U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/11/96 - 12/12/96 ** EVENT NUMBERS ** 31358 31432 31433 31434 31435 31436 31437 31438 31439 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31358 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 11/19/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 20:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/19/96 | +------------------------------------------------+EVENT TIME: 18:30[EST]| |NRC NOTIFIED BY: JAMES BAKER |LAST UPDATE DATE: 12/11/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE EMERGENCY DIESEL GENERATOR (EDG) EXHAUST FANS DID NOT START WITH THE | | EDG AND COULD HAVE CAUSED THE EDG TO FAIL. | | | | THE "1B-B" EDG'S EXHAUST FAN FAILED TO START WITH THE EDG DUE TO A LATCHED | | RELAY, AND THE EDG COULD HAVE FAILED FROM HIGH EDG ROOM TEMPERATURE. THE | | RELAY GOT LATCHED IN OCTOBER 1996 DURING A TEST OF THE CO2 SYSTEM. THE | | LICENSEE REVIEWED RECORDS AND FOUND THAT THE "A" RHR PUMP WAS OUT OF | | SERVICE DURING THIS TIME FRAME, SO BOTH TRAINS OF RHR WOULD HAVE BEEN | | UNAVAILABLE. OTHER EQUIPMENT MIGHT ALSO HAVE BEEN OUT OF SERVICE. THE | | LICENSEE IS CONTINUING TO REVIEW RECORDS TO DETERMINE IF OTHER EQUIPMENT | | WAS ALSO AFFECTED. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ****RETRACTION BY PAUL PACE AT 1422ET ON 12/11/96 TAKEN BY MACKINNON**** | | | | THE ABOVE NOTIFICATION IS BEING WITHDRAWN BASED ON FURTHER INVESTIGATION OF | | THE EVENT. A TIME ANALYSIS WAS PERFORMED ON THE SIMULATOR FOR ACCIDENT | | SCENARIOS THAT WOULD AUTOMATICALLY START THE DIESELS TO ESTABLISH TOTAL | | TIMES FROM INITIATION OF THE EMERGENCY PROCEDURE UNTIL THE OPERATORS | | ARRIVAL AT THE DIESEL BUILDING. BASED ON THESE ANALYSIS, IT WAS DETERMINED | | THAT THE SITUATION WOULD NOT HAVE GONE UNDETECTED IF THE DIESELS | | AUTOMATICALLY STARTED. A SIMPLE MANUAL ACTION OF PUSHING A BUTTON TO RESET | | THE EXHAUST FANS CORRECTED THE PROBLEM WITH THE FANS. NUREG-1022 STATES | | THAT REASONABLE OPERATOR ACTIONS TO CORRECT MINOR PROBLEMS MAY BE | | CONSIDERED. AN EVALUATION BASED ON THE WORST CASE TIME FROM THE ACCIDENT | | SCENARIOS PLUS THE TIME TO DETECT AND CORRECT THE PROBLEM VERSUS THE | | TEMPERATURE RISE IN THE ROOM WAS PERFORMED. BASED ON THESE EVALUATIONS, IT | | WAS DETERMINED THAT SUFFICIENT TIME EXISTED TO CORRECT THE SITUATION WITH | | MINOR EFFORT. CONSEQUENTLY, THERE WOULD BE NO EFFECT ON SAFETY-RELATED | | SHUTDOWN EQUIPMENT. THEREFORE, TVA HEREBY WITHDRAWS THIS EVENT. R2DO (LEN | | WERT) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31432 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/11/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/10/96 | +------------------------------------------------+EVENT TIME: 21:08[CST]| |NRC NOTIFIED BY: PETE KARABA |LAST UPDATE DATE: 12/11/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WAYNE KROPP 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THREE MOTOR OPERATED VALVES (MOV) MAY NOT BE CAPABLE OF OPENING AGAINST | | WORST CASE SYSTEM DIFFERENTIAL PRESSURE. | | | | DURING A REVIEW OF MOV CAPABILITY THE LICENSEE DETERMINED THAT THREE | | DRYWELL SPRAY VALVES (3-1501-27B, 