U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/29/97 - 07/30/97 ** EVENT NUMBERS ** 32692 32693 32694 32695 32696 32697 32698 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32692 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 02:26 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 02:04[EDT]| |NRC NOTIFIED BY: LATZ |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SECURITY EVENT - | | | | A SAFEGUARDS SYSTEM DEGRADATION RELATED TO THE SECURITY COMPUTER AND ALARMS | | OCCURRED. COMPENSATORY MEASURES WERE IN PLACE WITHIN 10 MINUTES. (REFER | | TO THE HOO LOG FOR ADDITIONAL DETAILS.) THE LICENSEE NOTIFIED STATE AND | | LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32693 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:19 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 09:55[EDT]| |NRC NOTIFIED BY: WILLIS |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFFORD ANDERSON 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SERVICE WATER CHECK VALVE LEAK RATE GREATER THAN TWO GALLONS PER MINUTE | | (GPM) PLACES THE PLANT OUTSIDE ITS DESIGN BASIS. | | | | A CHECK VALVE USED TO PREVENT SYSTEM DRAINDOWN IS INSTALLED IN THE SERVICE | | WATER SYSTEM, AND THIS SYSTEM COOLS THE SPENT FUEL POOL HEAT EXCHANGERS. A | | SURVEILLANCE TEST OF THIS VALVE MEASURED A LEAK RATE OF FOUR TO FIVE GPM. | | THE ACCEPTANCE CRITERIA LEAK RATE LIMIT IS TWO GPM. | | | | BY EXCEEDING THIS LEAK RATE LIMIT, THE POTENTIAL EXISTS FOR A WATER HAMMER, | | AND THIS CONDITION PLACES THE PLANT OUTSIDE ITS DESIGN BASIS. THE LICENSEE | | PLANS TO RETEST THE VALVE, AND IF IT FAILS A SECOND TIME, THE LICENSEE | | PLANS TO EITHER REPAIR OR REPLACE THE VALVE. | | | | SPENT FUEL POOL COOLING HAS BEEN MAINTAINED THROUGHOUT THIS EVENT. | | | | THE LICENSEE NOTIFIED THE STATE OF CONNECTICUT AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32694 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 10:20 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 09:00[CDT]| |NRC NOTIFIED BY: BOYLE |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 3 STARTUP | 3 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISQUALIFYING INFORMATION WAS RECEIVED REGARDING A CONTRACT EMPLOYEE WHO | | HAD BEEN GRANTED TEMPORARY UNESCORTED ACCESS TO THE SITE. IMMEDIATE | | COMPENSATORY ACTIONS WERE TAKEN UPON DISCOVERY. (REFER TO THE HOO LOG FOR | | ADDITIONAL DETAILS.) THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32695 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 02:10[CDT]| |NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO INOPERABLE PRIMARY CONTAINMENT | | | | AT 0210 CDT, DURING THE PERFORMANCE OF A DRYWELL TO TORUS (SUPPRESSION | | CHAMBER) VACUUM BREAKER OPERATION SURVEILLANCE TEST, VACUUM BREAKER | | #PC-AO-NRV28 FAILED TO GIVE AN INDICATED CLOSED SIGNAL AFTER BEING CYCLED. | | PER THE TEST ACCEPTANCE CRITERIA, A DRYWELL TO SUPPRESSION CHAMBER LEAKAGE | | SURVEILLANCE TEST IS REQUIRED TO BE PERFORMED IN ORDER TO DEMONSTRATE THAT | | THE VACUUM BREAKER IS CLOSED. THE VACUUM BREAKER WAS DECLARED INOPERABLE, | | AND TROUBLESHOOTING WAS PERFORMED WITHOUT A CHANGE TO THE INDICATED | | POSITION. | | | | TECH SPEC 