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Set point calculations for RAPID project

Description: The Respond and Pump in Days (RAPID) project was initiated to pump part of the contents of tank 241-SY-101 into tank 241-SY-102. This document establishes the basis for all set points and ranges used in the RAPID project. There are 23 instrument and/or control loops utilized by the RAPID project. These range from the simple indication loop with two components to complex indication, control, and alarm loops with up to eight components. Several loops include safety class elements. This document is intended to describe the loops in full and to provide the basis for each of the element setpoints, ranges and accuracies identified in the RAPID project Master Equipment List (MEL). These values are developed in two steps. First, the base value is identified with reference to the supporting document providing that value. Second, a spreadsheet calculation is performed on each element and loop, utilizing a standard methodology described below, that takes into account known and suspected variance in output and establishes the actual setpoint used on a given element. The results of the spreadsheet are reported directly in this document.
Date: August 27, 1999
Creator: HICKMAN, G.L.
Partner: UNT Libraries Government Documents Department

Conceptual Design Report Cask Loadout Sys and Cask Drop Redesign for the Immersion Pail Support Structure and Operator Interface Platform at 105 K West

Description: This conceptual design report documents the redesign of the IPSS and the OIP in the 105 KW Basin south loadout pit due to a postulated cask drop accident, as part of Project A.5/A.6, Canister Transfer Facility Modifications. Project A.5/A.6 involves facility modifications needed to transfer fuel from the basin into the cask-MCO. The function of the IPSS is to suspend, guide, and position the immersion pail. The immersion pail protects the cask-MCO from contamination by basin water and acts as a lifting device for the cask-MCO. The OIP provides operator access to the south loadout pit. Previous analyses studied the effects of a cask-MCO drop on the south loadout pit concrete structure and on the IPSS. The most recent analysis considered the resulting loads at the pit slab/wall joint (Kanjilal, 1999). This area had not been modeled previously, and the analysis results indicate that the demand capacity exceeds the allowable at the slab/wall joint. The energy induced on the south loadout pit must be limited such that the safety class function of the basin is maintained. The solution presented in this CDR redesigns the IPSS and the OIP to include impact-absorbing features that will reduce the induced energy. The impact absorbing features of the new design include: Impact-absorbing material at the IPSS base and at the upper portion of the IPSS legs. A sleeve which provides a hydraulic means of absorbing energy. Designing the OIP to act as an impact absorber. The existing IPSS structure in 105 KW will be removed. This conceptual design considers only loads resulting from drops directly over the IPSS and south loadout pit area. Drops in other areas of the basin are not considered, and will be covered as part of a future revision to this CDR.
Date: July 12, 1999
Creator: LANGEVIN, A.S.
Partner: UNT Libraries Government Documents Department

Analysis for Eccentric Multi Canister Overpack (MCO) Drops at the Canister Storage Building (CSB) (CSB-S-0073)

Description: Multi-Canister Overpacks (MCOs) containing spent nuclear fuel (SNF) will be routinely handled at the Canister Storage Building (CSB) during fuel movement operations in the SNF Project. This analysis was performed to investigate the potential for damage from an eccentric accidental drop onto the standard storage tube, overpack tube, service station, or sample/weld station. Appendix D was added to the FDNW document to include the peer Review Comment Record & transmittal record.
Date: October 8, 1999
Creator: TU, K.C.
Partner: UNT Libraries Government Documents Department

Analysis for SNF Multi Canister Overpack (MCO) Drop into the Cask from the MCO Handling Machine (MHM) with Air Cushion

Description: The purpose of this report is to investigate the potential for damage to the MCO during impact from an accidental drop from the MHM into the shipping cask. The MCO is dropped from a height of 8.2 feet above the cask enters the cask concentrically and falls the additional 12.83 feet to the cask bottom. Because of the interface fit between the MCO and the cask and the air entrapment the MCO fall velocity is slowed. The shipping cask is resting on an impact absorber at the time of impact. The energy absorbing properties of the impact absorber are included in this analysis.
Date: January 12, 2000
Creator: RAINS, D.J.
Partner: UNT Libraries Government Documents Department

Calculation note for Consequences of a fire in the sorting and repackaging glovebox in room 636 of bldg 2736-ZB Plutonium Finishing Plant

