3,882 Matching Results

Search Results

Advanced search parameters have been applied.

Removal of mixing pump in tank 102-AP -- pump drop onto central pit

Description: The mixing pump, if dropped in the pump pit following its removal from the tank, is incapable of compromising the tank structure either locally or in a structural displacement mode to an extent which might allow dispersion of the contents. A drop from 10 ft above the pit floor (considered the maximum credible height) of a pump which is considered perfectly rigid does not approach the required perforation velocity. The velocity required to perforate requires a drop height which is physically impossible to attain with existing cranes. An analysis of the location of the deposition of the strain energy required to match the pump`s impact kinetic energy, the results of which are shown in Table 2, verifies that there is no credible chance for compromise of the tank roof by such a drop.
Date: June 20, 1995
Creator: Jimenez, R. F.
Partner: UNT Libraries Government Documents Department

CURE: Clean use of reactor energy

Description: This paper presents the results of a joint Westinghouse Hanford Company (Westinghouse Hanford)-Pacific Northwest Laboratory (PNL) study that considered the feasibility of treating radioactive waste before disposal to reduce the inventory of long-lived radionuclides, making the waste more suitable for geologic disposal. The treatment considered here is one in which waste would be chemically separated so that long-lived radionuclides can be treated using specific processes appropriate for the nuclide. The technical feasibility of enhancing repository performance by this type of treatment is considered in this report. A joint Westinghouse Hanford-PNL study group developed a concept called the Clean Use of Reactor Energy (CURE), and evaluated the potential of current technology to reduce the long-lived radionuclide content in waste from the nuclear power industry. The CURE process consists of three components: chemical separation of elements that have significant quantities of long-lived radioisotopes in the waste, exposure in a neutron flux to transmute the radioisotopes to stable nuclides, and packaging of radionuclides that cannot be transmuted easily for storage or geologic disposal. 76 refs., 32 figs., 24 tabs.
Date: May 1, 1990
Partner: UNT Libraries Government Documents Department

Westinghouse Hanford Company operational environmental monitoring annual report, calendar year 1994

Description: This document presents the results of the Westinghouse Hanford Company near-facility operational environmental monitoring for 1994 in the 100, 200/600, and 300/400 Areas of the Hanford Site, in south-central Washington State. Surveillance activities included sampling and analyses of ambient air surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with Federal, State, and/or local regulations. In general, although effects from nuclear facilities are still seen on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.
Date: August 1, 1995
Creator: Schmidt, J.; Fassett, J.W.; Johnson, A.R.; Johnson, V.G.; Markes, B.M.; McKinney, S.M. et al.
Partner: UNT Libraries Government Documents Department

Gas and liquid sampling for closed canisters in KW Basin - Work Plan

Description: Work Plan for the design and fabrication of gas/liquid sampler for closed canister sampling in KW Basin. This document defines the tasks associated with the design, fabrication, assembly, and acceptance testing equipment necessary for gas and liquid sampling of the Mark I and Mark II canisters in the K-West basin. The sampling of the gas space and the remaining liquid inside the closed canisters will be used to help understand any changes to the fuel elements and the canisters. Specifically, this work plan will define the scope of work and required task structure, list the technical requirements, describe design configuration control and verification methodologies, detail quality assurance requirements, and present a baseline estimate and schedule.
Date: February 1, 1995
Creator: Pitkoff, C.C.
Partner: UNT Libraries Government Documents Department

Interface agreement for the management of FFTF Spent Nuclear Fuel

Description: The Hanford Site Spent Nuclear Fuel (SNF) Project was formed to manage the SNF at Hanford. The mission of the Fast Flux Test Facility (FFTF) Transition Project is to place the facility in a radiologically and industrially safe shutdown condition for turnover to the Environmental Restoration Contractor (ERC) for subsequent D&D. To satisfy both project missions, FFTF SNF must be removed from the FFTF and subsequently dispositioned. This documented provides the interface agreement between FFTF Transition Project and SNF Project for management of the FFTF SNF.
Date: February 2, 1995
Creator: McCormack, R.L.
Partner: UNT Libraries Government Documents Department

