U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/13/98 - 05/14/98 ** EVENT NUMBERS ** 34106 34195 34217 34219 34220 34221 34222 34223 34224 34225 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34106 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/20/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/20/98 | +------------------------------------------------+EVENT TIME: 10:17[EDT]| |NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 05/13/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 80 POWER OPERATION | 80 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - RCIC SYSTEM INOPERABLE DUE TO FAILURE OF RCIC SYSTEM BATTERY CHARGER - | | | | AT 1017 ON 04/20/98, THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM | | BATTERY CHARGER UNEXPECTEDLY SHUT DOWN. THE LICENSEE DECLARED THE RCIC | | SYSTEM INOPERABLE WHICH PLACES THE PLANT IN A 14 DAY SHUTDOWN LCO. | | LICENSEE ATTEMPTS TO RESET THE CHARGER HAVE, AS YET, PROVEN UNSUCCESSFUL. | | LICENSEE TROUBLESHOOTING IS CONTINUING. THE RCIC SYSTEM IS LINED UP FOR | | OPERATION AND ITS BATTERIES ARE STILL CAPABLE OF SUPPLYING ELECTRICAL | | ENERGY TO THE REQUIRED SYSTEM COMPONENTS NECESSARY TO SUPPORT OPERATION. | | | | THE PLANT REMAINS AT 80% POWER IN SUPPORT OF ONLINE HYDRAULIC CONTROL UNIT | | MAINTENANCE ACTIVITIES. CURRENTLY, SEVEN CONTROL RODS ARE INOPERABLE. | | PLANT TECHNICAL SPECIFICATIONS PERMIT A MAXIMUM OF EIGHT CONTROL RODS TO | | BE INOPERABLE AT ANY ONE TIME. | | | | ADDITIONALLY, THE FOLLOWING EQUIPMENT IS INOPERABLE FOR SCHEDULED | | MAINTENANCE ACTIVITIES AND IS EXPECTED TO BE RESTORED TO OPERABLE STATUS | | THIS AFTERNOON: 'B' STANDBY LIQUID CONTROL PUMP, 'B' MAIN GENERATOR | | STATOR WATER COOLING PUMP, AND THE 'B' HYDROGEN/OXYGEN ANALYZER (ONE OF | | ITS CONTAINMENT ISOLATION VALVES). | | | | THE LICENSEE NOTIFIED LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | | | | *** RETRACTION ON 5/13/98 @ 1427 BY MEYERS TO GOULD *** | | | | SUBSEQUENT TO THE ABOVE INFORMATION, THE CAUSE OF THE RCIC BATTERY CHARGER | | TRIP WAS ATTRIBUTED TO A DEFECTIVE HIGH VOLTAGE SHUTDOWN(HVSD) CARD. A NEW | | CARD WAS INSTALLED AND THE RCIC SYSTEM BATTERY CHARGER WAS DECLARED | | OPERABLE. WHILE THE RCIC BATTERY CHARGER WAS INOPERABLE, THE RCIC SYSTEM | | WAS LINED UP FOR OPERATION AND THE RCIC BATTERIES WERE STILL CAPABLE OF | | SUPPLYING ELECTRICAL ENERGY TO THE REQUIRED RCIC SYSTEM COMPONENTS TO | | SUPPORT OPERATION. A CONSERVATIVE ASSESSMENT OF BATTERY CAPACITY | | THROUGHOUT THE APPROXIMATE FIVE HOUR PERIOD WHEN THE BATTERY CHARGER WAS | | DISCONNECTED FROM THE RCIC BATTERY CONCLUDED THAT THE RCIC BATTERIES | | REMAINED CAPABLE OF PERFORMING ITS SAFETY FUNCTION DURING THE PERIOD THE | | BATTERY CHARGER WAS INOPERABLE. THEREFORE THE LICENSEE IS RETRACTING THIS | | EVENT. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | THE REG 1 RDO(WHITE) WAS NOTIFIED | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34195 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/08/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:24 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:10[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/13/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND RDO | | DOCKET: 0707002 |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR 91-01 BULLETIN NOTIFICATION INVOLVING A LOSS OF SPACING. | | | | "ON MAY 8, 1998 AT 0110 HOURS OPERATIONS PERSONNEL DISCOVERED THAT A | | NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) WAS NOT BEING MAINTAINED WITH | | THE X-330 PROCESS BUILDING. DRY ACTIVE WASTE (DAW) WAS DISCOVERED STORED | | TOO CLOSE TO A WATER SOLUBLE LAUNDRY BAG (<2 FEET). THIS VIOLATES | | REQUIREMENT #5 OF NCSA-PLANT018.A01 WHICH STATES IN PART, 'DAW SHALL | | MAINTAIN A MINIMUM TWO (2) FEET EDGE-TO-EDGE SPACING FROM ALL OTHER URANIUM | | BEARING MATERIALS/EQUIPMENT.' THIS CONSTITUTES A LOSS OF ONE CONTROL | | (INTERACTION/SPACING) IN THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY | | EVENT B.4.1. CONTROL 'A' (INTERACTION/SPACING) WAS LOST. CONTROL 'B' | | (MASS) WAS MAINTAINED THROUGHOUT THIS EVENT. CONTROL 'A' WAS ESTABLISHED | | AT 0150 HOURS UNDER THE DIRECTION OF ON SCENE NUCLEAR CRITICALITY | | PERSONNEL. THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIALS OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE DOE SITE | | REPRESENTATIVE. | | | | ***RETRACTION ON 05/13/98 AT 1436 ET BY KURT SISLER TAKEN BY MACKINNON*** | | | | TODAY AT O800 ET THE PLANT SHIFT SUPERINTENDENT DOWNGRADED THE ABOVE EVENT. | | AFTER A NUCLEAR CRITICALITY SAFETY REVIEW, IT WAS DETERMINED THAT THE WATER | | SOLUBLE BAG DID NOT CONTAIN URANIUM BEARING MATERIAL. SINCE THERE WAS NO | | VIOLATION OF NCSA-PLANT018.A01 REQUIREMENT # 5, THIS IS NOT REPORTABLE PER | | NRC BULLETIN 91-01. NOTIFIED R3DO (JIM CREED) AND EO(LARRY CAMPER). | | | | THE NRC RESIDENT INSPECTOR AND THE ONSITE DEPARTMENT OF ENERGY WERE | | INFORMED OF THIS RETRACTION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34217 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/12/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:52 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/12/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:54[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/13/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 |JOHN GREEVES EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: VANDERPOOL | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR 91-01 BULLETIN RESPONSE | | | | OPERATIONS PERSONNEL IDENTIFIED A NUCLEAR CRITICALITY SAFETY APPROVAL(NCSA) | | WHICH WAS NOT BEING MAINTAINED WITHIN THE "X-330" PROCESS BUILDING. | | | | A [WEEKLY SAMPLING] SURVEILLANCE FOR CELLS 29-5-2 AND 29-5-8 INDICATED THAT | | [THESE] CELLS, WHICH SHOULD HAVE BEEN IN A