Event Notification Report for July 12, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/11/2000 - 07/12/2000 ** EVENT NUMBERS ** 37160 37161 37162 37163 +------------------------------------------------------------------------------+ |Other Nuclear Material |Event Number: 37160 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: U.S. AIR FORCE |NOTIFICATION DATE: 07/11/2000| |LICENSEE: U.S. AIR FORCE |NOTIFICATION TIME: 10:33[EDT]| | CITY: LEXINGTON REGION: 2 |EVENT DATE: 07/10/2000| | COUNTY: STATE: SC |EVENT TIME: 12:00[EDT]| |LICENSE#: 42-23539-01AF AGREEMENT: Y |LAST UPDATE DATE: 07/11/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |GEORGE BELISLE R2 | | |LINDA HOWELL R4 | +------------------------------------------------+DON COOL NMSS | | NRC NOTIFIED BY: MAJOR WROBEL | | | HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |IBAC 30.50(b)(1)(i) ACCESS DENIED >24 HRS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO AIRCRAFT ENGINE SET OFF PORTAL ALARMS | | | | TWO AIRCRAFT ENGINES SENT TO CMC LEXINGTON IN LEXINGTON, SC SET OFF THE | | PORTAL ALARMS AT THEIR FACILITY ON 6/7/00. CMC LEXINGTON NOTIFIED THE U.S. | | AIR FORCE OF THE EVENT. THE AIR FORCE HAD INITIALLY ASSUMED THAT THE ALARMS | | WERE CAUSED BY A MAGNESIUM THORIUM ALLOY USED IN THE ENGINES. HOWEVER, | | SURVEYS CONDUCTED ON 7/6/00, DISCOVERED LOW LEVELS OF BOTH BETA/GAMMA AND | | ALPHA CONTAMINATION. | | | | THE AIR FORCE IS SENDING A TEAM TO THE SITE TOMORROW TO FURTHER ANALYZE THE | | CONTAMINANTS AND PLAN A COURSE OF ACTION. THE ISOTOPE(S) INVOLVED WERE NOT | | KNOWN AT THE TIME OF THE REPORT. THE ENGINES HAVE BEEN PLACED IN A LOCATION | | TO PREVENT ANY SPREAD OF CONTAMINATION. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37161 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 07/11/2000| | UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 16:33[EDT]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/11/2000| +------------------------------------------------+EVENT TIME: 16:10[EDT]| | NRC NOTIFIED BY: BRANFORD STANLEY |LAST UPDATE DATE: 07/11/2000| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |THOMAS DECKER R2 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | FITNESS FOR DUTY REPORT | | | | A licensed operator tested positive for illegal drug use during a random | | test administered on 6/29/00. The individual's site access has been | | suspended. The NRC resident inspector will be informed of this notification | | by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 37162 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/11/2000| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:02[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/11/2000| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:45[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/11/2000| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN R3 | | DOCKET: 0707002 | | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM McCLEERY | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | "NCSA-PLANT-012 (Favorable Geometry Vacuum Cleaner) Control number 3 | | requires a steel liner to be used in an F-can when enrichment is known or | | expected to exceed >80%. At 0945 on 7/11/00, it was discovered that the | | steel liner was constructed of expanded metal (grating), therefore the liner | | would not perform its intended function as described in the associated NCSE. | | The intended function is to reduce the internal diameter of the F-can to | | less than five inches. The affected F-cans were verified to contain less | | than the safe mass of U-235. The NCSA is deficient since it references a | | drawing of a liner that cannot perform its intended function. | | | | SAFETY SIGNIFICANCE OF EVENTS: | | | | Safety significance is low because the highest mass in any F-can on site | | with greater than 80% enrichment material is 304 grams U-235 and the USEC | | site limit for >20% enrichment material is 1000 grams U-235. The mass in the | | F-cans and the site limit are well below the contingency limit for not using | | an F-can liner(2500 grams U-235 at 80% enrichment) and current | | NCSA-PLANT-012 operations are below 80% enrichment, in the unlikely event | | that 2500 grams of high enriched U-235 was present in the F can, an | | additional event, such as the presence of full reflection or spacing | | violation would be required before obtaining a critical configuration | | | | "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW | | CRITICALITY COULD OCCUR): | | | | "A critical configuration would require an F-can to be used to collect 80% | | or greater enriched material that exceeded 2500 grams. In the unlikely event | | of exceeding 2500 grams of 80% enriched material in the F-can, an additional | | unlikely event, such as the F-can being exposed to full water reflection or | | a spacing violation would have [been] necessary before a critical | | configuration existed. The probability of all of these conditions existing | | simultaneously is very low. | | | | "CONTROLLED PARAMETERS (MASS, MODERATION. GEOMETRY, CONCENTRATION, ETC.): | | | | "Volume, geometry, moderation and interaction are controlled. Geometry | | control could have been lost since the referenced drawing for the liner does | | not meet the geometry requirements of the NCSE. Full reflection or an | | interaction violation is required before a criticality configuration could | | exist. | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE OF CRITICAL MASS): | | | | "The highest mass in any F-can with greater than 80% enriched material on | | site is 304 grams U-235. Since this is 87% of safe mass, the safety | | significance is low. | | | | "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: | | | | "The NCS control system is deficient since the NCSA references a steel liner | | in a drawing that does not perform its intended function of reducing the | | F-can liner diameter to 5 inches or less. The safety significance is low | | since the mass in F-cans is low and an additional event such as full | | reflection or a spacing violation would have to accompany an excessive F-can | | mass before a criticality would be possible. | | | | "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | | | "A stop work notice was issued for favorable geometry vacuum cleaners when | | enrichment is known or suspected to exceed 80%." | | | | The NRC resident inspector has been informed of this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 37163 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/11/2000| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 21:40[EDT]| | RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/11/2000| +------------------------------------------------+EVENT TIME: 19:50[CDT]| | NRC NOTIFIED BY: RUSSELL BENNETT |LAST UPDATE DATE: 07/11/2000| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BRUCE JORGENSEN R3 | |10 CFR SECTION: | | |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 | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT OUTSIDE DESIGN BASIS DUE TO 10 CFR PART 50, APPENDIX R ISSUE | | | | "At approximately 1610 on 7/11/2000, it was identified by plant walkdown | | that in electrical switchgear Bus 142Y (1AP06B) cubicle 4 (for the Unit 1 B | | Residual Heat Removal pump) that an unsealed borehole of approximately three | | (3) inches in diameter existed. This borehole is located in the floor | | separating the Unit 1 Division 2 Switchgear room from the Unit 1 Division 1 | | switchgear room. The borehole is located in a three (3) hour rated fire | | barrier that is required by Administrative Technical Requirement 3/4.7.6 | | (Fire Rated Assemblies). This has been considered an event that is outside | | the design basis due to required design basis protective features for safe | | shutdown trains as described in 10 CFR 50, Appendix R and Final Safety | | Analysis Report [being] lacking. Compensatory measures (fire watches) have | | been established per Administrative Technical Specifications and plans for | | repairs are in progress." | | | | The NRC resident inspector has been notified of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021