Financial services FY 1996 site support program plan, WBS 6.10.4. Revision 1

Description: This program plan outlines the financial services to be provided to the Hanford reservation by the Westinghouse Hanford Company. The topics of the plan include the Hanford strategic plan, program mission, program strategy, technical requirements baseline, schedule baseline, cost baseline, performance measures, technical objectives, program performance and program funding required.
Date: September 1, 1995
Creator: Schafer, D.D.
Partner: UNT Libraries Government Documents Department

Radioisotope Thermoelectric Generator Transporation System licensed hardware second certification test series and package shock mount system test

Description: This paper presents a summary of two separate drop test a e performed in support of the Radioisotope Thermoelectric Generator (RTG) Transportation System (RTGTS). The first portion of this paper presents the second series of drop testing required to demonstrate that the RTG package design meets the requirements of Title 10, Code of Federal Regulations, ``Part 71`` (10 CFR 71). Results of the first test series, performed in July 1994, demonstrated that some design changes were necessary. The package design was modified to improve test performance and the design changes were incorporated into the Safety Analysis Report for Packaging (SARP). The second full-size certification test article (CTA-2) incorporated the modified design and was tested at the US Department of Energy`s (DOE) Hanford Site near Richland, Washington. With the successful completion of the test series, and pending DOE Office of Facility Safety Analysis approval of the SARP, a certificate of compliance will be issued for the RTG package allowing its use. The second portion of this paper presents the design and testing of the RTG Package Mount System. The RTG package mount was designed to protect the RTG from excessive vibration during transport, provide shock protection during on/off loading, and provide a mechanism for moving the RTG package with a forklift. Military Standard (MIL-STD) 810E, Transit Drop Procedure (DOE 1989), was used to verify that the shock limiting system limited accelerations in excess of 15 G`s at frequencies below 150 Hz. Results of the package mount drop tests indicate that an impact force of 15 G`s was not exceeded in any test from a free drop height of 457 mm (18 in.).
Date: October 1, 1995
Creator: Ferrell, P.C. & Moody, D.A.
Partner: UNT Libraries Government Documents Department

Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 3 testing

Description: This document summarizes the results of the phase 3 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The purpose of this acceptance test is to verify the sealing integrity of the FRS to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at the 306E Facility in the 300 area from January 10, 1995 to January 17, 1995. The Phase 3 test consisted of two parts. Part one was a water leak test of the seal between the blast shield and mock load distribution frame (LDF) to ensure that significant contamination of the pump pit and waste interaction with the aluminum impact-limiting material under the LDF are prevented during the pump removal operation. The second part of this acceptance test was an air leak test of the assembled flexible receiver system. The purpose of this test was to verify that the release of hazardous aerosols will be minimized if the tank dome pressure becomes slightly positive during the decontamination of the mixer pump.
Date: February 6, 1995
Creator: Ritter, G.A.
Partner: UNT Libraries Government Documents Department

K-Basins S/RIDS

Description: The Standards/Requirements Identification Document(S/RID) is a list of the Environmental, Safety, and Health (ES&H) and Safeguards and Security (SAS) standards/requirements applicable to the K Basins facility
Date: September 22, 1995
Creator: Watson, D.J.
Partner: UNT Libraries Government Documents Department

System requirements specification for the TMAD Code

Description: This document is intended to meet, in part, the quality assurance documentation requirements for the development of software as outlined in WHC-CM-3-10, `Software Practices.` Specifically, this document will serve as the System Project Management Plan and the System Configuration Management Plan.
Date: September 1, 1995
Creator: Finfrock, S.H.
Partner: UNT Libraries Government Documents Department

Plutonium storage phenomenology

Description: Plutonium has been produced, handled, and stored at Department of Energy (DOE) facilities since the 1940s. Many changes have occurred during the last 40 years in the sources, production demands, and end uses of plutonium. These have resulted in corresponding changes in the isotopic composition as well as the chemical and physical forms of the processed and stored plutonium. Thousands of ordinary food pack tin cans have been used successfully for many years to handle and store plutonium. Other containers have been used with equal success. This paper addressees the exceptions to this satisfactory experience. To aid in understanding the challenges of handling plutonium for storage or immobilization the lessons learned from past storage experience and the necessary countermeasures to improve storage performance are discussed.
Date: December 1, 1995
Creator: Szempruch, R.
Partner: UNT Libraries Government Documents Department

