U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/23/97 - 10/24/97 ** EVENT NUMBERS ** 32948 33129 33134 33135 33136 33137 33138 33139 33140 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32948 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/17/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/17/97 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: DEPUYDT |LAST UPDATE DATE: 10/23/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IT WAS DETERMINED THAT FIBROUS MATERIAL IS PRESENT IN BOTH UNIT 1 AND UNIT | | 2 CONTAINMENT IN ENOUGH QUANTITY TO POTENTIALLY CAUSE EXCESSIVE BLOCKAGE OF | | THE CONTAINMENT RECIRCULATION SUMP SCREEN DURING THE RECIRCULATION PHASE OF | | A LOSS OF COOLANT ACCIDENT. | | | | IN 1985, 1986, AND 1995 "FIBERFRAX" REFRACTORY INSULATION MATERIALS IN | | BULK, BLANKET OR BOARD FORM WERE USED AS DAMMING MATERIAL WHEN INSTALLING | | FIRE STOPS IN CABLE TRAYS IN BOTH CONTAINMENTS. THE SPECIFICATION GOVERNING | | INSTALLATION OF THE FIRE STOPS DID NOT REQUIRE REMOVAL OF THE MATERIAL, | | ONLY STATING THAT IT SHOULD BE REMOVED "IF NECESSARY." THE MATERIAL WAS | | NOT REMOVED. THE MATERIAL IS PRESENT IN 12 CABLE TRAYS IN UNIT 1 AND 15 | | CABLE TRAYS IN UNIT 2. | | | | WHEN THE FIBERFRAX IS EXPOSED TO WATER OR STEAM/WATER ENVIRONMENT IT COULD | | POTENTIALLY BREAK INTO SMALL PIECES, WHICH COULD BE TRANSPORTED TO THE | | RECIRCULATION SUMP BY THE WATER FLOW IN CONTAINMENT DURING A LOSS OF | | COOLANT ACCIDENT. ONCE IT REACHES THE RECIRCULATION SUMP IT HAS THE | | POTENTIAL TO CLOG THE SCREENS IN EXCESS OF THE DESIGN VALUE. EXCESSIVE | | SCREEN BLOCKAGE COULD RESULT IN ECCS INOPERABILITY DURING THE RECIRCULATION | | MODE. | | | | THE FIBERFRAX MATERIAL IS CURRENTLY BEING REMOVED FROM THE CONTAINMENTS, | | AND REMOVAL WILL BE COMPLETED PRIOR TO RESTART OF THE UNITS. THE | | POSSIBILITY THAT THE LICENSEE'S WORK CONTROL PROCESS ALLOWED UNENCAPSULATED | | FIBROUS MATERIAL TO BE INSTALLED IN OTHER LOCATIONS INSIDE CONTAINMENT IS | | BEING INVESTIGATED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 1020EDT 10/1/97 FROM MARY BETH DePUYDT TO S.SANDIN * * * | | THE FOLLOWING UPDATE WAS RECEIVED: | | | | "AS A FOLLOWUP TO THE ORIGINAL ISSUE, ADDITIONAL REVIEWS WERE CONDUCTED OF | | INDUSTRY INFORMATION RELATED TO CONTAINMENT SUMP STRAINER BLOCKAGE AND | | PLANT INSULATION SPECIFICATIONS. WALKDOWNS WERE PERFORMED OF BOTH | | CONTAINMENTS. THE WALKDOWNS INDICATED SEVERAL INSTANCES WHERE FIBROUS | | INSULATION, KNOWN AS TEMP-MAT, WAS INSTALLED IN A CONFIGURATION WHICH WAS | | NOT IN ACCORDANCE WITH INSULATION SPECIFICATIONS. SPECIFICALLY, TEMP-MAT | | MATERIAL WAS EITHER EXPOSED OR ENCAPSULATED IN STAINLESS STEEL MESH. | | SIMILAR TO THE FIBERFRAX OF THE ORIGINAL NOTIFICATION, THE TEMP-MAT | | MATERIAL COULD BE TRANSPORTED TO AND POTENTIALLY BLOCK THE RECIRCULATING | | SUMP FOLLOWING A DESIGN BASIS ACCIDENT. THIS MATERIAL WILL BE | | DISPOSITIONED PRIOR TO THE STARTUP OF EITHER UNIT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(JACOBSON). | | | | * * * UPDATE 2220EDT 10/23/97 FROM STEVEN CZUK TO S.SANDIN * * * | | THE LICENSEE IS RETRACTING THE UNIT 1 