FLUORINATING ENVIRONMENT, | | EXHIBITED CONFLICTING RESULTS FROM ADJACENT [SAMPLED] STAGES SUCH THAT THE | | FLUORINATING ENVIRONMENT COULD NOT BE CONFIRMED. WITHOUT A FLUORINATING | | ENVIRONMENT, THE CELLS ARE AT A UF6 NEGATIVE. THESE CELLS HAVE BEEN | | CLASSIFIED AS PEH(PLANNED EXPEDITIOUS HANDLING) INDICATING MORE THAN A SAFE | | MASS OF FISSIONABLE MATERIAL WAS INVOLVED. NCSA-0330-004.A02, REQUIREMENT | | #8 STATES IN PART, "ANY CASCADE EQUIPMENT SHUTDOWN(MOTORS OFF) AND AT A UF6 | | NEGATIVE SHALL HAVE A PLANT DRY AIR OR NITROGEN BUFFER ESTABLISHED ò14 | | PSIA. THE NCSA FURTHER STATES THAT WHEN A PEH DEPOSIT EXISTS, THE SYSTEM | | DOES NOT MEET THE DOUBLE CONTINGENCY PRINCIPLE. OPERATIONS PRESSURED THE | | CELLS TO >14 PSIA WITHIN 8 HOURS WHICH IS A TSR REQUIREMENT. NCSA CONTROL | | WAS ESTABLISHED AT 1900 HRS FOR 29-5-8 AND 2100 HRS FOR 29-5-2. NCSA | | CONTROL FOR BOTH CELLS WAS ESTABLISHED WITHIN THE 4 HR RECOVERY TIME FRAME. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED AND THE DOE RESIDENT WILL BE | | INFORMED. | | | | ***UPDATE ON 05/13/98 AT 1440 ET BY RICK LARSON TAKEN BY MACKINNON*** | | | | PORTSMOUTH IS CHANGING THIS REPORT FROM A 4 HOUR NRC BULLETIN 91-01 TO A 24 | | HOUR NRC BULLETIN 91-01 REPORT. ALSO SOME WORDING WAS CHANGED IN THE ABOVE | | TEXT- NOTED BY []. R3DO (JIM CREED) AND EO (LARRY CAMPER) | | | | THE NRC RESIDENT INSPECTOR AND THE ONSITE DEPARTMENT OF ENERGY | | REPRESENTATIVE WERE NOTIFIED OF THIS EVENT UPDATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34219 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 05/13/98 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 10:32 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 05/13/98 | +------------------------------------------------+EVENT TIME: 09:55[EDT]| |NRC NOTIFIED BY: ROBERT J. HANKE |LAST UPDATE DATE: 05/13/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANN BOLAND RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 40 POWER OPERATION | 40 POWER OPERATION | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED THAT IF CERTAIN NON SAFETY RELATED LOADS WERE TO FAULT, | | A LOSS OF THE "B" TRAIN EMERGENCY SUMP RECIRCULATION COULD OCCUR. THIS | | DESIGN DISCREPANCY APPLIES TO BOTH UNITS. | | | | "DURING A DESIGN REVIEW BEING PERFORMED ON THE 120 VOLT AC INSTRUMENT BUSES | | FOR TURKEY POINT UNITS 3 AND 4 CERTAIN NON-SAFETY RELATED CIRCUITS WERE | | IDENTIFIED WHICH, IF THEY WERE TO FAULT, WOULD RESULT IN A LOSS OF POWER TO | | SAFETY RELATED CIRCUITS SUCH THAT THE SAFETY RELATED CIRCUITS WOULD FAIL IN | | AN UNSAFE CONDITION. FAULTS OF NON SAFETY RELATED INSTRUMENT CIRCUITS | | ASSOCIATED WITH INSTRUMENT PANEL 3(4) P06 WOULD RESULT IN OPENING OF A | | VITAL INSTRUMENT BUS BREAKER CAUSING A LOSS OF POWER TO PRESSURE CONTROLLER | | AUXILIARY RELAY PC-600X. A LOSS OF POWER TO THIS PRESSURE CONTROLLER | | AUXILIARY RELAY WOULD PREVENT MOV-863B