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Reuse of Concrete within DOE from Decontamination and Decommissioning Projects

Description: A protocol has been developed for use in the disposition of concrete from Decontamination and Decommissioning (D&D) projects. The purpose of this protocol is to assist U.S. Department of Energy (DOE) sites in releasing concrete for re-use within the DOE complex. Current regulations allow sites to release surface-contaminated materials if they contain very low amounts of radioactivity and to possibly release materials with volumetric contamination, or higher levels of surface contamination on a case-bycase basis. In all cases, an ALARA (as low as reasonably achievable) analysis that evaluates the risks of releasing volumetrically contaminated concrete or concrete with higher levels of surface contamination, is required. To evaluate the dose impacts of re-using radioactively contaminated material, the measured radiation levels (pCi/g or disintegrations per minute (dpm)/100 cm2) must be converted to the estimated dose (mrem/yr) that would be received by affected individuals. The dose depends on the amounts and types of isotopes present and the time, distance, and method of exposure (e.g., inhalation or external exposure). For each disposition alternative, the protocol provides a systematic method to evaluate the impact of the dose on affected individuals. The cost impacts of re-using concrete also need to be evaluated. They too depend on the disposition alternative and the extent and type of contamination. The protocol provides a method to perform a detailed analysis of these factors and evaluate the dose and cost impacts for various disposition alternatives. Once the dose and cost impacts of the various alternatives have been estimated, the protocol outlines the steps required to release and re-use the concrete material.
Date: September 1, 2000
Creator: Tripp, Julia Lynn; Meservey, Richard Harlan; Smith, Anthony Mactier; Chen, S. Y. & Kamboj, S.
Partner: UNT Libraries Government Documents Department

ALARA Center of Technology promotes good radiological work practices at Hanford

Description: The central Radiological Control Organization, originally under the previous Management and Operations contractor (Westinghouse Hanford Company) decided that a significant improvement in ALARA implementation would result if examples of engineered controls used for radiological work were assembled in one location to provide a ``showcase`` for workers and managers. The facility would be named the ALARA Center of Technology (ACT) and would include the latest technologies used to accomplish radiological work, as well as proven techniques, tools, and equipment. A location for the Center was selected in the 200 East Area of Hanford in a central location to be easily accessible to all facilities and contractors. Since there was little money available for this project, a decision was made to contact several vendors and request loans of their tools, equipment, and materials. In return, the center would help market products on site and assist with product demonstrations when the vendors visited Hanford. Out of 28 vendors originally contacted, 16 responded with offers to loan products. This included a containment tent, several glove bags, BEPA filtered vacuum cleaners, portable ventilation systems, fixatives, temporary shielding, pumps, and several special tools. Vendors who could not provide products sent videos and brochures. Westinghouse Hanford Company began using the ACT in June 1996. Fluor Daniel Hanford, Inc., the present Management and Integrating Contractor for the Hanford Site, held the formal opening ceremony of the ALARA Center of Technology on October 1, 1996. The Center now has about 1200 ft{sup 2} of floor space fi Iled with tools, equipment and material used to perform radiological work.
Date: October 31, 1997
Creator: Waggoner, L.O., Westinghouse Hanford, Richland, WA
Partner: UNT Libraries Government Documents Department

Protocols for Authorized Release of Concrete

Description: Much of the clean or slightly contaminated concrete from Decontamination and Decommissioning (D&D) activities could be re-used. Currently, there is no standardized approach, or protocol, for managing the disposition of such materials. Namely, all potential disposition options for concrete, including authorized release for re-use, are generally not fully evaluated in D&D projects, so large quantities have been unduly disposed of as low-level radioactive waste. As a result, costs of D&D have become prohibitively high, hindering expedient cleanup of surplus facilities. The ability to evaluate and implement the option of authorized release of concrete from demolition would result in significant cost savings, while maintaining protection of environmental health and safety, across the Department of Energy (DOE) complex. The Idaho National Engineering and Environmental Laboratory (INEEL), Argonne National Laboratory East (ANL-E), and Vanderbilt University have teamed to develop a protocol for the authorized release of concrete, based on the existing DOE guidance of Order 5400.5, that applies across the DOE complex. The protocol will provide a streamlined method for assessing risks and costs, and reaching optimal disposal options, including re-use of the concrete within the DOE system.
Date: June 1, 2000
Creator: Smith, Agatha Marie; Meservey, Richard Harlan; Chen, S.Y.; Powell, James Edward & PArker, F.
Partner: UNT Libraries Government Documents Department