PORTION OF THIS NOTIFICATION BASED ON | | THE FOLLOWING: | | | | "WE HAVE CONDUCTED AN ANALYSIS USING BOUNDING NUMBERS FROM THE BEST | | AVAILABLE DATA. THE FIBROUS MATERIAL FOUND IN CABLE TRAYS AND TEMPORARY | | INSULATION ON PIPING IN THE UNIT 1 CONTAINMENT WOULD NOT HAVE CAUSED THE | | UNIT 1 RECIRCULATION PUMP TO BE INOPERABLE. THE ANALYSIS CALCULATIONS | | INCLUDED ALLOWANCES FOR PAINT FLAKING, RUST, DUST/DIRT AND DESTRUCTION OF A | | PORTION OF THE VARIOUS PERMANENT INSULATION TYPES IN THE ZONE OF INFLUENCE. | | WE WILL UPDATE WITH THE UNIT 2 RESULTS WHEN THEY BECOME AVAILABLE." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R3DO(WRIGHT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33129 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/22/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:04 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/23/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT RDO | | DOCKET: 0707002 |JOHN GREEVES EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: RON CRABTREE | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUCLEAR CRITICALITY SAFETY (NCS) REQUIREMENT NOT MET | | | | THE NCSA FOR THE X-710 LAB FACILITY (UF6 DUMPING AREA STEAM BATH LOCATIONS) | | HAS TWO NCS CONTROLS. THE FIRST CONTROL REQUIRES AT LEAST NINE INCHES OF | | SPACING BETWEEN STEAM BATH CONTAINERS, AND THE SECOND CONTROL REQUIRES THE | | AVERAGE U235 ENRICHMENT IN THE DUMP CYLINDER TO BE LESS THAN 8 WT %. THE | | FIRST CONTROL WAS VIOLATED WHEN THE STEAM BATH CONTAINERS WERE DISCOVERED | | TO BE SPACED LESS THAN THE REQUIRED 9 INCHES (2 1/2" - 8"). THE SECOND | | CONTROL WAS MAINTAINED THROUGHOUT THIS EVENT. THERE WAS NO RELEASE OF | | HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE ASSOCIATED WITH | | THIS EVENT. PROPER SPACING HAS BEEN RE-ESTABLISHED. EVERY OTHER STEAM | | BATH CONTAINER LOCATION HAS BEEN TAGGED OUT TO PREVENT REOCCURRENCE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS REPORT. | | | | * * * UPDATE 1445EDT 10/23/97 FROM CRABTREE TO S.SANDIN * * * | | THE REGULATEE NOTED THAT THE U235 ENRICHMENT OF LESS THAN 8 WT % SHOULD | | READ LESS THAN 5 WT %. THIS ERROR OCCURRED DURING TRANSCRIPTION OF THE FAX | | BY THE HOO. NOTIFIED R3DO(WRIGHT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/23/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 08:57 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/22/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 18:15[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/23/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT RDO | | DOCKET: 0707002 |PICCONE NMSS EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: CRABTREE | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PORTSMOUTH GDP REPORTED UNDER 24-HOUR BULLETIN 91-01 THAT 6 CELLS WERE | | LOWER THAN THE MINIMUM SAFE TEMPERATURE. | | | | AT 1815 HRS ON 10/22/97, OPERATIONS PERSONNEL DISCOVERED THAT CELLS | | "31-2-1", "31-2-6", "31-2-7", "31-2-8", "31-2-10" AND "31-1-4", LOCATED IN | | THE X-330 PROCESS BUILDING HAD CELL COOLANT TEMPERATURES WHICH WERE LOWER | | THAN THE MINIMUM SAFE TEMPERATURE AS DEFINED IN