FROM BEING OPENED. THIS VALVE IS | | REQUIRED TO BE OPENED POST-LOCA TO PERMIT EMERGENCY SUMP RECIRCULATION IN | | THE 'PIGGY-BACK' MODE OF OPERATION. THE REDUNDANT 'A' TRAIN PRESSURE | | CONTROLLER RELAY PC-601X WAS FOUND TO BE PROPERLY DESIGNED. IN THE EVENT | | OF A LOCA, MOV-863B WOULD NOT OPEN IF PC-600X LOSES POWER. IF A SINGLE | | FAILURE IS ASSUMED OF EITHER PC-601X, AN 'A' TRAIN POWER SUPPLY, OR | | MOV-863A, EMERGENCY SUMP RECIRCULATION CAPABILITY WOULD BE LOST. THIS IS A | | CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT. | | | | "BECAUSE THE 'A' RECIRCULATION LOOP REMAINS OPERABLE, BOTH TURKEY POINT | | UNITS HAVE ENTERED TECHNICAL SPECIFICATION 3.5.2 ACTION STATEMENT a (72 | | HOURS) FOR HAVING ONE OF TWO EMERGENCY RECIRCULATION LOOPS OUT OF SERVICE. | | THOUGH THE 'B' LOOP OF RHR HAS BEEN DECLARED INOPERABLE, IT REMAINS | | AVAILABLE. CORRECTIVE ACTION IS PROCEEDING TO REPOWER THE AFFECTED | | PRESSURE CONTROLLERS FROM APPROPRIATELY PROTECTED SAFETY RELATED POWER | | SUPPLIES." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34220 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 05/13/98 | |UNIT: [1] [ ] [ ] STATE: MD |NOTIFICATION TIME: 10:35 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 05/13/98 | +------------------------------------------------+EVENT TIME: 10:35[EDT]| |NRC NOTIFIED BY: PAUL CATZ |LAST UPDATE DATE: 05/13/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |NINF INFORMATION ONLY | | |NLCO TECH SPEC LCO A/S |JIM WIGGINS REG1 | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TOTAL STEAM TUBES PLUGGED IN 1998 IS 114 FOR STEAM GENERATOR 11 AND 169 FOR | | STEAM GENERATOR 12. | | | | A 100% BOBBIN COIL INSPECTION WAS MADE TUBE END TO TUBE END. A PLUS POINT | | INSPECTION FOCUSED ON REGIONS OF THE STEAM GENERATORS THAT HAVE EXPERIENCED | | DEGRADATION IN THE PAST OR RECENT INDUSTRY INFORMATION IDENTIFIES A | | DEGRADATION MECHANISM TO WHICH CALVERT CLIFFS NUCLEAR POWER PLANT STEAM | | GENERATORS ARE SUSCEPTIBLE. THE EXAM RESULTS ARE AS FOLLOWS: | | | | STEAM GENERATOR 11: TOTAL HOT LEG TOP OF TUBESHEET PLUGGED, 29; TOTAL UPPER | | TUBE BUNDLE ARC AND STAY DOME REGIONS PLUGGED, 55; TOTAL STEAM BLANKET | | REGION PLUGGED,3; TOTAL COLD LEG TOP OF TUBESHEET PLUGGED, 10; AND OTHER | | REGIONS PLUGGED, 17. TOTAL PLUGGED FOR STEAM GENERATOR 11 FOR 1998 IS 114. | | | | STEAM GENERATOR 12: TOTAL HOT LEG TOP OF TUBESHEET PLUGGED, 33; TOTAL UPPER | | TUBE BUNDLE ARC AND STAY DOME REGIONS PLUGGED, 95; TOTAL STEAM BLANKET | | REGION, 2; TOTAL COLD LEG OF TUBESHEET PLUGGED, 19; AND OTHER REGIONS | | PLUGGED, 20. TOTAL PLUGGED FOR STEAM GENERATOR 12 FOR 1998 IS 169. | | | | OUTSIDE DIAMETER STRESS CORROSION CRACKING REMAINS THE PRIMARY FORM OF | | DEGRADATION. OUTSIDE DIAMETER STRESS CORROSION CRACKING INITIATION RATES | | AND GROWTH RATES ARE SMALLER THAN THE 1996 INSPECTION RESULTS IMPLIED. 