U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/09/96 - 02/12/96 ** EVENT NUMBERS ** 29962 29963 29964 29965 29966 29967 29968 29969 29970 29971 29972 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29962 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/09/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 11:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/09/96 | +------------------------------------------------+EVENT TIME: 11:03[EST]| |NRC NOTIFIED BY: ENOCH |LAST UPDATE DATE: 02/09/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANDERSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE COMMENCED UNIT SHUTDOWN DUE TO PROBLEMS WITH SOLID STATE | | PROTECTION SYSTEM | | | | DURING ROUTINE SURVEILLANCE TESTING, THE LICENSEE DISCOVERED THAT THE P-9 | | INTERLOCK WAS NOT FUNCTIONING PROPERLY. WITH REACTOR POWER LESS THAN THE | | P-9 INTERLOCK, A TURBINE TRIP DOES NOT AUTOMATICALLY GENERATE A REACTOR | | TRIP SIGNAL. THE LICENSEE STATED THAT THE PROBLEM APPEARED TO BE CAUSED BY | | A CIRCUIT CARD FAILURE. REACTOR POWER IS BEING REDUCED AT A RATE OF 10% PER | | HOUR. THE LICENSEE IS CURRENTLY TROUBLESHOOTING, AND EXPECTS THE PROBLEM TO | | BE CORRECTED WITHIN THE NEXT SEVERAL HOURS. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED BY THE LICENSEE. | | | | ***UPDATE @1320ET 02/09/96 BY ENOCH TAKEN BY MACKINNON*** | | | | STOPPED REACTOR POWER REDUCTION AT 57%. HAVE COMPLETED REPLACING THE | | UNIVERSAL LOGIC CARD ASSOCIATED WITH THE P-9 INTERLOCK. COMPLETED TESTING | | THE REPLACED LOGIC CARD. WILL START INCREASING REACTOR POWER AT 5% PER | | HOUR. RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. R1DO (CLIFF | | ANDERSON) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29963 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 02/09/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/08/96 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: R. VINCENT |LAST UPDATE DATE: 02/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EIGHT HOUR AVERAGE POWER LEVEL EXCEEDED 100% (2530MWt). THE AVERAGE POWER | | LEVEL WAS 100.1%. | | | | THIS EVENT IS REPORTED UNDER PALISADES OPERATING LICENSE PARAGRAPH 2F AS A | | POTENTIAL VIOLATION OF LICENSE CONDITION 2.C.(1). | | DURING REVIEW OF HOURLY REACTOR POWER LEVEL LOG ENTRIES FOR 02/07/96, IT | | WAS DETERMINED THAT THE 8 HOUR AVERAGE POWER LEVEL EXCEEDED 2530MWt. THE | | AVERAGE POWER WAS 100.1% OVER THE "B" SHIFT AND 100.02% OVER THE "C" SHIFT. | | OPERATING LICENSE CONDITION 2.C(1) AUTHORIZES OPERATION AT A STEADY STATE | | POWER LEVEL NOT IN EXCESS OF 2530MWt. PALISADES PROCEDURES DEFINE THIS TO | | MEAN THE AVERAGE POWER OVER A 24 HOUR PERIOD MAY NOT EXCEED 2530MWt. AN | | INTERNAL NRC MEMO DATED AUGUST 22, 1980 FROM E.L. JORDAN TO REGION STAFFS | | SPECIFIES THAT AVERAGE POWER LEVEL OVER AN EIGHT HOUR PERIOD SHOULD NOT | | EXCEED THE LICENSE LIMIT. PLANT PROCEDURES WERE NOT VIOLATED SINCE 24-HOUR | | AVERAGED POWER MET THE LICENSE LIMIT. THE POWER INCREASE ABOVE 100% WAS | | CONTROLLED AND MONITORED AS THE EXPECTED RESULT OF A PLANNED PRIMARY SYSTEM | | DELITHIATION OF ONE OF THEIR ION EXCHANGERS. DELITHIATION CAUSES BORON | | CONCENTRATION TO DECREASE WHICH IN TURN CAUSED REACTOR POWER TO INCREASE. | | MAXIMUM POWER LEVEL DURING THE DELITHIATION EVOLUTION WAS