U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/08/98 - 07/09/98 ** EVENT NUMBERS ** 34402 34490 34491 34492 34493 34494 34495 34496 34497 34498 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34402 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/16/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 08:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/16/98 | +------------------------------------------------+EVENT TIME: 05:54[CDT]| |NRC NOTIFIED BY: HOLLAND |LAST UPDATE DATE: 07/08/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN AUTOMATIC TRANSFER OF A SAFETY BUS OCCURRED DUE TO A POWER INTERRUPTION. | | | | A SHORT (0.3 SECONDS) INTERRUPTION IN POWER TO THE 138KV OFFSITE POWER | | SOURCE CAUSED AN AUTOMATIC TRANSFER OF THE '1C1' 4160V SAFETY BUS FROM THE | | EMERGENCY RESERVE AUXILIARY TRANSFORMER (ERAT) TO THE RESERVE AUXILIARY | | TRANSFORMER. THIS POWER INTERRUPTION WAS CAUSED BY A STORM IN THE AREA. | | THE OTHER TWO SAFETY-RELATED BUSES POWERED BY THE ERAT DID NOT TRANSFER, | | AND THEIR LOADS REMAINED ENERGIZED. NONE OF THE EMERGENCY DIESEL | | GENERATORS STARTED DURING THIS EVENT. CURRENTLY RESTORATION ACTIVITIES ARE | | UNDERWAY. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | * * * UPDATE AT 2356 EDT ON 06/17/98 FROM M. FUNKHOUSER TO MACKINNON * * * | | | | AS A RESULT OF THE ABOVE EVENT, ALL INSTRUMENT AIR AND SERVICE AIR | | CONTAINMENT ISOLATION VALVES CLOSED. (THE CLOSING OF THESE VALVES IS THE | | ENGINEERED SAFETY FEATURE (ESF) ACTUATION.) THE SIX INSTRUMENT AIR AND | | SERVICE CONTAINMENT ISOLATION VALVES THAT CLOSED WERE RE-OPENED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT NOTIFICATION UPDATE | | BY THE LICENSEE. THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO (CLAYTON). | | | | * * * UPDATE AT 0904 EDT 07/08/98 FROM MICHAEL HUDSON TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED ON THE FOLLOWING: | | | | THE FOLLOWING IS A PORTION OF A FACSIMILE RECEIVED IN THE HEADQUARTERS | | OPERATIONS CENTER FROM THE LICENSEE: | | | | "REVIEW OF THIS EVENT HAS DETERMINED THAT THE CONTAINMENT ISOLATION VALVE | | CLOSURE WAS INITIATED BY A LOSS OF POWER TO THE VALVE'S CONTROL CIRCUIT. | | CLOSURE OF THESE VALVES IS INITIATED FROM LEVEL 1 REACTOR VESSEL WATER | | LEVEL INSTRUMENTATION WHICH WAS NOT INITIATED AS A RESULT OF THIS EVENT. | | PER NUREG 1022, SECTION 3.3.2, 'VALID' ESF ACTUATIONS ARE THOSE WHICH ARE A | | RESULT OF VALID SIGNALS INITIATED IN RESPONSE TO ACTUAL PLANT CONDITIONS OR | | PARAMETERS SATISFYING THE REQUIREMENTS FOR AN ESF ACTUATION. SINCE | | INITIATION OF THE LEVEL 1 ISOLATION INSTRUMENTATION DID NOT OCCUR AS A | | RESULT OF THIS EVENT AND [SINCE] THE ISOLATION WAS DETERMINED TO BE A | | RESULT OF THE LOSS OF POWER TO THE VALVE'S CONTROL CIRCUIT, THIS EVENT IS | | NOT CONSIDERED A RESULT OF AN ACTUATION OF AN ESF SYSTEM. THEREFORE, | | CLINTON POWER STATION IS RETRACTING EVENT NOTIFICATION #34402." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R3DO (GARDNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34490 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MATERIALS TESTING LABORATORY |NOTIFICATION DATE: 07/08/98 | | CITY: NEWINGTON REGION: 1 |NOTIFICATION TIME: 10:03 [ET]| | COUNTY: STATE: CT |EVENT DATE: 07/06/98 | |LICENSE#: 31-19-502-01 AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/08/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |NIEL DELLA GRECA RDO | | |JOSIE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEVIN COSGROVE | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MISSING UNDAMAGED TROXLER MOISTURE DENSITY GAUGE - | | | | ON 07/06/98, AN UNDAMAGED TROXLER MOISTURE DENSITY GAUGE (MODEL #3411B) | | CONTAINING 8 MILLICURIES OF CESIUM-137 AND 40-MILLICURIES OF AMERICIUM-241 | | WAS DETERMINED TO BE MISSING DURING AN INVENTORY CHECK. THE GAUGE WAS LAST | | ACCOUNTED FOR ON 05/29/98. ON 05/29/98, AN EMPLOYEE WAS FIRED FROM | | TRI-STATE MATERIALS TESTING COMPANY. ON 07/06/98, THE LOCAL POLICE | | DEPARTMENT WAS INFORMED OF THE POSSIBLE THEFT OF THE GAUGE. TRI-STATE | | MATERIALS TESTING COMPANY OFFICIALS PLAN TO ISSUE A PRESS RELEASE ON THIS | | MISSING GAUGE. | | | | KEVIN COSGROVE OF TRI-STATE MATERIALS TESTING COMPANY HAS ALREADY DISCUSSED | | THIS EVENT WITH NRC REGION 1 (STEVEN COURTEMANCHE), AND HE PLANS TO SUBMIT | | A WRITTEN REPORT TO NRC REGION 1 WITHIN 30 DAYS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34491 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 07/08/98 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 10:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/08/98 | +------------------------------------------------+EVENT TIME: 08:57[EDT]| |NRC NOTIFIED BY: RUSSELL GUMBERT |LAST UPDATE DATE: 07/08/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NEW JERSEY OFFSITE EMERGENCY SIRENS (30 OF THE 34) ARE INOPERABLE DUE TO A | | LOSS OF POWER FOR REASONS UNKNOWN. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "[ARTIFICIAL ISLAND EXPERIENCED A] LOSS OF 30 [OF THE] NEW JERSEY OFFSITE | | SIRENS DUE TO [THE] LOSS OF 2 OFFSITE POWER SUBSTATIONS. ONLY 4 OFFSITE | | SIRENS [ARE] OPERABLE IN NEW JERSEY. ALL OFFSITE SIRENS IN DELAWARE [(37)] | | ARE OPERABLE. CONECTIV DID NOT GIVE AN ESTIMATE OF [THE] TIME [REQUIRED] | | TO RETURN POWER. [THE] TIME OF [THE] POWER LOSS [WAS] 0857 ON 07/08/98. | | [THE] CAUSE OF [THE] LOSS OF POWER IS UNKNOWN AT THIS TIME; HOWEVER, THERE | | ARE STORMS IN THE SOUTH NEW JERSEY AREA." THIS EVENT ALSO AFFECTS HOPE | | CREEK. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1216 ON 07/08/98 FROM RUSSELL GUMBERT TO TROCINE * * * | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | AS OF 1115 [ON 07/08/98], POWER HAS BEEN RESTORED TO ALL OFFSITE SIRENS | | PREVIOUSLY EFFECTED. [IN ADDITION,] THE SIRENS HAVE BEEN TESTED | | SATISFACTORILY EXCEPT FOR [ONE]. INVESTIGATION INTO [THE] CAUSE OF THE | | [ONE] SIREN TEST FAILURE IS ONGOING. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO (NIEL DELLA GRECA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34492 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/08/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:04 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/07/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:11[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/08/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER RDO | | DOCKET: 0707001 |JOSIE PICCONE, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF A 'Q' SAFETY SYSTEM IN RESPONSE TO A VALID SIGNAL | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PADUCAH | | PERSONNEL: | | | | "AT 1511 [CDT ON 07/07/98], THE [#2] NORMETEX PUMP [IN THE] C-315 | | [FACILITY] TRIPPED WHILE RUNNING ON STREAM. [THIS NORMETEX PUMP IS A UF6 | | TAILS PRODUCT STREAM PUMP IN THE TAILS WITHDRAW SYSTEM.] THE OPERATIONAL | | TRIP AND SAFETY SYSTEM TRIP ALARM LIGHTS WERE RECEIVED MOMENTARILY AND | | SUBSEQUENTLY CLEARED. A PRESSURE OF 43 PSIA WAS OBSERVED WHICH IS GREATER | | THAN THE 42-PSIA SAFETY SYSTEM SETTING. THE SAFETY LIMIT OF 45 PSIA WAS | | NOT REACHED. THE APPARENT REASON FOR THE PRESSURE TRANSIENT WAS THE | | CLOSING OF THE DISCHARGE VALVE. THERE IS A NON-SAFETY INTERLOCK WHICH IS | | DESIGNED TO SHUT DOWN THE PUMP IN THE EVENT THE DISCHARGE VALVE CLOSES. | | THERE IS ALSO A NON-SAFETY OPERATIONAL TRIP WHICH IS DESIGNED TO SHUT DOWN | | THE PUMP AT A PRESSURE OF 39 PSIA. THE SAFETY SYSTEM SHUTS DOWN THE PUMP | | AT A PRESSURE OF 42 PSIA. IT IS NOT POSSIBLE AT THIS TIME TO DETERMINE | | WHICH TRIP FUNCTION ACTUALLY SHUT DOWN THE PUMP. [HOWEVER], SINCE A | | PRESSURE OF 43 PSIA WAS OBSERVED, IT IS ASSUMED THAT THE SAFETY SYSTEM TRIP | | PROBABLY ACTUATED IN ADDITION TO THE OTHER TWO NON-SAFETY TRIPS. THE PUMP | | WAS ISOLATED AND REMOVED FROM SERVICE PENDING INVESTIGATION, MAINTENANCE, | | AND TESTING TO RESTORE OPERABILITY." | | | | "THIS EVENT IS REPORTABLE AS A 24-HOUR NOTIFICATION TO THE NRC IN | | ACCORDANCE WITH SAFETY ANALYSIS REPORT, TABLE 6.9-1, CRITERIA J.2, AS AN | | ACTUATION OF A 'Q' SAFETY SYSTEM IS RESPONSE TO A VALID SIGNAL." | | | | PADUCAH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34493 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 07/08/98 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 07/06/98 | +------------------------------------------------+EVENT TIME: : [EDT]| |NRC NOTIFIED BY: JACK BREEN |LAST UPDATE DATE: 07/08/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ELEVEN ENDANGERED BIRDS DIED IN A ROOF DRAINAGE SYSTEM DURING HEAVY RAINS | | | | ELEVEN JUVENILE LEAST TERNS DIED IN THE ROOF DRAINAGE SYSTEM AT THE PLANT'S | | NUCLEAR TRAINING CENTER DURING HEAVY RAINS THAT OCCURRED ON JULY 6 AND 7, | | 1998. (LEAST TERNS ARE BIRDS THAT ARE LISTED ON