1996 | | RESULTS WERE THE RESULT OF CRACK INITIATION AND GROWTH OVER SEVERAL CYCLES | | OF OPERATION. WEAR IS MINOR AND SLOWLY PROGRESSING. | | | | THIS EVENT WAS REPORTED TO NRC REGION 1 ADMINISTRATOR PER CALVERT CLIFFS | | UNIT 1 TECHNICAL SPECIFICATION 4.4.5.5.C. NRC REGION 1 REQUESTED THAT NRC | | REGION 1 AND THE LICENSEE BE PLACED ON THE NRC OPERATIONS CENTER BRIDGE AND | | THAT THE NRC OPERATIONS CENTER TAKE THE INFORMATION SUPPLIED BY THE | | LICENSEE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT NOTIFICATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 34221 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NEW YORK HOSPITAL-CORNELL MED CTR |NOTIFICATION DATE: 05/13/98 | | CITY: NEW YORK CITY REGION: 1 |NOTIFICATION TIME: 14:39 [ET]| | COUNTY: STATE: NY |EVENT DATE: 05/12/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/13/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN WHITE RDO | | |LARRY CAMPER EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: MISKIN(BUR OF RAD HEALTH) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NEW YORK HOSPITAL-CORNELL MEDICAL CENTER NOTIFIED THE NY BUREAU OF | | RADIOLOGICAL HEALTH OF A MEDICAL MISADMINISTRATION. | | | | THE MEDICAL MISADMINISTRATION OCCURRED ON 5/12/98 AND INVOLVED A NOVOSTE | | INTRACORONARY RADIATION DEVICE. THIS DEVICE WAS INSERTED INTO THE PATIENT | | BUT INSTEAD OF 12 SOURCES OF Sr-90 BEING TRANSFERRED TO THE INTRACORONARY | | SITE, ONLY 6 SOURCES WERE TRANSFERRED. THE THERAPY PHYSICIST HAS | | CALCULATED THAT INSTEAD OF THE PATIENT RECEIVING THE INTENDED 18 Gy OVER A | | DISTANCE OF 3 CM, THE PATIENT RECEIVED ONLY 8.7 Gy OVER A DISTANCE OF 1.5 | | CM. THE 6 Sr-90 SOURCES WERE RETURNED TO THE DEVICE AND THE DEVICE WAS | | RETURNED TO NOVOSTE TO DETERMINE WHAT CAUSED THE DEVICE TO FAIL TO DELIVER | | 6 OF THE 12 SOURCES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34222 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/13/98 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/13/98 | +------------------------------------------------+EVENT TIME: 14:35[EDT]| |NRC NOTIFIED BY: RUPPERT |LAST UPDATE DATE: 05/13/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ELECTRICAL PENETRATION OVERCURRENT PROTECTION CIRCUITS | | DO NOT MEET SINGLE FAILURE CRITERION. | | | | THE PRIMARY CONTAINMENT ELECTRICAL PENETRATION OVERCURRENT PROTECTION | | CIRCUITS FOR INBOARD PCIVs ON UNIT 1 AND 2 RHR SHUTDOWN COOLING LINE, RWCU | | SYSTEM, MAIN STEAM LINE DRAIN, AND PRIMARY CONTAINMENT INSTRUMENT GAS | | SUCTION LINE DO NOT MEET SINGLE FAILURE CRITERION FOR SPECIFIC, BUT | | LIMITED, TIME CURRENT FAULTED CONDITIONS. A TOTAL OF 4 VALVES PER UNIT ARE | | AFFECTED. UNDER THESE LIMITED CONDITIONS, THE INSTANTANEOUS OVERCURRENT | | TRIP BREAKER WOULD NOT ACTUATE AND A FAILURE OF THE THERMAL MAGNETIC | | OVERCURRENT TRIP BREAKER COULD RESULT IN SUFFICIENT DAMAGE TO THE | | ELECTRICAL PENETRATION