Tests Conducted with Strippable Coatings

Description: This report details the testing and evaluation of several strippable coatings and their use in decontamination. Pentek 604, Bartlett (TLC), and ALARA 1146 were products examined for their overall effectiveness and ease of use. Conclusions were reached about the effective use of these coatings, and field test examples, with radioactive contamination are incorporated.
Date: August 1, 1999
Creator: Archibald, K. E. & Demmer, R. L.
Partner: UNT Libraries Government Documents Department

Engineering study of riser equipment contamination

Description: This Engineering Study was to evaluate the current equipment and operating procedures to determine if changes could be made to improve ALARA and evaluate the feasibility of implementing the proposed solutions. As part of this study input from the cognizant characterization engineers and operating sampling crews was obtained and evaluated for ALARA improvements.
Date: August 25, 1999
Creator: Boger, R. M.
Partner: UNT Libraries Government Documents Department

Westinghouse Hanford Company health and safety performance report. Third quarter calendar year 1995

Description: The lost/restricted workday severity rate posted in CY 1994 of 45.50 was a significant improvement over the prior years and, remarkably, this rate has been reduced to 16.40 thus far in CY 1995 (Table 2--2). The indications from this sustained reduction are that employee, management, HEHF, and accident investigator efforts to manage injuries are becoming stronger (page 2--8). Congratulations to the Human Resources Department for working over 835,000 hours without a lost workday away injury/illness! The last lost workday away case occurred on 12/17/92. The Workers Compensation Report shows significant reduction in the amount of money expended for medical treatments and time loss due to industrial injuries. The cost of insurance continues to decrease. Continued savings can be attributed to aggressive claims and safety case management, an enhanced attitude by management creating a positive and proactive safety awareness culture, and a more aggressive return-to-work philosophy.
Date: November 1, 1995
Creator: Lansing, K.A.
Partner: UNT Libraries Government Documents Department

Applied ALARA techniques

Description: The presentation focuses on some of the time-proven and new technologies being used to accomplish radiological work. These techniques can be applied at nuclear facilities to reduce radiation doses and protect the environment. The last reactor plants and processing facilities were shutdown and Hanford was given a new mission to put the facilities in a safe condition, decontaminate, and prepare them for decommissioning. The skills that were necessary to operate these facilities were different than the skills needed today to clean up Hanford. Workers were not familiar with many of the tools, equipment, and materials needed to accomplish:the new mission, which includes clean up of contaminated areas in and around all the facilities, recovery of reactor fuel from spent fuel pools, and the removal of millions of gallons of highly radioactive waste from 177 underground tanks. In addition, this work has to be done with a reduced number of workers and a smaller budget. At Hanford, facilities contain a myriad of radioactive isotopes that are 2048 located inside plant systems, underground tanks, and the soil. As cleanup work at Hanford began, it became obvious early that in order to get workers to apply ALARA and use hew tools and equipment to accomplish the radiological work it was necessary to plan the work in advance and get radiological control and/or ALARA committee personnel involved early in the planning process. Emphasis was placed on applying,ALARA techniques to reduce dose, limit contamination spread and minimize the amount of radioactive waste generated. Progress on the cleanup has,b6en steady and Hanford workers have learned to use different types of engineered controls and ALARA techniques to perform radiological work. The purpose of this presentation is to share the lessons learned on how Hanford is accomplishing radiological work.
Date: February 5, 1998
Creator: Waggoner, L.O.
Partner: UNT Libraries Government Documents Department

Westinghouse Hanford Company health and safety performance report

Description: Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% ...
Date: May 15, 1996
Creator: Rogers, L.
Partner: UNT Libraries Government Documents Department