THE ENDANGERED SPECIES | | ACT.) A LARGE NUMBER OF THESE BIRDS WERE NESTING ON THE ROOF AT THE TIME. | | SCREENS HAD BEEN PLACED AROUND THE DRAINS EARLIER IN THE NESTING SEASON TO | | PREVENT THE BIRDS FROM ENTERING THE DRAIN GUTTERS. HOWEVER, HEAVY RAINFALL | | DAMAGED THE SCREENING (SOME OF THE SCREENS COLLAPSED.), AND THIS ALLOWED | | SOME OF THE YOUNG BIRDS TO BE SWEPT INTO THE DRAINS. THE NUMBER OF BIRDS | | THAT DIED DURING THIS EVENT REPRESENTED A VERY SMALL PORTION OF THE LEAST | | TERN HATCHLINGS FROM THIS PARTICULAR AREA. | | | | INITIAL ACTIONS INCLUDED THE REPAIR OF THE PRESENT SCREEN DEVICES THAT WERE | | ALREADY IN PLACE. ADDITIONAL MONITORING OF THE SCREENING HAS ALSO BEEN | | IMPLEMENTED TO HELP PREVENT FURTHER MORTALITIES. IN ADDITION, PRIOR TO THE | | NEXT NESTING SEASON, THE LICENSEE PLANS TO TAKE MEASURES TO PREVENT THE | | BIRDS FROM NESTING IN THIS PRECARIOUS AREA. THE LICENSEE IS CURRENTLY | | INVESTIGATING OTHER PROTECTIVE MEASURES. | | | | THIS EVENT NOTIFICATION WAS MADE AS A 72-HOUR REPORT IN ACCORDANCE WITH | | SECTION 4.1 OF THE LICENSEE'S ENVIRONMENTAL PROTECTION PLAN WHICH IS | | APPENDIX 'B' OF THE FACILITY'S OPERATING LICENSE. THE LICENSEE ALSO PLANS | | TO SUBMIT A 30-DAY WRITTEN REPORT TO DOCUMENT THIS EVENT PURSUANT TO THE | | SAME REQUIREMENT. | | | | HOO NOTE: ANOTHER EVENT REGARDING THE DEATH OF TWO LEAST TERNS WAS | | REPORTED ON 07/17/91. (REFER TO EVENT #21398 FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE. THE | | LICENSEE ALSO PLANS TO NOTIFY APPROPRIATE LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34494 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 07/08/98 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 07/08/98 | +------------------------------------------------+EVENT TIME: 15:05[PDT]| |NRC NOTIFIED BY: HOWARD SMITH |LAST UPDATE DATE: 07/08/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FAILURE OF CONTROL ROOM PERSONNEL THYROID DOSE TO MEET THE | | REQUIREMENTS OF GENERAL DESIGN CRITERIA 19 WHEN SPECIFIC ASSUMPTIONS ARE | | USED | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON JULY 8, 1998, AT 1505 PDT, ... WHILE REVIEWING AND REVISING POST-[LOSS | | OF COOLANT ACCIDENT] CONTROL ROOM DOSE CALCULATIONS, [THE LICENSEE] | | RECOGNIZED THAT THYROID DOSE TO CONTROL ROOM PERSONNEL MAY NOT MEET THE | | REQUIREMENTS OF GENERAL DESIGN CRITERIA [(GDC)] 19 (30 REM) WHEN THE | | ASSUMPTIONS LISTED IN THE [UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR)] AS | | 'DESIGN BASIS' ARE USED. WHILE THE CALCULATIONS ARE NOT FINALIZED, [THE | | LICENSEE] NO LONGER HAS REASONABLE ASSURANCE THAT THE ACCEPTANCE CRITERIA | | WILL BE MET. FINAL RESULTS ARE EXPECTED IN ABOUT 4 WEEKS." | | | | "THIS CONDITION WAS CAUSE PRIMARILY BY [THE FOLLOWING] TWO FACTORS:" | | | | "FIRST, THE ORIGINAL CALCULATIONS (CIRCA 1980) DID NOT INCLUDE LEAKAGE | | INTO THE CONTROL ROOM." | | | | "SECOND, SOME LEAKAGE TERMS