U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/20/97 - 06/23/97 ** EVENT NUMBERS ** 32516 32517 32518 32519 32520 32521 32522 32523 32524 32525 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32516 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/20/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:43 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/19/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:45[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/20/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: HALICKS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT NO CONTROLS WERE ESTABLISHED FOR SOME | | LEGACY PROCESS EQUIPMENT TO DEMONSTRATE DOUBLE CONTINGENCY. THIS EVENT WAS | | REPORTED IN RESPONSE TO BULLETIN 91-01. | | | | THE LICENSEE'S TSR 3.11.5 REQUIRES IMPLEMENTATION OF THE DOUBLE CONTINGENCY | | PRINCIPLE FOR ALL FISSILE/POTENTIALLY FISSILE OPERATIONS, EXCEPT THOSE | | EXPLICITLY NOTED AS SINGLE CONTINGENT OPERATIONS. THE LICENSEE HAS NOT HAD | | ANY NUCLEAR CRITICALITY SAFETY (NCS) CONTROLS FOR REMOVED PROCESS | | EQUIPMENT. TWO NUCLEAR CRITICALITY SAFETY APPROVALS (NCSA) WERE WRITTEN TO | | ESTABLISH DOUBLE CONTINGENCY FOR POTENTIALLY FISSILE LEGACY PROCESS | | EQUIPMENT. THESE NCSA'S WERE WRITTEN TO BRING THIS EQUIPMENT INTO A STATE | | OF COMPLIANCE, BUT NEITHER WAS FULLY IMPLEMENTED BY 3/3/97, THEREFORE | | DOUBLE CONTINGENCY COULD NOT BE SHOWN. | | | | FOR EQUIPMENT ORIGINATING FROM OFFSITE (K-25 OR PORTSMOUTH), DOT | | REQUIREMENTS FOR SHIPPING WERE MET AND GAMMA/NEUTRON SCANS PERFORMED TO | | DATE BY THE LICENSEE HAVE NOT IDENTIFIED ANY SIGNIFICANT DEPOSITS ON THE | | EQUIPMENT. THE COMBINATION OF HISTORICAL DATA AND TRANSPORTATION | | REQUIREMENTS FOR RADIOACTIVE AND FISSILE MATERIAL SHIPPING LEAD TO THE | | CONCLUSION THAT IT IS EXTREMELY UNLIKELY THAT AN UNSAFE MASS EXISTS IN | | EQUIPMENT RECEIVED FROM OFFSITE. | | | | FOR PADUCAH GDP EQUIPMENT, THE PROCESSES THAT PRODUCE EQUIPMENT DEPOSITS DO | | NOT TEND TO FORM UNSAFE GEOMETRIES AND POTENTIALLY FISSILE LEGACY PGDP | | EQUIPMENT IS SPACED TWO FEET EDGE-TO-EDGE WITH MOVEMENT AND HANDLING OF THE | | EQUIPMENT PROHIBITED. GAMMA SCANS PERFORMED ON THIS EQUIPMENT DID NOT | | DETECT ANY SIGNIFICANT DEPOSITS. | | | | PLANS ARE BEING DEVELOPED TO QUALITATIVELY SCAN THE LEGACY EQUIPMENT FOR | | NEUTRON AND/OR GAMMA RADIATION TO VERIFY THAT NO SIGNIFICANT DEPOSITS | | EXIST. FULL CHARACTERIZATION OF DEPOSIT MASS WILL FOLLOW TO ESTABLISH | | DOUBLE CONTINGENCY. | | | | ADMINISTRATIVE CONTROLS ARE IN PLACE TO PREVENT MOVEMENT OF THE MATERIAL | | AND TO PRECLUDE PLACING ADDITIONAL FISSILE MATERIAL IN THE AREA TO REDUCE | | THE POSSIBILITY OF A CRITICALITY. | | | | DOUBLE CONTINGENCY WILL BE ESTABLISHED UPON COMPLETE IMPLEMENTATION OF NCSA | | GEN-27 WHICH WILL CONTROL MASS AND INTERACTION. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32517 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 06/20/97 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:05 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 06/20/97 | +------------------------------------------------+EVENT TIME: 12:44[EDT]| |NRC NOTIFIED BY: REGIS REPKO |LAST UPDATE DATE: 06/20/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |NINF INFORMATION ONLY | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | KEOWEE UNIT ONE FAILED TO CLOSE ONTO THE STANDBY BUS | | | | "ON 6/20/97, AT 1244, ELECTRICAL POWER WAS BRIEFLY INTERRUPTED TO OCONEE | | UNIT 1 DURING CONDUCT OF A TEST OF THE LEE STEAM STATION POWER PATH. OCONEE | | UNIT 1 WAS IN COLD SHUTDOWN FOR A FORCED OUTAGE. AS A RESULT OF THE LOSS | | OF POWER TO THE OCONEE UNIT 1 MAIN FEEDER BUSES, THE KEOWEE HYDRO UNITS | | RECEIVED AN EMERGENCY START SIGNAL FROM THE MAIN FEEDER BUS MONITOR PANEL. | | POWER WAS RESTORED TO THE OCONEE UNIT 1 MAIN FEEDER BUSES IN APPROXIMATELY | | 26 SECONDS BY CLOSING IN THE BREAKERS TO THE AUXILIARY TRANSFORMER WHICH IS | | POWERED BY THE SWITCHYARD. KEOWEE UNIT 2 (OVERHEAD) PATH STARTED PROPERLY | | AND REMAINED IN STANDBY. KEOWEE UNIT 1 (UNDERGROUND PATH) EMERGENCY | | STARTED BUT DID NOT CLOSE IN TO THE STANDBY BUS DUE TO THE EMERGENCY START | | COMPLETE SIGNAL WAS NOT RECEIVED. OCONEE UNIT 1 IS AT STABLE COLD SHUTDOWN | | CONDITIONS AND OCONEE UNITS 2 AND 3 WERE UNAFFECTED BY THIS EVENT, WITH THE | | EXCEPTION THAT THE UNDERGROUND PATH IS CURRENTLY INOPERABLE AND UNDER A 72 | | HOUR TECHNICAL SPECIFICATION ACTION STATEMENT. THE CAUSE OF THE POWER | | INTERRUPTION DURING TESTING OF LEE STEAM STATION, AND THE CAUSE OF THE | | FAILURE OF KEOWEE UNIT 1 ARE UNDER INVESTIGATION. NO OTHER ABNORMALITIES | | WERE NOTED IN THIS EVENT." | | | | THE LICENSEE DID NOT CLASSIFY THIS EVENT AS AN ESF ACTUATION BECAUSE THE | | SPECIFIC INPUT WHICH STARTED THE KEOWEE UNITS (MAIN FEEDER BUS MONITOR | | PANEL) IS NOT CLASSIFIED AS AN ESF SIGNAL. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32518 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 06/20/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:08 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/20/97 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: JOHN DRAHOTA |LAST UPDATE DATE: 06/20/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - SEWAGE RELEASE | | | | AT APPROXIMATELY 1130 CDT, FLOW FROM THE NEW CARP/WAREHOUSE LIFT STATION | | WAS DISCOVERED. FLOW WAS TERMINATED AT APPROXIMATELY 1230 WHEN BLOWN POWER | | FUSES WERE REPLACED TO THE LIFT STATION PUMPS, AND THE PUMPS AUTOMATICALLY | | STARTED. | | | | APPROXIMATELY 250 GALLONS OF SEWAGE WATER WAS SPILLED, OF WHICH | | APPROXIMATELY 50 GALLONS LEAKED TO THE RIVER VIA A STORM DRAIN. A HAZMAT | | TEAM DIKED THE STORM DRAIN TO PREVENT THE REMAINING 200 GALLONS FROM | | ENTERING THE RIVER. THE SEWAGE WATER WAS TREATED WITH CHLORINE TO | | NEUTRALIZE THE LIQUID. | | | | A CONDITION REPORT WAS GENERATED BY THE CHEMISTRY DEPARTMENT TO INVESTIGATE | | THE EVENT. THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY WAS NOTIFIED | | AT 1330. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32519 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 06/20/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 23:02 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/20/97 | +------------------------------------------------+EVENT TIME: 22:10[EDT]| |NRC NOTIFIED BY: MIKE WILLIAMS |LAST UPDATE DATE: 06/21/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AHIN 50.72(b)(1)(vi) OTHER HIND TO SAFE OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | 60 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FIRE SUPPRESSION WATER SYSTEM FLOW DID NOT MEET TEST ACCEPTANCE CRITERION | | | | THE TEST CRITERION IS STATED IN TERMS OF RESISTANCE TO FLOW AND THE SYSTEM | | DEMONSTRATED TOO MUCH RESISTANCE, POTENTIALLY RESULTING IN TOO LOW OF A | | WATER FLOW TO MEET SYSTEM REQUIREMENTS. THE LICENSEE HAD 24 HOURS TO | | RESTORE THE SYSTEM TO OPERABILITY OR ESTABLISH A BACKUP FIRE SUPPRESSION | | WATER SYSTEM. NEITHER ONE OF THESE OPTIONS WAS MET, AND THE 24 HOUR CLOCK | | EXPIRED AT 1800 ON 6/20/97. THE LICENSEE HAS 12 HOURS TO PLACE BOTH UNITS | | IN HOT SHUTDOWN AND AN ADDITIONAL 24 HOURS TO PLACE BOTH UNITS IN COLD | | SHUTDOWN. THESE REQUIREMENTS ARE NOT CONTAINED IN TECHNICAL SPECIFICATIONS, | | BUT RATHER IN PLANT PROCEDURES. | | | | ALL ON AND OFFSITE POWER SUPPLIES ARE OPERABLE AS IS ALL ECCS EQUIPMENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 0616EDT 6/21/97 FROM MIKE WILLIAMS TO S.SANDIN * * * | | | | FURTHER TESTING IDENTIFIED WHICH AREAS WERE AFFECTED BY THE FLOW BLOCKAGES. | | THE AFFECTED AREAS ARE COMPENSATED FOR BY CONTINUOUS FIRE WATCHES AND | | BACKUP FIRE SUPPRESSION. THE LICENSEE TERMINATED THE SHUTDOWN AT 0530EDT | | WITH BOTH UNITS AT 20% POWER. CURRENT INTENTIONS ARE TO INCREASE POWER | | LATER TODAY. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED | | R2DO(LESSER). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32520 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/21/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 11:30 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/20/97 | +------------------------------------------------+EVENT TIME: 16:20[CDT]| |NRC NOTIFIED BY: JOE SIPEK |LAST UPDATE DATE: 06/21/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FITNESS FOR DUTY REPORT | | | | AT 1620EDT ON 6/20/97, A NON-LICENSED MAINTENANCE SUPERVISOR TESTED | | POSITIVE FOR MARIJUANA DURING A RANDOM FITNESS FOR DUTY TEST. THE | | INDIVIDUAL'S SITE ACCESS HAS BEEN SUSPENDED IN ACCORDANCE WITH THE SITE | | FITNESS FOR DUTY PROCEDURES AND A WORK HISTORY REVIEW IS IN PROGRESS. THE | | INDIVIDUAL WILL BE REFERRED TO THE EMPLOYEE ASSISTANCE PROGRAM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32521 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 06/21/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 12:53 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 06/21/97 | +------------------------------------------------+EVENT TIME: 12:14[EDT]| |NRC NOTIFIED BY: BARRY MINSER |LAST UPDATE DATE: 06/21/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |FRANK MIRAGLIA EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |DEPUGH FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |FRANK CONGEL IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP AND LOSS OF OFFSITE POWER | | | | AT 1214EDT THE UNIT TRIPPED AND LOST OFFSITE POWER. ALL RODS FULLY | | INSERTED, EMERGENCY FEEDWATER STARTED AND THE EMERGENCY DIESEL GENERATORS | | STARTED AND LOADED ON TO THEIR RESPECTIVE EMERGENCY BUSES. SINCE FORCED | | CIRCULATION WAS LOST DURING THIS EVENT, DECAY