TO RENDER THE PENETRATION INOPERABLE. THE UFSAR AND | | THE CORRESPONDING SECTIONS OF THE SER STATE THAT THE PENETRATION | | OVERCURRENT PROTECTION SYSTEM MEETS THE SINGLE FAILURE CRITERION AND IS | | CONSIDERED NECESSARY TO MEET THE DESIGN BASIS FOR THIS SYSTEM. THE | | NOTIFICATION IS BEING MADE FOR UNIT 2 SINCE IT IS OPERATING. UNIT 1 HAS A | | SIMILAR CONDITION, BUT IT IS IN A REFUELING OUTAGE AND PRIMARY CONTAINMENT | | PENETRATION PROTECTION IS NOT REQUIRED TO BE OPERABLE. FOR EACH AFFECTED | | PENETRATION, THE THERMAL MAGNETIC OVERCURRENT PROTECTION BREAKER IS | | OPERABLE AND AN EVALUATION HAS CONCLUDED THAT THERE ARE NO CREDIBLE FAULTED | | CONDITIONS NOTED. THEREFORE, IT IS CONCLUDED THAT THIS CONDITION DOES NOT | | RESULT IN A SERIOUSLY DEGRADED NOR UNANALYZED CONDITION. A PLANT | | MODIFICATION WILL PROVIDE A REDUNDANT OVERCURRENT TRIP DEVICE THAT WILL | | INCLUDE PROTECTION FOR THE LIMITED TIME CURRENT CONDITION. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | HOO NOTE: SEE SIMILAR EVENT #34186 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34223 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY FT RILEY KS |NOTIFICATION DATE: 05/13/98 | | CITY: FT RILEY REGION: 4 |NOTIFICATION TIME: 16:09 [ET]| | COUNTY: STATE: KS |EVENT DATE: 05/13/98 | |LICENSE#: 12-00722-13 AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/13/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES CREED RDO | | |LARRY CAMPER EO | +------------------------------------------------+TOM STETKA RDO4 | |NRC NOTIFIED BY: HAVENNER |FRANK CONGEL IRD | |HQ OPS OFFICER: CHAUNCEY GOULD |FEMA, DOE, USDA, HHS FAX | +------------------------------------------------+EPA, DOT (NRC) FAX | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. ARMY AT FORT RILEY, KS. REPORTED THEY HAD LOST A CHEMICAL AGENT | | DETECTOR (CAD) CONTAINING 250 MICROCURIES OF Am-241. | | | | THE M43A1 CAD WAS DETERMINED TO BE MISSING BY A UNIT DURING AN INVENTORY OF | | RADIOACTIVE COMMODITIES IN PREPARATION FOR GOING TO THE NATIONAL TRAINING | | CENTER. A SEARCH OF THE UNIT AREA HAS FAILED TO TURN UP THE DEVICE. IT IS | | UNKNOWN WHEN THE LOSS ACTUALLY OCCURRED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/13/98 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 02/04/93 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: DAVIS |LAST UPDATE DATE: 05/13/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE CONTROL ROOM VENTILATION HAS BEEN IN A CONDITION WHERE IT WAS NOT ABLE | | TO PERFORM ITS DESIGN BASIS FUNCTION. | | | | ON 5/13/98, A RADIOLOGICAL ASSESSMENT CONCLUDED THAT ON SIX PRIOR OCCASIONS | | (1987-1993) WHILE THE PLANT WAS IN OPERATION, THE CONTROL ROOM VENT SYSTEM | | WOULD NOT HAVE BEEN ABLE TO KEEP CONTROL ROOM DOSES WITHIN THE DESIGN BASIS | | LIMIT OF 30 REM TO THE THYROID. THIS WAS CAUSED BY PAST DEGRADED | | CONDITIONS IN THE CONTROL ROOM VENT SYSTEM