APPROXIMATELY | | 100.3%. | | POWER LEVEL DURING SUBSEQUENT OPERATION HAS MET THE LICENSE LIMIT USING THE | | 8-HOUR AVERAGE GUIDANCE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29964 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: POWER RESOURCES |NOTIFICATION DATE: 02/09/96 | | CITY: GLENROCK REGION: 4 |NOTIFICATION TIME: 16:11 [ET]| | COUNTY: CONVERSE STATE: WY |EVENT DATE: 02/09/96 | |LICENSE#: SUA 1511 AGREEMENT: N |EVENT TIME: 14:00[MST]| | DOCKET: |LAST UPDATE DATE: 02/09/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DALE POWERS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BILL KEARNEY | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAVE TWO MINES IN EXCURSION STATUS. THIS | | DOES NOT POSE ANY THREAT TO THE HEALTH AND SAFETY OF LICENSEE'S PERSONNEL. | | | | POWER RESOURCES IS LOCATED 30 MILES NORTH EAST OF GLENROCK, WYOMING. | | ON 02/09/96 AT 1400MST LICENSEE PLACED WELL M62, LOCATED IN "B" WELL FIELD | | INTO EXCURSION STATUS AFTER THE WELL'S BICARBONATES AND CONDUCTIVITY | | CHEMISTRY RESULTS SHOWED THAT THEY WERE OUT OF SPECIFICATiON. TO ENTER AN | | EXCURSION STATUS YOU MUST BE OUT OF SPECIFICATION IN 2 OUT OF 3 OF THE | | FOLLOWING ITEMS: CHLORIDES, BICARBONATES, OR CONDUCTIVITY. BICARBONATES | | FOR THE WELL WAS 282mg/liter (LIMIT IS <281mg/liter) AND CONDUCTIVITY FOR | | THE WELL WAS 779æmhos/cm (LIMIT IS <735æmhos/cm). WELL M63 HAS BEEN IN AN | | EXCURSION STATUS FOR SEVERAL DAYS. LICENSEE IS REPORTING THIS EVENT BECAUSE | | TWO WELLS (M62 AND M63) ARE IN EXCURSION STATUS AT THE SAME TIME. | | THE REASON WHY CONDUCTIVITY AND BICARBONATES FOR WELLS M62 AND M63 ARE | | INCREASING IS BECAUSE THE WATER FROM AN ABANDONED UNDERGROUND URANIUM MINE | | LOCATED UP HILL FROM THESE WELLS IS SLOWLY LEAKING INTO THEM. | | CHLORIDE AND URANIUM (U3O8) LIMITS ARE WITHIN SPECIFICATION. | | LICENSEE WILL SUBMIT A WRITTEN REPORT WITHIN 7 DAYS WHICH WILL SPECIFY WHAT | | CORRECTIVE ACTIONS THEY ARE GOING TO TAKE TO GET THE CURRENT BICARBONATE | | AND CONDUCTIVITY LIMITS BACK TO WITHIN SPECIFICATION. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29965 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 02/09/96 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 17:27 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 02/09/96 | +------------------------------------------------+EVENT TIME: 10:45[PST]| |NRC NOTIFIED BY: C. WILLIAMS |LAST UPDATE DATE: 02/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL LOG POWER CHANNEL'S LOW LEVEL TRIP, INTENDED TO PREVENT INADVERTENT | | CRITICALITY, WERE FOUND TO BE SET TOO LOW. | | | | ABB COMBUSTION ENGINEERING NOTIFIED SAN ONOFRE ENGINEERING ABOUT A | | CONDITION AT WATERFORD 3 WHICH WAS ALSO BELIEVED TO BE APPLICABLE TO SAN | | ONOFRE UNITS 2 AND 3. | | THE CONCERN AT WATERFORD 3 WAS THAT THE LOGARITHMIC POWER CHANNELS WERE | | READING A FEW PERCENT BELOW THE ACTUAL LOG POWER. AT WATERFORD 3 AND SAN | | ONOFRE, THE LOG POWER CHANNELS PROVIDE A PLANT TRIP SAFETY FUNCTION BELOW | | 1% POWER IF AN UNPLANNED CRITICALITY DURING STARTUP OCCURS. SAN ONOFRE WAS | | NOTIFIED OF THE POTENTIAL FOR THESE LOG POWER CHANNELS TO READ LOWER THAN | | THE ACTUAL POWER LEVEL AND CONFIRMED THAT THEY WERE INDICATING 90% POWER | | WHEN BOTH UNITS WERE AT 100% POWER LEVEL. BECAUSE THE LOG POWER CHANNELS | | MAY HAVE BEEN OUT OF TOLERANCE, THEY MAY NOT HAVE FUNCTIONED PROPERLY. IT | | WAS DETERMINED THAT THESE ERRANT READINGS WERE CAUSED BY INSTRUMENT | | DECALIBRATING EFFECTS OF CORE PHYSICS PARAMETERS. SAN ONOFRE DOES NOT | | BELIEVE ANY TECHNICAL SPECIFICATION LIMITS WERE VIOLATED, BUT AN | | INVESTIGATION IS IN PROGRESS. BOTH UNITS 2 AND 3 ARE AT ABOUT 100% POWER AT | | THIS TIME. | | SAN ONOFRE BELIEVES THIS SITUATION MAY HAVE EXISTED AT SONGS DURING STARTUP | | IN THE PAST. HOWEVER, SINCE THIS CONDITION ONLY AFFECTS STARTUP, THIS IS | | CURRENTLY OF LIMITED SIGNIFICANCE. SONGS WILL PROVIDE A WRITTEN REPORT TO | | THE NRC CONCERNING THE ABOVE MENTIONED PROBLEM. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | (SEE WATERFORD 3 EVENT # 29908 REPORTED ON 01/30/96 FOR SAME PROBLEM) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29966 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 02/09/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:23 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 02/09/96 | +------------------------------------------------+EVENT TIME: 17:45[EST]| |NRC NOTIFIED BY: L. MOFFATT |LAST UPDATE DATE: 02/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | COMPENSATORY MEASURES NOT TAKEN WITHIN SPECIFIED TIME REQUIREMENT. | | | | PLANT EMPLOYEE INADVERTENTLY TOOK HIS SECURITY BADGE HOME. WHEN SECURITY | | WAS INFORMED OF THIS, SECURITY DID NOT TAKE COMPENSATORY ACTIONS WITHIN THE | | SPECIFIED TIME LIMIT. | | SECURITY WAS NOT COMPROMISED DURING THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | SEE HOO LOG BOOK FOR FURTHER DETAILS | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29967 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 02/09/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:47 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/09/96 | +------------------------------------------------+EVENT TIME: 19:40[EST]| |NRC NOTIFIED BY: LIJOI |LAST UPDATE DATE: 02/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFF ANDERSON 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 +------------------------------------------------------------------------------+ | RECEIVED A CONTAINMENT VENTILATION ISOLATION SIGNAL WHILE PLACING | | PRESSURIZER RELIEF TANK (PRT) EDUCTOR IN SERVICE. | | | | WHILE LINING UP TO PLACE THE PRT EDUCTOR IN SERVICE, WITH CONTAINMENT PURGE | | SYSTEM IN SERVICE AN INCREASE IN PARTICULATE AND RADIONUCLIDE GAS WAS | | OBSERVED. THE INCREASED PARTICULATE AND RADIONUCLIDE GAS LEVELS CAUSED | | CONTAINMENT RADIATION MONITOR R41/R42 TO ALARM. THIS CAUSED AN AUTOMATIC | | CLOSURE OF THE CONTAINMENT VENTILATION SYSTEM. THE PRT EDUCTOR WAS SECURED | | AND CONTAINMENT PURGE WAS PLACED BACK IN SERVICE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29968 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 02/10/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 00:35 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 02/09/96 | +------------------------------------------------+EVENT TIME: 23:34[EST]| |NRC NOTIFIED BY: RICK ADAMSON |LAST UPDATE DATE: 02/10/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | A/R Y 59 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TURBINE TRIP & REACTOR TRIP ON HIGH STEAM GENERATOR LEVEL- | | | | THE PLANT HAD REDUCED POWER TO