Event Notification Report for March 18, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/15/2002 - 03/18/2002 ** EVENT NUMBERS ** 38770 38771 38772 38773 38774 38775 +------------------------------------------------------------------------------+ |Hospital |Event Number: 38770 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: FOX CHASE CANCER CENTER |NOTIFICATION DATE: 03/15/2002| |LICENSEE: FOX CHASE CANCER CENTER |NOTIFICATION TIME: 10:23[EST]| | CITY: PHILADELPHIA REGION: 1 |EVENT DATE: 03/15/2002| | COUNTY: STATE: PA |EVENT TIME: [EST]| |LICENSE#: 37-02766-01 AGREEMENT: N |LAST UPDATE DATE: 03/15/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |DAVID LEW R1 | | |SUSAN FRANT NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: KAREN SHEEHAN | | | HQ OPS OFFICER: RICH LAURA | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | P-32 SOURCE USED IN RESEARCH DISCOVERED MISSING | | | | The following preliminary information was provided by the licensee: | | | | "This is to inform you of an incident that occurred at our facility | | involving a recent shipment of 250 microcuries of phosphorous-32 [P-32] | | deoxyguanosine 5 triphosphate. The shipment was delivered to our facility | | (License # 37-02766-01) on March 8, 2002 as an excepted package, limited | | quantity [49 CFR173.421]. The package was delivered to the recipient lab and | | the blue plastic container was placed in a freezer that was locked for | | storage of the material. On March 11, 2002 when the freezer was unlocked and | | the blue container was removed for use there was no vial of P-32 inside. The | | lab worker immediately reported the situation to her Principal Investigator. | | Initially the assumption was simply that the facility was shortchanged a | | vial and indeed that is our conclusion after investigation of the incident. | | The Radiation Safety Officer [RSO] was notified via e-mail at or about the | | time the purchasing department was notified. | | | | "The RSO immediately began an investigation of the incident. It was | | determined that the initial recipient did not follow the facilities | | procedure for opening packages of radioactive material and failed to monitor | | the surface of the package or look inside and verify the contents. The | | shipper, Perkin Elmer, was notified and asked to investigate the matter. The | | distribution coordinator at Perkin Elmer indicated that there might have | | been other incidents where primary vials have been omitted from a shipment. | | She declined to give further details until they finish their investigation. | | The RSO was informed that each package is not routinely surveyed by Parker | | Elmer even though an exposure rate was indicated on the packing slip. | | | | "Physical inventories of the laboratory concerned and an adjacent laboratory | | were conducted and there were no discrepancies. Hospital security has been | | notified and they are conducting an investigation. A radiation survey using | | a Ludlum Model 3 survey meter with a 44-9 probe was performed of the lab in | | question, as well as the tissue culture room where the material was stored, | | and the Principal Investigator's Office. The shelves, drawers, cabinets, | | sinks, trashcans were surveyed in these areas with no positive results. A | | water cooler in the vicinity was swipe tested on the advice of our | | consultant. The water cooler showed no evidence of P-32 contamination. All | | the bottles next to the water cooler were also surveyed via a meter and no | | levels were found. | | | | "The Principal Investigator [ ] was interviewed by the RSO. She indicated | | that she was not aware of any personal conflicts within her lab nor any | | other labs at the facility. She indicated that not only is their | | radioactive material kept locked within a freezer dedicated to radioactive | | materials storage, but that the tissue culture room is kept locked when not | | in use. | | | | "Access to the building requires an access card and there is a record of all | | personnel who entered the building during the period March 8-11. They are in | | the process of interviewing those personnel on the list. | | | | "Shipping and Receiving was checked for other shipments from Perkin Elmer | | but none were received on March 8. | | | | "We have completed the following corrective actions. A review of package | | receipt procedures including survey of the package and inspection of the | | primary vial was done with the personnel in the lab that received the | | shipment. The lab in question also developed a procedure checklist that | | includes not only the above but also the step of matching the lot number on | | the vial with that on the shipping papers. A memo has been sent to all of | | the other research labs reminding them of the procedures for receiving | | packages include a survey of the surface of the package even though | | regulations do not require that for an exempt quantity package and an email | | send as urgent went to all research areas, Nuclear Medicine and Radiation | | Oncology. A review of the incident and package receipt procedures will be | | included in annual inservices and information conveyed during routine | | inspections of radioactive materials laboratories. | | | | "We have concluded that the primary vial was probably not shipped, because | | the material was secured within the building, the tissue culture room, and | | within the freezer from the time delivered until the attempt to use it. No | | evidence of