Effective use of metrics in an ALARA program

Description: ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include; external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting and processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific ``indicators``. To choose the site-specific indicators that will be tracked and trended requires careful review. This required the end users to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that customers can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer`s most frequently asked questions. It is now also a tool to communicate the status of the radiation protection program to facility managers. Finally it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, ``user friendly``, software and contains information from RIR`s, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics.
Date: July 1, 1996
Creator: Bates, B.B. Jr.
Partner: UNT Libraries Government Documents Department

ALARA Center of Technology -- resource guide

Description: The purpose is to provide a source of information that can be used to assist personnel in the planning, training, and execution of radiological work using the principles of ALARA. This document is not intended to replace HNF or WHC Control Manual requirements. The ALARA Tools-List provides detailed information on the use and procurement of engineered controls, mockup training guidelines, and good radiological work practices that have been proven to be ALARA.
Date: February 5, 1998
Creator: Waggoner, L.O.
Partner: UNT Libraries Government Documents Department

Spent Nuclear Fuel Project dose management plan

Description: This dose management plan facilitates meeting the dose management and ALARA requirements applicable to the design activities of the Spent Nuclear Fuel Project, and establishes consistency of information used by multiple subprojects in ALARA evaluations. The method for meeting the ALARA requirements applicable to facility designs involves two components. The first is each Spent Nuclear Fuel Project subproject incorporating ALARA principles, ALARA design optimizations, and ALARA design reviews throughout the design of facilities and equipment. The second component is the Spent Nuclear Fuel Project management providing overall dose management guidance to the subprojects and oversight of the subproject dose management efforts.
Date: March 1, 1996
Creator: Bergsman, K. H.
Partner: UNT Libraries Government Documents Department

Collective dose as a performance measure for occupational radiation protection programs: Issues and recommendations

Description: Collective dose is one of the performance measures used at many US Department of Energy (DOE) contractor facilities to quantitatively assess the objectives of the radiation protection program. It can also be used as a management tool to improve the program for keeping worker doses as low as reasonably achievable (ALARA). Collective dose is used here to mean the sum of all total effective dose equivalent values for all workers in a specified group over a specified time. It is often used as a surrogate estimate of radiological risk. In principle, improvements in radiation protection programs and procedures will result in reduction of collective dose, all other things being equal. Within the DOE, most frequently, a single collective dose number, which may or may not be adjusted for workload and other factors, is used as a performance measure for a contractor. The purpose of this report is to evaluate the use of collective dose as a performance measure for ALARA programs at DOE sites.
Date: July 1, 1998
Creator: Strom, D.J.; Harty, R.; Hickey, E.E.; Martin, J.B.; Peffers, M.S. & Kathren, R.L.
Partner: UNT Libraries Government Documents Department

Acceptance test procedure for K basins dose reduction project clean and coat equipment

Description: This document is the Acceptance Test Procedure (ATP) for the clean and coat equipment designed by Oceaneering Hanford, Inc. under purchase order MDK-XVC-406988 for use in the 105 K East Basin. The ATP provides the guidelines and criteria to test the equipment`s ability to clean and coat the concrete perimeter, divider walls, and dummy elevator pit above the existing water level. This equipment was designed and built in support of the Spent Nuclear Fuel, Dose Reduction Project. The ATP will be performed at the 305 test facility in the 300 Area at Hanford. The test results will be documented in WHC-SD-SNF-ATR-020.
Date: March 11, 1996
Creator: Creed, R.F.
Partner: UNT Libraries Government Documents Department

ALARA Review for the Sediment Relocation and Removal from the 105-N Fuel Storage Basin

Description: This as low as reasonable achievable (ALARA) review revision provides a description of the engineering and administrative controls used to manage personnel exposure, control contamination levels, and airborne radioactivity concentrations during sediment relocation and removal in the 105-N Fuel Storage Basin. This document updates and supercedes the ALARA review of the sediment-related activities contained in 100-N Basin Stabilization Project As Low As Reasonably Achievable Plan (BHI 1995).
Date: March 1998
Creator: Demers, J. W.
Partner: UNT Libraries Government Documents Department

A simplified ALARA approach to demonstration of compliance with surface contaminated object regulatory requirements

