U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/14/97 - 11/17/97 ** EVENT NUMBERS ** 33096 33185 33259 33260 33261 33262 33263 33264 33265 33266 33267 33268 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33096 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 10/16/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 10/16/97 | +------------------------------------------------+EVENT TIME: 14:15[EDT]| |NRC NOTIFIED BY: J. WEBERS |LAST UPDATE DATE: 11/14/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FLOWPATH EXISTS FOR LOSS OF INVENTORY DURING AN APPENDIX "R" FIRE | | | | DURING A PLANT WALKDOWN IT WAS DISCOVERED THAT A POTENTIAL FLOWPATH EXISTS | | FOR LOSS OF REACTOR COOLANT INVENTORY TO THE MAIN CONDENSER FOR CERTAIN | | APPENDIX "R" FIRES. SPECIFICALLY, IF A FIRE WERE TO CAUSE MULTIPLE HOT | | SHORTS IN THE MOVs OF THE REACTOR WATER CLEANUP SYSTEM (RWCS), WATER COULD | | FLOW FROM THE REACTOR VESSEL TO THE MAIN CONDENSER THROUGH THE REJECT | | FLOWPATH. THE FLOWPATH WOULD BE THROUGH A LOW PRESSURE PUMP IN THE RWCS | | WHICH HAD NOT BEEN PREVIOUSLY CONSIDERED. | | | | THE LICENSEE HAS IDENTIFIED TWO MANUAL ISOLATION VALVES THAT WOULD | | TERMINATE FLOW UNDER THE ABOVE CIRCUMSTANCES. THE VALVE NUMBERS ARE 33-05 | | AND 33-06. THESE VALVES WILL BE ADDED TO THE PROCEDURE DEALING WITH FIRES | | (N-1-SOP-9). | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1215 11/14/97 FROM LECOYER TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. THE FOLLOWING IS TEXT | | OF A FACSIMILE SUBMITED BY THE LICENSEE: | | | | "AT APPROXIMATELY 1724 HOURS ON OCTOBER 16, 1997, IT WAS REPORTED THAT NMP1 | | WAS OUTSIDE DESIGN BASIS FOR 10CFR50, APPENDIX R. WHILE REVISING THE SAFE | | SHUTDOWN ANALYSIS, A PREVIOUSLY UNIDENTIFIED INVENTORY LOSS PATH THROUGH | | THE REACTOR WATER CLEANUP AUXILIARY PUMP SYSTEM WAS DISCOVERED BY | | ENGINEERING AND REPORTED UNDER 10CFR50.72(b)(2). | | | | BASED UPON FURTHER REVIEW OF THE NMP1 APPENDIX R DESIGN BASIS, ENGINEERING | | HAS DETERMINED THAT THE PREMISE FOR INITIAL CONCERN WAS OVER AND ABOVE | | NMP1'S CURRENT LICENSING BASIS FOR APPENDIX R. BASED ON THIS, ENGINEERING | | HAS DETERMINED THE REACTOR WATER CLEANUP AUXILIARY PUMP SYSTEM COULD NOT | | RESULT IN A LOSS OF REACTOR WATER INVENTORY CAUSED BY FIRE INDUCED CIRCUIT | | FAILURES OPENING VALVES AND IS IN COMPLIANCE WITH 10CFR50 APPENDIX R." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R1DO (DURR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 11/14/97 | |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. | | | | * * * UPDATE 1855 11/14/97 FROM MAGRUDER TAKEN BY STRANSKY * * * | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | "WESTINGHOUSE HAS RECENTLY COMPLETED A BOUNDING GENERIC ANALYSIS | | INCORPORATING NEW MODELS FOR CLAD OXIDATION OF ZIRC-4 FUEL CLADDING AND | | HELIUM RELEASE IN INTEGRAL FUEL BURNABLE ABSORBER (IFBA) FUEL RODS. PG&E | | WAS INFORMED THAT THIS ANALYSIS PREDICTS THAT PELLET-CLAD GAP REOPENING MAY | | OCCUR FOR HIGH DUTY IFBA RODS AS EARLY AS THE SECOND HALF OF THEIR SECOND | | DUTY CYCLE. ONE OF THE FUEL DESIGN CRITERIA FOR WESTINGHOUSE FUEL IS THAT | | PELLET-CLAD GAP REOPENING WILL NOT OCCUR. DIABLO CANYON UNIT 2 IS IN THE | | SECOND HALF OF ITS FUEL CYCLE AND HAS SECOND DUTY CYCLE ZIRC-4 IFBA FUEL. | | WESTINGHOUSE HAS INFORMED PG&E THAT, BASED ON THE BOUNDING ANALYSIS AND | | ABSENT REVISED PLANT SPECIFIC ANALYSIS, GAP REOPENING MAY BE PREDICTED FOR | | UNIT 2 AT THIS TIME. UNIT 1 IS IN THE FIRST HALF OF ITS FUEL CYCLE