U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/28/97 - 10/29/97 ** EVENT NUMBERS ** 33130 33159 33160 33161 33162 33163 33164 33165 33166 33167 33168 33169 33170 33171 33172 33173 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33130 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/22/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:14 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:21[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/29/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |GEOFFREY WRIGHT RDO | | DOCKET: 0707001 |JOHN GREEVES EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MIKE UNDERWOOD | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE ISOLATED ON HIGH STEAM PRESSURE | | | | THE STEAM PRESSURE CONTROL SYSTEM ACTUATED ON AUTOCLAVE 3 SOUTH IN C-333-A | | AT 2305 ON 10/21/97. ACTUATION OF THE STEAM PRESSURE CONTROL SYSTEM | | RESULTS IN THE AUTOMATIC CLOSURE OF THE STEAM VALVES SERVING THE AUTOCLAVE. | | | | AUTOCLAVE 3 SOUTH WAS THE SUBJECT OF ANOTHER EVENT REPORT BECAUSE OF A UF6 | | LEAK, REPORTED TO THE NRC ON 10/7/97. THIS AUTOCLAVE HAD BEEN SHUTDOWN AND | | WAS RESTARTED A FEW HOURS PRIOR TO THIS EVENT. | | | | SYSTEMS ENGINEERING IS INVESTIGATING THE ACTUATION. | | | | THE NRC RESIDENT HAS BEEN INFORMED OF THE EVENT. | | | | * * * UPDATE AT 0026 ON 10/29/97 BY W. CAGE, ENTERED BY FANGIE JONES * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE RESULTS OF THEIR | | INVESTIGATION. " SPECIFICALLY, THE HIGH PRESSURE SWITCH (PSH-515), WHICH IS | | DESIGNED TO ACTUATE AT 7 PSIG, WAS FOUND TO BE SET AT APPROXIMATELY 1.5 | | PSIG. THUS THE SYSTEM ACTUATED WELL BELOW THE DESIGNED SET POINT FROM AN | | INVALID SIGNAL." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER INFORMED R3DO RONALD GARDNER AND NMSS EO MARGARET | | FEDERLINE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33159 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 10:26 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 09:05[CST]| |NRC NOTIFIED BY: TIM BORGEN |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STU RICHARDS, NRR EO | | |BAGWELL FEMA | | |RICH BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNUSUAL EVENT DECLARED DUE TO ONSITE FIRE LASTING LONGER THAN 10 MINUTES- | | | | AT 0846 CST, A FIRE IGNITED IN THE CUTTING TABLE HOOD IN THE MAINTENANCE | | SHOP IN THE TURBINE BUILDING. THE ONSITE FIRE BRIGADE AND THE OFFSITE RED | | WING FIRE DEPARTMENT RESPONDED TO FIGHT THE FIRE. | | | | AT 0905 CST, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO AN ONSITE FIRE | | LASTING LONGER THAN 10 MINUTES. | | | | AT 0915 CST, THE FIRE (LASTED FOR 29 MINUTES) WAS EXTINGUISHED USING WATER. | | THERE WERE NO PERSONNEL INJURIES. THERE WAS NO DAMAGE TO SAFETY RELATED | | EQUIPMENT AND NO IMPACT ON PLANT OPERATIONS. THE LICENSEE HAS POSTED A | | REFLASH WATCH. THE LICENSEE IS TAKING AIR SAMPLES TO DETERMINE AIR QUALITY | | AND IS INVESTIGATING THE CAUSE. | | | | THE LICENSEE NOTIFIED STATE & LOCAL OFFICIALS & THE NRC RESIDENT INSPECTOR | | OF THE DECLARATION OF THE UNUSUAL EVENT AND WILL ISSUE A PRESS RELEASE. | | | | * * * UPDATE AT 1108 FROM TIM BERGEN ENTERED BY JOLLIFFE * * * | | | | AT 0950 CST, THE LICENSEE TERMINATED THE UNUSUAL EVENT DUE TO ACCEPTABLE | | AIR QUALITY AND ADEQUATE HABITABILITY IN THE TURBINE BUILDING. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE TERMINATION OF THE UNUSUAL EVENT. | | | | THE OPERATIONS OFFICER NOTIFIED THE R3DO RON GARDNER, NRR EO STU RICHARDS, | | AND FEMA BAGWELL OF THE TERMINATION OF THE UNUSUAL EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33160 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 12:30[CST]| |NRC NOTIFIED BY: MARK SMITH |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "WESTINGHOUSE REPORTED TO COMMONWEALTH EDISON BYRON STATION THAT CURRENT | | MODELING FOR FUEL DESIGN DEMONSTRATES THAT THERE IS A POTENTIAL TO NOT MEET | | THE 10CFR50.46 DESIGN CRITERIA FOR MAXIMUM CLADDING OXIDATION OF 17% FOR | | TWICE BURNED INTEGRAL FUEL BURNABLE ABSORBER (IFBA) FUEL. OPERATING FUEL | | REGIONS MAY POTENTIALLY EXCEED THE GAP REOPENING DESIGN CRITERION. | | ADDITIONALLY, IF THE GAP REOPENING DESIGN CRITERION IS EXCEEDED, THE LOSS | | OF COOLANT ACCIDENT (LOCA) 17% LOCAL OXIDATION CRITERION FOLLOWING A | | POSTULATED LOCA EVENT MAY LIKEWISE BE EXCEEDED. WESTINGHOUSE HAS REPORTED | | THIS AS A GENERIC ISSUE TO THE NRC AND HAS SUPPLIED INFORMATION FOR A | | GENERIC JUSTIFICATION FOR CONTINUED OPERATION (JCO) FOR AFFECTED PLANTS. IN | | ITS JCO WESTINGHOUSE HAS CONCLUDED THAT A SUBSTANTIAL SAFETY HAZARD DOES | | NOT EXIST FOR OPERATING PLANTS. THE BASIS FOR THIS DETERMINATION IS THAT | | SHUTDOWN CAPABILITY WILL NOT BE HINDERED, COOLABLE GEOMETRY WILL BE | | MAINTAINED TO THE EXTENT REQUIRED IN ALL DESIGN BASIS ACCIDENTS AND | | 10CFR100 OFFSITE DOSE LIMITS WILL BE MET SINCE ADDITIONAL FUEL FAILURES ARE | | NOT EXPECTED. THIS IS BEING REPORTED BY BYRON STATION AS A CONDITION | | POTENTIALLY OUTSIDE THE DESIGN BASIS OF THE PLANT. WESTINGHOUSE IS | | CONTINUING TO EVALUATE THEIR MODEL AND WILL BE WORKING WITH THE UTILITY TO | | PERFORM AN INDIVIDUAL PLANT DETERMINATION." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33161, 33163 TO 33170, AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33161 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:30 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 12:35[CST]| |NRC NOTIFIED BY: DAVE KRUCK |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "WESTINGHOUSE REPORTED TO COMMONWEALTH EDISON BRAIDWOOD STATION THAT | | CURRENT MODELING FOR FUEL DESIGN DEMONSTRATES THAT THERE IS A POTENTIAL TO | | NOT MEET THE 10CFR50.46 DESIGN CRITERIA FOR MAXIMUM CLADDING OXIDATION OF | | 17% FOR TWICE BURNED INTEGRAL FUEL BURNABLE ABSORBER (IFBA) FUEL. OPERATING | | FUEL REGIONS MAY POTENTIALLY EXCEED THE GAP REOPENING DESIGN CRITERION. | | ADDITIONALLY, IF THE GAP REOPENING DESIGN CRITERION IS EXCEEDED, THE LOSS | | OF COOLANT ACCIDENT (LOCA) 17% LOCAL OXIDATION CRITERION FOLLOWING A | | POSTULATED LOCA EVENT MAY LIKEWISE BE EXCEEDED. WESTINGHOUSE HAS REPORTED | | THIS AS A GENERIC ISSUE TO THE NRC AND HAS SUPPLIED INFORMATION FOR A | | GENERIC JUSTIFICATION FOR CONTINUED OPERABILITY (JCO) FOR AFFECTED PLANTS. | | IN ITS JCO WESTINGHOUSE HAS CONCLUDED THAT A SUBSTANTIAL SAFETY HAZARD DOES | | NOT EXIST FOR OPERATING PLANTS. THE BASIS FOR THIS DETERMINATION IS THAT | | SHUTDOWN CAPABILITY WILL NOT BE HINDERED, COOLABLE GEOMETRY WILL BE | | MAINTAINED TO THE EXTENT REQUIRED IN ALL DESIGN BASIS ACCIDENTS AND | | 10CFR100 OFFSITE DOSE LIMITS WILL BE MET SINCE ADDITIONAL FUEL FAILURES ARE | | NOT EXPECTED. THIS IS BEING REPORTED BY BRAIDWOOD STATION AS A CONDITION | | POTENTIALLY OUTSIDE THE DESIGN BASIS OF THE PLANT. WESTINGHOUSE IS | | CONTINUING TO EVALUATE THEIR MODEL AND WILL BE WORKING WITH THE UTILITY TO | | PERFORM AN INDIVIDUAL PLANT DETERMINATION." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33163 TO 33170, AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33162 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ISOTOPE PRODUCTS LABORATORIES |NOTIFICATION DATE: 10/28/97 | | CITY: BURBANK REGION: 4 |NOTIFICATION TIME: 15:00 [ET]| | COUNTY: LOS ANGELES STATE: CA |EVENT DATE: 07/22/97 | |LICENSE#: CA 1509-19 AGREEMENT: Y |EVENT TIME: 00:00[PST]| | DOCKET: |LAST UPDATE DATE: 10/28/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE YANDELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: KEVIN RAMSEY (NMSS) | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | |NINF INFORMATION ONLY | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE CALIFORNIA DEPARTMENT OF HEALTH SERVICES, RADIOLOGIC HEALTH BRANCH | | (RHB), ISSUED THE FOLLOWING PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL | | OCCURRENCE: | | | | "THIS PRELIMINARY NOTIFICATION CONSTITUTES EARLY NOTICE OF AN INTERNAL | | EXPOSURE TO A WORKER THAT MAY BE IN EXCESS OF THE REGULATORY REQUIREMENTS. | | THIS INFORMATION IS AS INITIALLY RECEIVED WITHOUT VERIFICATION OR | | EVALUATION BY THE RADIOLOGIC HEALTH BRANCH, CALIFORNIA DEPARTMENT OF HEALTH | | SERVICES. | | | | LICENSEE: | | | | ISOTOPE PRODUCTS LABORATORIES | | 1800 N. KEYSTONE STREET | | BURBANK, CA | | LICENSE NO: 1509-19 | | | | "SUBJECT: NOTIFICATION OF A TEDE >5 REMS TO A RADIATION WORKER UNDER THIS | | LICENSE | | | | "THE ACTIVITY WAS MANUFACTURING OF A 10 MICROCURIE AM-241 SOURCE IN A HOOD. | | THE SOURCE WAS DEPOSITED ON A CANE WHICH WAS FIRED IN THE HOOD. THERE WAS | | POTENTIAL FOR AIRBORNE RELEASE TO THE WORK AREA FROM THIS ACTIVITY. THE | | LICENSEE STATES FIRING OF DEPOSITED AM-241 IS DONE IN A CONTAINER WHILE | | INSIDE A FUME HOOD. | | | | "ON JULY 22, 1997, A ROUTINE TRANSURANIC URINE BIOASSAY WAS COUNTED AND THE | | INTERNAL EXPOSURE WAS DISCOVERED. A FOLLOW-UP BIOASSAY ON AUGUST 29, 1997 | | SUBSTANTIATED THE FIRST RESULT. RESULTS WERE 22% HIGHER THAN THE FIRST | | BIOASSAY. A THIRD BIOASSAY IS NOW IN PROGRESS, RESULTS ARE NOT YET KNOWN. | | | | "PRELIMINARY DOSE ASSESSMENT: | | | | "DEPENDING ON THE DATE OF THE INITIAL UPTAKE, THIS EXPOSURE RANGE IS FROM | | 0.9 TO 14.2 NANOCURIES AM-241. THE REGULATORY LIMIT IS 6 NANOCURIES, | | (ALI). THEREFORE, THIS EXPOSURE RANGE IS FROM 900 MREMS TO 11,850 MREMS. | | | | "STATUS: A COMPLETE INVESTIGATION BY RHB HAS BEEN INITIATED. THE | | INDIVIDUAL EXPOSED ALSO RECEIVED A 15 NANOCURIE AM-241 OVEREXPOSURE IN MAY, | | 1995. THE USE OF A WHOLE-BODY COUNTER AND CONSULTATION BY AN INTERNAL | | DOSIMETRIST IS ALSO BEING CONSIDERED FOR A MORE DEFINITIVE DOSE ESTIMATE." | | | | SEE HOO LOG FOR CONTACT INFORMATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:14 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 12:30[EST]| |NRC NOTIFIED BY: DOUGLAS J. GOMEZ |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "ROCHESTER GAS & ELECTRIC PERSONNEL WERE NOTIFIED BY REPRESENTATIVES OF | | WESTINGHOUSE ELECTRIC CORPORATION THAT CERTAIN LIMITS ESTABLISHED IN THE | | CURRENTLY LICENSED PAD CODE FOR FUEL ROD DESIGN MAY HAVE BEEN EXCEEDED. THE | | WESTINGHOUSE CRITERIA EXCEEDED IS ROD INTERNAL PRESSURE WHICH AFFECTS THE | | ASSUMPTION THAT THE FUEL PELLET TO CLAD GAP SHALL NOT REOPEN OVER THE FUEL | | ASSEMBLY LIFETIME. IN ADDITION, THE 17% CLAD OXIDATION LIMIT AS DESCRIBED | | IN 10CFR50.46 MAY ALSO HAVE BEEN IMPACTED. IT IS OUR UNDERSTANDING THAT | | NRC REPRESENTATIVES HAVE PREVIOUSLY BEEN APPRAISED OF THIS CONDITION ON A | | GENERIC BASIS BY WESTINGHOUSE PERSONNEL." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33161, 33164 TO 33170, AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33164 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/28/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:20 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: MELISSA STREIBER |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "IN ACCORDANCE WITH 10CFR50.72(b)(2)(i), THE FOLLOWING REPORT IS BEING: | | CON EDISON WAS NOTIFIED TODAY BY WESTINGHOUSE ELECTRIC CORPORATION THAT | | CALCULATIONS PERFORMED BY WESTINGHOUSE FOR FUEL SUPPLIED TO INDIAN POINT | | UNIT 2 MAY NOT BE CONSERVATIVE. SPECIFICALLY, WESTINGHOUSE BELIEVES THAT | | IN VERY LIMITING CASES FOR HIGH POWER, HIGH BURNUP ZIRCALOY-4 CLAD | | IFBA-CONTAINING FUEL RODS, CALCULATED PRESSURES ARE IN EXCESS OF THE | | WESTINGHOUSE FUEL ROD DESIGN CRITERION THAT 'THE FUEL ROD PELLET-TO-CLAD | | GAP SHALL NOT RE-OPEN.' IN ADDITION, IF THE 'NO GAP RE-OPENING' CRITERION | | IS EXCEEDED, THE 17% CLAD OXIDATION LIMIT FOLLOWING A POSTULATED LOCA | | EVENT, AS DEFINED IN 10CFR50.46, CAN LIKEWISE BE EXCEEDED. | | | | "THIS NOTIFICATION BY WESTINGHOUSE WAS AS A RESULT OF NEW DATA ON | | ZIRCALOY-4 CORROSION AND CONSERVATIVE ASSUMPTIONS ON GAS RELEASE AND OTHER | | RELEVANT PARAMETERS FOR ZIRCONIUM DIBORIDE INTEGRAL FUEL BURNABLE ABSORBER | | (IFBA) FUEL RODS, IN CONJUNCTION WITH CORRECTIONS MADE TO RECENTLY | | IDENTIFIED DISCREPANCIES IN THE LICENSED VERSION OF THE PAD CODE. | | | | "THE WESTINGHOUSE NOTIFICATION IS GENERIC IN NATURE, AND DOES NOT REPRESENT | | A PLANT SPECIFIC DETERMINATION FOR INDIAN POINT UNIT 2. PLANT SPECIFIC | | REVIEW WILL BE PERFORMED, AND IN THE INTERIM, WESTINGHOUSE HAS PROVIDED A | | JUSTIFICATION FOR CONTINUED OPERATION WHICH CONCLUDES THAT A SUBSTANTIAL | | SAFETY HAZARD DOES NOT EXIST." THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33161, 33163, 33165 TO 33170, AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33165 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/28/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 16:50 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 16:33[EST]| |NRC NOTIFIED BY: STEVE DAVIS |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "ON OCTOBER 28, 1997 AT APPROXIMATELY 1633, THE POWER AUTHORITY DETERMINED, | | BASED ON INFORMATION PROVIDED BY WESTINGHOUSE, THAT INDIAN POINT 3 COULD | | POTENTIALLY BE IN A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT AT SOME | | POINT IN THE OPERATING CYCLE. THE CURRENT DEVELOPMENTAL MODEL OF THE | | WESTINGHOUSE PAD CODE INDICATES A POTENTIAL PHENOMENA ('GAP RE-OPENING') | | THAT COULD CAUSE THE 17 PERCENT CLAD OXIDATION LIMIT OF THE 10CFR50.46 TO | | BE EXCEEDED FOR HIGHER BURNUP INTEGRAL FUEL BURNABLE ABSORBER (IFBA) FUEL | | RODS. THIS ISSUE IS STILL BEING EVALUATED BY BOTH THE POWER AUTHORITY AND | | WESTINGHOUSE." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33161, 33163, 33164, 33166 TO 33170 AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33166 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 17:08 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 14:15[CST]| |NRC NOTIFIED BY: RANDY JOHNSON |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "CURRENT WESTINGHOUSE NRC APPROVED METHODOLOGY FOR DETERMINATION OF FUEL | | ROD INTERNAL PRESSURE AND CLADDING CORROSION WAS FOUND TO BE NOT AS | | CONSERVATIVE AS PREVIOUSLY BELIEVED. AS A RESULT CALCULATION OF 10CFR50.46 | | ECCS ACCEPTANCE CRITERIA MAY BE AFFECTED. THE MAGNITUDE OF THIS EFFECT HAS | | NOT BEEN SPECIFICALLY CALCULATED FOR FARLEY NUCLEAR PLANT. THIS | | DETERMINATION IS BASED ON NEWER MODELS STILL UNDER DEVELOPMENT BY | | WESTINGHOUSE. THE NEWER MODELS ARE BELIEVED BY WESTINGHOUSE TO MORE | | ACCURATELY PREDICT FUEL CLADDING BEHAVIOR. THE EFFECT OF THIS EVALUATION | | IS TO SHOW THAT POTENTIALLY FOR LBLOCA THE 17% CLADDING OXIDATION | | REQUIREMENT OF 10CFR50.46 MAY NOT BE MET. 