U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/29/97 - 10/30/97 ** EVENT NUMBERS ** 33006 33018 33066 33130 33174 33175 33176 33177 33178 33179 33180 33181 33182 33183 33184 33185 33186 33187 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33006 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 09/29/97 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 10:22 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 09/29/97 | +------------------------------------------------+EVENT TIME: 06:15[CDT]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 +------------------------------------------------------------------------------+ | - REACTOR BUILDING CCW PRIMARY CONTAINMENT OUTLET VALVE FAILED ITS LLRT - | | | | WITH UNIT 2 IN CONDITION 4 IN A REFUELING OUTAGE, THE LICENSEE PERFORMED A | | LEAK RATE TEST OF THE PRIMARY CONTAINMENT. DURING THE TEST, THE LEAK RATE | | THROUGH THE REACTOR BUILDING CLOSED COOLING WATER (CCW) PRIMARY CONTAINMENT | | OUTLET VALVE #2-FCV-70-47, COMBINED WITH THE THE LEAKAGE THROUGH ALL OTHER | | PRIMARY CONTAINMENT COMPONENTS, EXCEEDED THE TECH SPEC LEAK RATE LIMIT OF | | 655.9 SCFH. | | | | THE LICENSEE PLANS TO SUBMIT A LICENSEE EVENT REPORT TO THE NRC WITHIN | | 30 DAYS AND WILL REPAIR THIS VALVE PRIOR TO RESTARTING UNIT 2. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1705EST 10/29/97 FROM RODNEY NACOSTE TO S.SANDIN * * * | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "A SUBSEQUENT INVESTIGATION PROVED THAT THE VALVE LINEUP FOR THE TEST WAS | | IMPROPER. A SUBSEQUENT RETEST OF #2-FCV-70-47 BEFORE RESTART SHOWED NO | | LEAKAGE. THERE ARE NO PLANS TO SUBMIT A 30-DAY REPORT." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | R2DO(SKINNER). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33018 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/01/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 13:23 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/01/97 | +------------------------------------------------+EVENT TIME: 12:25[EDT]| |NRC NOTIFIED BY: MLACHAK |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |JIM CREED IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A CRIMINAL ACT INVOLVING AN INDIVIDUAL GRANTED ACCESS TO THE | | SITE. COMPENSATORY MEASURES TAKEN SOON AFTER THE DISCOVERY WAS MADE. | | THE RESIDENT INSPECTOR WAS NOTIFIED. REFER TO HOO LOG FOR ADDITIONAL | | DETAILS. | | | | * * * UPDATE 1402EST 10/29/97 FROM DAVID GUDGER TO S.SANDIN * * * | | THIS EVENT IS BEING RETRACTED BASED ON A SUBSEQUENT EVALUATION THAT | | DETERMINED THIS WAS NOT A PROGRAMMATIC FAILURE. THE EVENT HAS BEEN | | DOWNGRADED TO LOGGABLE. THE LICENSEE INFORMED REGION 3 (BELANGER) AND THE | | NRC RESIDENT INSPECTOR. NOTIFIED R3DO(GARDNER). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/10/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/10/97 | +------------------------------------------------+EVENT TIME: 14:25[EDT]| |NRC NOTIFIED BY: MARK MLACHAK |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON, R3 RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |JIM BELANGER, R3 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SECURITY EVENT - | | | | DISCOVERY OF PREVIOUS DRUG USE BY CONTRACTOR GRANTED UNESCORTED ACCESS | | TO THE SITE. