1,766 Matching Results

Search Results

Advanced search parameters have been applied.

Calculation notes that support accident scenario and consequence determination of a waste tank criticality

Description: The purpose of this calculation note is to provide the basis forcriticality consequences for the Tank Farm Safety Analysis Report(FSAR). Criticality scenario is developed and details and description of the analysis methods are provided.
Date: August 2, 1996
Creator: Crowe, R.D., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

Safety analysis report for packaging upgrade plan

Description: This Safety Analysis Report for Packaging (SARP) Upgrade Plan reflects a SARP upgrade schedule based on the most current program needs. A performance agreement has been assigned, beginning in FY 1997, to update, revise, and/or cancel 20 percent of the existing onsite SARPS, so that 100 percent are reviewed and within current standards by the completion of the Project Hanford Management Contract (five-year period).
Date: December 9, 1996
Creator: Kelly, D. L.
Partner: UNT Libraries Government Documents Department

Safety analysis report for packaging (onsite) doorstop samplecarrier system

Description: The Doorstop Sample Carrier System consists of a Type B certified N-55 overpack, U.S. Department of Transportation (DOT) specification or performance-oriented 208-L (55-gal) drum (DOT 208-L drum), and Doorstop containers. The purpose of the Doorstop Sample Carrier System is to transport samples onsite for characterization. This safety analysis report for packaging (SARP) provides the analyses and evaluation necessary to demonstrate that the Doorstop Sample Carrier System meets the requirements and acceptance criteria for both Hanford Site normal transport conditions and accident condition events for a Type B package. This SARP also establishes operational, acceptance, maintenance, and quality assurance (QA) guidelines to ensure that the method of transport for the Doorstop Sample Carrier System is performed safely in accordance with WHC-CM-2-14, Hazardous Material Packaging and Shipping.
Date: February 24, 1997
Creator: Obrien, J.H.
Partner: UNT Libraries Government Documents Department

Laser Safety and Hazardous Analysis for the ARES (Big Sky) Laser System

Description: A laser safety and hazard analysis was performed for the ARES laser system based on the 2000 version of the American National Standards Institute's (ANSI) Standard Z136.1,for Safe Use of Lasers and the 2000 version of the ANSI Standard Z136.6, for Safe Use of Lasers Outdoors. The ARES laser system is a Van/Truck based mobile platform, which is used to perform laser interaction experiments and tests at various national test sites.
Date: January 1, 2003
Creator: AUGUSTONI, ARNOLD L.
Partner: UNT Libraries Government Documents Department

The Pit and the Safety Pendulum

Description: The hypothesis of this paper is that the safety analysis pendulum has swung considerably in the direction of increasingly complex and lengthy safety evaluations and intense reviews during the past 30 years. The test of this hypothesis will be a review of the safety analysis conducted for various activities associated with the retrieval of transuranic radioactive waste from burial pits at a National Laboratory site over a span of 30 years. The examination will focus on the safety aspects and the safety analysis that was conducted for the projects. At the conclusion of this examination, the paper will identify five reasons why the changes have taken place.
Date: November 1, 2000
Creator: Nitschke, Robert Leon & Ramos, Amadeo Gabriel
Partner: UNT Libraries Government Documents Department

MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING

Description: This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.
Date: May 18, 2006
Creator: Abramczyk, G; Paul Blanton, P & Kurt Eberl, K
Partner: UNT Libraries Government Documents Department

CRITICALITY HAZOP EFFICIENTLY EVALUATING HAZARDS OF NEW OR REVISED CRITICALITY SAFETY EVALUATIONS

Description: The 'Criticality HazOp' technique, as developed at Hanford's Plutonium Finishing Plant (PFP), has allowed for efficiencies enabling shortening of the time necessary to complete new or revised criticality safety evaluation reports (CSERs). For example, in the last half of 2007 at PFP, CSER revisions undergoing the 'Criticality HazOp' process were completed at a higher rate than previously achievable. The efficiencies gained through use of the 'Criticality HazOp' process come from the preliminary narrowing of potential scenarios for the Criticality analyst to fully evaluate in preparation of the new or revised CSER, and from the use of a systematized 'Criticality HazOp' group assessment of the relevant conditions to show which few parameter/condition/deviation combinations actually require analytical effort. The 'Criticality HazOp' has not only provided efficiencies of time, but has brought to criticality safety evaluation revisions the benefits of a structured hazard evaluation method and the enhanced insight that may be gained from direct involvement of a team in the process. In addition, involved personnel have gained a higher degree of confidence and understanding of the resulting CSER product.
Date: April 15, 2008
Creator: DM, CARSON
Partner: UNT Libraries Government Documents Department