Description: This Calculation Note provides a conservative estimate of the grams of plutonium released from Building 2736-ZB of the Plutonium Finishing Plant as a result of a fire within Glovebox 636, without consideration of mitigation.
Date: August 31, 1999
Creator: JOHNSON, L.E.
Partner: UNT Libraries Government Documents Department

Design package lazy susan for the fuel retrieval system

Description: This is a design package that contains the details for a Lazy Susan style small tool for the Fuel Retrieval System. The Lazy Susan tool is used to help rotate an MCO Fuel Basket when loading it. This document contains requirements, development design information, tests and test reports that pertain to the production of Lazy Susan small tool.
Date: September 10, 1999
Creator: TEDESCHI, D.J.
Partner: UNT Libraries Government Documents Department

Set point calculations for RAPID project

Description: The Respond and Pump in Days (RAPID) project was initiated to pump part of the contents of tank 241-SY-101 into tank 241-SY-102. This document establishes the basis for all set points and ranges used in the RAPID project.
Date: October 18, 1999
Creator: Hickman, G. L.
Partner: UNT Libraries Government Documents Department

Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

Description: This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria--HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.
Date: August 11, 1999
Creator: BLACK, D.M.
Partner: UNT Libraries Government Documents Department

Hazards evaluation of plutonium metal opening and stabilization

Description: Hazards evaluation is the analysis of the significance of hazardous situations associated with an activity OK process. The HE used qualitative techniques of Hazard and Operability (HazOp) analysis and What-If analysis to identify those elements of handling and thermal stabilization processing that could lead to accidents.
Date: August 31, 1999
Creator: JOHNSON, L.E.
Partner: UNT Libraries Government Documents Department

Performance objectives for the Hanford immobilized low-activity waste (ILAW) performance assessment

Description: Before low-level waste may be disposed of, a performance assessment must be written and then approved by the DOE (DOE 1988a DOE 1999a). The performance assessment is to determine whether ''reasonable assurance'' exists that the performance objectives of the disposal facility will be met. The DOE requirements for waste disposal (DOE 1988a DOE 1999a) require the protection of public health and safety; and the protection of the environment. Although quantitative limits are sometimes stated (for example, the all-pathways exposure limit is 25 mrem/year), usually the requirements are stated in a general nature. Quantitative limits were established by: investigating all potentially applicable regulations as well as interpretations of the review panels which DOE has established to review performance assessments, interacting with program management to establish the additional requirements of the program, and interacting with the public (i.e., the Hanford Advisory Board members; as well as affected Tribal Governments) to understand the values of residents in the Pacific Northwest. Because of space considerations, not all radionuclides and dangerous chemicals are listed in this document. The radionuclides listed here are those which were explicitly treated in the ILAW PA (Mann 1998). The dangerous chemicals listed here are those most often detected in Hanford tank waste as documented in the Regulatory Data Quality Objectives Supporting Tank Waste Remediation System Privatization Project (Wiemers 1998).
Date: September 9, 1999
Creator: MANN, F.M.
Partner: UNT Libraries Government Documents Department

Fire Hazard Analysis for the Cold Vacuum Drying (CVD) Facility

Description: This Fire Hazard Analysis assesses the risk from fire within individual fire areas in the Cold Vacuum Drying Facility at the Hanford Site in relation to existing or proposed fire protection features to ascertain whether the objectives of DOE Order 5480.7A Fire Protection are met.
Date: August 19, 1999
Creator: JOHNSON, B.H.
Partner: UNT Libraries Government Documents Department

Cold Vacuum Drying (CVD) Facility Technical Safety Requirements

Description: The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included.
Date: December 16, 1999
Creator: KRAHN, D.E.
Partner: UNT Libraries Government Documents Department

Human Factors Engineering and Ergonomics Analysis for the Canister Storage Building (CSB) Results and Findings