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG | | FOR ADDITIONAL DETAILS. | | | | * * * UPDATE 1402EST 10/29/97 FROM DAVID GUDGER TO S.SANDIN * * * | | THIS EVENT IS BEING RETRACTED BASED ON A SUBSEQUENT EVALUATION THAT | | DETERMINED THIS WAS NOT A PROGRAMMATIC FAILURE. THE EVENT HAS BEEN | | DOWNGRADED TO LOGGABLE. THE LICENSEE INFORMED REGION 3 (BELANGER) AND THE | | NRC RESIDENT INSPECTOR. NOTIFIED R3DO(GARDNER). | +------------------------------------------------------------------------------+ !!!!!!!!! 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: 33174 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 11:49 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 10:49[CST]| |NRC NOTIFIED BY: DAVE BONO |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 70 POWER OPERATION | 70 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "THIS REPORT IS PROVIDED FOR INFORMATION. CALLAWAY WAS INFORMED BY | | WESTINGHOUSE THAT THE METHODOLOGY FOR DETERMINATION OF FUEL ROD INTERNAL | | PRESSURE AND CLADDING CORROSION WAS FOUND TO BE POTENTIALLY LESS | | CONSERVATIVE THAN PREVIOUSLY BELIEVED. AS A RESULT, CALCULATION OF | | 10CFR50.46 ECCS ACCEPTANCE CRITERIA MAY BE AFFECTED. THIS DETERMINATION IS | | BASED ON NEWER MODELS STILL UNDER DEVELOPMENT, WHICH ARE BELIEVED TO MORE | | ACCURATELY PREDICT FUEL-CLADDING BEHAVIOR. THE EFFECT OF THIS EVALUATION | | INDICATES THAT POTENTIALLY, FOR A POSTULATED LOCA, THE 17% CLAD OXIDATION | | LIMIT REQUIREMENT OF 10CFR50.46 MAY NOT BE MET. THE ANALYSIS PROVIDED BY | | WESTINGHOUSE IS GENERIC IN NATURE AND HAS NOT BEEN SPECIFICALLY APPLIED TO | | CALLAWAY. HOWEVER, THE GENERIC EVALUATION PROVIDED BY WESTINGHOUSE | | DETERMINED THAT THIS DOES NOT REPRESENT A CONDITION THAT SIGNIFICANTLY | | COMPROMISES PLANT SAFETY AND THAT IT DOES NOT REPRESENT A SUBSTANTIAL | | SAFETY CONCERN. THE BASIS FOR THIS JUDGMENT IS THAT IF THE POSTULATED | | EVENT 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. | | | | "WESTINGHOUSE HAS NOTIFIED THE NRC AND THEIR CUSTOMERS OF THIS ISSUE THOUGH | | THEY HAVE CONCLUDED THAT EXCEEDING THE AFOREMENTIONED CRITERIA DOES NOT | | POSE A SUBSTANTIAL SAFETY HAZARD AND IS NOT REPORTABLE PER 10CFR21 | | REQUIREMENTS. ADDITIONALLY, THEY HAVE PROVIDED A PLAN FOR INCORPORATION OF | | THE NEW ZIRCALOY CORROSION MODEL INTO THEIR PAD CODE. CALLAWAY WILL | | MONITOR PROGRESS ON THIS PLAN FOR FURTHER DEVELOPMENTS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 33175 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: OLIN E. TEAGUE VETERANS CENTER |NOTIFICATION DATE: 10/29/97 | | CITY: TEMPLE REGION: 4 |NOTIFICATION TIME: 12:15 [ET]| | COUNTY: BELL STATE: TX |EVENT DATE: 10/28/97 | |LICENSE#: 42-10739 AGREEMENT: Y |EVENT TIME: 09:00[CST]| | DOCKET: |LAST UPDATE DATE: 10/29/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE YANDELL RDO | | |JOSEPHINE PICCONE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DR. DONALD M. FOSTER | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INCORRECT DOSAGE AND FORM OF Tc-99 ADMINISTERED DUE TO TECHNICIAN ERROR. | | | | AT APPROXIMATELY 0900CST ON 10/28/97, A PATIENT RECEIVED 21.4 mCi Tc-99m | | CARDIOLITE (USED FOR CORONARY STUDIES) INSTEAD OF THE PRESCRIBED 20mCi | | Tc-99m MDP FOR A BONE SCAN. THE PRESCRIBING PHYSICIAN INFORMED BOTH THE | | RADIATION SAFETY OFFICER AND THE PATIENT. THERE ARE NO ADVERSE HEALTH | | CONSEQUENCES ASSOCIATED WITH THIS MISADMINISTRATION. THE PATIENT HAS BEEN | | RESCHEDULED FOR THE BONE SCAN. THE RSO ATTRIBUTED THE ERROR TO A | | MISLABELLED LEAD PIG RECEIVED FROM THE SUPPLIER AND THE FAILURE OF | | TECHNICIANS TO READ AND SELECT THE PROPER SYRINGE. THE LICENSEE IS | | IMPLEMENTING ADMINISTRATIVE ACTIONS TO PREVENT RECURRENCE. | | | | * * * UPDATE 1525EST 10/29/97 FROM DR. FOSTER TO S.SANDIN * * * | | DR. FOSTER CALLED TO RETRACT THIS REPORT BASED ON A REVIEW OF THE THRESHOLD | | REPORTING CRITERIA. NOTIFIED R4DO(YANDELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33176 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 13:53 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 08:00[CST]| |NRC NOTIFIED BY: JENNIFER YUNK |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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. | | | | "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 WOLF CREEK. 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 FOR CERTAIN LIMITING FUEL RODS | | CONTAINING INTEGRAL FUEL BURNABLE ABSORBER (IFBA). THESE GENERIC | | EVALUATIONS INDICATE THAT IFBA RODS COULD EXPERIENCE GAP RE-OPENING | | SOMETIME IN THE SECOND HALF OF THEIR SECOND CYCLE OF OPERATION UNDER THE | | MOST DEMANDING PLANT CONDITIONS. WOLF CREEK HAS OPERATED ONE CYCLE WITH | | IFBA RODS. 'BEST ESTIMATE' CALCULATIONS PERFORMED BY WESTINGHOUSE INDICATE | | THAT GAP RE-OPENING MAY NOT NECESSARILY OCCUR, EVEN FOR THE MOST LIMITING | | FUEL ROD IN THE MOST LIMITING PLANT. | | | | "WESTINGHOUSE HAS CONSERVATIVELY EVALUATED THE POSSIBILITY OF GAP REOPENING | | AND CONCLUDED IT DOES NOT REPRESENT A SUBSTANTIAL SAFETY HAZARD. | | WESTINGHOUSE CONCLUDES THAT A PLANT COULD BE SHUTDOWN SAFELY, SINCE PLANT | | CONTROL MECHANISMS WOULD FUNCTION PROPERLY AND A COOLABLE GEOMETRY WOULD BE | | MAINTAINED TO THE EXTENT REQUIRED FOR DESIGN BASIS ACCIDENTS. 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 10CRF21 REQUIREMENTS. WOLF CREEK IS MAKING THIS | | VOLUNTARY REPORT BECAUSE THIS ISSUE MIGHT BE OF GENERIC INTEREST OR | | CONCERN." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33177 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 14:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 11:10[CST]| |NRC NOTIFIED BY: KEN TAPLETT |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 THE SOUTH TEXAS PROJECT | | UNITS. THIS DETERMINATION IS MADE 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 ISSUER IS | | NOT REPORTABLE PER 10CFR21 REQUIREMENTS. | | | | "WESTINGHOUSE HAS NOT PERFORMED ANY PLANT SPECIFIC ANALYSES TO CONCLUDE | | THAT THIS CONDITION IS APPLICABLE TO THE SOUTH TEXAS PROJECT UNITS. SOUTH | | TEXAS PROJECT IS MAKING THIS VOLUNTARY REPORT BECAUSE THIS ISSUE MIGHT BE | | OF GENERIC INTEREST OR CONCERN. | | | | "THIS CONDITION WILL NOT BE FULLY UNDERSTOOD REGARDING APPLICABILITY TO THE | | SOUTH TEXAS PROJECT UNITS UNTIL WESTINGHOUSE REFINES THEIR MODEL AND | | PERFORMS SOUTH TEXAS PROJECT PLANT SPECIFIC ANALYSES." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33178 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/29/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:19 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 14:02[EST]| |NRC NOTIFIED BY: JOHN STODDARD |LAST UPDATE DATE: 10/29/97 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | A NEW CORROSION MODEL WILL BE IMPLEMENTED INTO THE FUEL PERFORMANCE CODE. | | | | THE LICENSEE INFORMED STATE AND LOCAL AGENCIES AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33179 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 14:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 13:15[EST]| |NRC NOTIFIED BY: STEVE SAUER |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | 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 WESTINGHOUSE PROVIDED INFORMATION TO PSE&G INDICATING | | THAT REVISED FUEL DESIGN MODELING (PAD CODE) ADJUSTED TO ACCOUNT FOR FIELD | | EXPERIENCE (OXIDATION AND FUEL PIN PRESSURE) PREDICTS THAT THERE IS A | | POTENTIAL TO EXCEED 10CFR50.46 ACCEPTANCE CRITERIA OF 17% FOR CLADDING | | OXIDATION. IN ADDITION, THE FUEL DESIGN CRITERIA OF CLAD TO FUEL PELLET | | GAP REOPENING MAY ALSO BE EXCEEDED. THIS CONCERN APPLIES TO TWICE BURNED | | ZIRCALOY-4 FUEL WITH INTEGRAL FUEL BURNABLE ABSORBER (IFBA) AND IS | | APPLICABLE TO SALEM UNITS 1 & 2. | | | | "PSE&G UNDERSTANDS THAT WESTINGHOUSE HAS DISCUSSED THIS GENERICALLY WITH | | THE NRC. WESTINGHOUSE HAS ALSO PREPARED A GENERIC BOUNDING JUSTIFICATION | | FOR CONTINUED OPERATION (JCO) FOR AFFECTED PLANTS AND HAS CONCLUDED THAT A | | SUBSTANTIAL SAFETY HAZARD DOES NOT EXIST. 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 THE | | RADIOLOGICAL CONSEQUENCES OF THE DESIGN BASIS ACCIDENTS WILL NOT EXCEED | | 10CFR100 LIMITS. | | | | "NO PLANT SPECIFIC ANALYSIS FOR THE SALEM UNITS HAS BEEN PERFORMED. PSE&G | | UNDERSTANDS THAT WESTINGHOUSE WILL FURTHER REFINE THE EVALUATION MODEL TO | | RESOLVE THIS ISSUE. THIS ISSUE IS BEING REPORTED TO THE NRC AS A VOLUNTARY | | REPORT DUE TO POTENTIAL NRC MANAGEMENT INTEREST IN THIS ISSUE." | | | | THE LICENSEE INFORMED LOCAL AUTHORITIES (LOWER ALLOWAYS CREEK TOWNSHIP) AND | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33180 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 10/29/97 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 15:20 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 15:20[EST]| |NRC NOTIFIED BY: DANNY EDDINGER |LAST UPDATE DATE: 10/29/97 