INVESTIGATE A SUSPECTED PROBLEM WITH ONE OF | | THE MAIN FEED PUMP DISCHARGE CHECK VALVES. AFTER SECURING THE "B" FEED | | PUMP, THE "B" DISCHARGE CHECK VALVE STUCK OPEN. THIS CAUSED FEED FROM THE | | "A" FEED PUMP TO SHORT CYCLE THROUGH THE "B" PUMP. OPERATORS COMPENSATED | | FOR THE RESULTING REDUCTION IN FEED FLOW TO THE STEAM GENERATORS BY TAKING | | MANUAL CONTROL OF THE "A" FLOW CONTROL VALVE AND INCREASING FLOW. | | | | SECURING THE "B" FEED PUMP CAUSED THE DISCHARGE MOV FOR THAT PUMP TO START | | CLOSING. THIS VALVE FULLY CLOSED AFTER THE "A" FLOW CONTROL VALVE HAD | | ALREADY BEEN OPENED FURTHER TO INCREASE FLOW. THE IMMEDIATE RESULT WAS A | | RAPID RISE IN STEAM GENERATOR LEVELS. A TURBINE TRIP SIGNAL WAS RECEIVED | | ON HIGH LEVEL IN THE "C" STEAM GENERATOR BEFORE FEED FLOW COULD BE REDUCED. | | | | THE TURBINE TRIP CAUSED A REACTOR TRIP. ALL RODS FULLY INSERTED AND | | AUXILIARY FEEDWATER STARTED AS EXPECTED. THE PLANT IS STABLE IN MODE 3. | | AFW HAS SINCE BEEN SECURED AND THE STEAM GENERATORS ARE BEING FED BY THE | | MAIN FEED SYSTEM. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29969 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING COMPANY |NOTIFICATION DATE: 02/10/96 | | CITY: CASPER REGION: 4 |NOTIFICATION TIME: 10:09 [ET]| | COUNTY: JOHNSON STATE: WY |EVENT DATE: 02/07/96 | |LICENSE#: SUA-1341 AGREEMENT: N |EVENT TIME: 12:00[MST]| | DOCKET: |LAST UPDATE DATE: 02/10/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DALE POWERS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN VASELIN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -GROUND WATER PARAMETERS ABOVE THE UPPER CONTROL BAND- | | | | CHLORIDES WERE MEASURED 15.2 PPM WITH AN UPPER CONTROL LEVEL OF 14.7 PPM. | | ALKALINITY WAS MEASURED AT 134.6 mg/L WITH AN UPPER CONTROL LEVEL OF 119.4 | | PPM. | | | | THESE MEASUREMENTS WERE TAKEN AT A SHALLOW MONITOR WELL IN AN AQUIFER ABOVE | | THE ONE THAT HAD BEEN MINED. THIS MINE IS IN THE RESTORATION PHASE. THE | | LICENSEE WILL FOLLOW UP WITH A WRITTEN REPORT WITHIN SEVEN DAYS. | | | | A CONTACT PHONE NUMBER IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29970 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 02/10/96 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 11:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/96 | +------------------------------------------------+EVENT TIME: 08:19[EST]| |NRC NOTIFIED BY: MUTZ |LAST UPDATE DATE: 02/10/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 Y 94 POWER OPERATION | 94 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE ATTEMPTING TO PERFORM A CONTAINMENT PRESSURE RELIEF (CPR) A STANDING | | CONTAINMENT VENTILATION ISOLATION SIGNAL WAS FOUND ON TRAIN "A". | | | | WHILE ATTEMPTING TO PERFORM A CPR AT 0819ET, THE OPERATOR WAS SURPRISED | | WHEN VALVE 2-VCR-107 (TRAIN "A" CPR VALVE INSIDE CONTAINMENT) WOULD NOT | | OPEN. THE REASON FOR THIS WAS DISCOVERED TO BE A STANDING CONTAINMENT | | VENTILATION ISOLATION (CVI) SIGNAL ON TRAIN "A". NO CAUSE FOR THIS COULD BE | | IDENTIFIED AND THE CVI WAS RESET, ALLOWING THE CPR TO BE PERFORMED. | | THE PROCESS COMPUTER TYPEWRITER ALARM REVIEWS INDICATED THE CVI OCCURRED AT | | 0225ET ON 02/10/96. LICENSEE IS NOT REQUIRED TO REVIEW THE PROCESS COMPUTER | | TYPEWRITER ALARM OUTPUT AT ANY SET TIMES. NO COMPONENTS THAT RECEIVED A CVI | | WERE REQUIRED TO REPOSITION BECAUSE THEY WERE ALREADY IN THEIR REQUIRED | | POSITION. AN INVESTIGATION FOR THE CAUSE OF THE CVI IS IN PROGRESS. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29971 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 02/10/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:21 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 02/10/96 | +------------------------------------------------+EVENT TIME: 03:17[EST]| |NRC NOTIFIED BY: BOURASSA |LAST UPDATE DATE: 02/10/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT OUTBOARD ISOLATION VALVE EXCEEDED THE 24 HOUR CONTAINMENT | | INTEGRATED LEAK RATE TECHNICAL SPECIFICATION LIMIT BY 16%. | | | | CONTAINMENT LEAK RATE SURVEILLANCE TEST TR-39E, CLEAN AND DIRTY SUMP | | ISOLATION VALVE LEAK RATE TEST, WAS PERFORMED WITH THE FOLLOWING RESULTS: | | THE CLEAN SUMP ISOLATION VALVES PASSED THE ACCEPTANCE CRITERIA OF THE PLANT | | PROCEDURE. THE DIRTY SUMP ISOLATION VALVE CV-4025 (INSIDE CONTAINMENT | | ISOLATION VALVE) LEAKAGE WAS 24.4 psi/24hr; AND CV-4103 (OUTBOARD | | CONTAINMENT ISOLATION VALVE) WAS 207psi/24hr. PLANT ADMINISTRATIVE | | ACCEPTANCE CRITERIA IS ó 24psi/24hr. | | TOTAL INTEGRATED CONTAINMENT LEAKAGE IS CALCULATED BY CONSERVATIVELY | | APPLYING THE VALVE WITH THE MOST LEAKAGE INTO THE CALCULATION (CV-4103; | | 207psi/24hr). THE TECHNICAL SPECIFICATION FRACTION AUTHORIZED LEAKAGE RATE | | WAS CALCULATED, AND THE LEAKAGE RATE EXCEEDED THE TECHNICAL SPECIFICATION | | LIMIT BY 16%. SINCE THE PLANT IS IN ITS 36TH DAY OF REFUELING, AND THERE IS | | NO FUEL IN THE CORE, CONTAINMENT INTEGRITY IS NOT REQUIRED AT THIS TIME. | | THIS CONDITION WAS DISCOVERED 02/10/96 AT 0317CT. AN ENS REPORT WAS NOT | | BELIEVED TO BE REQUIRED. FOLLOWING FURTHER REVIEW, THE BIG ROCK STAFF HAS | | CONCLUDED THAT THIS EVENT IS REPORTABLE. | | PRIOR TO PERFORMING ANY WORK REQUIRING CONTAINMENT INTEGRITY, THE LICENSEE | | WILL ASSURE THAT THE TECHNICAL SPECIFICATION REQUIREMENT DESCRIBED ABOVE | | SHALL BE MET. VALVE REPAIRS AND LEAKAGE TESTS ARE PLANNED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29972 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 02/10/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 15:22 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 02/10/96 | +------------------------------------------------+EVENT TIME: 11:29[CST]| |NRC NOTIFIED BY: WELCH |LAST UPDATE DATE: 02/10/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 3 EMERGENCY DIESEL GENERATOR (EDG) INADVERTENTLY STARTED. | | | | WHILE A HIGH VOLTAGE OPERATOR WAS PERFORMING ROUTINE CHECKS ON THE UNIT 3 | | EDG, HE INADVERTENTLY DEPRESSED THE LOCAL MANUAL START PUSH BUTTON INSTEAD | | OF THE LAMP CHECK PUSH BUTTON. (THE TWO BUTTONS ARE ABOUT 1 OR 2 INCHES | | APART FROM EACH OTHER AND THE MANUAL START BUTTON DOES NOT HAVE A | | PROTECTIVE COVER TO PREVENT IT FROM BEING ACCIDENTALLY DEPRESSED) THE UNIT | | 3 EDG STARTED. THE 2/3 EDG (SWING) AT THE TIME WAS IN THE MIDDLE OF AN | | OPERABILITY RUN FOLLOWING A 2 YEAR SCHEDULED OVERHAUL. THE UNIT 3 EDG WAS | | VERIFIED TO OPERATE SUCCESSFULLY IN AN UNLOADED CONDITION AND WAS SECURED. | | SUBSEQUENTLY, THE UNIT 3 EDG WAS VERIFIED TO BE IN A STANDBY READINESS | | CONDITION. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+