any irregularity resulted from the investigations conducted by | | the RSO and Security. But since we cannot rule out that the vial was shipped | | we are notifying the Nuclear Regulatory Commission. Security has always been | | a priority at Fox Chase Cancer Center and we are aware of the heightened | | concerns due to the terrorist attacks of September 11". | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38771 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/15/2002| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:55[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/14/2002| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/15/2002| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |MONTE PHILLIPS R3 | | DOCKET: 0707002 |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: ERIC SPAETH | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | "During Field-testing of the west annex floor, the floor failed to maintain | | the solution in a safe slab by allowing water to seep in cracks along the | | wall. This is a violation of NCSA- 0705_076 (inadvertent containers) | | administrative controls on potential inadvertent containers. While an unsafe | | amount of solution was NOT lost in this event, the cracks represent a loss | | of one leg of double contingency control as defined in NCSE- 0705_076. | | | | "Background information: On March 6, a low level probe for the storage | | columns in the West Annex developed a leak and allowed uranium-bearing | | solution to accumulate on the floor. The amount of spilled solution on the | | floor was estimated at that time to be no more than 18.4 liters. The spill | | amount did not meet the definition of an unsafe amount of uranium bearing | | material, the process conditions credited for meeting double contingency in | | the NCSE's were maintained. | | | | "On March 14, after completing repairs to the low level probe, the solution | | level in the West Annex storage columns was remeasured. The solution volume | | lost, calculated from the system sight glasses was calculated to be | | approximately 97.5 liters. Given the known assay and concentration of | | uranium, the spilled solution still did not represent an unsafe amount of | | uranium bearing material even when the volume was increased from 18.4 liters | | to 97.5 liters. | | | | "On March 14, an NCS engineer and Operations personnel investigated the | | difference between the amount of solution observed on the floor and the | | amount estimated by the level of the sight glass. A field test was conducted | | where as water was observed to seep into cracks between the floor and the | | wall. | | | | "SAFETY SIGNIFICANCE OF EVENTS: Low. The solution in question could not | | support a criticality in any geometry. Less than a safe mass amount of | | solution was involved. | | | | "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW | | CRITICALITY COULD OCCUR): | | For a criticality to occur, the following events are required. The West | | Annex blending system would have to be operating and processing solution | | with a high concentration of uranium and assay. Then a leak would have to | | occur such that an unsafe amount of solution would collect on the floor. The | | solution would then flow into the cracks on the floor into an unsafe | | geometry. Depending on the amount of solution collected some reflection | | would be required to maintain a critical chain reaction. | | | | "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): | | N/A. Volume or Geometry | | | | "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS | | LIMIT AND % WORST CASE OF CRITICAL MASS): Based upon the amount of solution | | that leaked on the floor, 51 grams U235. This represents 3% of the required | | amount of solution | | | | "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: Cracks between the floor and the wall could | | allow solution to enter an unknown unfavorable geometry in the event of a | | spill. | | | | "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: | | The PSS directed remaining in an anomalous condition until the repairs to | | the cracks can be made." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38772 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: WV RADIOLOGICAL HEALTH PROGRAM |NOTIFICATION DATE: 03/15/2002| |LICENSEE: WEIRTON MEDICAL CENTER |NOTIFICATION TIME: 17:37[EST]| | CITY: WEIRTON REGION: 2 |EVENT DATE: 03/02/2002| | COUNTY: STATE: WV |EVENT TIME: [EST]| |LICENSE#: 47-17567-01 AGREEMENT: N |LAST UPDATE DATE: 03/15/2002| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MARK LESSER R2 | | | | +------------------------------------------------+ | | NRC NOTIFIED BY: DAN HILL | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION | | | | The West Virginia Radiological Health Program was notified by the Ohio | | Bureau of Radiation Protection that a shipment of medical waste from the | | Weirton Medical Center activated a radiation detector at the Stericycle | | medical waste incineration facility in Ohio. The dose rate at the surface of | | the package was greater than 500 microR/hr (as of 3/15/02, it was 200 | | microR/hr). The incinerator facility is holding the package in a secure | | location until the Weirton Medical Center is able to retrieve it. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38773 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/16/2002| | UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 06:59[EST]| | RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/16/2002| +------------------------------------------------+EVENT TIME: 02:40[EST]| | NRC NOTIFIED BY: ROBERT BOESCH |LAST UPDATE DATE: 03/16/2002| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |DAVID LEW R1 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 ENTERED TS 3.0.3 AFTER DECLARING ESS BUSES INOPERABLE DUE TO ERROR IN | | CLEARANCE | | | | "On 3/16/02 at 0240 hours, a field operator was directed to remove a | | clearance and rack in 4 Kv breakers for the Unit 1 A & B Control Rod Drive | | system. The system had been out of service for maintenance during the refuel | | outage. Upon arrival at the load center, the operator found both breakers | | racked out but not secured with the required seismic restraints. According | | to plant procedures, this renders the associated bus inoperable. Shift | | supervision was notified and the Unit 1 'A' and 'D' ESS Busses were declared | | inoperable. The immediate effects were for Unit 2 to enter TS 3.0.3 which | | was exited 30 minutes later, once the breakers were returned to their | | racked-in position. In review of the Loss of Safety Function, it was | | discovered that, with the 'A' and 'D' ESS Busses inoperable, the Control | | Structure chillers were inoperable resulting in an event or condition that | | could have prevented fulfillment of a Safety Function required to Mitigate | | the consequences of an accident. In accordance with 10CFR50.72(b)(3)(,v)(D) | | this loss of safety function requires an 8 hour ENS Notification." | | | | The 4 Kv breakers were racked out 8 days ago. Due to an oversight in | | preparation of the clearance, the procedure requiring installation of the | | seismic restraints was not referenced. The licensee informed the NRC | | Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38774 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 03/16/2002| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 13:55[EST]| | RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 03/16/2002| +------------------------------------------------+EVENT TIME: 12:15[CST]| | NRC NOTIFIED BY: MICHAEL FITZPATRICK |LAST UPDATE DATE: 03/16/2002| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MONTE PHILLIPS R3 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SHUTDOWN IN ACCORDANCE WITH TECHNICAL SPECIFICATIONS | | | | "This notification is being made pursuant to 10CFR50.72(b)(2)(i), and Exelon | | Reportability Manual section SAF 1.2. At 1215 CST on 03/16/02, during Unit 2 | | steady state operation at 100% power, a unit shutdown was initiated due to | | an increase in Reactor Coolant System Unidentified Leakage in excess of | | Technical Specification limits. RCS unidentified leakage has increased by | | 2.1 gallons per minute over a 24 hour period, from 0.9 gpm to 3.0 gpm, which | | is above the Tech Spec limit of less than or equal to 2 gpm. On 3/16/02 at | | 0555 CST, a 12 hour timeclock was entered to be in Hot Shutdown by 1755 CST, | | followed by Cold Shutdown on 3/17/02 at 1755 CST. Current plans are to enter | | Cold Shutdown in order to enter the Primary Containment, and determine and | | correct the cause of the unidentified leakage." | | | | The NRC resident inspector has been informed of this event by the licensee. | | | | * * * UPDATE 2214 EST 3/16/2002 FROM DANIEL COVEYOU TAKEN BY BOB STRANSKY * | | * * | | | | "This notification provides an update of EN #38774 and is being made | | pursuant to 10CFR50.72(c)(2) and Exelon Reportability Manual section SAF | | 1.2. | | | | "As of 1540 CST, the indicated increase in the Unit 2 unidentified leakage | | rate over the previous 24 hr period has decreased to 1.7 gpm. As this value | | meets the LCO requirements of LaSalle Technical Specification 3.4.5 (<2 gpm | | increase within previous 24 hours), the plant shutdown initiated at 1215 CST | | is no longer required. | | | | "The increase (and subsequent decrease) in the indicated unidentified | | leakage rate is consistent with previously observed behaviors following | | primary containment cooling equipment lineup changes that induce containment | | air temperature changes. Initial chemistry analyses of the primary | | containment environment (air and sump samples) indicate that there has been | | no increase in reactor coolant system leakage. | | | | "The shutdown was terminated with the reactor operating at 69% power. | | Current plans are to return the unit to full power operation." | | | | The NRC resident inspector has been informed of this update by the licensee. | | Notified R3DO (Phillips). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38775 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 03/17/2002| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 17:03[EST]| | RXTYPE: [1] CE |EVENT DATE: 03/17/2002| +------------------------------------------------+EVENT TIME: 15:25[CST]| | NRC NOTIFIED BY: ANTHONY CHRISTIANSON |LAST UPDATE DATE: 03/17/2002| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |GAIL GOOD R4 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 98 Power Operation |98 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO BRUSH FIRE NEAR SITE | | | | The licensee contacted the local volunteer fire department to respond to two | | small brush fires burning under the plant access road bridge. The fire | | department responded at 1537 CST and both fires were extinguished by 1556 | | CST. The licensee believes that the fires were caused by a passing train. | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021