COUPLED WITH LEAKAGE FROM | | SYSTEMS THAT COULD RECIRCULATE FLUID OUTSIDE CONTAINMENT. SYSTEM LEAKAGE | | EXCEEDED THE VALUE (0.7054 GPH) USED IN THE CONTROL ROOM HABITABILITY DOSE | | CALCULATION. THIS SYSTEM WAS DEGRADED IN THAT THE SURVEILLANCE TEST FLOW | | REQUIREMENTS FOR THE BOOSTER FANS DID NOT ASSURE FLOWS CONSISTENT WITH THE | | DOSE CALCULATIONS OR ACCOUNT FOR LOADING OF THE FILTER SYSTEM DURING THE 30 | | DAYS FOLLOWING A POSTULATED ACCIDENT. THIS CONDITION WAS IDENTIFIED WHEN A | | 1997 EVALUATION OF THE DEGRADED CONTROL ROOM VENTILATION SYSTEM WAS | | RE-ASSESSED, CONSIDERING HISTORICAL LEAKAGE RATES FROM SYSTEMS THAT COULD | | RECIRCULATE FLUID OUTSIDE CONTAINMENT. CORRECTIVE ACTION WAS TAKEN IN 1997 | | TO ASSURE THAT THE BOOSTER FANS WERE PROPERLY SET AND PREVIOUS ACTION HAS | | CORRECTED THE LEAKS. | | | | THE RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34225 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/14/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 02:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/14/98 | +------------------------------------------------+EVENT TIME: 01:40[EDT]| |NRC NOTIFIED BY: DEVON PRICE |LAST UPDATE DATE: 05/14/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM 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 +------------------------------------------------------------------------------+ | ARTIFICIAL ISLAND EXPERIENCED A MAJOR LOSS OF OFFSITE COMMUNICATIONS | | CAPABILITY. | | | | "ARTIFICIAL ISLAND, SALEM UNITS 1 AND 2 AND HOPE CREEK GENERATING STATION | | HAVE LOST A MAJOR PORTION OF OUR TELECOMMUNICATIONS SYSTEM. LINES AFFECTED | | INCLUDE THE ENS LINES FROM BOTH STATIONS, APPROXIMATELY 75% OF THE NUCLEAR | | EMERGENCY TELECOMMUNICATIONS SYSTEM (NETS) AND ALL NORMAL DIRECT INWARD | | DIAL PHONE LINES, i.e., COMMON CARRIER LINES TO/FROM THE STATION. SEVERAL | | NETS LINES FROM EACH STATION ARE FUNCTIONING AND THE ESSEX PHONE LINES OUT | | OF NEW JERSEY ARE AVAILABLE." | | | | THE CAUSE OF THE PHONE PROBLEM IS A LOSS OF THE NORMAL POWER SUPPLY | | COMPLICATED BY A DEGRADED BATTERY BACKUP. THE LICENSEE IS CURRENTLY | | PURSUING REPAIRS, HOWEVER, NO TIME ESTIMATE FOR COMPLETION WAS AVAILABLE AT | | THIS TIME. THE LICENSEE PROVIDED A CONTACT PHONE NUMBER FOR EACH CONTROL | | ROOM USING THE ESSEX EXCHANGE. SALEM UNIT 1 IS CURRENTLY OPERATING AT 60% | | POWER. SALEM UNIT 2 AND HOPE CREEK ARE BOTH OPERATING AT 100% POWER. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 0445EDT FROM DEVON PRICE TO S.SANDIN * * * | | | | PHONES WERE RESTORED AT 0440EDT. THE LICENSEE'S PRELIMINARY INVESTIGATION | | FOUND THAT THE MAIN DISCONNECT TO THE INVERTER FOR THE NORMAL POWER SUPPLY | | WAS SHUT OFF. THE INVESTIGATION WILL CONTINUE IN ORDER TO DETERMINE WHEN | | AND WHY THIS OCCURRED. NOTIFIED R1DO(WHITE). | +------------------------------------------------------------------------------+