3.7.A.4.a REQUIRES THAT ALL DRYWELL TO SUPPRESSION CHAMBER VACUUM | | BREAKERS BE POSITIONED IN THE FULLY CLOSED POSITION AS INDICATED BY THE | | POSITION INDICATING SYSTEM. IF THIS IS NOT THE CASE, THE TOTAL LEAKAGE | | BETWEEN THE DRYWELL AND SUPPRESSION CHAMBER IS REQUIRED TO BE LESS THAN THE | | EQUIVALENT LEAKAGE THROUGH A ONE-INCH DIAMETER ORIFICE. | | | | AT 0835 CDT, IT WAS DETERMINED THAT THE LEAKAGE TEST ACCEPTANCE CRITERIA | | HAD NOT BEEN MET, AND THE PRIMARY CONTAINMENT WAS DECLARED INOPERABLE. AT | | 0950 CDT, A PLANT SHUTDOWN REQUIRED BY TECH SPEC 1.0.J WAS INITIATED. THE | | PLANT IS REQUIRED TO BE IN HOT SHUTDOWN WITHIN 6 HOURS AND COLD SHUTDOWN | | WITHIN THE FOLLOWING 30 HOURS. | | | | THE LICENSEE PLANS TO PLACE THE PLANT IN COLD SHUTDOWN WITHIN 24 HOURS, | | DE-INERT THE CONTAINMENT, AND REPAIR THE VACUUM BREAKER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1633 07/29/97, UPDATE FROM FRED SCHIZAS ENTERED BY JOLLIFFE * * * | | | | AT 1412 CDT, CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE REACTOR FROM 30% | | POWER IN ACCORDANCE WITH A NORMAL PLANT SHUTDOWN EVOLUTION. ALL CONTROL | | RODS INSERTED COMPLETELY. PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 | | (EMERGENCY CORE COOLING SYSTEMS), GROUP 3 (REACTOR WATER CLEANUP SYSTEM), | | AND GROUP 5 (STANDBY GAS TREATMENT SYSTEM) ACTUATED AS EXPECTED. | | | | AT 1419 CDT, ALL SYSTEMS WERE RESET TO NORMAL. | | | | THE PLANT IS CURRENTLY STABLE IN CONDITION 3 (HOT SHUTDOWN). DECAY HEAT | | STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A | | PRESS RELEASE. THE OPERATIONS OFFICER NOTIFIED THE R4DO (CHUCK CAIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32696 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/29/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 10:44[CDT]| |NRC NOTIFIED BY: DAN COVEYOU |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 +------------------------------------------------------------------------------+ | - MISC EQUIPMENT NOT SEISMICALLY MOUNTED IN UNIT 1 AND 2 SWITCHGEAR ROOMS - | | | | THE LICENSEE IDENTIFIED THAT MISCELLANEOUS EQUIPMENT (PORTABLE RADIATION | | MONITORS, REMOVED SWITCHGEAR CIRCUIT BREAKERS, ETC.) LOCATED IN THE UNIT 1 | | AND 2 SWITCHGEAR ROOMS WERE NOT SEISMICALLY MOUNTED. IF A SEISMIC EVENT | | WERE TO OCCUR, NON-SEISMICALLY MOUNTED MISCELLANEOUS EQUIPMENT COULD FALL | | ONTO ELECTRICAL RELAYS ASSOCIATED WITH IMPORTANT-TO-SAFETY EQUIPMENT, | | CAUSING THE RELAYS TO CHATTER. THE LICENSEE RELOCATED THE MISCELLANEOUS | | EQUIPMENT TO ACCEPTABLE AREAS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32697 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 07/29/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:33 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 07/29/97 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: TERRY GALLENTINE |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 Y 97 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SAFE SHUTDOWN CABLE USED DURING A FIRE COULD BE DAMAGED BY THAT FIRE. | | | | DURING A LICENSEE SELF ASSESSMENT OF PLANT FIRE SCENARIOS AS PART OF THE | | INDEPENDENT PLANT EVALUATION OF EXTERNAL EVENTS (IPEEE), THE