DID NOT INCLUDE THE MARGIN REQUIRED BY THE | | REGULATIONS SUCH AS DOUBLING THE ALLOWABLE ENGINEERING SAFETY FEATURE | | (ESF) SYSTEM LEAKAGE." | | | | "[THE LICENSEE] BELIEVES [THAT] THIS CONDITION HAS NO SAFETY SIGNIFICANCE | | [FOR THE FOLLOWING REASONS:]" | | | | "FIRST, THE DESIGN BASIS ASSUMPTIONS AND METHODOLOGY USED FOR | | PERFORMING THE CALCULATIONS ARE CONSERVATIVE COMPARED TO THE | | 'REALISTIC' CALCULATION (ABOUT A FACTOR OF 30), AND THE RESULTS ARE | | EXPECTED TO EXCEED THE CRITERIA ONLY MARGINALLY (ABOUT 15%). FOR | | EXAMPLE, THE UFSAR ASSUMES [THAT REACTOR COOLANT SYSTEM] LEAKAGE | | OUTSIDE CONTAINMENT IS 5,950 CC/HR, WHEN IN REALITY, THE MEASURED | | LEAKAGE IS APPROXIMATELY 3 CC/HR." | | | | "SECOND, THE CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM ... REMAINS | | OPERABLE AND CAPABLE OF MAINTAINING DOSES BELOW THE GDC-19 CRITERION. | | GENERIC LETTER 91-18 ALLOWS THE USE OF TEST INFORMATION TO SUPPORT | | OPERABILITY DETERMINATIONS. IN THIS CASE, ... THE MEASURED CHARCOAL | | FILTER EFFICIENCY IS GREATER THAN THE ASSUMED VALUE[, AND] THE ESF | | LEAKAGES MEASURED DURING THE LAST REFUELING OUTAGE ARE LESS THAN THE | | ASSUMED VALUES." | | | | "ON MAY 7, 1998, [THE LICENSEE] REQUESTED APPROVAL OF [TECHNICAL | | SPECIFICATION PLANT CHANGE NOTICE] PCN-492. THIS CHANGE OF THE DEFINITION | | OF 'DOSE EQUIVALENT IODINE-131' WILL ALLOW USE OF THE MORE REALISTIC | | [INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION] PUBLICATION 30 | | THYROID INHALATION DOSE CONVERSION FACTORS RATHER THAN THOSE OF | | [REGULATION] GUIDE 1.109. THIS NEW DEFINITION IS INCORPORATED INTO THE | | COMBUSTION ENGINEERING STANDARD [TECHNICAL SPECIFICATIONS], AND [IT] HAS | | BEEN APPROVED FOR PALO VERDE." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34495 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/08/98 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/08/98 | +------------------------------------------------+EVENT TIME: 18:10[EDT]| |NRC NOTIFIED BY: MARK SCHALL |LAST UPDATE DATE: 07/08/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL TO EXCEED FUEL DESIGN LIMITS DURING A GENERATOR LOAD REDUCTION | | WHICH IS INITIATED AUTOMATICALLY IN RESPONSE TO A LOSS OF STATOR COOLING | | | | "[A] REVIEW OF [THE] UNIT 2 PLANT DESIGN HAS QUESTIONED THE ABILITY TO | | RESPOND TO A CREDIBLE STEAM PLANT TRANSIENT. DURING A GENERATOR LOAD | | REDUCTION, WITHOUT OPERATOR ACTION, INITIATED AUTOMATICALLY IN RESPONSE TO | | A LOSS OF STATOR COOLING, IT MAY BE POSSIBLE TO EXCEED THE FUEL DESIGN | | LIMITS. DURING A LOSS OF STATOR COOLING, THE TURBINE CONTROL SYSTEM | | RESPONDS TO TRANSFER STEAM FROM THE TURBINE TO THE CONDENSER VIA [THE] | | TURBINE BYPASS VALVES. THIS REDUCES THE FEEDWATER PREHEATING BY TURBINE | | EXTRACTION STEAM AND CAUSES A REDUCTION IN MODERATOR TEMPERATURE. THE | | AUTOMATIC GENERATOR LOAD REDUCTION MAY RESULT IN A FINAL FEEDWATER | | TEMPERATURE