3-1501-28A & B) MAY NOT BE ABLE TO OPEN | | AND/OR CLOSE AGAINST FULL PUMP SHUTOFF PRESSURE AND WORST CASE MOV | | PARAMETERS. MODIFICATIONS HAD BEEN PREVIOUSLY PREPARED FOR THESE VALVES | | FOR IMPLEMENTATION DURING THE REFUELING OUTAGE SCHEDULED FOR 4/26/97. THESE | | MODIFICATIONS MIGHT BE RESCHEDULED FOR THIS OUTAGE. | | | | THESE VALVES BECAME INOPERABLE AS A RESULT OF A CHANGE IN VALVE THRUST | | TESTING METHODOLOGY. UNIT 2 VALVES AND THE REMAINDER OF UNIT 3 VALVES HAVE | | SUFFICIENT OPERATING MARGIN USING THE ENHANCED METHODOLOGY. THE LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31433 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/11/96 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 11:07 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 12/11/96 | +------------------------------------------------+EVENT TIME: 10:00[EST]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 12/11/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEN WERT 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STEAM GENERATOR SHELL DRAIN BLOCK VALVE HAD DISKS INSTALLED BACKWARD | | AND THRUST SETTINGS SET TOO LOW. THE VALVE WOULD NOT HAVE SEATED INTO THE | | CLOSED POSITION IN RESPONSE TO A CONTAINMENT ISOLATION SIGNAL. THE | | LICENSEE DETERMINED THAT THE DISKS IN VALVE 3FDW-103 WERE INSTALLED IN THE | | "NON-PREFERRED DIRECTION". THIS CONDITION EXISTED FROM 12/9/89 TO 12/4/96. | | ADDITIONALLY THE THRUST REQUIRED TO CLOSE THE VALVE WITH THE DISKS IN BOTH | | THE PREFERRED AND NON-PREFERRED DIRECTION IS SET TOO LOW TO COMPLETELY | | CLOSE THE VALVE. THE LICENSEE HAS RESET THE THRUST SETTING TO ASSURE | | PROPER VALVE CLOSURE. THIS PROBLEM ONLY APPLIES TO THIS SPECIFIC UNIT 3 | | VALVE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31434 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 12/11/96 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 11:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/11/96 | +------------------------------------------------+EVENT TIME: 11:15[EST]| |NRC NOTIFIED BY: JACK BRISSOM |LAST UPDATE DATE: 12/11/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEN WERT RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IF ALL THREE AUXILIARY FEEDWATER PUMPS WERE OPERATING AND IF THE ASSURED | | MAKEUP WATER SYSTEM WERE SUPPLYING WATER TO THE AUXILIARY FEEDWATER PUMPS | | THE NET POSITIVE SUCTION HEAD FOR THE AUXILIARY FEEDWATER PUMPS WOULD NOT | | BE MET. | | | | DURING A DESIGN REVIEW OF THE ASSURED MAKEUP SUPPLY (NUCLEAR SERVICE WATER | | SYSTEM WHOSE WATER SOURCE IS FROM LAKE WYLIE) TO THE AUXILIARY FEEDWATER | | SYSTEM (AFW) TO SUPPORT THE REDUCTION OF ICE CONDENSER ICE WEIGHT TECHNICAL | | SPECIFICATION CHANGE, A PROBLEM WAS DISCOVERED WITH THE ADEQUACY OF FLOW | | REQUIREMENTS TO THE AFW PUMPS SUCTION. UNDER CERTAIN ACCIDENT SCENARIOS | | WITH A SINGLE FAILURE OF ONE OF TWO ASSURED MAKEUP SUPPLY VALVES AND ALL | | THREE AFW PUMPS RUNNING, THE NET POSITIVE SUCTION HEAD REQUIREMENTS WOULD | | NOT BE MET FOR THE PUMPS. THIS RENDERS ALL THREE AFW PUMPS INOPERABLE (BOTH | | MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS AND THE TURBINE AUXILIARY FEEDWATER | | PUMP). THIS IS A CONDITION OUTSIDE THE DESIGN BASIS FOR THE AFW SYSTEM. | | THIS CONDITION IS BEING CLEARED BY REALIGNMENT OF VALVES IN THE SYSTEM. THE | | UNITS ARE EXPECTED TO REMAIN AT 100% POWER. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31435 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LOWER BUCKS HOSPITAL, BRISTOL, PA |NOTIFICATION DATE: 12/11/96 | | CITY: BRISTOL REGION: 1 |NOTIFICATION TIME: 16:02 [ET]| | COUNTY: STATE: PA |EVENT DATE: 12/10/96 | |LICENSE#: SNM-1800 AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | |Dr COOL (NMSS) EO | +------------------------------------------------+Dr CONGEL (IRD) AEOD | |NRC NOTIFIED BY: DR MARK ANSLEY |BILL HEHL REG1 | |HQ OPS OFFICER: JOHN MacKINNON |PHIL TING (NMSS) IAT | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OABB 76.120(a)(2) LOSS OF SNM | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISSING NUCLEAR POWERED CARDIAC PACEMAKER CONTAINING PLUTONIUM-238. | | | | THE RADIATION SAFETY OFFICER FOR LOWER BUCKS HOSPITAL, BRISTOL, PA, GAVE | | THE FOLLOWING INFORMATION: | | | | A PATIENT OF THEIRS HAD A NUCLEAR POWERED CARDIAC PACEMAKER AND THEY HAD | | BEEN KEEPING TRACK OF HER. SHE WAS ADMITTED TO NAZARETH HOSPITAL IN | | PHILADELPHIA, PA ON 10/31/96. THE PACEMAKER WAS TAKEN OUT OF HER ON | | 10/31/96, AT THE NAZARETH HOSPITAL. THE PACEMAKER MODEL NUMBER IS "C101" | | (SERIAL # 302) AND IT WAS MADE BY CORE ATOMIC (THE PACEMAKER CONTAINS | | PLUTONIUM-238). CORE ATOMIC HAS CHANGED ITS NAME AND THEY NOW CALL | | THEMSELVES BIO-CONTROL. ON 12/10/96, IN THE AFTERNOON, BIO-CONTROL | | CONTACTED THE RSO FOR LOWER BUCKS HOSPITAL AND INFORMED HIM THAT THE | | PACEMAKER WAS MISSING AND THEY DID NOT KNOW WHERE IT WAS (THEY THINK IT IS | | STILL AT NAZARETH HOSPITAL). THE RSO HAS ALREADY CONTACTED NRC REGION 1 | | OFFICE AND INFORMED NEELAM BHALLA OF THIS EVENT BEFORE CALLING THE NRC | | OPERATION CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 31436 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AMERSHAM |NOTIFICATION DATE: 12/11/96 | | CITY: BURLINGTON REGION: 1 |NOTIFICATION TIME: 16:22 [ET]| | COUNTY: MIDDLESEX STATE: MA |EVENT DATE: 12/10/96 | |LICENSE#: 20-12836-01 AGREEMENT: N |EVENT TIME: 14:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | |Dr COOL (NMSS) EO | +------------------------------------------------+Dr CONGEL (IRD) AEOD | |NRC NOTIFIED BY: ERIK OKVIST |BILL HEHL REG1 | |HQ OPS OFFICER: JOHN MacKINNON |TOM TANNER DOE | +------------------------------------------------+FINKBEINER DOT | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 64.4 CURIE, IRIDIUM-192 RADIOGRAPHY SOURCE BEING SHIPPED TO WEST VIKING | | COLLEGE, NEWFOUNDLAND, CANADA, IS MISSING. | | | | A REPRESENTATIVE FROM AMERSHAM RELAYED THE FOLLOWING INFORMATION: | | | | ON 11/21/96, A 64.4 CURIE IRIDIUM-192 SOURCE (64.4 CURIES AS MEASURED ON | | 11/20/96), MODEL # 650 SOURCE CHANGER WAS SHIPPED OUT OF AMERSHAM OFFICE | | LOCATED IN BURLINGTON, MA, BY AIRBORNE EXPRESS. THE IRIDIUM-192 (HALF LIFE | | IS 74 DAYS) IS USED IN RADIOGRAPHY DEVICES. THE IRIDIUM-192 WAS IN A LOCKED | | TYPE "B" PACKAGE (DEPLETED URANIUM SURROUNDING THE IRIDIUM-192 