'BEST ESTIMATE' CALCULATIONS | | PERFORMED BY WESTINGHOUSE HAS DETERMINED THAT THIS CONDITION DOES NOT | | REPRESENT A CONDITION THAT SIGNIFICANTLY COMPROMISES PLANT SAFETY AND THAT | | IT DOES NOT REPRESENT A SUBSTANTIAL SAFETY HAZARD. THE BASIS FOR THIS | | CONCLUSION IS THAT A PLANT COULD BE SHUTDOWN SAFELY, SINCE PLANT CONTROL | | MECHANISMS WOULD FUNCTION PROPERLY AND A 'COOLABLE GEOMETRY' IN THE SENSE | | REQUIRED FOR LOCA PROTECTION WOULD BE MAINTAINED. IN ADDITION 10CFR100 | | LIMITS FOR OFFSITE DOSE WOULD NOT BE EXCEEDED IN ANY POSTULATED EVENT. | | | | "WESTINGHOUSE HAS NOTIFIED THE NRC OF THIS ISSUE AND IS CURRENTLY | | ADDRESSING FUEL PERFORMANCE ANALYSIS METHODOLOGY TO REFINE THEIR MODEL AND | | RESOLVE THIS ISSUE. WESTINGHOUSE HAS ALSO DETERMINED THAT THIS ISSUE IS | | NOT REPORTABLE PER 10CFR21 REQUIREMENTS. THE LICENSEE IS MAKING THIS | | VOLUNTARY REPORT BECAUSE THIS ISSUE MIGHT BE OF GENERIC INTEREST OR | | CONCERN." THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | HOO NOTE: SEE EVENT #33160, 33161, 33163 TO 33165, 33167 TO 33170 & 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33167 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 14:30[CST]| |NRC NOTIFIED BY: CURTIS BASNER |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "10CFR50.46 (ACCEPTANCE CRITERIA FOR EMERGENCY CORE COOLING SYSTEMS FOR | | LIGHT-WATER REACTORS) REQUIRES MAXIMUM CLADDING OXIDATION TO NOT EXCEED 17% | | OF THE TOTAL CLADDING THICKNESS BEFORE OXIDATION." | | | | "WESTINGHOUSE ANALYSIS SHOWS THAT FOR HIGH POWER, HIGH BURNUP ASSEMBLY | | INTEGRAL FUEL BURNABLE ABSORBER (IFBA) FUEL RODS, CALCULATED ROD INTERNAL | | PRESSURE ARE IN EXCESS OF THE WESTINGHOUSE FUEL ROD DESIGN CRITERION THAT | | 'THE FUEL ROD PELLET-TO-CLAD GAP SHALL NOT RE-OPEN.'" | | | | "ADDITIONALLY, IF THE 'NO-GAP RE-OPENING' CRITERION IS EXCEEDED, THE 17% | | CLAD OXIDATION LIMIT FOLLOWING A POSTULATED LOCA EVENT, AS DEFINED IN | | 10CFR50.46, CAN LIKEWISE BE EXCEEDED." | | | | "THE MOST LIMITING CASE CALCULATED BY WESTINGHOUSE IS FOR 17X17 [OPTIMIZED | | FUEL ASSEMBLY] FUEL WITH 1.5XIFBA COATING. WESTINGHOUSE HAS NOT PERFORMED | | DETAILED ANALYSIS FOR 15X15 FUEL WITH 1.0XIFBA COATING WHICH IS CURRENTLY | | UTILIZED AT ZION. HOWEVER, FOR ZION, WESTINGHOUSE HAS NOT RULED OUT THE | | POSSIBILITY OF POTENTIALLY BEING OUTSIDE THE 10CFR50.46 CRITERIA." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33161, 33163 TO 33166, 33168 TO 33170 & 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33168 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 17:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 17:23[EST]| |NRC NOTIFIED BY: D.T. McCARY |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "CURRENT WESTINGHOUSE NRC APPROVED METHODOLOGY FOR DETERMINATION OF FUEL | | ROD INTERNAL PRESSURE AND CLADDING CORROSION WAS FOUND TO BE NOT AS | | CONSERVATIVE AS PREVIOUSLY BELIEVED. AS A RESULT, CALCULATION OF | | 10CFR50.46 ECCS ACCEPTANCE CRITERIA MAY BE AFFECTED. THE MAGNITUDE OF THIS | | EFFECT HAS NOT BEEN SPECIFICALLY CALCULATED FOR PLANT VOGTLE. THIS | | DETERMINATION IS BASED ON NEWER MODELS STILL UNDER DEVELOPMENT BY | | WESTINGHOUSE. THE NEWER MODELS ARE BELIEVED BY WESTINGHOUSE TO MORE | | ACCURATELY PREDICT FUEL CLADDING BEHAVIOR. THE EFFECT OF THIS EVALUATION | | IS TO SHOW THAT POTENTIALLY FOR LBLOCA, THE 17% CLADDING OXIDATION | | REQUIREMENT OF 10CFR50.46 MAY NOT BE MET. 