NCSA-0330.004.A00. THIS | | NONCOMPLIANCE CONSTITUTES THE LOSS OF ONE NUCLEAR CRITICALITY SAFETY | | CONTROL IN A TWO CONTROL SYSTEM. THE CONTROL WHICH IS VIOLATED (MIN. CELL | | COOLANT TEMPERATURE) IS IN PLACE TO PREVENT A FREEZE-OUT OF UF-6 MATERIAL. | | THERE IS NO EVIDENCE OF UF-6 FREEZE-OUT OR FORMATION OF DEPOSITS IN ANY OF | | THE SIX CELLS AS A RESULT OF THIS NCSA NON-COMPLIANCE. THERE WAS NO | | RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE | | ASSOCIATED WITH THIS EVENT. THE REASON FOR THE NON-COMPLIANCE WAS DUE TO | | THE USE OF ABSOLUTE PRESSURE INSTEAD OF GAUGE PRESSURE READINGS IN THE NCSA | | FORMULA FOR CONVERSION. | | | | THE RESIDENT INSPECTOR AND DOE WERE NOTIFIED. | | | | HOO NOTE: SEE EVENT #33123 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 10/23/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/23/97 | +------------------------------------------------+EVENT TIME: 08:30[EDT]| |NRC NOTIFIED BY: BILL SUSLICK |LAST UPDATE DATE: 10/23/97 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION |BOB DENNIG EO | | |JOE GIITTER IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL NON-CONSERVATISM IN POWER-FLOW PROHIBITED OPERATION AREA. | | | | DUKE ENERGY CORPORATION'S SAFETY ANALYSIS GROUP HAS DETERMINED A POTENTIAL | | NON-CONSERVATISM IN A CALCULATION USED TO DISTINGUISH THE REACTOR POWER | | RESTRICTED OPERATION AND PROHIBITED OPERATION REGION. THE RESTRICTED AND | | PROHIBITED OPERATION REGIONS OF TECHNICAL SPECIFICATION 3/4.2.5, DNB | | PARAMETERS, IS ILLUSTRATED IN FIGURE 3.2-1, " REACTOR COOLANT SYSTEM TOTAL | | FLOW RATE VS. RATED THERMAL POWER - FOUR LOOPS IN OPERATION." | | | | UNIT 1 IS OPERATING AT FULL POWER WITHIN THE PERMISSIBLE OPERATION REGION, | | WITH FLOW GREATER THAN 382,000 GALLONS PER MINUTE (GPM). THERE ARE NO | | CURRENT POWER LIMITS WITH REACTOR COOLANT FLOW GREATER THAN 382,000 GPM. | | MCGUIRE HAS IMPLEMENTED ADMINISTRATIVE CONTROLS TO TAKE OPERATOR ACTION FOR | | PROHIBITED OPERATION FOR REACTOR COOLANT FLOW LESS THAN 382,000 GPM. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE SIMILAR EVENT #33136. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33136 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 10/23/97 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 12:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/23/97 | +------------------------------------------------+EVENT TIME: 08:30[EDT]| |NRC NOTIFIED BY: CHRISTOPHER ORR |LAST UPDATE DATE: 10/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION |BOB DENNIG EO | | |JOSEPH GIITTER IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL NON-CONSERVATISM IN POWER-FLOW PROHIBITED OPERATION AREA. | | | | "DUKE ENERGY CORPORATION SAFETY ANALYSIS GROUP HAS DISCOVERED A POTENTIAL | | NON-CONSERVATISM IN A CALCULATION USED TO DISTINGUISH BETWEEN REACTOR | | COOLANT SYSTEM FLOW VERSUS REACTOR POWER RESTRICTED OPERATION REGION AND | | THE PROHIBITED OPERATION REGION. THE RESTRICTED AND PROHIBITED OPERATION | | REGIONS ARE SHOWN IN TECHNICAL SPECIFICATION 3/4.2.5 DNB PARAMETERS, FIGURE | | 3.2-1 REACTOR COOLANT SYSTEM TOTAL FLOW RATE VS. RATED THERMAL POWER - FOUR | | LOOPS IN OPERATION. | | | | "UNIT 1 AND UNIT 2 ARE CURRENTLY IN MODE 1 AT 100% POWER AND ARE OPERATING | | IN THE PERMISSIBLE OPERATION REGION OF FIGURE 3.2-1. FOR REACTOR COOLANT | | FLOW RATES GREATER THAN 382,000 GPM ON UNIT 1 AND GREATER THAN 385,000 GPM | | ON UNIT 2 THERE ARE NO REACTOR POWER RESTRICTIONS. | | | | "CATAWBA IS IMPLEMENTING ADMINISTRATIVE CONTROLS TO IDENTIFY THE RESTRICTED | | OPERATION AS A PROHIBITED REGION ON FIGURE 3.2-1. | | | | "THIS REPORT IS BEING REPORTED UNDER 10CFR50.72(b)(2)(iii)(D), AN EVENT OR | | CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF A SAFETY | | FUNCTION OF SYSTEMS OR STRUCTURES THAT ARE NEEDED TO MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT." | | | | THE LICENSEE WAS INFORMED EARLIER THIS WEEK BY WESTINGHOUSE OF THE | | POTENTIAL NON-CONSERVATISM. LONG-TERM CORRECTIVE ACTION WILL BE A | | TECHNICAL SPECIFICATION CHANGE. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | HOO NOTE: SEE SIMILAR EVENT #33135. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33137 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/23/97 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/23/97 | +------------------------------------------------+EVENT TIME: 11:57[CDT]| |NRC NOTIFIED BY: KURT RATHGABER |LAST UPDATE DATE: 10/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 1 IDENTIFIED LACK OF CABLE SEPARATION FOR TWO AUXILIARY FEEDWATER | | PUMPS. | | | | "SEVERAL LOW VOLTAGE SIGNAL CABLES ASSOCIATED WITH THE UNIT 1 STEAM DRIVEN | | AUXILIARY FEED PUMP (1P29) AND THE UNIT COMMON AUXILIARY FEED PUMP (P38A) | | HAVE BEEN FOUND TO BE IN COMMON CONDUITS AND CABLE RACEWAYS. A SINGLE | | FAILURE IN THE CABLE TRAY COULD, THEREFORE, MAKE BOTH PUMPS INOPERABLE FOR | | UNIT 1. THIS IS NOT A CONCERN FOR UNIT 1 UNDER PRESENT PLANT CONDITIONS. | | SINCE UNIT 1 IS IN COLD SHUTDOWN. IT IS NOT A CONCERN FOR UNIT 2 SINCE THE | | POSTULATED FAILURE WOULD ONLY MAKE A SINGLE UNIT 2 RELATED PUMP INOPERABLE | | AND THIS IS WITHIN OUR DESIGN BASIS. | | | | "THIS CONDITION IS STILL BEING EVALUATED AND THE CORRECTIVE ACTIONS WILL BE | | DEVELOPED FOLLOWING COMPLETION OF THE EVALUATION. | | | | "THIS IS BEING REPORTED UNDER 10CFR50.72(b)(2)(i) - AN EVENT, FOUND WHILE | | SHUTDOWN, THAT HAD IT BEEN FOUND AT POWER, WOULD HAVE SHOWN THE PLANT TO BE | | IN AN UNANALYZED CONDITION. IT IS ALSO BEING REPORTED UNDER | | 10CFR50.72(b)(2)(iii) - AN EVENT OR CONDITION THAT ALONE COULD HAVE PREVENT | | A SAFETY FUNCTION NEED TO REMOVE DECAY HEAT. | | | | "NOTE: THE AUXILIARY FEED SYSTEM IS NOT REQUIRED TO BE OPERABLE FOR UNIT 1 | | UNTIL PRIMARY TEMPERATURES REACH 350øF. THIS SITUATION WILL BE EVALUATED | | AND RESOLVED PRIOR TO THE TIME UNIT 1 AUXILIARY FEED PUMPS ARE REQUIRED TO | | BE OPERABLE DURING THE UNIT 1 RESTART PROCESS." | | | | THE LICENSEE IDENTIFIED THIS CONDITION DURING A MODIFICATION OF THE | | AUXILIARY FEED PUMP LOW PRESSURE SUCTION TRIP CIRCUIT. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33138 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 10/23/97 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 15:47 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/23/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: JOHN OSBORNE |LAST UPDATE DATE: 10/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED THAT A DATABASE ERROR RESULTED IN THE OMISSION OF | | NUMEROUS INDIVIDUALS WITH UNESCORTED ACCESS FROM THE RANDOM DRUG TESTING | | PROGRAM. | | | | DURING A DATABASE UPGRADE, THE LICENSEE IDENTIFIED SEVERAL INSTANCES WHERE | | INDIVIDUALS GRANTED UNESCORTED ACCESS WERE NOT INCLUDED IN THE RANDOM DRUG | | TESTING PROGRAM. THESE INSTANCES INCLUDED: | | | | 13 CONTRACTORS WITH ACCESS SINCE AS EARLY AS 11/17/95, | | 128 INDIVIDUALS ON LOAN FROM OTHER LICENSEES SINCE AS EARLY AS 4/93 | | INVOLVING ACCESS FROM 1 TO 6 WEEKS (NO CURRENT ACCESS) AND, | | 2 SUPPORT PERSONNEL WITH ACCESS TO THE EOF. | | | | THE 13 CONTRACTORS ARE UNAWARE THAT THEY WERE NOT INCLUDED IN THE RANDOM | | DRUG TESTING PROGRAM, WERE UNDER CONTINUOUS BEHAVIORAL OBSERVATION WITH | | NONE TESTED FOR CAUSE DURING THIS PERIOD. THE LICENSEE INTENDS TO | | ADMINISTER A DRUG TEST EITHER FRIDAY OR MONDAY. | | | | THE OTHER 128 INDIVIDUALS ON LOAN WERE INCLUDED IN THEIR OWN ORGANIZATION | | DRUG TESTING PROGRAM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33139 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 10/23/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 18:40 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/23/97 | +------------------------------------------------+EVENT TIME: 15:35[CDT]| |NRC NOTIFIED BY: TERRY HOLCOMBE |LAST UPDATE DATE: 10/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 +------------------------------------------------------------------------------+ | NON-CONTAMINATED CONTRACT EMPLOYEE TRANSPORTED OFFSITE PRONOUNCED DEAD AT | | COUNTY HOSPITAL. | | | | A 49 YEAR OLD CONTRACT HEALTH PHYSICS (HP) TECHNICIAN COLLAPSED IN THE HP | | LAB COUNTROOM LOCATED INSIDE THE CONTROLLED ACCESS AREA. CARDIOPULMONARY | | RESUSCITATION (CPR) WAS ADMINISTERED WHILE HE WAS TRANSPORTED OFFSITE TO | | THE CLAYBORNE COUNTY HOSPITAL WHERE, AT 1627CDT, HE WAS PRONOUNCED DEAD DUE | | TO AN APPARENT HEAT ATTACK. THERE WAS NO RADIOACTIVE CONTAMINATION | | INVOLVED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33140 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/24/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 02:56 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/97 | +------------------------------------------------+EVENT TIME: 00:08[EDT]| |NRC NOTIFIED BY: ACKERMAN |LAST UPDATE DATE: 10/24/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT VENTILATION ISOLATION | | | | A CONTAINMENT VENTILATION ISOLATION OCCURRED DUE TO A HIGH-FAILURE OF THE | | UPPER CONTAINMENT AREA RADIATION MONITOR "VRS2101". THERE WAS NO | | INDICATION OF HIGH RADIATION ON ANY OTHER RADIATION MONITORS; THEREFORE, | | THE ACTUATION SIGNAL IS CONSIDERED TO BE INVALID. CONTAINMENT PURGE WAS IN | | SERVICE AT THE TIME OF THE ACTUATION. THE CONTAINMENT VENTILATION | | ISOLATION VALVES ARE CURRENTLY CLOSED, AND WILL REMAIN SO UNTIL | | TROUBLESHOOTING AND NECESSARY REPAIRS ARE COMPLETED. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+