Calculation notes that support accident scenario and consequence of the in-tank fuel fire/deflagration

Description: The purpose of this calculation note is to provide the basis for In-Tank Fuel Fire/Deflageration consequence for the Tank Farm Safety Analysis Report (FSAR). Tank Fuel Fire/Deflageration scenario is developed and details and description of the analysis methods are provided.
Date: September 27, 1996
Creator: Crowe, R.D.
Partner: UNT Libraries Government Documents Department

B Plant interim safety basis

Description: This interim safety basis (ISB-008) replaces the B Plant Safety Analysis Report, WHC-SD-WM-SAR-013, Rev. 2 (WHC 1993a). ISB-008 uses existing accident analyses, modified existing accident analyses, and new accident analyses to prove that B Plant remains within the safety envelope for transition, deactivation, standby, and shutdown activities. The analyses in ISB-008 are in accordance with the most current requirements for analytical approach, risk determination, and configuration management. This document and supporting accident analyses replace previous design-basis documents.
Date: September 1, 1996
Creator: Chalk, S.E.
Partner: UNT Libraries Government Documents Department

45-Day safety screening results for tank 241-U-102, push mode cores 143 and 144

Description: This document is the 45-day report deliverable for tank 241-U-102 push mode core segments collected between April 16, 1996 and May 6, 1996 and received by the 222-S Laboratory between April 17, 1996 and May 8, 1996. The segments were subsampled and analyzed in accordance, with the Tank 241-U-102 Push Mode Core Sampling and analysis Plan (TSAP) (Hu, 1996) and the Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). The analytical results are included in Table 1. Attachment I is a cross reference to relate the tank farm identification numbers to the 222-S Laboratory LabCore sample numbers. The subsamples generated in the laboratory for analysis are identified in these diagrams with their sources shown. The diagram identifying the hydrostatic head fluid (HHF) blank is also included, Primary safety screening results and the raw data from Differential Scanning Calorimetry (DSC) and thermogravimetric analysis (TGA) analyses are included in this report. Two of the samples submitted for DSC analysis exceeded notification limits as stated in the Safety Screening DQO (Dukelow, et al., 1995). Cyanide analysis was requested on these samples and a Reactive System Screening Tool analysis was requested for the sample exhibiting the highest exothenn in accordance with the TSAP (Hu, 1996). The results for these analyses will be reported in a revision to this document.
Date: June 28, 1996
Creator: Steen, F.H.
Partner: UNT Libraries Government Documents Department

Safety evaluation for packaging (onsite) type B shipment of 222-S cargo tank

Description: This safety evaluation for packaging (SEP) document was developed to provide safety evaluations necessary to approve the transfer of the 222-S Cargo Tank from the 222-S Lab to the 204-AR Transfer Station. The SEP demonstrates that the onsite transfer will provide an equivalent degree of safety as would be provided by a package meeting the U.S. Department of Transportation requirements. This fulfills the onsite transportation safety requirements implemented in WHC-CM-2-14, Hazardous Material Packaging and Shipping.
Date: February 27, 1997
Creator: Edwards, W.S., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Fire hazard analyses and safety analysis reports relationship

Description: DOE Order 5480.7A requires that Fire Hazard Analyses (FHA) be performed for new facilities, for facilities requiring a DOE 5480.23 Safety Analysis, or as directed by the DOE Program Secretarial Officer. DOE Order 5480.23 requires that a Safety Analysis Report (SAR) be prepared for DOE nuclear facilities. Both the FHA and SAR `documents provide important information and direction for facility design and operation. Each of the two documents address the effects of postulated fire scenarios, and both have common or at least consistent bases, and have overlapping elements. However, some of the objectives of the required analyses are distinctly different. These differences have historically resulted in variations in the interpretation and Understanding of the DOE Orders and associated guidance by organizations and individuals within the Westinghouse Hanford Company.
Date: May 30, 1996
Creator: Olson, W. W.
Partner: UNT Libraries Government Documents Department