SOURCE FOR | | SHIELDING AND THIS IS ENCLOSED IN A STEEL CONTAINER). THE TYPE "B" PACKAGE | | HAD RADIATION WARNING SIGNS ON IT. | | THE IRIDIUM-192 SOURCE CHANGER WAS BEING SHIPPED TO WEST VIKING COLLEGE | | LOCATED IN NEWFOUNDLAND. | | | | ON 11/29/96, PUROLATOR (AIRBORNE EXPRESS COMPANY OF CANADA) SAID THAT THEY | | HAD CUSTODY OF THE IRIDIUM-192 SOURCE AT THEIR DEPOT (CALLER DID NOT KNOW | | WHERE PUROLATOR DEPOT WAS LOCATED). THIS IS THE LAST KNOWN LOCATION OF THE | | IRIDIUM-192 SOURCE. | | | | THE IRIDIUM-192 SOURCE WAS SUPPOSED TO HAVE ARRIVED AT WEST VIKING COLLEGE | | ON 12/05/96. | | | | PUROLATOR IS LOOKING FOR THE MISSING SOURCE. | | | | BILL UPSHAW OF THE NRC CONTACTED THE CANADIAN AECB DUTY OFFICER AND | | INFORMED HIM OF THIS EVENT AND REQUESTED THE DUTY OFFICER TO NOTIFY THE | | CANADIAN RADIOGRAPH GROUP OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31437 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/11/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/11/96 | +------------------------------------------------+EVENT TIME: 14:45[CST]| |NRC NOTIFIED BY: BART CROW |LAST UPDATE DATE: 12/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - THE DIESEL FIRE PUMP (DFP) MAY NOT PERFORM AS REQUIRED DURING A FIRE - | | | | THE LICENSEE APPENDIX 'R' REVALIDATION EFFORT HAS IDENTIFIED THAT A SAFE | | SHUTDOWN COMPONENT (DIESEL FIRE PUMP #FP-P-D) MAY NOT PERFORM AS REQUIRED | | DURING A FIRE IN THE CABLE SPREADING ROOM OR CONTROL ROOM. FIRE INDUCED | | CABLE FAULTS COULD SPURIOUSLY ENERGIZE THE REMOTE STOP RELAY AND THEREBY | | PREVENT THE DFP FROM STARTING, OR STOPPING, IF ALREADY RUNNING. | | | | THE DFP PERFORMS TWO FUNCTIONS WITH REGARD TO APPENDIX R SAFE SHUTDOWN. | | FIRST: THE DFP PROVIDES A SOURCE OF WATER FOR THE SERVICE WATER PUMP GLAND | | SEAL SYSTEM. THE FIRE PROTECTION SUPPLY TO THE SERVICE WATER PUMP GLAND | | SEALS IS ONLY CREDITED FOR ALTERNATE SHUTDOWN FIRE SCENARIOS. IN ACCORDANCE | | WITH THE APPENDIX R FUNCTIONAL REQUIREMENTS DOCUMENT, SERVICE WATER PUMP | | GLAND SEAL COOLING MUST BE AVAILABLE WITHIN APPROXIMATELY 20 SECONDS AFTER | | THE START OF A SERVICE WATER PUMP. THE LOSS OF GLAND SEAL COOLING WOULD | | NOT RESULT IN CATASTROPHIC FAILURE OF THE SERVICE WATER PUMP, BUT WOULD | | RESULT IN A RAPID DEGRADATION OF THE SERVICE WATER PUMP PACKING GLAND. | | SECOND: THE DFP PROVIDES A SOURCE OF WATER FOR THE MANUAL AND/OR AUTOMATIC | | SUPPRESSION SYSTEMS WHICH FORM THE BASIS FOR AN APPENDIX R EXEMPTION | | GRANTED FOR THE CABLE SPREADING ROOM. THE CABLE SPREADING ROOM AND CONTROL | | ROOM ARE BOTH ALTERNATE SHUTDOWN FIRE AREAS. IN ACCORDANCE WITH SECTION | | III.L OF 10CFR50, APPENDIX R, OFFSITE POWER CANNOT BE CREDITED FOR | | ALTERNATE SHUTDOWN FIRE SCENARIOS. THE DFP DOES NOT REQUIRE AC POWER AND | | IS THEREFORE THE ONLY FIRE PUMP WHICH CAN BE CREDITED FOR ALTERNATE | | SHUTDOWN. | | | | THE DFP IS COVERED BY TECHNICAL SPECIFICATIONS. BASED UPON THE LICENSEE | | DOCUMENT ENTITLED "ASSESSMENT OF APPENDIX R VULNERABILITIES", DATED | | 08/22/96, A CONTINUOUS FIRE WATCH WILL BE REQUIRED FOR THE TWO AFFECTED | | FIRE ZONES. A PLANT MODIFICATION WILL BE PERFORMED TO DISABLE THE REMOTE | | STOP CAPABILITY OF THE DFP. | | | | THIS EVENT REPRESENTS AN INABILITY OF A STRUCTURE, SYSTEM, OR COMPONENT | | TO MAINTAIN THE REACTOR IN A SAFE SHUTDOWN CONDITION. | | | | THE LICENSEE WILL INCLUDE THE DETAILS OF THIS REPORT IN A SUPPLEMENT TO | | PREVIOUSLY REPORTED LER #96-009. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31438 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 12/11/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 16:32 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 12/10/96 | | FABRICATION & SCRAP RECOVERY |EVENT TIME: 15:54[PST]| | COMMERICAL LWR FUEL |LAST UPDATE DATE: 12/11/96 | | CITY: RICHLAND REGION: 4 +-----------------------------+ | COUNTY: BENTON STATE: WA |PERSON ORGANIZATION| |LICENSE#: SNM-1227 AGREEMENT: Y |GARY SANBORN RDO | | DOCKET: 07001257 | | +------------------------------------------------+ | |NRC NOTIFIED BY: LOREN MAAS | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -FIRE LASTING 5 MINUTES & PARTIAL LOSS OF ELECTRICAL POWER DUE TO A SHORT- | | | | AT 1554 (PST) ON 12/10/96, AN APPARENT PHASE-TO-PHASE SHORT IN A 480 VOLT | | ELECTRICAL POWER JUNCTION BOX TO THE PRODUCT DEVELOPMENT FACILITY (PDTF) | | CAUSED A BRIEF FIRE AND PARTIAL LOSS OF ELECTRICAL POWER AFFECTING SEVERAL | | BUILDINGS ON THE SIEMENS POWER CORPORATION (SPC) RICHLAND, WASHINGTON SITE. | | | | THE FIRE WAS CONTAINED IN A POWER JUNCTION BOX MOUNTED ON THE REAR EXTERIOR | | WALL OF THE PDTF AND A SMALL AREA OF INSULATION ON THE INTERIOR WALL OF THE | | PDTF. THE LOSS OF ELECTRICAL POWER TERMINATED THE FIRE ENERGY SOURCE AND | | THE REMAINING FIRE WAS EXTINGUISHED WITH A HAND HELD FIRE EXTINGUISHER BY | | AN SPC EMPLOYEE AT 1559 (PST). AT 1558 (PST), BOTH A FIRE TROUBLE ALARM | | AND AN EMERGENCY PHONE REPORT WERE RECEIVED IN THE CENTRAL GUARD STATION | | (CGS). THE CITY OF RICHLAND FIRE DEPARTMENT (RFD) RESPONDED TO THE REQUEST | | BY THE CGS AND ARRIVED AT THE SITE AT 1609 (PST). THE RFD CONFIRMED THAT | | THE FIRE WAS EXTINGUISHED, PERFORMED SMOKE REMOVAL, AND RESTORED ACCESS TO | | THE PDTF. THE RFD DEPARTED THE SITE AT 1700 (PST). | | | | THE PDTF IS OPERATED UNDER NRC LICENSE FOR HYDRAULIC FLOW AND SEISMIC TESTS | | INVOLVING SINGLE FUEL ELEMENTS CONTAINING SPECIAL NUCLEAR MATERIAL OF UP TO | | 5 WEIGHT % OF U-235. TESTING WAS NOT IN PROGRESS AND NO SPECIAL NUCLEAR | | MATERIAL WAS PRESENT AT THE TIME OF THE FIRE. THE PDTF DOES CONTAIN TEST | | ASSEMBLIES CONTAINING EITHER DEPLETED OR NATURAL URANIUM. THESE TEST | | ASSEMBLIES WERE NOT AFFECTED BY THE FIRE. | | | | THE ELECTRICAL POWER OUTAGE CAUSED BY THE SHORT RESULTED IN A COMPLETE LOSS | | OF ELECTRICAL POWER TO CERTAIN OFFICE BUILDINGS AND ANCILLARY FACILITIES | | AND A PARTIAL LOSS OF ELECTRICAL POWER TO THE MAIN UO2 BUILDING. THE | | PARTIAL LOSS OF ELECTRICAL POWER TO THE UO2 BUILDING RESULTED IN A LOSS OF | | LINE 2 CONVERSION PROCESS EQUIPMENT, VENTILATION SUPPLY FANS, AND THE TWO | | UO2 BUILDING AIR SAMPLING SYSTEM VACUUM PUMPS. UO2 BUILDING AND PROCESS | | EXHAUST SYSTEMS REMAINED OPERABLE MAINTAINING NEGATIVE CONTAINMENT PRESSURE | | IN THE UO2 BUILDING AND CONVERSION AREA PROCESS