AND THIS | | ISSUE WILL NOT BE APPLICABLE UNTIL MAY 1998. | | | | WESTINGHOUSE HAS PERFORMED A GENERIC SAFETY ASSESSMENT WHICH EVALUATES THE | | CONSEQUENCES OF THE GAP REOPENING CONCERN IN ZIRC-4 IFBA FUEL AND HAS HAD | | ONGOING DISCUSSIONS WITH THE NRC OF THE CONDITION. THEY HAVE ASSESSED THE | | IMPLICATIONS OF THIS POTENTIAL PRE-CONDITION FOR ANALYZED EVENTS AND | | CONCLUDED THAT PLANT SAFETY IS MAINTAINED AT THE SAME LEVELS AS CONSIDERED | | IN THEIR ORIGINAL DESIGN BASIS EVALUATION. PG&E IS PREPARING A PLANT | | SPECIFIC OPERABILITY EVALUATION TO ADDRESS THIS ISSUE. | | | | IN THE INITIAL REPORT, PG&E INFORMED THE NRC THAT THE NEW FUEL MODEL | | IDENTIFIED THE POTENTIAL FOR CLADDING OXIDATION TO EXCEED THE 17% | | ACCEPTANCE CRITERIA OF 10CFR50.46. PG&E WAS RECENTLY INFORMED BY | | WESTINGHOUSE THAT, BASED ON THE RECENTLY PERFORMED BOUNDING ANALYSIS, UNIT | | 2 PRE-ACCIDENT FUEL OXIDATION WILL NOT EXCEED 12% BEFORE JANUARY 9, 1998. | | WESTINGHOUSE HAS DETERMINED THAT THIS 12% OXIDATION LIMIT ASSURES THAT THE | | SUM OF PRE-ACCIDENT AND POST-LOCA OXIDATION WILL NOT EXCEED 17%. | | WESTINGHOUSE IS IN THE PROCESS OF PERFORMING PLANT SPECIFIC ANALYSIS FOR | | PLANTS WHICH WILL EXCEED THE 12% OXIDATION CRITERIA IN THE NEAR FUTURE, | | INCLUDING DIABLO CANYON. THEY ANTICIPATE THAT THE EVALUATION WILL | | DEMONSTRATE THAT THE 17% CLAD OXIDATION CRITERIA WILL NOT BE EXCEEDED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R4DO (MURRAY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33259 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/14/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 14:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/14/97 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 11/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 86 POWER OPERATION | 86 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF INSTRUMENT AIR COULD CAUSE INABILITY TO REFILL EDG DAY TANKS | | | | THE LICENSEE HAS IDENTIFIED A SCENARIO IN WHICH THE LOSS OF INSTRUMENT AIR | | COULD PREVENT THE EMERGENCY DIESEL GENERATOR (EDG) FUEL OIL DAY TANKS FROM | | BEING AUTOMATICALLY REFILLED. THE FUEL OIL TRANSFER VALVES FOR THE DAY | | TANKS ARE AIR-OPERATED, NORMALLY CLOSED VALVES, AND ARE DESIGNED TO FAILED | | CLOSED UPON A LOSS OF AIR PRESSURE. IN THIS SCENARIO, THE EDGs COULD BE | | RENDERED INOPERABLE DUE TO A LACK OF FUEL OIL AFTER APPROXIMATELY THREE | | HOURS OF CONTINUOUS FULL LOAD OPERATION. | | | | AFTER REVIEWING THEIR RESPONSE TO NRC GENERIC LETTER 88-14, THE LICENSEE | | HAS DETERMINED THAT THIS CONDITION PLACES THE UNIT OUTSIDE OF ITS LICENSING | | BASIS FOR THE EDG FUEL OIL SYSTEM. HOWEVER, THIS CONDITION DOES NOT POSE AN | | IMMEDIATE OPERABILITY CONCERN BECAUSE PROCEDURES ARE ALREADY IN PLACE FOR | | OPERATOR INTERVENTION IN THE EVENT OF A LOSS OF INSTRUMENT AIR PRESSURE. | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33260 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 11/14/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 14:41 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/14/97 | +------------------------------------------------+EVENT TIME: 11:20[CST]| |NRC NOTIFIED BY: CLARK |LAST UPDATE DATE: 11/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO EXCEEDING DAILY EFFLUENT LIMITS | | | | THE LICENSEE NOTIFIED THE LOUISIANA DEPARTMENT OF ENVIRONMENTAL QUALITY | | REGARDING THE EXCEEDENCE OF THE DAILY AVERAGE AND MAXIMUM LIMITS FOR FREE | | AVAILABLE CHLORINE, AS MEASURED AT THE CIRCULATING WATER NORMAL OUTFALL. | | THIS EVENT OCCURRED OVER A 24-HOUR PERIOD ON 10/22/97, AND THE LICENSEE | | BELIEVES THAT IT WAS DUE TO A UNIT STARTUP THAT WAS IN PROGRESS AT THAT | | TIME. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33261 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/14/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 15:48 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/14/97 | +------------------------------------------------+EVENT TIME: 15:16[EST]| |NRC NOTIFIED BY: WEAVER |LAST UPDATE DATE: 11/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EQUIPMENT DECLARED INOPERABLE DUE TO ENVIRONMENTAL QUALIFICATION CONCERNS | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "DURING ROUTINE WORK IN THE REACTOR BUILDING NORTH STAIRWELL, A PENETRATION | | TO THE NORTH AUXILIARY BAY FROM THE SECONDARY CONTAINMENT WAS DISCOVERED. | | THE HOLE IS APPROXIMATELY 6"x 8" IN SIZE. DUE TO EQ [ENVIRONMENTAL | | QUALIFICATION] CONCERNS, THE EQUIPMENT WITHIN THE NORTH AUXILIARY BAY WAS | | DECLARED INOPERABLE AND THE APPLICABLE TECHNICAL SPECIFICATIONS WERE | | ENTERED. THIS CONDITION APPEARS TO HAVE EXISTED SINCE ORIGINAL | | CONSTRUCTION. WORK IS UNDERWAY TO SEAL THE PENETRATION." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33262 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 11/14/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/14/97 | +------------------------------------------------+EVENT TIME: 15:09[CST]| |NRC NOTIFIED BY: SNIDER |LAST UPDATE DATE: 11/14/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 0 STARTUP | 0 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT BORON DILUTION PREVENTION SYSTEM ACTUATION DURING STARTUP | | | | DURING A UNIT STARTUP, A BORON DILUTION PREVENTION SYSTEM (BDPS) ACTUATION | | OCCURRED DUE TO A VALID SIGNAL. THE EVENT OCCURRED JUST AFTER CRITICALITY | | WHEN SOURCE RANGE COUNTS INCREASED ABOVE THE P-6 PERMISSIVE, THEN | | MOMENTARILY DECREASED BELOW THE P-6 SETPOINT, CAUSING THE PREVIOUSLY | | BLOCKED 'B' TRAIN BDPS ACTUATION LOGIC TO RESET. THE ACTUATION CAUSED | | REFUELING WATER STORAGE TANK VALVE 2CV112E TO OPEN, AND VOLUME CONTROL TANK | | VALVE 2CV112C TO CLOSE, AS DESIGNED. OPERATORS TOOK IMMEDIATE ACTION TO | | BLOCK THE BDPS AND REALIGN THE VALVES TO THEIR ORIGINAL POSITIONS. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33263 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/15/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 03:43 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/15/97 | +------------------------------------------------+EVENT TIME: 01:41[EST]| |NRC NOTIFIED BY: EMPEY |LAST UPDATE DATE: 11/15/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A GROUP 3 PRIMARY CONTAINMENT ISOLATION SIGNAL(PCIS) DUE TO | | THE FAILURE OF A RADIATION MONITOR. | | | | A GROUP 3 PCIS ISOLATION OCCURRED DUE TO AN APPARENT FAILURE OF REACTOR | | BUILDING VENTILATION EXHAUST RADIATION MONITOR CHANNEL "B". THE RESULTING | | ISOLATION INVOLVED THE TRIP AND ISOLATION OF THE REACTOR BUILDING HVAC | | SYSTEM, START OF THE SBGT SYSTEM, ISOLATION OF PRIMARY CONTAINMENT MAKEUP, | | PURGE, INERTING AND EXHAUST VALVES, ISOLATION OF CONTAINMENT AIR MONITORING | | AND ATMOSPHERE DILUTION SYSTEMS. | | | | THE PLANT ENTERED OFF NORMAL PROCEDURE 3153(EXCESSIVE RADIATION LEVELS) AND | | OPERATING EMERGENCY PROCEDURE 3105(SECONDARY CONTAINMENT CONTROL) BASED ON | | A REACTOR BUILDING "B" HI RAD ALARM AND SPIKE OF >14MR/HR OF THE REACTOR | | BUILDING RAD MONITOR "B". THEY COMPLETED IMMEDIATE ACTIONS, VERIFIED NO HI | | RAD LEVELS EXISTED, DETERMINED APPARENT INSTRUMENTATION FAILURE, DETERMINED | | INSTRUMENT INOPERABLE AND RESTORED ALL EQUIPMENT TO ITS ORIGINAL CONDITION. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33264 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/15/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 14:31 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/15/97 | +------------------------------------------------+EVENT TIME: 13:17[CST]| |NRC NOTIFIED BY: JOHN JAECKLE |LAST UPDATE DATE: 11/15/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 47 POWER OPERATION | 47 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO FAILURE TO TEST A PORTION | | OF THE REACTOR PROTECTION SYSTEM LOGIC | | | | "DURING A REVIEW OF GENERIC LETTER 96-01 RESPONSES, IT WAS DETERMINED THAT | | POTENTIAL DISCREPANCIES EXIST IN THE TESTING OF THE REACTOR PROTECTION | | LOGIC PERMISSIVES (P-6, P-7, P-8, P-9, AND P-10). IT WAS DETERMINED THAT | | THIS CONSTITUTED A MISSED SURVEILLANCE OF THESE PERMISSIVES UNDER TECHNICAL | | SPECIFICATION TABLE 15.4.1-1 ITEM #45. AT 1710 CST ON 11/14/97, TS 15.4.0.3 | | WAS ENTERED ON UNIT 2 FOR THE MISSED SURVEILLANCE, WHICH ALLOWS 24 HOURS TO | | PERFORM THE SURVEILLANCE. AT 1130 CST ON 11/15/97, IT WAS DETERMINED THAT | | THE SURVEILLANCE COULD NOT BE PERFORMED WITHIN THE 24 HOURS, AND THE | | REACTOR TRIP FUNCTIONS ASSOCIATED WITH THE PERMISSIVES WERE DECLARED | | INOPERABLE. THE 8 HOUR ACTION STATEMENT OF TS TABLE 15.3.5-2 WAS ENTERED TO | | BRING THE UNIT TO HOT SHUTDOWN. UNIT 2 COMMENCED A LOAD DECREASE FROM 47% | | POWER TO HOT SHUTDOWN AT 1317 CST. UNIT 1 IS CURRENTLY IN COLD SHUTDOWN. A | | CONCURRENT, CONSERVATIVE 4 HOUR REPORT IS BEING MADE FOR THIS SAME | | CONDITION ON UNIT 1." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33265 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 11/16/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 00:39 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/15/97 | +------------------------------------------------+EVENT TIME: 22:00[CST]| |NRC NOTIFIED BY: JACOBSON |LAST UPDATE DATE: 11/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT DECLARED HIGH PRESSURE CORE SPRAY(HPCS) INOPERABLE DUE TO RELAYS | | FAILING TO MEET SURVEILLANCE CRITERIA. | | | | DURING THE PERFORMANCE OF I&C DRYWELL FUNCTIONAL SURVEILLANCE, THREE OUT OF | | FOUR RELAYS FAILED TO MEET ACCEPTANCE CRITERIA. THE FAILURE OF THESE | | RELAYS, E22K77, E22K87, AND E22K97, AFFECTS THREE OUT OF FOUR DRYWELL | | PRESSURE CHANNELS AND THEREFORE HPCS INITIATION CAPABILITY. THE PLANT DID | | NOT ENTER ANY LCO ACTION STATEMENT. WHEN THE RELAYS WERE DISCOVERED TO BE | | INOPERABLE, THEY WERE REPLACED. THE LICENSEE BELIEVES THAT THEIR TESTING | | CRITERIA MAY BE IN QUESTION, SO THEY WILL BE MAKING FURTHER EVALUATION OF | | THE CRITERIA. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33266 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 11/16/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 03:53 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 11/16/97 | +------------------------------------------------+EVENT TIME: 01:23[EST]| |NRC NOTIFIED BY: KNIGHT |LAST UPDATE DATE: 11/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTOMATIC REACTOR TRIP FROM 100% POWER DUE TO LOW STEAM | | GENERATOR LEVEL AND STEAM FLOW GREATER THAN FEEDWATER FLOW. | | | | THE REACTOR TRIP WAS DUE TO LOW LEVEL ON "C" STEAM GENERATOR AND STEAM FLOW | | GREATER THAN FEEDWATER FLOW. THE