U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/20/96 - 12/23/96 ** EVENT NUMBERS ** 31252 31487 31488 31489 31490 31491 31492 31493 31494 31495 31496 31497 31498 31499 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:10 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 16:55[CST]| |NRC NOTIFIED BY: HOUSTON |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THE PLANT IS IN AN UNANALYZED CONDITION. | | | | THIS WAS DETERMINED DURING THE PERFORMANCE OF SPECIAL PROCEDURE(LST-96-070) | | WHEN THE AUX EQUIPMENT ROOM WAS FOUND NOT TO MEET THE 1/8" POSITIVE | | PRESSURE REQUIREMENT. IT HAS BEEN DETERMINED THAT IT IS POSSIBLE THAT THE | | GENERAL DESIGN CRITERIA 19 OF APPENDIX A OF 10CFR50 MAY NOT BE ADHERED TO. | | DUE TO THE ABOVE CONDITION, THE POSSIBILITY EXIST THAT THE PLANT IS IN AN | | UNANALYZED CONDITION. THE RI WAS INFORMED. | | | | * * * UPDATE AT 2122 EST ON 12/20/96 FROM R. CALVIN TAKEN BY KARSCH * * * | | AN INSPECTION OF THE DUCT WORK FOR THE AUXILIARY ELECTRIC EQUIPMENT ROOM | | VENTILATION SYSTEM REVEALED DAMAGE TO A SECTION ASSOCIATED WITH THE FAN | | RISERS. DUCT WORK WAS FOUND TO BE IMPLODED APPROXIMATELY 4 TO 6 INCHES TOP | | AND BOTTOM BEYOND ITS YIELD. ALL VENTILATION DUCT WORK THAT IS UNDER | | NEGATIVE PRESSURE WILL BE INSPECTED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. R3DO (HOLT) INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31487 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 12/20/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:30 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 13:20[EST]| |NRC NOTIFIED BY: VAN BLARCOM |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE OCEAN COUNTY, N.J., AND LOCAL TOWNSHIP GOVERNMENT | | THAT RAD MONITORS IN THEIR SEWER LINE WERE OUT OF SERVICE. NO RELEASE | | OCCURRED. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31488 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 12/20/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:17 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 12:27[CST]| |NRC NOTIFIED BY: ERIK MATZKE |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 +------------------------------------------------------------------------------+ | FOUR VALVES ACTUATED BY ESF SIGNALS COULD UNEXPECTEDLY CHANGE STATE WHEN | | THE ESF SIGNAL IS RESET. | | | | THE LICENSEE DETERMINED THAT SAFETY INJECTION (SI) CHECK VALVE LEAKAGE | | COOLER VALVES "PCV-2909, 2929, 2949, & 2969" COULD OPEN WHEN THE SI | | ACTUATION SIGNAL (SIAS) IS RESET. THE PROPER POST ACCIDENT POSITION FOR | | THESE VALVES IS THE CLOSED POSITION. SI FLOW IS MEASURED UPSTREAM OF THESE | | VALVES SO INDICATIONS WOULD SHOW SUFFICIENT INJECTION FLOW. HOWEVER, WITH | | THESE VALVES OPEN SIGNIFICANT FLOW COULD BE DIVERTED TO THE REACTOR COOLANT | | DRAIN TANK. THE DIVERSION OF FLOW COULD RESULT IN THE LOSS OF RCS | | INVENTORY FOR A SPECTRUM OF SMALL BREAK LOSS OF COOLANT ACCIDENTS (SB LOCA) | | WHICH HOLD RCS PRESSURE BETWEEN THE "SI-222" RELIEF VALVE PRESSURE OF 360 | | PSIG AND THE HPSI PUMP SHUTOFF HEAD OF APPROXIMATELY 1375 PSIG. | | | | THE LICENSEE HAS ISSUED AN OPERATIONS MEMORANDUM TO INFORM THE REACTOR | | OPERATORS OF THE SITUATION AND TO DIRECT THAT THE FUSES ASSOCIATED WITH THE | | SOLENOID CONTROL CIRCUIT BE PULLED BEFORE RESETTING THE ESF SIGNALS | | FOLLOWING A SB LOCA. THIS WILL PREVENT THE VALVES FROM OPENING ON ESF | | RESET. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31489 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/20/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:02 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 14:25[EST]| |NRC NOTIFIED BY: RAYMOND ALEJANDRO |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS FOUND THREE SECTIONS OF PIPING WHICH COULD BE | | OVERPRESSURIZED WHEN WATER TRAPPED BETWEEN CLOSED VALVES IS HEATED | | FOLLOWING A LOCA. | | | | THE FOLLOWING REPORT WAS RECEIVED FROM THE LICENSEE: | | "BASED UPON RESULTS OF PRELIMINARY EVALUATION BY ENGINEERING OF SHUTDOWN | | COOLING LINES INSIDE CONTAINMENT, IT WAS DETERMINED THAT THE PLANT WAS | | OPERATED OUTSIDE OF THE DESIGN BASIS. THE EVALUATION WAS BEING PERFORMED | | AS A RESULT OF NRC GENERIC LETTER 96-06. THE PRELIMINARY EVALUATION | | INDICATED THAT DURING THE DESIGN BASIS LOCA, WATER IN THESE LINES THAT IS | | TRAPPED BETWEEN THE ISOLATION VALVES WOULD HEAT UP AND EXPAND POTENTIALLY | | CAUSING PRESSURE IN THE PIPE TO EXCEED ALLOWABLE STRESSES. THE SYSTEM IS | | CURRENTLY OPERABLE BECAUSE CURRENT DOCUMENTED VALVE LEAKAGE IS SUFFICIENT | | TO MAINTAIN THE PENETRATION PIPING TEMPERATURE SUFFICIENTLY HOT SUCH THAT | | THE MAXIMUM PRESSURE POST LOCA IS MAINTAINED LESS THAN DESIGN PRESSURE. | | | | "IN ADDITION THE LINES FOR THE DRYWELL EQUIPMENT DRAIN AND FLOOR DRAIN ARE | | ALSO AFFECTED. THESE LINES ARE CONSIDERED OPERABLE BASED UPON THE | | CAPABILITY OF THE OUTBOARD ISOLATION VALVES TO RELIEVE PRESSURE IN THE | | LINES AND THUS PREVENT OPERPRESSURIZING THE PIPING. ADDITIONAL EVALUATIONS | | PER GENERIC LETTER 96-06 ARE CONTINUING." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31490 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 12/20/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:16 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 14:51[EST]| |NRC NOTIFIED BY: ED GOETCHES |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS SHUTTING DOWN PER TECH SPEC 3.0.1 BECAUSE THEY FOUND | | EVIDENCE OF AN UNISOLABLE LEAK IN A BRANCH LINE FROM THE PIPING BETWEEN THE | | RWST AND THE SI PUMP'S SUCTION. THIS LEAKAGE IS UNDETECTABLE BY DYE | | PENETRANT TESTING, BUT OVER THE LAST 10 DAYS A DIME SIZE SPOT OF BORIC ACID | | APPEARED ON THE PIPE AT A WELD AT AN ELBOW. | | | | THE LICENSEE HAS REQUESTED ENFORCEMENT DISCRETION REGARDING THE SHUTDOWN. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1745 EST FROM GOETCHES TAKEN BY KARSCH * * * | | SHUTDOWN TERMINATED AT 1656 EST. THE NRC GRANTED THE EXTENSION REQUEST | | BASED ON THE OVERALL GOOD CONDITION OF THE PIPE, THE SMALL SIZE OF THE LEAK | | AND THE PENDING SUBMISSION OF A FORMAL ACTION PLAN BY THE LICENSEE. THE | | LOWEST POWER REACHED WAS 50%. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. R1DO (BELLAMY) INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 31491 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AMERSHAM |NOTIFICATION DATE: 12/20/96 | | CITY: BURLINGTON REGION: 1 |NOTIFICATION TIME: 15:39 [ET]| | COUNTY: MIDDLESEX STATE: MA |EVENT DATE: 11/23/96 | |LICENSE#: 20-12830-01 AGREEMENT: N |EVENT TIME: : [EST]| | DOCKET: |LAST UPDATE DATE: 12/20/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RONALD BELLAMY RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ERIK OKVIST | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A PACKAGE CONTAINING 108 Ci OF Ir-192 IS BELIEVED TO BE STRANDED AT THE | | AIRPORT IN ALGIERS, ALGERIA (A FOREIGN COUNTRY). THE PERSON TO WHOM THE | | PACKAGE WAS SHIPPED FLED THE COUNTRY IN FEAR OF TERRORIST ATTACK WHILE THE | | PACKAGE WAS ENROUTE. THE LICENSEE HAS BEEN UNSUCCESSFUL IN THEIR ATTEMPTS | | TO CONVINCE THE LOCAL AIRLINE TO SEND THE PACKAGE BACK. THE LICENSEE HAS | | CONTACTED REGION 1 (ULRICH) REGARDING THIS PROBLEM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31492 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/20/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 15:28[EST]| |NRC NOTIFIED BY: A. FAULKNER |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAS IDENTIFIED A WATER HAMMER CONCERN AS A RESULT OF | | INVESTIGATIONS DIRECTED BY GENERIC LETTER 96-06. | | | | DURING EVALUATIONS OF WATER HAMMER CONCERNS IDENTIFIED IN GL 96-06, THE | | LICENSEE DETERMINED THAT PRIMARY CONTAINMENT INTEGRITY MIGHT BE JEOPARDIZED | | WHEN DRYWELL COOLER ISOLATION INTERLOCKS ARE DEFEATED IN ACCORDANCE WITH | | EOPs IN POST LOCA SCENARIOS. A WATER HAMMER MIGHT OCCUR IF THE VALVES ARE | | OPENED. DRYWELL COOLERS ARE NOT REQUIRED TO MITIGATE THE CONSEQUENCES OF A | | LOCA OR A MAIN STEAM LINE BREAK. THIS PIPING WAS NOT DESIGNED TO WITHSTAND | | THE EFFECTS OF WATER HAMMER AND COULD, THEREFORE, CHALLENGE CONTAINMENT | | INTEGRITY. ADMINISTRATIVE CONTROLS HAVE BEEN PUT IN PLACE TO PREVENT | | DEFEATING THE DRYWELL COOLER ISOLATION INTERLOCKS IN POST LOCA CONDITIONS. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31493 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/20/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:30 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 17:10[EST]| |NRC NOTIFIED BY: RODGER ORZELL |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DURING REVIEW FOR RESPONSE TO GENERIC LETTER 96-06, THE LICENSEE DETERMINED | | THAT THE PRESSURE DUE TO THE THERMAL EXPANSION OF ENTRAPPED WATER IN TWO | | DRYWELL PENETRATIONS COULD EXCEED DESIGN PRESSURE. THE AFFECTED SYSTEMS | | ARE THE PENETRATIONS TO THE DRYWELL UNIT COOLERS AND THE REACTOR | | RECIRCULATION PUMP SEAL COOLERS. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31494 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 12/20/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 +------------------------------------------------------------------------------+ | TWO CLEAN UP SYSTEM VALVES HAVE THERMAL OVERLOADS THAT MIGHT PREVENT THE | | VALVES FROM CLOSING UNDER THE HIGH TEMPERATURE CONDITIONS FOLLOWING A HIGH | | ENERGY LINE BREAK (HELB). | | | | IN RESPONSE TO GE SIL-604 "HIGH ENERGY LINE BREAK RESPONSE" THE LICENSEE | | DETERMINED THAT CLEAN UP SYSTEM VALVES "V-16-1 AND V-16-61" WOULD NOT | | ISOLATE UNDER ALL CONDITIONS. THE THERMAL OVERLOADS ARE NOT ADEQUATELY | | SIZED FOR PEAK TEMPERATURES WHICH COULD OCCUR FOLLOWING A HELB. THE SYSTEM | | IS CONSIDERED OPERABLE AS LONG AS THE REACTOR IS AT 100% POWER. THE SYSTEM | | WOULD ISOLATE ON LOW REACTOR VESSEL LEVEL BEFORE HIGH TEMPERATURES WOULD BE | | REACHED. HOWEVER, AT LOWER REACTOR POWER LEVELS THE FEED PUMPS MIGHT KEEP | | WATER LEVEL IN THE VESSEL UP LONG ENOUGH FOR THE TEMPERATURE LIMITS TO BE | | REACHED. AS A TEMPORARY FIX THE LICENSEE WILL JUMPER OUT THE THERMAL | | OVERLOADS. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31495 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/20/96 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 21:00 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 19:37[CST]| |NRC NOTIFIED BY: RODGER STOBERT |LAST UPDATE DATE: 12/21/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B.J. HOLT RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ECCS SYSTEMS MAY BE SUSCEPTIBLE TO NPSH PROBLEMS DUE TO SUCTION STRAINER | | DESIGN BEING BASED ON AN INCORRECT HEAD LOSS VALUE. | | | | THE UFSAR VALUE FOR HEAD LOSS ACROSS THE ECCS SUCTION STRAINERS IS | | APPARENTLY INCORRECT. UNDER CERTAIN CONDITIONS THE ECCS SYSTEMS MAY FAIL | | TO OPERATE AS INTENDED. THE LICENSEE IS CONDUCTING AN OPERABILITY | | DETERMINATION WITH ASSISTANCE FROM GENERAL ELECTRIC. | | | | BASED ON CALCULATIONS PERFORMED FOR RECENT NPSH EVALUATIONS, THERE MAY BE | | INSUFFICIENT NPSH AVAILABLE, USING A NEW CALCULATED VALUE FOR THE HEAD LOSS | | ACROSS THE SUCTION STRAINERS OF 5.5 FEET VS. THE CURRENT UFSAR VALUE OF 1 | | FOOT, WITHOUT TAKING CREDIT FOR CONTAINMENT PRESSURIZATION. WITHIN 24 | | HOURS THE LICENSEE WILL COMPLETE THEIR NPSH CALCULATIONS AND THEN THE | | OPERABILITY EVALUATION. REDESIGN OF THE SUCTION STRAINERS MAY BE REQUIRED. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2100 EST ON 12/21/96 FROM COYLE TAKEN BY KARSCH * * * | | THE LICENSEE HAS PERFORMED ADDITIONAL EVALUATIONS WHICH SHOW THAT | | SUFFICIENT OVERPRESSURE IS AVAILABLE TO PROVIDE ADEQUATE NPSH. THE | | METHODOLOGY CONFORMS TO BTP CSB 6-1 AND MINIMIZES THE CALCULATED | | OVERPRESSURE. THE EVALUATIONS SHOW THAT THE CORE SPRAY PUMPS WILL CAVITATE | | FOR THE FIRST TEN MINUTES, BUT WILL DELIVER THE REQUIRED FLOW RATES. THE | | LICENSEE HAS DOCUMENTED THE ACCEPTABILITY OF SHORT TERM CAVITATION. | | | | LONG TERM EVALUATIONS TAKE CREDIT FOR ACTIONS TO THROTTLE THE ECCS PUMPS | | BACK TO NORMAL FLOWS IF CAVITATION IS OBSERVED. AS PEAK SUPPRESSION POOL | | TEMPERATURE IS REACHED THE PUMPS MAY BEGIN TO CAVITATE AGAIN IF ALL SIX | | ECCS PUMPS ARE RUNNING. OPERATOR ACTION WILL BE TAKEN TO THROTTLE BACK | | LPCI PUMPS UNTIL NO CAVITATION IS OBSERVED. THE EVALUATION SHOWED THAT | | SUFFICIENT FLOW IS AVAILABLE WHEN THE PUMPS ARE THROTTLED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R3DO (HOLT) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31496 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 12/20/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 21:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/20/96 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: WILFRED CONNELL |LAST UPDATE DATE: 12/20/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | |VERN HODGE NRR | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WESTINGHOUSE DHP CIRCUIT BREAKERS FAILED TO CLOSE ON DEMAND DUE TO A DIRTY | | AND BINDING MOTOR CUT-OFF SWITCH AND SPRING CHARGE INDICATOR MECHANISM. THE | | VENDOR LITERATURE FAILED TO PROVIDE GUIDANCE FOR INSPECTING, CLEANING, | | ADJUSTING, OR LUBRICATING THESE VITAL COMPONENTS. THE LICENSEE HAS | | EVALUATED THIS ISSUE AND CONCLUDES THAT IT IS REPORTABLE UNDER THE | | PROVISIONS OF 10 CFR PART 21. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31497 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 12/21/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 04:44 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 12/21/96 | +------------------------------------------------+EVENT TIME: 04:05[EST]| |NRC NOTIFIED BY: NELSON |LAST UPDATE DATE: 12/21/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BELLAMY 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 +------------------------------------------------------------------------------+ | UNIT OUTSIDE DESIGN BASIS DUE TO CONCERNS WITH BWST SWITCHOVER ANALYSIS | | | | THE LICENSEE RECENTLY PERFORMED A REVISED, MORE CONSERVATIVE, REACTOR | | BUILDING PRESSURE ANALYSIS WHICH ASSUMED MAXIMUM COOLING OF REACTOR | | BUILDING AIR SPACES, RESULTING IN LOWER PRESSURES. THE REVISED AIR PRESSURE | | RESULTS WERE THEN USED AS ASSUMPTIONS FOR A NEW ECCS BORATED WATER | | SWITCHOVER ANALYSIS. THE RESULTS OF THIS ANALYSIS INDICATED THAT EXISTING | | PLANT PROCEDURES FOR ECCS SWITCHOVER FROM THE BWST TO THE REACTOR BUILDING | | SUMP COULD RESULT IN INSUFFICIENT NET POSITIVE SUCTION HEAD (NPSH) FOR ECCS | | PUMPS DUE TO DECREASED AIRSPACE OVERPRESSURIZATION. | | | | THE LICENSEE HAS DECLARED THE ECCS INOPERABLE, AND IS PRESENTLY DEVELOPING | | REVISED PROCEDURES FOR BWST SWAPOVER TO ADDRESS THE NPSH CONCERNS. THE | | LICENSEE STATED THAT THESE REVISED PROCEDURES SHOULD BE COMPLETED SHORTLY. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31498 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 12/22/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/22/96 | +------------------------------------------------+EVENT TIME: 13:18[CST]| |NRC NOTIFIED BY: RON JACKSON |LAST UPDATE DATE: 12/22/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY REPORT IN CONFORMANCE WITH 10CFR73.71 APP G, INTRODUCTION OF | | CONTRABAND MATERIAL INTO THE PROTECTED AREA. A SEMI-AUTOMATIC PISTOL WAS | | FOUND IN A TRUCK UNDERGOING INSPECTION PRIOR TO ENTRY INTO THE PROTECTED | | AREA. THE LICENSEE DOES NOT BELIEVE THERE WAS ANY MALICIOUS INTENT ON THE | | PART OF THE DRIVER. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31499 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/22/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 23:18 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/22/96 | +------------------------------------------------+EVENT TIME: 19:56[EST]| |NRC NOTIFIED BY: JEFF KLENK |LAST UPDATE DATE: 12/22/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 2 STARTUP | 2 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC STEAM LINE INBOARD ISOLATION VALVE CLOSED UNEXPECTEDLY DURING STEAM | | LINE WARMING. | | | | INBOARD STEAM LINE ISOLATION VALVE HV49-2F007 RECEIVED AN ISOLATION SIGNAL | | AS THE VALVE WAS BEING INITIALLY BUMPED OPEN FOR STEAM LINE WARM UP. THE | | VALVE AUTOMATICALLY CLOSED, POSSIBLY DUE TO A HIGH STEAM FLOW SIGNAL. THE | | HIGH STEAM FLOW MAY HAVE BEEN CAUSED BY CONDENSATION IN THE STILL COOL | | STEAM LINE. THE ISOLATION VALVE WAS SUCCESSFULLY OPENED AT 2130EST. | | | | THE LICENSEE IS CONTINUING TO EVALUATE THE REPORTABILITY OF THIS EVENT. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+