REDUCTION IN EXCESS OF THOSE USED IN THE CURRENT CORE LOAD | | ANALYSIS. [GENERAL ELECTRIC] [SERVICE INFORMATION LETTER] 581, LOSS OF | | MAIN GENERATOR STATOR COOLING, DESCRIBES THE EVENT AND POTENTIAL PLANT | | TRANSIENTS. THIS DOES NOT APPLY TO BRUNSWICK UNIT 1 DUE TO A SMALLER | | TURBINE BYPASS CAPABILITY." | | | | "[THE LICENSEE BELIEVES THAT] THIS EVENT HAS MINOR SAFETY SIGNIFICANCE. A | | REVIEW OF [THE] GENERIC [BOILING WATER REACTOR]-4 DESIGN INDICATES THAT FOR | | FEEDWATER TEMPERATURE REDUCTIONS LARGER THAN BELIEVED CREDIBLE FOR THE | | BRUNSWICK SPECIFIC DESIGN, [THE WORST CASE MINIMUM CRITICAL POWER RATIO] | | WILL NOT BE EXCEEDED. ADDITIONALLY, THE TRANSIENT PROCEEDS SLOWLY, AND | | IMMEDIATE OPERATOR ACTION AS DIRECTED BY CURRENT PROCEDURES, IF INITIATED | | WITHIN APPROXIMATELY 5 MINUTES, WOULD BE SUFFICIENT TO PREVENT EXCEEDING | | DESIGN LIMITS FOR THE FUEL. THE EVENT AT 100 PERCENT POWER IS BELIEVED TO | | BE PROTECTED BY THE FLOW REFERENCED SCRAM SETPOINT. AT LOWER POWER LEVELS, | | [MAXIMUM AVERAGE PLANAR RATIO (MAPRAT)] LIMITS MIGHT BE EXCEEDED, DEPENDING | | ON CORE INITIAL CONDITIONS." | | | | "ADMINISTRATIVE LIMITS HAVE BEEN ESTABLISHED TO LIMIT MAPRAT SUCH THAT THE | | PLANT WOULD BE WITHIN THE CURRENT DESIGN LIMITS FOLLOWING A STATOR COOLING | | RUNBACK." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34496 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/08/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:56 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:15[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/08/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER RDO | | DOCKET: 0707001 |SUSAN SHANKMAN, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | |OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EQUIPMENT DISABLED OR FAILS TO FUNCTION AS DESIGNED (24-HOUR REPORT) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE PADUCAH | | PERSONNEL: | | | | "AT 0115 CDT [ON 07/08/98], A UF6 DETECTOR IN [THE] C-315 [FACILITY] ON | | [THE #2] WITHDRAWAL POSITION FIRED [(ACTUATED)]. THIS DETECTOR IS PART OF | | THE HIGH VOLTAGE UF6 RELEASE DETECTION SYSTEM FOR UF6 CONDENSERS, | | ACCUMULATORS, AND PIPING HEATED HOUSINGS, AND [IT] SOUNDS THE BUILDING | | ALARM HORN AND AN ALARM IN THE LOCAL CONTROL ROOM TO ALERT PERSONNEL TO A | | POSSIBLE RELEASE OF HAZARDOUS MATERIAL. THE ALARM RESPONSE PROCEDURE WAS | | FOLLOWED. NO EVIDENCE OF A RELEASE WAS FOUND, BUT THE ALARM WOULD NOT | | CLEAR. WITH THIS ALARM 'LOCKED IN,' SUBSEQUENT AUDIBLE ALARMS FROM OTHER | | DETECTORS COULD NOT BE RECEIVED. THE RELEASE DETECTION SYSTEM WAS DECLARED | | INOPERABLE, AND A 'SMOKE' WATCH WAS IMPLEMENTED IN ACCORDANCE WITH | | [TECHNICAL SPECIFICATION REQUIREMENT' 2.3.4.4, ACTION A.1. THE DETECTOR IN | | ALARM WAS DISCONNECTED, AND THE SYSTEM WAS TESTED AND RESTORED TO OPERABLE | | STATUS. THE WITHDRAWAL POSITION SERVED BY THIS DETECTOR WAS