'BEST ESTIMATE' CALCULATIONS | | PERFORMED BY WESTINGHOUSE HAVE DETERMINED THAT THIS CONDITION DOES NOT | | REPRESENT A CONDITION THAT SIGNIFICANTLY COMPROMISES PLANT SAFETY AND THAT | | IT DOES NOT REPRESENT A SUBSTANTIAL SAFETY HAZARD. THE BASIS FOR THIS | | CONCLUSION IS THAT A PLANT COULD BE SHUTDOWN SAFELY, SINCE PLANT CONTROL | | MECHANISMS WOULD FUNCTION PROPERLY AND A 'COOLABLE GEOMETRY' IN THE SENSE | | REQUIRED FOR LOCA PROTECTION WOULD BE MAINTAINED. IN ADDITION 10CFR100 | | LIMITS FOR OFFSITE DOSE WOULD NOT BE EXCEEDED IN ANY POSTULATED EVENT. | | | | "WESTINGHOUSE HAS NOTIFIED THE NRC OF THIS ISSUE AND IS CURRENTLY | | ADDRESSING FUEL PERFORMANCE ANALYSIS METHODOLOGY TO REFINE THEIR MODEL AND | | RESOLVE THIS ISSUE. WESTINGHOUSE HAS ALSO DETERMINED THAT THIS ISSUE IS | | NOT REPORTABLE PER 10CFR21 REQUIREMENTS. THE LICENSEE IS MAKING THIS | | VOLUNTARY REPORT BECAUSE THIS ISSUE MIGHT BE OF GENERIC INTEREST OR | | CONCERN." THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | HOO NOTE: SEE EVENT #33160, 33161, 33163 TO 33167, 33169, 33170 AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33169 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 17:45 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 17:30[EST]| |NRC NOTIFIED BY: MIKE DAVID |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "NORTH ATLANTIC ENERGY SERVICE CORPORATION (NORTH ATLANTIC), THE OPERATOR | | OF SEABROOK STATION, HEREBY MAKES THE FOLLOWING ONE HOUR NON-EMERGENCY | | REPORT PURSUANT TO 10CFR50.72(b)(1)(ii)(B), AS A CONSERVATIVE MEASURE, | | FOR A CONDITION THAT MAY BE OUTSIDE THE DESIGN BASIS OF THE PLANT. | | | | "ON 10/28/97, WESTINGHOUSE INFORMED NORTH ATLANTIC THAT WHILE UPDATING THE | | PAD CODE FOR FUEL PERFORMANCE, IT WAS DETERMINED THAT THE DEVELOPMENTAL | | MODEL OF THE CODE CALCULATES REDUCED FUEL ROD INTERNAL PRESSURE MARGINS | | WHEN COMPARED TO THE PREVIOUSLY LICENSED CODE. WESTINGHOUSE HAS DETERMINED | | THAT IN VERY LIMITING CASES FOR HIGH POWER, HIGH BURNUP INTEGRAL FUEL | | BURNABLE ABSORBER (IFBA) CONTAINING FUEL RODS, CALCULATED PRESSURES ARE IN | | EXCESS OF THE FUEL ROD DESIGN CRITERION THAT THE FUEL ROD PELLET TO CLAD | | GAP SHALL NOT REOPEN. ADDITIONALLY, IF THE NO GAP RE-OPENING CRITERION IS | | EXCEEDED, THE 17% CLAD OXIDATION LIMIT FOLLOWING A POSTULATED LOCA EVENT, | | AS DEFINED IN 10CFR50.46, CAN LIKEWISE BE EXCEEDED. | | | | "WESTINGHOUSE HAS NOT PERFORMED ANY PLANT SPECIFIC ANALYSES TO CONCLUDE | | THAT THIS CONDITION IS APPLICABLE TO SEABROOK STATION. HOWEVER, THEY HAVE | | NOTIFIED LICENSEES, ON A GENERIC BASIS, OF THE POTENTIAL CONDITION AND | | PROVIDED A RATIONALE FOR WHY THE CONDITION DOES NOT AFFECT CONTINUED | | OPERATION OF THE FACILITY. IT IS WESTINGHOUSE'S JUDGMENT THAT THIS | | CONDITION POSES NO ADVERSE SAFETY OR RELIABILITY CONCERNS. NORTH ATLANTIC | | WILL CONTINUE TO INVESTIGATE THIS CONDITION." THE LICENSEE INFORMED THE | | NRC RESIDENT INSPECTOR. | | HOO NOTE: SEE EVENT #33160, 33161, 33163 TO 33168, 33170, AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33170 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:53 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 15:53[CST]| |NRC NOTIFIED BY: JOHN A. SCHROEDER |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "THIS REPORT IS PROVIDED FOR INFORMATION. INFORMATION WAS RECEIVED TODAY | | FROM OUR NSSS SUPPLIER THAT BASED UPON A NEW CONSERVATIVE