EQUIPMENT. AN ORDERLY | | SHUTDOWN OF ALL PROCESS OPERATIONS WAS PERFORMED UNTIL NORMAL ELECTRICAL | | POWER WAS RESTORED AT 1805 (PST). BECAUSE NORMAL AIRBORNE SAMPLING WAS | | LOST DUE TO THE VACUUM SAMPLE PUMP LOSS, RESPIRATORY PROTECTION WAS | | PRESCRIBED FOR REQUIRED PERSONNEL IN THE UO2 BUILDING PROCESS AREAS UNTIL | | RESTORATION OF POWER. HEPA EXHAUST FILTER BANK SYSTEM INTEGRITY WAS | | VERIFIED BY VERIFICATION OF FILTER BANK DIFFERENTIAL PRESSURE CONTINUOUS | | MEASUREMENT. | | | | THE CITY OF RICHLAND UTILITIES SERVICE ISOLATED THE DAMAGED ELECTRICAL | | POWER SUPPLY TO THE PDTF AND RESTORED NORMAL POWER TO THE UO2 BUILDING | | BY 1805 (PST). FOUR TECHNICIANS HAD EVACUATED THE PDTF. THERE WERE NO | | PERSONNEL INJURIES, NO PERSONNEL EXPOSURES TO RADIATION, NO RELEASE OF | | RADIATION FROM THE PLANT, NO DAMAGE TO ANY LICENSED MATERIAL, AND NO | | ADVERSE IMPACT ON THE ENVIRONMENT. | | | | THIS INCIDENT RESULTED IN THE TEMPORARY SUSPENSION OF CERTAIN LICENSED | | ACTIVITIES IN THE SPC PRIMARY PRODUCTION FACILITY. | | | | SPC IS CONDUCTING A FORMAL INVESTIGATION OF THIS INCIDENT. | | | | A CONFERENCE CALL AMONG WENSLAWSKI (NRC FIELD OFFICE), PHIL TING (NMSS), | | AND Dr COOL (NMSS EO) WAS SET UP TO DISCUSS THE EVENT. Dr CONGEL (IRD) WAS | | NOTIFIED OF THIS EVENT AND OF THE CONFERENCE CALL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31439 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 12/11/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 21:12 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/11/96 | +------------------------------------------------+EVENT TIME: 20:00[EST]| |NRC NOTIFIED BY: DAN MCDOUGOLD |LAST UPDATE DATE: 12/11/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY DOERFLEIN 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFIED THE STATE OF MAINE OF AN UNPLANNED RELEASE. | | | | MAINE YANKEE IS REQUIRED BY STATE LAW TO PROVIDE ADVANCE NOTICE OF TWO DAYS | | SCHEDULED RELEASES FOR PUBLIC INFORMATION. IF THE ACTUAL VALUE FOR THE DAY | | IS EXCEEDED, MAINE YANKEE IS REQUIRED TO NOTIFY THE STATE THAT AN | | UNSCHEDULED RELEASE HAS OCCURRED. THE SCHEDULED PRIMARY VENT STACK RELEASE | | FOR WEDNESDAY 12/11/96 WAS 0.06CI. | | | | AT 0005 ON 12/11/96, A PRIMARY VENT STACK SAMPLE WAS TAKEN AND WAS FOUND TO | | BE HIGHER THAN EXPECTED. SUBSEQUENT SAMPLING HAS VERIFIED THAT THE PRIMARY | | VENT STACK RELEASE FOR 12/11/96 WILL BE APPROXIMATELY 0.256 CURIES. SINCE | | THE ACTUAL VALUE EXCEEDS THE SCHEDULED VALUE. THE DEVIATION REQUIRES A | | NOTIFICATION TO THE STATE AND THEREFORE IS ALSO REPORTABLE TO THE NRC. | | | | FOR 12/12/96, THE SCHEDULED RELEASE WAS TO BE 0.10 CURIES BUT THE PROJECTED | | AMOUNT IS NOW ESTIMATED TO BE APPROXIMATELY 0.25 CURIES. THEREFORE, | | TOMORROW WILL ALSO BE UNSCHEDULED. FURTHER PROJECTIONS WILL INCLUDE THE | | HIGHER VALUES. | | | | NO NOTICEABLE CHANGE OCCURRED ON THE PRIMARY VENT STACK GAS RADIATION | | MONITOR. THE ODCM LIMIT FOR PERSONNEL EXPOSURE HAS NOT BEEN EXCEEDED. | | | | PLANT OPERATIONS, CHEMISTRY, AND RADIATION CONTROLS ARE INVESTIGATING THE | | SOURCE OF THE RELEASE FOR TERMINATION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+