Releases of UF{sub 6} to the atmosphere after a potential fire in a cylinder storage yard

Description: Uranium hexafluoride (UF{sub 6}), a toxic material, is stored in just over 6200 cylinders at the K-25 site in Oak Ridge, Tennessee. The safety analysis report (SAR) for cylinder yard storage operations at the plant required the development of accident scenarios for the potential release of UF{sub 6} to the atmosphere. In accordance with DOE standards and guidance, the general approach taken in this SAR was to examine the functions and contents of the cylinder storage yards to determine whether safety-significant hazards were present for workers in the immediate vicinity, workers on-site, the general public off-site, or the environment. and to evaluate the significance of any hazards that were found. A detailed accident analysis was performed to determine a set of limiting accidents that have potential for off-site consequences. One of the limiting accidents identified in the SAR was the rupture of a cylinder engulfed in a fire.
Date: June 1, 1997
Creator: Lombardi, D.A.; Williams, W.R. & Anderson, J.C.
Partner: UNT Libraries Government Documents Department

Lift truck safety review

Description: This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.
Date: March 1, 1997
Creator: Cadwallader, L. C.
Partner: UNT Libraries Government Documents Department

Safety evaluation for packaging (onsite) for concrete-shielded RHTRU waste drum for the 327 postirradiation testing laboratory

Description: This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete- Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per WHC-CM-2-14, Hazardous Material Packaging and Shipping. The drum will be used for transport of 327 Building legacy waste from the 300 Area to the Transuranic Waste Storage and Assay Facility in the 200 West Area and on to a Solid Waste Storage Facility, also in the 200 Area.
Date: October 29, 1996
Creator: Adkins, H. E.
Partner: UNT Libraries Government Documents Department

Tank 241-S-106, cores 183, 184 and 187 analytical results for the final report

Description: This document is the final laboratory report for tank 241-S-106 push mode core segments collected between February 12, 1997 and March 21, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (TSAP), the Tank Safety Screening Data Quality Objective (Safety DQO), the Historical Model Evaluation Data Requirements (Historical DQO) and the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO). The analytical results are included in Table 1. Six of the twenty-four subsamples submitted for the differential scanning calorimetry (DSC) analysis exceeded the notification limit of 480 Joules/g stated in the DQO. Appropriate notifications were made. Total Organic Carbon (TOC) analyses were performed on all samples that produced exotherms during the DSC analysis. All results were less than the notification limit of three weight percent TOC. No cyanide analysis was performed, per agreement with the Tank Safety Program. None of the samples submitted for Total Alpha Activity exceeded notification limits as stated in the TSAP. Statistical evaluation of results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. No core composites were created because there was insufficient solid material from any of the three core sampling events to generate a composite that would be representative of the tank contents.
Date: June 30, 1997
Creator: Esch, R.A.
Partner: UNT Libraries Government Documents Department

Risk assessment of high altitude free flight commercial aircraft operations

Description: A quantitative model is under development to assess the safety and efficiency of commercial aircraft operations under the Free Flight Program proposed for air traffic control for the US National Airspace System. The major objective of the Free Flight Program is to accommodate the dramatic growth anticipated in air traffic in the US. However, the potential impacts upon aircraft safety from implementing the Program have not been fully explored and evaluated. The model is directed at assessing aircraft operations at high altitude over the continental US airspace since this action is the initial step for Free Flight. Sequential steps with analysis, assessment, evaluation, and iteration will be required to satisfactorily accomplish the complete transition of US commercial aircraft traffic operations.
Date: April 23, 1998
Creator: Kimura, C.Y.; Sandquist, G.M.; Slaughter, D.M. & Sanzo, D.L.
Partner: UNT Libraries Government Documents Department