REMOVED FROM | | SERVICE PENDING INVESTIGATION, MAINTENANCE, AND TESTING." | | | | PADUCAH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34497 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/08/98 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:29 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/08/98 | +------------------------------------------------+EVENT TIME: 17:50[EDT]| |NRC NOTIFIED BY: MICHELE SAVINO |LAST UPDATE DATE: 07/08/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A DEFICIENCY IN AN EMERGENCY OPERATING PROCEDURE | | | | BASED UPON PRELIMINARY ENGINEERING ANALYSIS, IT WAS DETERMINED THAT A | | DEFICIENCY IN EMERGENCY OPERATING PROCEDURE ES1.3, TRANSFER TO COLD LEG | | RECIRCULATION, COULD HAVE RESULTED IN OPERATOR ACTIONS, IN THE EVENT OF AN | | ACCIDENT, THAT COULD PLACE THE PLANT OUTSIDE ITS DESIGN BASIS. | | SPECIFICALLY, IN THE EVENT OF A LARGE BREAK LOSS OF COOLANT ACCIDENT | | OCCURRING CONCURRENTLY WITH A SINGLE FAILURE OF ONE INTERNAL RECIRCULATION | | PUMP, THE OPERATOR WOULD BE DIRECTED TO INITIATE HIGH HEAD RECIRCULATION AS | | A RESULT OF CONSIDERATION OF ADVERSE CONTAINMENT INSTRUMENT ERRORS WHEN | | PLACING RECIRCULATION SPRAY INTO SERVICE. THE DESIGN BASIS FOR THE | | INTERNAL RECIRCULATION SYSTEM IS TO ACCOMMODATE BOTH CORE COOLING AND | | CONTAINMENT SPRAY ASSUMING A SINGLE ACTIVE FAILURE. | | | | THE UNIT IS NOT IN A LIMITING CONDITION FOR OPERATION AS A RESULT OF THIS | | ISSUE BECAUSE OF THE CURRENT MODE (COLD SHUTDOWN). | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34498 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/09/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:28 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:58[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/09/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |RONALD GARDNER RDO | | DOCKET: 0707001 |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RANDY BOSHELL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT EQUIPMENT OVERLOADED NORMETEX PUMP PGLD SYSTEM POWER SUPPLY - | | | | AT 0958 CDT ON 07/08/98, THE C-310 BUILDING NORMETEX PUMP PROCESS GAS | | LEAK DETECTOR (PGLD) SYSTEM SUPPLY POWER WAS INTERRUPTED WHEN THE CIRCUIT | | BREAKER SUPPLYING POWER TO THE PGLD SYSTEM TRIPPED. PLANT EQUIPMENT | | CONNECTED TO RECEPTACLES FED FROM THIS CIRCUIT BREAKER CAUSED THE TRIP. | | PLANT PERSONNEL DECLARED THE PGLD SAFETY SYSTEM INOPERABLE AND INITIATED | | TECHNICAL SAFETY REQUIREMENT REQUIRED ACTIONS. | | | | PLANT PERSONNEL DISCONNECTED THE PLANT EQUIPMENT FROM THE RECEPTACLES, | | RESET THE CIRCUIT BREAKER TO RETURN THE NORMETEX PUMP PGLD SYSTEM TO | | SERVICE, AND DECLARED THE PGLD SYSTEM OPERABLE. | | | | PLANT PERSONNEL PLACED CAUTION TAGS ON THE RECEPTACLES TO PREVENT THEM | | FROM BEING USED AND ARE DETERMINING LONG TERM CORRECTIVE ACTIONS. | | | | PLANT PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+