ENS 43234
ENS Event | |
---|---|
21:30 Mar 13, 2007 | |
Title | Potential Hazard Affecting Criticality Controls Discovered |
Event Description | BACKGROUND:
AREVA NP Richland routinely uses propane powered forklifts to move SNM in and between process buildings and warehouses. These forklifts have been routinely left inside these warehouses when not being used. During re-evaluations of facility hazards, AREVA safety staff questioned the acceptability of such practices in the context of 10CFR 70.61. EVENT DESCRIPTION: On March 13, 2007 at approximately 14:30 PDST, a member of the AREVA safety staff briefed site management on the conclusion of the safety staff that the practice of leaving propane powered forklifts unattended inside SNM storage warehouses for extended periods of time did not meet the performance requirements of 10 CFR 70.61 in that under certain postulated circumstances, a propane deflagration could occur and initiate a large fire. During some postulated fire-fighting scenarios, it was determined that accidental nuclear criticality was not 'highly unlikely'. SAFETY SIGNIFICANCE OF EVENT: The safety significance of this condition is low because an accidental nuclear criticality is still considered unlikely. The municipal fire department works closely with the AREVA emergency response organization when they respond to plant abnormal events and emergencies. The NCS organization is an integral part of the ERO and participates in the decision making during such events if NCS concerns exist. There have been no propane fires on site during the time of the deficient analysis. POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW CRITICALITY COULD OCCUR): Criticality could potentially occur during firefighting if the SNM in storage looses geometry control coincident with moderation. CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): The process parameters controlled in the various storage warehouses include geometry, mass, moderation and neutron absorbers depending upon the storage configuration. NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES: Plant-wide fire controls are established to ensure that large fires that would require the intervention by the municipal fire department are highly unlikely. This assures that the potential NCS concerns relative to fire-fighting with water are compliant with regulatory requirements. However, in certain areas of the plant the scenario of a propane deflagration and the potential subsequent large fire and response by the municipal fire department could not be shown to be highly unlikely during this unlikely condition. CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: After discovery of the deficiency, a prohibition of allowing propane powered vehicles to remain unattended for significant amounts of time in warehouses is being established. Additionally, a restriction against using water for fire-fighting in the areas of concern, without approval of a Criticality Safety Engineer is being established. These administrative actions will ensure that accidental nuclear criticality due to a propane-induced fire scenario remains highly unlikely. |
Where | |
---|---|
Areva Np Inc Richland Richland, Washington (NRC Region 2) | |
License number: | SNM-1227 |
Reporting | |
Part 70 App A (B)(1) | |
Time - Person (Reporting Time:+-1.25 h-0.0521 days <br />-0.00744 weeks <br />-0.00171 months <br />) | |
Opened: | Robert Link 20:15 Mar 13, 2007 |
NRC Officer: | Jason Kozal |
Last Updated: | Mar 13, 2007 |
43234 - NRC Website | |
Areva Np Inc Richland with Part 70 App A (B)(1) | |
WEEKMONTHYEARENS 517572016-02-25T19:45:00025 February 2016 19:45:00
[Table view]Part 70 App A (B)(1) Potential Common Mode Failure of Item Relied on for Safety ENS 483662012-10-02T14:30:0002 October 2012 14:30:00 Part 70 App A (B)(1) Unanalyzed Conditions May Lead to Intermediate Consequence Events ENS 479082012-05-08T14:30:0008 May 2012 14:30:00 Part 70 App A (B)(1) Improperly Analyzed Condition ENS 449972009-04-16T23:00:00016 April 2009 23:00:00 Part 70 App A (B)(1) Unanalyzed Condition Due to Possible Unfavorable Geometry ENS 432342007-03-13T21:30:00013 March 2007 21:30:00 Part 70 App A (B)(1) Potential Hazard Affecting Criticality Controls Discovered ENS 429812006-11-09T23:30:0009 November 2006 23:30:00 Part 70 App A (B)(1) Hydrogen Accumulation Due to Loss of Water Seal ENS 429362006-10-23T17:50:00023 October 2006 17:50:00 Part 70 App A (B)(1), Part 70 App A (B)(3) Workers Exposed to Hydrogen Floride Release 2016-02-25T19:45:00 | |