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | 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 ONLY. WESTINGHOUSE NOTIFIED | | FLORIDA POWER AND LIGHT CO. THAT BASED ON ANALYSIS PERFORMED WITH A NEW | | CONSERVATIVE COMPUTER MODEL, A POTENTIAL EXISTS FOR TURKEY POINT UNITS 3 | | AND 4 TO EXCEED THE 10CFR50.46 MAXIMUM CLADDING OXIDATION CRITERIA OF 17%. | | | | "WESTINGHOUSE ANALYSIS SHOWS THAT FOR HIGH POWER, HIGH BURNUP INTEGRAL FUEL | | BURNABLE ABSORBER (IFBA) CONTAINING FUEL RODS, CALCULATED ROD INTERNAL | | PRESSURE IS 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. THESE RESULTS ARE BASED ON THE MOST LIMITING CASE CALCULATED | | BY WESTINGHOUSE FOR 17x17 FUEL WITH 1.5xIFBA COATING. WESTINGHOUSE HAS NOT | | PERFORMED DETAILED ANALYSIS FOR 15x15 FUEL WITH 1.0xIFBA COATING WHICH IS | | CURRENTLY UTILIZED AT TURKEY POINT UNITS 3 AND 4. ALTHOUGH TURKEY POINT | | SPECIFIC CALCULATIONS HAVE NOT BEEN PERFORMED, WESTINGHOUSE HAS IDENTIFIED | | THE POTENTIAL FOR BEING OUTSIDE THE 10CFR50.46 CRITERIA. | | | | "WESTINGHOUSE HAS PROVIDED A GENERIC JUSTIFICATION FOR CONTINUED OPERATION | | (JCO). WESTINGHOUSE HAS CONCLUDED THAT SHUTDOWN CAPABILITY WILL NOT BE | | HINDERED, A 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 FAILURE ARE NOT EXPECTED. THE INFORMATION ONLY | | REPORT IS BEING MADE BECAUSE THIS ISSUE MIGHT BE OF GENERIC INTEREST OR | | CONCERN. | | | | "WESTINGHOUSE IS CONTINUING TO EVALUATE THEIR MODEL AND WILL BE WORKING | | WITH FLORIDA POWER AND LIGHT CO. TO PERFORM AN INDIVIDUAL PLANT | | DETERMINATION." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33181 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:00 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 14:18[CST]| |NRC NOTIFIED BY: ERICK MATZKE |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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. | | | | "FORT CALHOUN STATION (FCS) PERSONNEL WERE NOTIFIED BY REPRESENTATIVE 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 BE IMPACTED. FCS USES WESTINGHOUSE 14x14 FUEL WITH | | IFBA IN TWO THIRDS OF THE CORE. | | | | "THE WESTINGHOUSE NOTIFICATION IS GENERIC IN NATURE, AND DOES NOT REPRESENT | | A PLANT SPECIFIC DETERMINATION FOR THE FORT CALHOUN STATION. A PLANT | | SPECIFIC REVIEW WILL BE PERFORMED, AND IN THE INTERIM, WESTINGHOUSE HAS | | PROVIDED A JUSTIFICATION FOR CONTINUED OPERATION WHICH CONCLUDES THIS | | SITUATION POSES NO ADVERSE SAFETY OR RELIABILITY CONCERNS. | | | | "IT IS OUR UNDERSTANDING THAT NRC REPRESENTATIVES HAVE PREVIOUSLY BEEN | | APPRAISED OF THIS CONDITION ON A GENERIC BASIS BY WESTINGHOUSE PERSONNEL. | | | | "THIS CALL IS BEING MADE AS A CONSERVATIVE MEASURE PRIOR TO THE PLANT | | SPECIFIC ANALYSIS BEING COMPLETED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33182 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/29/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:10 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: JOHN BALLETTA |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT ISOLATION OF INSTRUMENT