TO DETERMINE CORRECTIVE ACTIONS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32074 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/02/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 20:52 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 15:55[CST]| |NRC NOTIFIED BY: VERN CARLSON |LAST UPDATE DATE: 04/02/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 MADE TO LOCAL PARISHES AND THE STATE INFORMING THEM | | THAT SOME OF THEIR OFFSITE EMERGENCY SIRENS ARE NOT OPERABLE. | | | | DURING THE MONTHLY PERFORMANCE OF THE EMERGENCY SIREN TEST OF THEIR 93 | | OFFSITE EMERGENCY SIRENS, FIVE SIRENS WERE VERIFIED NOT TO HAVE SOUNDED. | | THIS REPRESENTS LESS THAN SIX PERCENT OF THE TOTAL SIRENS AVAILABLE AND IS | | NOT CONSIDERED A MAJOR LOSS OF EMERGENCY NOTIFICATION SYSTEMS SINCE BACKUP | | NOTIFICATION MEASURES ARE AVAILABLE. THESE CONSIST OF USING LOCAL FIRE, | | POLICE, AND SHERIFF DEPARTMENTS, AND STATE POLICE TO NOTIFY INDIVIDUALS | | SHOULD THE NEED ARISE. EXISTING PROCEDURES ARE IN PLACE TO COMPENSATE FOR | | THE EMERGENCY SIRENS WHICH HAVE NOT SOUNDED. THE LICENSEE IS CONTINUING ITS | | INVESTIGATION AND WILL PROVIDE AN UPDATE IF FURTHER INFORMATION BECOMES | | AVAILABLE. THE STATE AND LOCAL OFFICIALS HAVE BEEN NOTIFIED OF THIS | | INFORMATION CALL. | | | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32075 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/03/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 01:12 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/02/97 | +------------------------------------------------+EVENT TIME: 23:00[CST]| |NRC NOTIFIED BY: DARYL CLARK |LAST UPDATE DATE: 04/03/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE | | FOLLOWING QUARTERLY SURVEILLANCE TEST. | | | | THE FOLLOWING TEXT IS FROM A FAX SENT BY THE LICENSEE: | | | | "ON APRIL 2, 1997, AT APPROXIMATELY 1700 CST, THE HPCI TURBINE WAS SHUTDOWN | | AFTER QUARTERLY FLOW RATE TESTING. WHEN THE TURBINE CAME TO REST, THE | | TURNING GEAR FAILED TO AUTOMATICALLY ENGAGE. AFTER SUBSEQUENT TESTING OF | | THE TURNING GEAR, IT WAS DETERMINED THAT THERE WAS A PROBLEM WITH THE | | TURNING GEAR ENGAGE LINKAGE. THE UNIT 1 HPCI SYSTEM WAS DECLARED | | INOPERABLE AT 2300 CST. UNIT 1 ENTERED A 14 DAY LCO PER TECHNICAL | | SPECIFICATION 3.5.A.3 AND ACTION 3." | | | | THE LICENSEE IS PREPARING A WORK ORDER TO ADJUST THE TURNING GEAR LINKAGE. | | COMPLETION OF THE WORK IS PLANNED FOR DAY SHIFT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+