Description: The US Department of Transportation (DOT) and the US Nuclear Regulatory Commission (NRC) have jointly prepared a comprehensive set of draft guidance for consignors and inspectors to use when applying the newly imposed regulatory requirements for low specific activity (LSA) material and surface contaminated objects (SCOs). The guidance is being developed to facilitate compliance with the new LSA material and SCO requirements, not to impose additional requirements. These new requirements represent, in some areas, significant departures from the manner in which packaging and transportation of these materials and objects were previously controlled. On occasion, it may be appropriate to use conservative approaches to demonstrate compliance with some of the requirements, ensuring that personnel are not exposed to radiation at unnecessary levels, so that exposures are kept as low as reasonably achievable (ALARA). In the draft guidance, one such approach would assist consignors preparing a shipment of a large number of SCOs in demonstrating compliance without unnecessarily exposing personnel. In applying this approach, users need to demonstrate that four conditions are met. These four conditions are used to categorize non-activated, contaminated objects as SCO-2. It is expected that, by applying this approach, it will be possible to categorize a large number of small contaminated objects as SCO-2 without the need for detailed, quantitative measurements of fixed, accessible contamination, or of total (fixed and non-fixed) contamination on inaccessible surfaces. The method, which is based upon reasoned argument coupled with limited measurements and the application of a sum of fractions rule, is described and examples of its use are provided.
Date: February 1, 1998
Creator: Pope, R.B.; Shappert, L.B.; Michelhaugh, R.D.; Boyle, R.W. & Cook, J.C.
Partner: UNT Libraries Government Documents Department

Permeation Barrier Coatings for the Helical Heat Exchanger

Description: A permeation barrier coating was specified for the Helical Heat Exchanger (HHE) to minimize contamination through emissions and/or permeation into the nitrogen system for ALARA reasons. Due to the geometry of the HHE, a special coating practice was needed since the conventional method of high temperature pack aluminization was intractable. A survey of many coating companies was undertaken; their coating capabilities and technologies were assessed and compared to WSRC needs. The processes and limitations to coating the HHE are described. Slurry coating appears to be the most technically sound approach for coating the HHE.
Date: May 26, 1999
Creator: Korinko, P.S.
Partner: UNT Libraries Government Documents Department

Waste-clearance strategy for DOE waste processed at commercial facilities

Description: In May 1991, a moratorium was issued on shipping potentially mixed waste from DOE facilities nationwide to commercial treatment, storage, and disposal facilities. A potential waste-clearance strategy was developed to address the DOE mixed-waste moratorium issues, which had resulted from a lack of exisitng volume contamination regulations. This strategy also has important potential applications for establishing site clearance limits that ensure worker and public risks remain well below regulatory limits.
Date: May 1, 1996
Creator: Chen, S.Y.; Pfingston, M. & LePoire, D.
Partner: UNT Libraries Government Documents Department

Design features of the cold vacuum drying facility to keep worker doses as low as reasonably achievable

Description: This report describes the design features and steps taken to ensure that the Cold Vacuum Drying Facility satisfies regulatory requirements that personnel doses be kept as low as reasonably achievable (ALARA). This report also documents an analysis of worker doses and demonstrates that the ALARA goal of limiting individual doses to 500 mrem per year can be met.
Date: June 24, 1999
Creator: NELSON, J.V.
Partner: UNT Libraries Government Documents Department

Now Enhancing Working Skills: The ``NEWS`` Program. Final report

Description: In October of 1992, Los Alamos National Laboratory and Merex Corporation began a pilot basic skills program to enhance workers` skills. The program, known as the NEWS (Now Enhancing Working Skills) Program, was implemented by the Training and Development Group of the Human Resources Division. A group of 106 employees known as Radiological Control Technicians (RCTs) from ESH-1 (Environmental, Safety, and Health) were targeted to take mandated DOE (Department of Energy) training. The main goal of the LANL/Merex partnership was to help RCTs prepare for mandated DOE Rad Con training and job performance by improving their information processing and math skills. A second goal of this project was to use the information from this small group to make some predictions about the Laboratory as a whole. This final report contains the description and an appendix for the ``NEWS`` program. The topics in this report include Merex class descriptions, test score results for the MAT, the WAT, the TABE, and Challenge test, a follow-up survey to Merex IPS and math training, student feedback statistics for skills programs, and lessons learned from the program.
Date: January 23, 1995
Creator: Kuiper, A.
Partner: UNT Libraries Government Documents Department