AIR SUPPLY TO CONTAINMENT RESULTED IN | | SEVERAL VALVES REPOSITIONING TO THE FAIL-SAFE CONDITION. | | | | DURING MAINTENANCE ACTIVITY ON PCV-1229, A CONTROL FUSE WAS PULLED | | RESULTING IN PCV-1228 (CONTAINMENT INSTRUMENT AIR SUPPLY) ALSO CLOSING. | | SEVERAL VALVES REPOSITIONED TO THE FAIL-SAFE CONDITION INCLUDING THE FAN | | COOLER UNIT CHARCOAL INLET AND OUTLET AND NORMAL OUTLET (ISOLATED), LETDOWN | | (ISOLATED), AND ALTERNATE CHARGING (OPEN). THE FUSE WAS IMMEDIATELY | | REINSTALLED AT WHICH TIME THE LICENSEE VERIFIED THAT ALL AFFECTED VALVES | | WERE RESTORED. THE LICENSEE ATTRIBUTES THE CAUSE TO AN INADEQUATE WORK | | PROCEDURE WHICH DID NOT RECOGNIZE THAT BOTH PCV-1228 AND PCV-1229 CONTROL | | SOLENOIDS RECEIVE POWER THROUGH A COMMON FUSE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33183 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/29/97 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 19:07 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 18:38[EST]| |NRC NOTIFIED BY: STEPHEN BAKER |LAST UPDATE DATE: 10/29/97 | |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A SCENARIO WHERE THE SUMP RECIRCULATION VALVES WOULD | | FAIL TO OPEN DUE TO PRESSURE INDUCED PRESSURE LOCKING FOLLOWING A DESIGN | | BASIS ACCIDENT. | | | | "ON JANUARY 25, 1995, PLANT INCIDENT REPORT (PIR) 2-95-057 DOCUMENTED THAT | | THE CONTAINMENT SUMP RECIRCULATION VALVES (2-CS-16.1A AND 2-CS-16.1B) WERE | | SUSCEPTIBLE TO PRESSURE LOCKING WHEN FLUID IN THE VALVE BONNET WAS HEATED | | WITH FLUID FROM THE CONTAINMENT SUMP DURING A DESIGN BASIS ACCIDENT. MOCKUP | | TESTING (CREARE REPORT, MTG-95-03-675, DATED 3/30/95) OF A VALVE SIMILAR TO | | THE SUMP RECIRCULATION VALVES (UNDER FLUID CONDITIONS SIMILAR TO DBA FLUID | | TEMPERATURES) DEMONSTRATED THAT THE VALVES WERE OPERABLE AND WOULD NOT | | PRESSURE LOCK WHEN HEATED WITH CONTAINMENT SUMP WATER TEMPERATURE. THE | | INITIAL DESIGN RESOLUTION, WHICH DRILLED A HOLE IN THE UPSTREAM DISC, WAS | | FOUND TO BE UNACCEPTABLE AND THE HOLES IN THE DISCS WERE PLUGGED. | | ENGINEERING PURSUED AND SUBMITTED AN ANALYTICALLY BASED SOLUTION FOR DESIGN | | RESOLUTION, HOWEVER, THE NRC DEEMED THIS APPROACH TO BE INSUFFICIENT. | | DURING A RECENT REVIEW OF A SUBSEQUENT DESIGN RESOLUTION, IT WAS DISCOVERED | | THAT PRESSURE LOCKING OF THE SUMP RECIRCULATION VALVES COULD NOT ONLY BE | | THERMALLY INDUCED (AS EVALUATED ABOVE), BUT THEY ARE ALSO POTENTIALLY | | SUSCEPTIBLE TO PRESSURE INDUCED PRESSURE LOCKING. PRESSURE INDUCED | | PRESSURE LOCKING COULD OCCUR DURING A DBA AS FOLLOWS: | | | | 1) THE CONTAINMENT IS INITIALLY PRESSURIZED TO 54 PSIG; | | 2) THE SUMP RECIRCULATION VALVES ARE INITIALLY PRESSURIZED TO 54 PSIG; | | 3) AT THE TIME OF THE RECIRCULATION ACTUATION SIGNAL (SRAS), THE | | CONTAINMENT PRESSURE DROPS TO APPROXIMATELY 37 PSIG WHILE THE BONNET OF | | CS-16A/B REMAINS AT 54 PSIG. | | | | "ON OCTOBER 17, 1997, THE BASIS FOR INITIAL OPERABILITY WAS PROVIDED IN CR | | M2-97-2384. THE DRAFT CALCULATION WAS BASED ON CONTAINMENT PRESSURE OF 37 | | PSIG. SAFETY