Description: The purpose for this supplemental report is to follow-up and update the information in SNF-3907, Human Factors Engineering (HFE) Analysis: Results and Findings. This supplemental report responds to applicable U.S. Department of Energy Safety Analysis Report review team comments and questions. This Human Factors Engineering and Ergonomics (HFE/Erg) analysis was conducted from April 1999 to July 1999; SNF-3907 was based on analyses accomplished in October 1998. The HFE/Erg findings presented in this report and SNF-3907, along with the results of HNF-3553, Spent Nuclear Fuel Project, Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report,'' Chapter A3.0, ''Hazards and Accidents Analyses,'' provide the technical basis for preparing or updating HNF-3553. Annex A, Chaptex A13.0, ''Human Factors Engineering.'' The findings presented in this report allow the HNF-3553 Chapter 13.0, ''Human Factors,'' to respond fully to the HFE requirements established in DOE Order 5480.23, Nuclear Safety Analysis Reports.
Date: September 20, 1999
Creator: GARVIN, L.J.
Partner: UNT Libraries Government Documents Department

Canister Storage Building Compliance Assessment SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DB-003

Description: This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DB-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.
Date: May 18, 2000
Creator: BLACK, D.M.
Partner: UNT Libraries Government Documents Department

The Settling and Compaction of Nuclear Waste Slurries

Description: The settling and compaction of simulated and real nuclear waste slurries were extensively studied. Experiments were carried out with simulated wastes at laboratory and large-scale sizes, and the results compared. A model of settling was derived and a method developed to correlate and scale-up settling data for different slurries and vessel sizes.
Date: November 15, 1999
Creator: MACLEAN, G.T.
Partner: UNT Libraries Government Documents Department

Scenarios for the Hanford immobilized Low-Activity waste (ILAW) performance assessment

Description: The purpose of the next version of the Hanford Immobilized Low-Activity Tank Waste (ILAW) Performance Assessment (ILAW PA) is to provide an updated estimate of the long-term human health and environmental impact of the disposal of ILAW and to compare these estimates against performance objectives displayed in Tables 1,2, and 3 (Mann 1999a). Such a radiological performance assessment is required by U.S. Department of Energy (DOE) Orders on radioactive waste management (DOE 1988a and DOE 1999a). This document defines the scenarios that will be used for the next update of the PA that is scheduled to be issued in 2001. Since the previous performance assessment (Mann 1998) was issued, considerable additional data on waste form behavior and site-specific soil geotechnical properties have been collected. In addition, the 2001 ILAW PA will benefit from improved computer models and the experience gained from the previous performance assessment. However, the scenarios (that is, the features, events, and processes analyzed in the Performance assessment) for the next PA are very similar to the ones in the 1998 PA.
Date: September 9, 1999
Creator: MANN, F.M.
Partner: UNT Libraries Government Documents Department

Tank waste isotope contributions

Description: This document presents the results of a calculation to determine the relative contribution of selected isotopes to the inhalation and ingestion doses for a postulated release of Hanford tank waste. The fraction of the dose due to {sup 90}Sr, {sup 90}Y, {sup 137}Cs and the alpha emitters for single shell solids and liquids, double shell solids and liquids, aging waste solids and liquids and all solids and liquids. An effective dose conversion factor was also calculated for the alpha emitters for each composite of the tank waste.
Date: August 26, 1999
Creator: VANKEUREN, J.C.
Partner: UNT Libraries Government Documents Department

CSER 95-007 Acceptability of Bettis Lab Waste Shipment to WHC Solid Waste

Description: The purpose of this document is to evaluate a potential discrepancy between the Solid Waste Management (SWM) criticality prevention specifications and a proposed receipt from Bettis Laboratories. The analysis has been performed to determine the acceptability of the Bettis Laboratories waste container with respect to SWM criticality requirements.
Date: December 3, 1999
Creator: MILLER, E.M.
Partner: UNT Libraries Government Documents Department

Integrity assessment report of tanks TK-101 and TK-102

Description: This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) for Waste Management Federal Services of Hanford, Inc., (WMH), the operations contractor; Fluor Daniel Hanford (FDH), the Hanford Site Manager; and the U. S. Department of Energy (DOE), the system owner. This IAR addresses the evaluation of Tanks 101 and 102 and other existing components located in the 219-S Waste Handling Facility. This report will be included in the Part B Permit for the 2226 Laboratory and is a portion of the integrity assessment of the overall 222-5 Laboratory radioactive liquid waste disposal system. This IAR is prepared in accordance with WAC 173-303, Dangerous Waste Regulations; Section 640(2), ''Assessment of Existing Tank Systems Integrity .''
Date: August 25, 1999
Creator: MCSHANE, D.S.
Partner: UNT Libraries Government Documents Department