Radiological Work Planning and Procedure

Description: Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.
Date: January 1, 2000
Creator: KURTZ, J.E.
Partner: UNT Libraries Government Documents Department

Dose Reduction Techniques

Description: As radiation safety specialists, one of the things we are required to do is evaluate tools, equipment, materials and work practices and decide whether the use of these products or work practices will reduce radiation dose or risk to the environment. There is a tendency for many workers that work with radioactive material to accomplish radiological work the same way they have always done it rather than look for new technology or change their work practices. New technology is being developed all the time that can make radiological work easier and result in less radiation dose to the worker or reduce the possibility that contamination will be spread to the environment. As we discuss the various tools and techniques that reduce radiation dose, keep in mind that the radiological controls should be reasonable. We can not always get the dose to zero, so we must try to accomplish the work efficiently and cost-effectively. There are times we may have to accept there is only so much you can do. The goal is to do the smart things that protect the worker but do not hinder him while the task is being accomplished. In addition, we should not demand that large amounts of money be spent for equipment that has marginal value in order to save a few millirem. We have broken the handout into sections that should simplify the presentation. Time, distance, shielding, and source reduction are methods used to reduce dose and are covered in Part I on work execution. We then look at operational considerations, radiological design parameters, and discuss the characteristics of personnel who deal with ALARA. This handout should give you an overview of what it takes to have an effective dose reduction program.
Date: May 16, 2000
Creator: WAGGONER, L.O.
Partner: UNT Libraries Government Documents Department

Using Weibull Distribution Analysis to Evaluate ALARA Performance

Description: As Low as Reasonably Achievable (ALARA) is the underlying principle for protecting nuclear workers from potential health outcomes related to occupational radiation exposure. Radiation protection performance is currently evaluated by measures such as collective dose and average measurable dose, which do not indicate ALARA performance. The purpose of this work is to show how statistical modeling of individual doses using the Weibull distribution can provide objective supplemental performance indicators for comparing ALARA implementation among sites and for insights into ALARA practices within a site. Maximum likelihood methods were employed to estimate the Weibull shape and scale parameters used for performance indicators. The shape parameter reflects the effectiveness of maximizing the number of workers receiving lower doses and is represented as the slope of the fitted line on a Weibull probability plot. Additional performance indicators derived from the model parameters include the 99th percentile and the exceedance fraction. When grouping sites by collective total effective dose equivalent (TEDE) and ranking by 99th percentile with confidence intervals, differences in performance among sites can be readily identified. Applying this methodology will enable more efficient and complete evaluation of the effectiveness of ALARA implementation.
Date: October 1, 2009
Creator: E. L. Frome, J. P. Watkins, and D. A. Hagemeyer
Partner: UNT Libraries Government Documents Department

HANFORD SITE LOW EXPOSURE PIPELINE REPAIR USING A NON-METALLIC COMPOSITE SYSTEM

Description: At the Department of Energy, Richland Operations (DOE-RL) Hanford site in eastern Washington, a 350 mm (14 inch) diameter high density polyethylene (HDPE) pump recirculation pipeline failed at a bonded joint adjacent to a radiologically and chemically contaminated groundwater storage basin. The responsible DOE-RL contractor, CH2MHill Plateau Remediation Company, applied a fiberglass reinforced plastic (composite) field repair system to the failed joint. The system was devised specifically for the HDPE pipe repair at the Hanford site, and had not been used on this type of plastic piping previously. This paper introduces the pipe failure scenario, describes the options considered for repair and discusses the ultimate resolution of the problem. The failed pipeline was successfully returned to service with minimal impact on waste water treatment plant operating capacity. Additionally, radiological and chemical exposures to facility personnel were maintained as low as reasonably achievable (ALARA). The repair is considered a success for the near term, and future monitoring will prove whether the repair can be considered for long term service and as a viable alternative for similar piping failures at the Hanford site.
Date: November 12, 2009
Creator: Huth, R. J.
Partner: UNT Libraries Government Documents Department