ANALYSIS BRANCH (SAB) HAS IDENTIFIED THAT 37 PSIG REPRESENTS | | THE APPROXIMATE PEAK CONTAINMENT PRESSURE AT THE TIME OF THE SUMP | | RECIRCULATION ACTUATION SIGNAL (SRAS) AND NOT THE MINIMUM (0-15 PSIG). A | | REVISION OF THE DRAFT CALCULATION USING A CONTAINMENT PRESSURE OF | | (0-15PSIG), VALVE BONNET PRESSURE OF 54 PSIG, AND A RWST PRESSURE OF 20 | | PSIG SHOWS THE SUMP RECIRCULATION VALVES (2-CS-16.1A AND 2-CS-16.1B) HAS | | INSUFFICIENT THRUST TO OPEN THE VALVES UNDER THIS PRESSURE INDUCED PRESSURE | | LOCKING SCENARIO. SUMP RECIRCULATION VALVES (2-CS-16.1A AND 2-CS-16.1B) | | ARE THEREFORE INOPERABLE UNDER THIS SCENARIO." | | | | THE LICENSEE INFORMED STATE AND LOCAL AGENCIES AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 20:00 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 17:30[EST]| |NRC NOTIFIED BY: APRIL RICE |LAST UPDATE DATE: 10/29/97 | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "VOLUNTARY REPORT FOR INFORMATION ONLY. VC SUMMER WAS INFORMED BY | | WESTINGHOUSE FUEL SUPPLIER THAT BASED UPON RESULTS FROM A NEW CONSERVATIVE | | DEVELOPMENTAL COMPUTER MODEL THERE IS THE POTENTIAL FOR SOME OF OUR ZIRC | | FUEL ASSEMBLIES TO EXCEED GAP RE-OPENING LIMITS ESTABLISHED BY WESTINGHOUSE | | AT SOME POINT DURING THE FUEL CYCLE. BEST ESTIMATE CALCULATIONS PERFORMED | | BY WESTINGHOUSE HAVE DETERMINED THAT THIS CONDITION DOES NOT REPRESENT A | | CONDITION THAT SIGNIFICANTLY COMPROMISES PLANT SAFETY AND IT DOES NOT | | REPRESENT A SUBSTANTIAL SAFETY HAZARD. WESTINGHOUSE HAS NOTIFIED THE NRC | | OF THIS ISSUE AND IS PURSUING RESOLUTION. VC SUMMER PLANS TO WORK WITH | | WESTINGHOUSE TO DEFINE SPECIFIC ACTIONS REQUIRED FOR THIS PLANT. THIS | | ISSUE DOES NOT IMPACT PLANT RESTART." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33185 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 20:30 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 17:30[PST]| |NRC NOTIFIED BY: GLEN GOELZER |LAST UPDATE DATE: 10/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 72 POWER OPERATION | 72 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "PG&E WAS NOTIFIED BY WESTINGHOUSE THAT RECENT EVALUATIONS HAVE INDICATED | | THAT THE LATEST WESTINGHOUSE PAD CODE UNDER DEVELOPMENT FOR DETERMINING | | FUEL ROD INTERNAL PRESSURE MAY NOT HAVE BEEN AS CONSERVATIVE AS ORIGINALLY | | BELIEVED. AS A RESULT OF THE CHANGES TO THE PAD CODE, THE POSSIBILITY OF | | EXCEEDING THE 17% CLAD OXIDATION ACCEPTANCE CRITERIA OF 10CFR50.46 HAS BEEN | | IDENTIFIED. HOWEVER, THE AFFECT OF THE CHANGES TO THE PAD MODEL AND THE | | IMPACT ON THE CLADDING OXIDATION HAVE NOT YET BEEN DETERMINED SPECIFICALLY | | FOR DIABLO CANYON. | | | | "ALTHOUGH THE NEW FUEL CLADDING MODEL IDENTIFIES THE POTENTIAL FOR CLADDING | | OXIDATION TO EXCEED 17% ACCEPTANCE CRITERIA FOR 10CFR50.46, BEST ESTIMATE | | MODELS INDICATE THAT THE CONDITION DOES NOT REPRESENT A CONDITION THAT | | SIGNIFICANTLY COMPROMISES PLANT SAFETY AND DOES NOT REPRESENT A SUBSTANTIAL | | SAFETY HAZARD. THE BASIS FOR THIS CONCLUSION IS THAT EVEN IF