LICENSEE | | DISCOVERED THAT A CABLE RELIED UPON FOR THE SAFE SHUTDOWN OF THE PLANT IS | | LOCATED IN A FIRE AREA OF CONCERN AND COULD BE DAMAGED BY THE SAME FIRE | | WHICH MAY REQUIRE THE USE OF THE PLANT SAFE SHUTDOWN EQUIPMENT. THIS CABLE | | RUNS FROM A 4-KV SAFETY-RELATED BUS TO A 480-V SAFETY-RELATED BUS IN THE | | HIGH PRESSURE HEATER BAY IN THE TURBINE BUILDING. THEREFORE, PROCEDURAL | | STEPS THAT COVER PROVIDING POWER TO VARIOUS COMPONENTS NEEDED TO BRING THE | | REACTOR TO A SAFE SHUTDOWN CONDITION ARE NOW INADEQUATE FOR A FIRE IN THIS | | AREA OF CONCERN. | | | | THE LICENSEE HAS POSTED AN HOURLY ROVING FIRE PATROL WATCH IN THIS AREA OF | | CONCERN AND IS DETERMINING LONG-TERM CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32698 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/29/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 17:02 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 07/24/97 | +------------------------------------------------+EVENT TIME: 21:00[EDT]| |NRC NOTIFIED BY: BILL WILSON |LAST UPDATE DATE: 07/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -EDG COULD BE OVERLOADED DUE TO THE BUS LOADING SEQUENCE FOLLOWING A LOOP- | | | | DURING THE PRESENT MAINTENANCE OUTAGE, THE TWO EMERGENCY DIESEL GENERATORS | | (EDGs) AT CRYSTAL RIVER UNIT 3 ARE BEING PHYSICALLY UPGRADED. | | | | AT 2100 ON 07/24/97, WHILE EVALUATING PLANT EMERGENCY OPERATING PROCEDURES | | (EOPs), THE LICENSEE DETERMINED THAT FOLLOWING A LOSS OF OFFSITE POWER | | (LOOP), EOP #AP-770 DIRECTS OPERATORS TO RESTORE PLANT CONDITIONS TO | | NORMAL. IF AN AUTOMATIC OR MANUAL EMERGENCY SAFEGUARDS (ES) (HIGH PRESSURE | | INJECTION) ACTUATION OCCURS DURING THE TIME THAT EDG #1A IS SUPPLYING POWER | | TO THE ES BUS, EDG #1A HAS THE POTENTIAL TO EXCEED ITS MAXIMUM RATING DUE | | TO THE STARTING CURRENT OF THE #1A 700 HP MAKEUP PUMP MOTOR. | | | | THE EDG #1A LOADING EVALUATION CALCULATION/ANALYSIS SPECIFIES A PARTICULAR | | AUTOMATIC BUS LOADING SEQUENCE TO PREVENT OVERLOADING THE EDG DUE TO | | EXCESSIVE MOTOR STARTING CURRENTS. HOWEVER, IF THE PLANT LOADS ARE | | MANUALLY SEQUENCED ONTO THE BUS IN AN ORDER DIFFERENT THAN THAT ASSUMED | | IN THE CALCULATIONS/ANALYSES, EDG #1A COULD BE OVERLOADED. | | | | THE DESIGN BASIS ACCIDENT ANALYSIS REQUIRES EDG #1A TO SUPPORT A LOSS OF | | COOLANT ACCIDENT (LOCA) COINCIDENT WITH A LOOP. HOWEVER, THE PLANT DESIGN | | CRITERIA COVERS ONLY A SINGLE FAILURE SCENARIO (LOCA OR LOOP) AND DOES NOT | | ASSUME A SECOND FAILURE SCENARIO (LOOP OR LOCA). | | | | AT 1610 ON 07/29/97, THE LICENSEE DETERMINED THAT THIS CONDITION WAS | | REPORTABLE TO THE NRC AS AN UNANALYZED CONDITION. | | | | EDG #1A IS OPERABLE, AND IN THE PRESENT PLANT OPERATING MODE (MODE 5 - COLD | | SHUTDOWN), THE ES ACTUATION SIGNAL IS BYPASSED. | | | | THE LICENSEE IS EVALUATING THIS ISSUE AND PLANS TO DEVELOP A WORST-CASE | | MODEL FOR EDG BUS LOADING TO SUPPORT THE EDG UPGRADE MODIFICATION. THE | | LICENSEE ALSO PLANS TO INCLUDE THE DETAILS IN THE EDG UPGRADE PLANT | | MODIFICATION DOCUMENTATION. IN ADDITION, THIS ISSUE WILL BE INCLUDED IN | | PLANT RESTART ITEM #D-14. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+