COMPUTER MODEL, | | THERE IS POTENTIAL FOR OUR FUEL ASSEMBLIES CONTAINING INTEGRAL FUEL | | BURNABLE ABSORBER (IFBA) FUEL RODS TO EXCEED THE 10CFR50.46 LOCAL OXIDATION | | CRITERIA OF 17%, FOLLOWING A LARGE BREAK LOCA. BASED UPON THE MODELING, | | THE OPERATING FUEL REGIONS MAY POTENTIALLY EXCEED THE GAP REOPENING | | CRITERIA AS WELL. THE CODE USED BY THE VENDOR IS VERY CONSERVATIVE, | | HOWEVER, USING THE CODE AND ITS CONSERVATIVE MODEL THERE IS THE POTENTIAL | | THAT HIGH BURNUP FUEL MAY EXHIBIT THESE CONDITION. THE VENDOR HAS REVIEWED | | THESE CONDITIONS AND HAS CONCLUDED THAT IT DOES NOT REPRESENT A SUBSTANTIAL | | SAFETY HAZARD NOR IS IT REPORTABLE UNDER 10CFR21. THE VENDOR IS NOTIFYING | | THE NRC AND ALL ITS CUSTOMERS WITH IFBA FUEL RODS. THE VENDOR HAS ALSO | | DEVELOPED A GENERIC JUSTIFICATION FOR CONTINUED OPERATION. THIS REPORT | | WILL BE FOLLOWED WITH ADDITIONAL INFORMATION, AS APPROPRIATE. THIS IS A | | POTENTIAL 10CFR50.72(b)(1)(ii)(B), 'OUTSIDE DESIGN BASIS,' CONDITION. IF | | THE INFORMATION IS SUBSTANTIATED FOR THE SPECIFIC FUEL DESIGN AND BURNUP | | FOR POINT BEACH, A FORMAL 10CFR50.72 REPORT WILL BE MADE." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33161, 33163 TO 33169, AND 33172. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33171 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 18:25 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 18:00[EST]| |NRC NOTIFIED BY: DONALD HART |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED SEVERAL EQ BARRIER AREA ACCESS DOORS WHICH ELECTRICALLY | | FAIL IN THE UNLOCKED INSTEAD OF THE LOCKED CONDITION. | | | | "WITH UNIT 1 AT 100% POWER AND UNIT 2 IN THE PROCESS OF STARTUP FOLLOWING | | COMPLETION OF A SCHEDULED REFUELING OUTAGE, A REVIEW OF SECURITY LOCKS ON | | THE EMERGENCY DIESEL GENERATOR ACCESS DOORS AND THE ACCESS DOOR TO THE | | EMERGENCY SWITCHGEAR ROOM FROM THE UNIT 1 TURBINE BUILDING REVEALED THAT | | THE DOOR LATCHES ELECTRICALLY FAIL IN THE UNLOCKED CONDITION. THESE | | SUBJECT DOORS ALSO FUNCTION AS ENVIRONMENTAL QUALIFICATION (EQ) BARRIERS. | | IF THIS CONDITION WERE TO EXIST AND A HIGH ENERGY LINE BREAK (HELB) | | WERE TO OCCUR IN THE TURBINE BUILDING, THESE AREAS COULD BE AFFECTED, | | THUS RESULTING IN THE STATION BEING IN AN UNANALYZED CONDITION THAT | | SIGNIFICANTLY COMPROMISES STATION SAFETY. CURRENTLY, THESE DOOR LATCHES | | ARE ENERGIZED AND THE DOORS ARE CAPABLE OF SERVING THEIR EQ FUNCTION. | | | | "THE DOOR TO THE EMERGENCY SWITCHGEAR ROOM IS BEING DEAD BOLTED TO ENSURE | | THAT IT WILL PERFORM THE EQ FUNCTION. THE ACCESS DOORS TO THE EMERGENCY | | DIESEL GENERATOR ROOMS ARE NOT BEING DEAD BOLTED AT THIS TIME PENDING | | REVIEW OF EQ CALCULATIONS FOR THE UNIT 1 TURBINE BUILDING HELB ON THE | | DIESEL ROOM DOORS, WHICH ARE LOCATED IN THE UNIT 2 TURBINE BUILDING | | HALLWAY. | | | | "THIS EVENT IS BEING REPORTED IN ACCORDANCE WITH 10CFR50.72(b)(1)(ii)(A)." | | | | THE LICENSEE IDENTIFIED THIS CONDITION FOLLOWING AN INTERRUPTION OF POWER | | TO THE ACCESS SYSTEM YESTERDAY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33172 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/28/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 18:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 18:30[EST]| |NRC NOTIFIED BY: MARK KELLY |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "THIS IS MARK KELLY FROM THE COOK NUCLEAR PLANT UNITS 1 AND 2 CALLING TO | | MAKE A REPORT PURSUANT TO 10CFR50.72(b)(2)(i), EVENT FOUND DURING SHUTDOWN | | THAT POTENTIALLY RESULTED IN A