LOSS OF FEEDWATER IS BELIEVED TO HAVE | | BEEN CAUSED BY SHEAR OF THE "B" MAIN CONDENSATE PUMP SHAFT. ALL RODS FULLY | | INSERTED ON THE REACTOR TRIP AND NO PRIMARY OR STEAM GENERATOR SAFETY | | VALVES LIFTED. THERE ALSO WERE NO ECCS OR ESF ACTUATIONS. THE PLANT | | ENTERED ABNORMAL OPERATING PROCEDURE(AOP-010) TO DETERMINE THE CAUSE OF | | LOSS OF STEAM GENERATOR LEVELS. THE PLANT INITIATED A TURBINE RUNBACK | | MANUALLY TO CONTROL LEVELS, BUT IT WAS UNSUCCESSFUL. ONE SOURCE RANGE | | NUCLEAR INSTRUMENT DID NOT ENERGIZE PROPERLY AND IT HAD TO BE MANUALLY | | ENERGIZED. THEY ARE STILL INVESTIGATING THE CAUSE. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33267 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 11/16/97 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 09:54 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 11/16/97 | +------------------------------------------------+EVENT TIME: 06:55[MST]| |NRC NOTIFIED BY: KELSEY |LAST UPDATE DATE: 11/16/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT WAS NOTIFIED BY THE MARICOPA COUNTY SHERIFF'S OFFICE THAT THEIR | | EMERGENCY SIRENS ARE INOPERABLE. | | | | THIS WAS DETERMINED WHEN THE SHERIFF'S DEPARTMENT MADE A TEST OF THE SIRENS | | AND NONE OF THE SIRENS RESPONDED TO THE TEST. THEY ARE LOOKING INTO WHY | | THE TEST FAILED, SINCE THEY DO NOT BELIEVE THEIR SIRENS ARE INOPERABLE. THE | | LICENSEE BELIEVES THE PROBLEM MAY BE WITH THE SOFTWARE AT THE SHERIFF'S | | OFFICE. THE RESIDENT INSPECTOR WILL BE INFORMED. | | | | * * * UPDATE 1500EST 11/16/97 FROM KELSEY TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT AFTER DETERMINING THAT THE PROBLEM IS | | ASSOCIATED WITH THE MARICOPA COUNTY SHERIFF'S DEPARTMENT. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R4DO(MURRAY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33268 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MQS INSPECTION |NOTIFICATION DATE: 11/16/97 | | CITY: LIMA REGION: 3 |NOTIFICATION TIME: 16:52 [ET]| | COUNTY: STATE: OH |EVENT DATE: 11/16/97 | |LICENSE#: 12-00622-07 AGREEMENT: N |EVENT TIME: 11:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/16/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MELVYN LEACH RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: DOUGLAS CULVER |DON COOL NMSS | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBE 30.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RADIOGRAPHY CAMERA SOURCE STUCK IN COLLIMATOR DUE TO DRIVE CABLE FAILURE | | DURING RETRACTION. | | | | A RADIOGRAPHY CAMERA SOURCE STUCK IN THE COLLIMATOR FOLLOWING A DRIVE CABLE | | CONNECTOR FAILURE AFTER PERFORMING A PIPING PROFILE SHOT AT THE BRITISH | | PETROLEUM OIL FACILITY IN LIMA, OHIO. THE CAMERA IS AN AMERSHAM MODEL | | 660B, SERIAL NUMBER B1430, CONTAINING AN IRIDIUM-192 SOURCE OF 98 CURIES, | | CAPSULE SERIAL NUMBER C4456. THE TWO RADIOGRAPHERS ONSITE CONTACTED THEIR | | RADIATION SAFETY OFFICER (RSO) WHEN THEY DID NOT OBSERVE THE EXPECTED | | INCREASE IN RADIATION LEVELS AS THE SOURCE LEAVES THE COLLIMATOR DURING | | RETRACTION INTO THE SHIELDED VOLUME. THE RSO RESPONDED TO THE SITE AND | | RECOVERED THE SOURCE USING TEMPORARY SHIELDING. THE RSO WAS UNABLE TO | | PROVIDE ANY PRELIMINARY EXPOSURE INFORMATION AND HAS SUBMITTED HIS FILM | | BADGE FOR DOSE ASSESSMENT. THERE WAS NO EXPOSURE TO THE GENERAL PUBLIC AND | | THE RSO NOTIFIED HIS CORPORATE HEADQUARTERS. | | | | SEE HOO LOG FOR CONTACT INFORMATION. | +------------------------------------------------------------------------------+