ENS 50425
ENS Event | |
---|---|
15:00 Sep 4, 2014 | |
Title | Unanalyzed Condition Related to Potential Material Transfer Cart Tipping |
Event Description | I. EVENT DESCRIPTION: On September 4, 2014 at approximately 1100 [EDT], a Nuclear Criticality Safety (NCS) engineer identified a safety concern. While working to consolidate information in the safety basis for the safe geometry storage and transport carts, it was determined that an unanalyzed condition existed that did not meet the performance requirements of 10 CFR 70.61. Tipping or impact of a cart during transport had not been considered as a credible upset condition.
II. EVALUATION OF THE EVENT: At B&W's NOG-L [Nuclear Operations Group] facilities, safe geometry storage and transport carts are used to transfer uranium bearing materials between radiologically controlled areas. The carts are typically used to transfer scrap and waste materials in favorable volumes less than or equal to 2.5 liter containers to the Drum Count Area for 235U assay. Because the 235U content of such containers is not known until they have been assayed, they are referred to as 'unknowns' and are subject to a net weight limit. These containers are limited to a maximum of 7,000 grams net weight (approximately 15 pounds) of uranium bearing material in any form. There are forty storage locations on a cart, twenty per side. The locations on each side are arranged in an array of 4 columns, each column contains 5 storage locations. During transport each column of storage locations is protected by closure of a door. The four column doors on each side of the cart are secured by a common locked bar. The NCS evaluation of the safe geometry storage and transport carts did not address possible tipping during transit. Although unlikely, it is believed at this point the event is credible. If a cart were to tip, no controls were identified to retain the containers on the cart. Although the doors on the cart are secured by a robust locking bar, this action is taken for security purposes and is not credited as an IROFS [Item Relied On For Safety]. Assuming the containers on the cart were fully loaded (7 kg net weight) with a U-metal water mixture at optimum H/X and the cart tipped over, and more than three containers fell out of the cart, a configuration could result that would exceed the keff safety limit of 0.95 in NRC License SNM-42 for a single contingency. The requirement of 10 CFR 70.61 (d) states in part: '... the risk of nuclear criticality accidents must be limited by assuring that under normal and credible abnormal conditions, all nuclear processes are subcritical, including use of an approved margin of subcriticality for safety.' Therefore the performance requirement of 10 CFR 70.61 (d) would not be maintained during this credible abnormal condition. The as-found condition had no actual safety significance. There was no immediate risk or threat to the safety of the workers, the public, or the environment as a result of this condition. The safe geometry storage and transport carts did not contain any uranium bearing materials. There was no actual tipping event. The carts were immediately removed from service. Ill. NOTIFICATION REQUIREMENTS: B&W is making this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report in accordance with 10 CFR 70, Appendix A, (b)(1)--Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of 70.61. IV. STATUS OF CORRECTIVE ACTIONS: The carts have been removed from service. An investigation of the root causes of this condition is ongoing. Corrective actions will be determined as a result of the investigation. The licensee notified the NRC Resident Inspector and will be notifying the facility NMSS Project Manager (Baker).
The initially identified abnormal condition was not analyzed in the Integrated Safety Analysis. A conservative approach was taken in evaluating the condition in order to ensure compliance with the specified time period established in the regulations for reporting. Further analysis has determined the condition is not credible. Although unlikely, should more than three containers fall from the cart, it is not credible that a configuration could occur that would exceed the keff limit of 0.95 in NRC License SNM-42 for a single contingency. The performance requirements of 10 CFR 70.61 would be maintained. Following the guidance of FCSS ISG-12, Rev 0, '10 CFR Part 70, Appendix A- Reportable Safety Events', B&W is correcting Event Notification #50425 in accordance with 10 CFR 70.74(a)(4) and withdrawing the 10 CFR 70, Appendix A, (b)(1) notification. The licensee has notified the NRC Resident Inspector. Notified R2DO (Sykes), NMSS EO (Gonzalez) and Fuels OUO Group via email. |
Where | |
---|---|
B&W Nuclear Operating Group, Inc. Lynchburg, Virginia (NRC Region 2) | |
License number: | SNM-42 |
Reporting | |
Part 70 App A (B)(1) | |
Time - Person (Reporting Time:+1.82 h0.0758 days <br />0.0108 weeks <br />0.00249 months <br />) | |
Opened: | Tony England 16:49 Sep 4, 2014 |
NRC Officer: | Jeff Rotton |
Last Updated: | Sep 18, 2014 |
50425 - NRC Website | |
B&W Nuclear Operating Group, Inc. with Part 70 App A (B)(1) | |
WEEKMONTHYEARENS 519982016-06-09T17:30:0009 June 2016 17:30:00
[Table view]Part 70 App A (B)(1) Unanalyzed Condition Due to a Chemical Processing Malfunction ENS 507762015-01-09T21:00:0009 January 2015 21:00:00 Part 70 App A (B)(1) Unanalyzed Condition While Cleaning the Catch Tray ENS 504252014-09-04T15:00:0004 September 2014 15:00:00 Part 70 App A (B)(1) Unanalyzed Condition Related to Potential Material Transfer Cart Tipping ENS 492582013-08-09T17:00:0009 August 2013 17:00:00 Part 70 App A (B)(1) Storage Racks Determined to Be in an Unanalyzed Condition ENS 480912012-07-10T16:30:00010 July 2012 16:30:00 Part 70 App A (B)(1) Metallurgical Sample Pans Exceeded Volume Limit ENS 460012010-06-11T13:45:00011 June 2010 13:45:00 Part 70 App A (B)(1) Unanalyzed Accumulation of Material in the Uranium Recovery Area 2016-06-09T17:30:00 | |