Immobilization index of liquid low-level waste in cementitious grouts

Description: The ability of grouts formulated from mixtures of cementitious materials and attapulgite clay to immobilize various chemical species in the projected off-gas waste stream from vitrification of Hanford low level tank wastes was studied. Three different solid blends were evaluated, with cement:fly ash: slag:clay weight ratios of 3:3:3:1, 3:0:6:1, and 0:0:9:1. The blended solids were mixed with a simulated low level liquid waste solution containing Na{sup +}, NO{sub 2}{sup {minus}}, NO{sub 3}{sup {minus}}, PO{sub 4}{sup 3{minus}} and OH{sup {minus}} ions, in the proportion of 1 liter of solution to 1 kg of solid blend, and were cured either at 22 C (room temperature), 50 C or 90 C. Pore solutions were expressed at various ages and were analyzed to determine the reductions in concentrations of the individual ionic species. The results were expressed in the form of immobilization index (I) calculated for each species. The immobilization indices for Na{sup +} (I Na{sup +}) and for OH{sup {minus}} (I OH{sup {minus}}) were similar in each case, and were found to be highest when only slag and clay was present (blend 0:0:9:1). The immobilization index for phosphate, I PO{sub 4}{sup 3{minus}}, was 1 in all cases, i.e. phosphate was completely removed from solution. On the other hand removal of NO{sub 2}{sup {minus}} and NO{sub 3}{sup {minus}} ions was generally ineffective.
Date: December 1, 1995
Creator: Kruger, A.A.
Partner: UNT Libraries Government Documents Department

Structural analysis of the equipment removal system for tank 241SY101

Description: The calculations documented in this report show that the ERS major components are structurally qualified to complete the objective, i.e., to install the removed equipment into a shipping container and transport and store the container at the Central Waste Complex (CWC). The analysis for the structural members of the ERS components considers live load with an impact factor of 125 % added to dead load. An allowable stress of one-third yield is used for all structural components carrying the load based on DOE-RL-92-36. Adherence to DOE-RL-92-36 is not a code requirement. However, the loads considered make this factor of safety appropriate. The calculations meet the strength requirements of the American Institute for Steel Construction (ASIC 1989) for all non-critical structural elements.
Date: March 2, 1995
Creator: Mackey, T.C .
Partner: UNT Libraries Government Documents Department

PFP MICON maintenance manual. Revision 1

Description: This manual covers the use of maintenance displays, maintenance procedures, system alarms and common system failures. This manual is intended to supplement the MICON maintenance training not replace it. It also assumes that the user is familiar with the normal operation of the MICON A/S system. The MICON system is a distributed control computer and, among other things, controls the HVAC system for the Plutonium Finishing Plant.
Date: January 25, 1995
Creator: Silvan, G.R.
Partner: UNT Libraries Government Documents Department

Hanford double shell tank corrosion monitoring instrument tree prototype

Description: High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks (DSTs and SSTs). The installation of a prototype corrosion monitoring instrument tree into DST 241-A-101 was completed in December 1995. The instrument tree has the ability to detect and discriminate between uniform corrosion, pitting, and stress corrosion cracking (SCC) through the use of electrochemical noise measurements and a unique stressed element, three-electrode probe. The tree itself is constructed of AISI 304L stainless steel (UNS S30403), with probes in the vapor space, vapor/liquid interface and liquid. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other US Department of Energy (DOE) sites. Keywords: Hanford, radioactive waste, high-level waste tanks, electrochemical noise, probes, double-shell tanks, single-shell tanks, corrosion.
Date: November 1, 1995
Creator: Nelson, J.L.; Edgemon, G.L. & Ohl, P.C.
Partner: UNT Libraries Government Documents Department

Improving sample recovery

Description: This Engineering Task Plan (ETP) describes the tasks, i.e., tests, studies, external support and modifications planned to increase the recovery of the recovery of the waste tank contents using combinations of improved techniques, equipment, knowledge, experience and testing to better the recovery rates presently being experienced.
Date: September 1995
Creator: Blanchard, R. J.
Partner: UNT Libraries Government Documents Department

Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1995

Description: This report presents the annual hydrogeologic evaluation of 19 Resource Conservation and Recovery Act of 1976 facilities and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Although most of the facilities no longer receive dangerous waste, a few facilities continue to receive dangerous waste constituents for treatment, storage, or disposal. The 19 Resource Conservation and Recovery Act facilities comprise 29 waste management units. Nine of the units are monitored under groundwater quality assessment status because of elevated levels of contamination indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration profiles, rate, and extent of migration are evaluated. Groundwater is monitored at the other 20 units to detect leakage, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1994 and September 1995. Groundwater quality is described for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.
Date: February 1, 1996
Creator: Hartman, M.J.
Partner: UNT Libraries Government Documents Department

Analysis of the Retained Gas Sample (RGS) Extruder Assembly

Description: In order for the Retained Gas Sample (RGS) Extruder Assembly to be safely used it was determined by the cognizant engineer that analysis was necessary. The use of the finite-element analysis (FEA) progarm COSMOS/M version 1.71 permitted a quick, easy, and detailed stress analysis of the RGS Extruder Assembly. The FEA model is a three dimensional model using the SHELL4T element type. From the results of the FEA, the cognizant engineer determined that the RGS extruder would be rated at 10,000 lbf and load tested to 12,000 lbf. The respective input and output files for the model are EXTR02.GFM and EXTR02.OUT and can be found on the attached tape.
Date: September 1, 1995
Creator: Coverdell, B.L.
Partner: UNT Libraries Government Documents Department

CNS 1-13G cask lid support work plan

Description: This work plan covers fabrication and load testing of one Chem-Nuclear Systems (CNS) 1-13G Cask lid Support Frame, per the attached drawing. The support frame is considered to be developmental equipment and as such may be fabricated in accordance with the engineering requirements and responsibilities identified in WHC-CM-6-1, Standard Engineering Practices, EP-2.4 Development Control Requirements. A final acceptance and load test is required by February 24, 1995. WHC will provide a released as-built drawing of the support frame by February 22, 1995 to allow final acceptance to occur prior to the completion date.
Date: February 17, 1995
Creator: Crow, S.R.
Partner: UNT Libraries Government Documents Department

Preliminary design review report for K Basin Dose Reduction Project

Description: The strategy for reducing radiation dose, originating from radionuclides absorbed in the K East Basin concrete, is to raise the pool water level to provide additional shielding. This report documents a preliminary design review conducted to ensure that design approaches for cleaning/coating basin walls and modifying other basin components were appropriate. The conclusion of this review was that design documents presently conclusion of this review was that design documents presently completed or in process of modification are and acceptable basis for proceeding to complete the design.
Date: January 1, 1996
Creator: Blackburn, L. D.
Partner: UNT Libraries Government Documents Department

Groundwater maps of the Hanford site, June 1995

Description: The Groundwater Maps of the Hanford Site, June 1995 is a continuation of a series of reports (see Serkowski et al. 1995) that document the configuration of the water table aquifer beneath the Hanford Site (Figure 1). This series presents the results of the semiannual water level measurement program and the water table maps generated from these measurements. The reports document the changes in the groundwater level at the Hanford Site during the transition from nuclear material production to environmental restoration and remediation. In addition, these reports provide water level data to support the various site characterization and groundwater monitoring programs currently in progress on the Hanford Site. Groundwater Maps of the Hanford Site is prepared for the U.S. Department of Energy by the Hanford Site Operations and Engineering Contractor, Westinghouse Hanford Company (WHC). This document fulfills reporting requirements specified in WHC-CM-7-5, Section 8.0 ``Water Quality`` and described in the environmental monitoring plan for the Hanford Site. (DOE-RL 1993a) This document highlights the three major operations areas (the 100, 200 and 300/1100 Areas) where wastes were discharged to the soil. Each area includes a summary discussion of the data, a well index map, and a contoured map of the water table surface. Appendix A contains all of the data collected for this program.
Date: March 15, 1996
Creator: Sweeney, M.D.
Partner: UNT Libraries Government Documents Department