THE | | PHENOMENON WERE TO BE PRESENT FOR A PARTICULAR PLANT, THE PLANT COULD BE | | SAFELY SHUT DOWN SINCE PLANT CONTROLS MECHANISMS WOULD BE EXPECTED TO | | FUNCTION PROPERLY AND A COOLABLE CORE GEOMETRY AS REQUIRED IN A LOCA COULD | | BE MAINTAINED. IN ADDITION, 10CFR100 DOSE LIMITS WOULD NOT BE EXPECTED TO | | BE EXCEEDED IN ANY POSTULATED EVENT. | | | | "WESTINGHOUSE HAS PREPARED A GENERIC JCO FOR USE BY PLANTS THAT DETERMINE | | THAT THE ISSUE IS APPLICABLE TO THEM AND HAS NOTIFIED THE NRC OF THE | | CONDITION. WESTINGHOUSE IS CURRENTLY ADDRESSING FUEL PERFORMANCE ANALYSIS | | METHODOLOGY TO REFINE THEIR MODEL AND RESOLVE THIS ISSUE. THE LICENSEE IS | | MAKING THIS VOLUNTARY REPORT BECAUSE, ALTHOUGH PG&E DOES NOT HAVE ADEQUATE | | INFORMATION AT THIS TIME (SUCH AS PLANT SPECIFIC ANALYSIS) TO KNOW IF THIS | | ISSUE IS APPLICABLE TO DIABLO CANYON, IT MAY BE OF GENERIC INTEREST OR | | CONCERN." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33186 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 10/30/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 00:37 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 21:00[CST]| |NRC NOTIFIED BY: MARTY WOLF |LAST UPDATE DATE: 10/30/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO HYDRAULIC OIL SPILL. | | | | THE LICENSEE NOTIFIED OFF SITE AGENCIES INCLUDING THE NATIONAL RESPONSE | | CENTER, ILLINOIS EMERGENCY MANAGEMENT AGENCY, AND OGLE COUNTY EMERGENCY | | PLANNING COMMITTEE ABOUT AN HAZMAT SPILL OF HYDRAULIC OIL. THE REPORTABLE | | QUANTITY OF 40CFR302.5(B) IS 15 GALLONS, THE SPILL WAS APPROXIMATELY 40 | | GALLONS OF HYDRAULIC OIL FROM A BROKEN HYDRAULIC LINE ON A MOBILE CRANE. | | THE SPILL WAS CONTAINED AND CLEANUP WAS IN PROGRESS. THERE WERE NO | | PERSONNEL INJURIES AND NO RELEASE OFFSITE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33187 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/30/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 02:39 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/30/97 | +------------------------------------------------+EVENT TIME: 01:02[EST]| |NRC NOTIFIED BY: GUY GRIFFIS |LAST UPDATE DATE: 10/30/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR WATER SAMPLE ISOLATION VALVE RECEIVED AUTOMATIC SIGNAL TO CLOSE. | | | | DURING MAINTENANCE ACTIVITY TO MEASURE ACCUMULATOR VALVE ACTUATOR (F013C) | | STROKE, AN IMPROPERLY INSTALLED JUMPER CAUSED A GROUP I ISOLATION SIGNAL | | WHICH CAUSED CONTAINMENT ISOLATION VALVE (1B31-F019), A REACTOR WATER | | SAMPLE VALVE, TO CLOSE. THIS IS A SMALL BORE VALVE OFF THE RECIRC LINE, | | USED FOR REACTOR WATER SAMPLING DURING NORMAL OPERATION, AND WAS THE ONLY | | VALVE IN GROUP I TO BE OPEN. THE JUMPER WAS INSTALLED IN THE WRONG PANEL | | CAUSING THE GROUP I ISOLATION SIGNAL. | | | | TROUBLESHOOTING IS IN PROGRESS, A BLOWN FUSE HAS BEEN FOUND AND FURTHER | | INVESTIGATION IS IN PROGRESS TO INSURE THERE IS NO OTHER PROBLEMS. THE | | PROBLEM WILL BE CORRECTED BEFORE THE PLANT IS RESTARTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+