HEAT IS BEING REMOVED VIA THE | | ATMOSPHERIC STEAM DUMPS. THE PLANT HAS VERY LOW PRIMARY TO SECONDARY | | LEAKAGE AND REACTOR COOLANT ACTIVITY WAS MORE THAN AN ORDER OF MAGNITUDE | | BELOW TECHNICAL SPECIFICATION LIMITS. | | | | AN UNUSUAL EVENT WAS DECLARED AT 1226EDT BASED ON THE LOSS OF OFFSITE | | POWER. | | | | THE EXACT CAUSE OF THIS EVENT IS NOT KNOWN, BUT IS UNDER INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1700EDT ON 6/21/97 BY WEAVER * * * | | | | A COMMISSIONER ASSISTANTS BRIEFING WAS HELD, CONDUCTED BY PETE ESELGROTH. | | THE FOLLOWING IS A PARTIAL LIST OF PARTICIPANTS. NRR(CHAFFEE), (ROE), | | (ZWOLINSKI); SECY (HART); CONGRESSIONAL AFFAIRS (MADDEN); CHAIRMAN | | JACKSON'S ASST (JOHNSON), (DEFINO); COMMISSIONER ROGERS' ASST (SORENSON), | | COMMISSIONER DICUS' ASST (LUBENAU); COMMISSIONER DIAZ' ASST (RADDATZ); | | COMMISSIONER MCGAFFIGAN'S ASST (GRAY); STATE PROGRAMS (BANGART). | | | | * * * UPDATE AT 2124EDT ON 6/21/97 TAKEN BY WEAVER * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 2124EDT. OFFSITE POWER HAS | | BEEN RESTORED. ALL FOUR REACTOR COOLANT PUMPS ARE OPERATING AND STEAM IS | | BEING DUMPED TO THE MAIN CONDENSER AS NECESSARY TO REMOVE DECAY HEAT. THE | | EDGs HAVE BEEN RETURNED TO STANDBY. THE HOO NOTIFIED THE RDO (BELLAMY); EO | | (HEBDON) AND FEMA (SWITZER). | | | | * * * UPDATE AT 0900EDT ON 6/22/97 TAKEN BY S.SANDIN * * * | | ADDITIONAL INFORMATION: | | | | THE INITIATING EVENT WAS THE FAILURE OF A CERAMIC INSULATOR ON GENERATOR | | OUTPUT BREAKER "GB1-02." THIS FAILURE CAUSED THE SECOND GENERATOR OUTPUT | | BREAKER "GB1-12" AND SEVEN OTHER BREAKERS IN THE SUBSTATION TO OPEN ON | | RELAY AND FAULT LOGIC. AS A RESULT, THE 230KV BUSES SUPPLYING THE STATION | | AUXILIARY TRANSFORMERS DEENERGIZED. WITH BOTH GENERATOR OUTPUT BREAKERS | | OPEN THE TURBINE TRIPPED WHICH IN TURN TRIPPED THE REACTOR. WITH THE LOSS | | OF OFFSITE POWER AT 1214EDT, OPERATORS ENTERED THE APPLICABLE EOP AND | | ESTABLISHED NATURAL CIRCULATION. BOTH EDGs STARTED ON UNDERVOLTAGE AND | | CLOSED ONTO THEIR RESPECTIVE 4160VAC BUSES WITHIN THE REQUIRED 10 SECS. THE | | STATION BLACKOUT DIESEL GENERATOR WAS LATER MANUALLY STARTED AND ALIGNED TO | | REENERGIZE ONE BALANCE OF PLANT BUS. AT 1337 AND 1347EDT, BOTH STATION | | AUXILIARY TRANSFORMERS WERE REENERGIZED FROM OFFSITE POWER. OPERATORS | | RESTARTED ALL FOUR REACTOR COOLANT PUMPS BETWEEN 2115 AND 2122EDT. THE | | LICENSEE HAS A 1400EDT MEETING TO EVALUATE WHETHER THE UNIT WILL BE | | RESTARTED BEFORE REPAIRING GENERATOR OUTPUT BREAKER "GB1-02." | | | | THE NRC ENTERED THE MONITORING PHASE OF NORMAL MODE AT APPROXIMATELY | | 1400EDT. THE MONITORING PHASE WAS EXITED WHEN FORCED CIRCULATION WAS | | REESTABLISHED AND THE UE TERMINATED AT 2124EDT. | | | | NOTIFIED R1DO(BELLAMY). | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32522 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 06/21/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 17:29 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 06/21/97 | +------------------------------------------------+EVENT TIME: 16:55[EDT]| |NRC NOTIFIED BY: MAX NELSON |LAST UPDATE DATE: 06/21/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE CONTROL RODS DID NOT MEET TECH SPEC INSERTION TIMES | | | | AT 1655EDT THE LICENSEE CONFIRMED THAT THREE CONTROL RODS DID NOT INSERT | | WITHIN THE TIME ALLOWED BY TECHNICAL SPECIFICATIONS. THE REACTOR TRIP | | OCCURRED IN CONJUNCTION WITH EVENT #32521. | | | | THE SPECIFIC RODS AND THEIR INSERTION TIMES ARE AS FOLLOWS: | | | | GPII ROD 3 1.696 SEC | | GPV ROD 8 2.007 SEC | | GPV ROD 5 2.172 SEC | | | | THE MAXIMUM TIME ALLOWED BY TECH SPECS IS 1.66 SEC IN EACH CASE. | | | | THE LICENSEE ATTRIBUTED THE SLOW INSERTION TIMES TO A DEGRADATION IN THE | | THERMAL BARRIER USED TO PROTECT THE CONTROL ROD DRIVE MECHANISMS. THE | | THERMAL BARRIER HAS VERY TIGHT TOLERANCES AND A SMALL AMOUNT OF CORROSION | | DEPOSITION EFFECTIVELY LIMITS WATER FLOW DURING A TRIP; THEREBY SLOWING | | DOWN THE CONTROL ROD. THE LICENSEE HAS MODIFIED SOME OF THERMAL BARRIERS, | | BUT THE RODS EXHIBITING THE SLOW TIMES HAVE NOT YET BEEN MODIFIED. | | | | THE LICENSEE WILL REPAIR THIS CONDITION PRIOR TO RESTART. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32523 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/22/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:15 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 00:20[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/22/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY RDO | | DOCKET: 0707001 |JOE HOLONICH EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: BILL HALICKS | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADEQUATE SPACING OF ION PUMPS TO MEET DOUBLE CONTINGENCY CRITERIA AS | | DESCRIBED IN BULLETIN 91-01 (24 HOUR NOTIFICATION). | | | | "ON JUNE 21, AT 0020CDT, IT WAS DISCOVERED DURING A WALK-THROUGH INSPECTION | | OF THE C-720 INSTRUMENT MAINTENANCE SHOP THAT 40 CONTAMINATED ION PUMPS | | WERE NOT CONTROLLED AS REQUIRED BY NCSA GPS-12. THE SPACING CONTROL FOR | | THE PUMPS REQUIRES 2 FOOT EDGE-TO-EDGE SPACING BETWEEN INDIVIDUAL BATCHES | | OF EIGHT PUMPS. THE 40 PUMPS WERE BAGGED IN BATCHES OF EIGHT PUMPS PER | | BAG, BUT PROPER SPACING WAS NOT MAINTAINED BETWEEN THE BATCHES AS REQUIRED. | | | | NUCLEAR CRITICALITY (NCS) PERSONNEL EVALUATED THE AS-FOUND CONDITION AND | | PROVIDED GUIDANCE TO ISOLATE AND CONTROL ACCESS TO THE AREA. IT WAS | | DETERMINED THAT A LOSS OF CONTROL DID OCCUR SUCH THAT ONLY ONE DOUBLE | | CONTINGENCY CONTROL REMAINED IN PLACE. THE NUCLEAR CRITICALITY SAFETY | | EVALUATION AND RESULTING CONTROLS FOR THIS PROCESS WERE BASED ON 5.5 wt % | | U235. THE ACTUAL PROCESS IS APPROVED FOR 2.0 wt % U235 AT THIS TIME. THE | | SAFE VOLUME FOR A BATCH OF 8 PUMPS AT 2.0 wt % U235 IS 95.1 LITERS. THE | | ACTUAL VOLUME OF THE 40 PUMPS IS LESS THAN 44 LITERS. THE SAFE VOLUME WAS | | NOT EXCEEDED AND THE VOLUME CONTROL REMAINED IN PLACE." | | | | THESE PUMPS WERE STAGED IN THE MAINTENANCE SHOP AWAITING APPROVAL OF | | PROCEDURES FOR CLEANING. SEE EVENT #32516. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32524 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/22/97 | |UNIT: [1] [2] [ ] STATE: AR |NOTIFICATION TIME: 19:26 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 06/22/97 | +------------------------------------------------+EVENT TIME: 17:46[CDT]| |NRC NOTIFIED BY: BONNER |LAST UPDATE DATE: 06/23/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT LOST THEIR SAFETY PARAMETER DISPLAY SYSTEM (SPDS) COMPUTERS. | | | | THIS OCCURRED DUE TO OVERHEATING IN THE ROOM BECAUSE OF FAILURE OF THE AIR | | CONDITIONING SYSTEM. THEY INSTALLED A TEMPORARY A/C UNIT, BUT IT ALSO | | FAILED. THE SPDS COMPUTERS WERE RESTARTED AND LOST A FEW TIMES WITHIN AN | | HOUR AND THE LICENSEE IS NOT CONFIDENT IN THE COMPUTERS RELIABILITY. THEY | | DON'T KNOW IF ANY DAMAGE TO THE COMPUTERS HAS RESULTED FROM THE ROOM | | OVERHEATING PROBLEM AND WILL CONTINUE TO INVESTIGATE. THEY HAVE THE SYSTEM | | UP AND RUNNING IN UNIT 2 CONTROL ROOM AND THE TSC. THE RESIDENT INSPECTOR | | AND THE STATE WILL BE NOTIFIED. | | | | * * * UPDATE 0500EDT ON 6/23/97 FROM HINTON TO S.SANDIN * * * | | | | THE FOLLOWING FACSIMILE WAS RECEIVED FROM THE LICENSEE: | | | | "THIS FOLLOW-UP NOTIFICATION FROM ARKANSAS ONE IS TO PROVIDE ADDITIONAL | | INFORMATION REGARDING THE LOSS, FOR MORE THAN ONE HOUR, OF THE SAFETY | | PARAMETER DISPLAY SYSTEM (SPDS) THAT WAS REPORTED AT 1826CDT ON 6/22/97. AS | | REPORTED, THE CONDITION WAS THE RESULT OF PROBLEMS WITH THE COMPUTER ROOM | | AIR CONDITIONING. OVERHEATING OF THE COMPUTER EQUIPMENT RESULTED IN THE | | LOSS OF CAPABILITY TO OBTAIN DISPLAYS THAT ARE NECESSARY FOR UNIT ONE | | ACCIDENT ASSESSMENT FROM THE UNIT ONE CONTROL ROOM. | | | | SINCE THE INITIAL REPORT WAS MADE, NORMAL COMPUTER ROOM AIR CONDITIONING | | HAS BEEN RESTORED AND BACK-UP EQUIPMENT HAS BEEN STAGED. THE 'A' SPDS | | COMPUTER WAS VERIFIED OPERABLE AT 1738CDT, AND IT WAS VERIFIED THAT UNIT | | ONE AND UNIT TWO PLANT DATA WAS AVAILABLE THROUGH SPDS TO THE EMERGENCY | | OPERATIONS FACILITY AND THE TECHNICAL SUPPORT CENTER. UNIT TWO CONTROL | | ROOM DISPLAYS WERE VERIFIED CAPABLE OF PROVIDING UNIT TWO ACCIDENT | | ASSESSMENT INFORMATION. THE UNIT ONE CONTROL ROOM, HOWEVER, COULD NOT | | ACCESS THE 'A' SPDS COMPUTER AND COMMUNICATION WITH SPDS REMAINED IMPAIRED | | UNIT THE 'B' SPDS COMPUTER WAS RESTORED AT 0240CDT ON 6/23/97. | | | | AT THIS TIME, BOTH SPDS COMPUTERS ARE FUNCTIONING NORMALLY AND ALL ACCIDENT | | ASSESSMENT CAPABILITY IS RESTORED." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | R4DO(POWERS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32525 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/23/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 06:00 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/23/97 | +------------------------------------------------+EVENT TIME: 02:00[EDT]| |NRC NOTIFIED BY: GREG RUPPERT |LAST UPDATE DATE: 06/23/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 2 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE | | AFTER FAILING TO MEET A REQUIRED MONTHLY SURVEILLANCE TEST. | | | | AT 0200EDT ON 6/23/97, THE UNIT 2 HPCI SYSTEM WAS DECLARED INOPERABLE AFTER | | THE STEAM EXHAUST DRAINPOT ORIFICE FAILED ITS ROUTINE TEST FOR PASSING | | FLOW. THIS PLACED UNIT 2 IN A 14 DAY LCO A/S 3.5.1. PER THE A/S THE | | LICENSEE VERIFIED THAT OTHER REQUIRED ECCS EQUIPMENT, i.e., RCIC, ADS, LPCI | | AND CS, WAS OPERABLE. TROUBLESHOOTING AND REPAIRS ARE IN PROGRESS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+