DEGRADED PRINCIPAL SAFETY BARRIER. THIS IS | | A GENERIC ISSUE APPLICABLE TO WESTINGHOUSE FUEL RODS CONTAINING INTEGRAL | | FUEL BURNABLE ABSORBER (IFBA). | | | | "WE WERE INFORMED BY WESTINGHOUSE ELECTRIC CORPORATION TODAY THAT CHANGES | | TO THEIR MODELING OF FUEL ROD CLADDING CORROSION AND ROD INTERNAL PRESSURE | | HAVE BEEN MADE TO CORRECT ERRORS AND MAKE OTHER ENHANCEMENTS. THE NEW | | MODEL HAS SHOWN THAT THERE IS A POSSIBILITY THAT THE PLANT WAS IN A | | CONDITION OUTSIDE ITS DESIGN BASIS. WESTINGHOUSE HAS A DESIGN CRITERION | | THAT MAY BE EXCEEDED IN IFBA CONTAINING RODS. THAT CRITERION IS THAT NO | | RE-OPENING OF THE FUEL PELLET TO CLAD GAP SHALL BE ALLOWED. THE GAP IS | | OPEN AT THE BEGINNING OF A FUEL ROD'S OPERATION, AND IS PROGRESSIVELY | | CLOSED DURING OPERATION DUE TO CLAD CREEPDOWN. THE RE-OPENING DESCRIBED IS | | DUE TO THE INCREASE OF INTERNAL FUEL ROD PRESSURE BECAUSE OF HELIUM RELEASE | | FROM THE BORON IN THE BURNABLE ABSORBER AND NORMAL FISSION GAS RELEASE, AND | | DUE TO THE INCREASE IN THE CLADDING CREEP-OUT RATE BECAUSE OF INCREASED | | OXIDATION AND TEMPERATURE. IF THE 'NO-GAP REOPENING' CRITERION IS | | EXCEEDED, THE CRITERION THAT CLAD WASTAGE, DUE TO OXIDATION, SHALL BE LESS | | THAN 17% OF THE TOTAL CLAD, COULD ALSO BE EXCEEDED FOR CERTAIN FUEL RODS. | | THE FIRST OF THESE CRITERIA IS A WESTINGHOUSE FUEL ROD DESIGN CRITERION, | | WHILE THE SECOND IS AN INPUT TO THE EVALUATION OF POTENTIAL LOSS-OF-COOLANT | | ACCIDENTS, AND IS A 10CFR50.46 CRITERION. | | | | "WE HAVE RECEIVED A GENERIC WESTINGHOUSE JUSTIFICATION FOR CONTINUED | | OPERATION (JCO). WESTINGHOUSE HAS CONCLUDED THAT THIS SITUATION IS NOT A | | 'SUBSTANTIAL SAFETY HAZARD' PURSUANT TO 10CFR21. THE BASIS FOR THEIR | | JUDGMENT IS THAT EVEN IF SUCH A SITUATION OCCURRED, (a) A PLANT COULD BE | | SHUTDOWN SAFELY, AS THE CONTROL MECHANISMS WOULD FUNCTION PROPERLY, (b) A | | COOLABLE GEOMETRY IN THE SENSE REQUIRED FOR LOCA PROTECTION WOULD BE | | MAINTAINED AND (c) 10CFR100 DOSE LIMITS WOULD NOT BE EXCEEDED IN ANY | | POSTULATED EVENT. | | | | "OUR ANALYSIS OF THE WESTINGHOUSE REPORTED CONDITION AND JCO IS ON-GOING. | | FUTURE ACTIONS WILL DEPEND ON THE OUTCOME OF OUR REVIEW." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #33160, 33161, AND 33163 TO 33170. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33173 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/28/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 19:38 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/28/97 | +------------------------------------------------+EVENT TIME: 15:09[CST]| |NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 10/28/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 71 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR SCRAM FOR UNKNOWN REASONS. | | | | WHILE OPERATING AT 71% REACTOR POWER, UNIT 2 EXPERIENCED AN AUTOMATIC | | REACTOR SCRAM FOR UNKNOWN REASONS. THE FIRST OUT ANNUNCIATOR INDICATED LOW | | REACTOR WATER LEVEL (SETPOINT +11 INCHES). THERE WAS MAINTENANCE IN | | PROGRESS AT THE TIME, HOWEVER, THE LICENSEE DOES NOT BELIEVE THIS WAS A | | CAUSAL FACTOR. ALL CONTROL RODS FULLY INSERTED AND THE UNIT IS STABLE IN | | CONDITION 3 REJECTING DECAY HEAT TO THE MAIN CONDENSER VIA THE BYPASS | | VALVES. NO SAFETY/RELIEF VALVES LIFTED DURING THIS TRANSIENT. ALL | | EQUIPMENT FUNCTIONED AS EXPECTED AND THERE IS NO SAFETY EQUIPMENT OUT OF | | SERVICE AT THIS TIME. THE LICENSEE WILL CONTINUE TROUBLESHOOTING TO | | IDENTIFY THE ROOT CAUSE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+