E10.03 - Radiological Protection for Decontamination and Decommissioning of Nuclear Facilities and Components

ABSTRACT
This specification prescribes the performance criteria for non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and protect uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction, respirable fraction, radiation resistance) as well as the mechanical and chemical properties for permanent coatings that are intended to immobilize dispersible radioactive contamination deposited on buildings and equipment as might result from anticipated to unanticipated events to include normal operating conditions, decommissioning, and radiological release. The coating is intended to reduce: migration of the contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air; and the spread of contamination as a result of external forces such as pedestrian traffic. It shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be applicable to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the coating may include constituents that will physically or chemically bind and hold radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification prescribes the performance criteria for strippable/removable coatings used in immobilizing radioactive contamination, minimizing worker exposure, and facilitating subsequent decontamination or protecting uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, tensile strength, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction) as well as the mechanical and chemical properties for strippable/removable coatings. The strippable/removable coating is intended to reduce: migration of the radioactive contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air and the airborne intake hazards of the contamination; and the spread of contamination as a result of external forces such as pedestrian traffic. The strippable/removable coating shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be readily applied to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the strippable/removable coating may include constituents that will physically or chemically bind and immobilize radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of strippable/removable materials used to immobilize radioactive contamination, minimize worker exposure, and facilitate subsequent decontamination or to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 This practice provides a protocol to compare different decontamination technologies with a standard contamination mechanism and analysis of subsequent decontamination factors/efficiencies.  
5.2 The use of this practice provides for the preparation of test coupons with a known amount of loose radiological or surrogate contaminant on the surface.  
5.3 A standard test coupon is described and a list of potential equipment, contaminants, and contaminating solutions is provided within the procedure.  
5.4 This practice describes a contamination simulation process that meets the requirements of testing performed (previously) by the U.S. Department of Energy and U.S. Environmental Protection Agency for the removal of loose contamination.
SCOPE
1.1 This practice is intended to provide a basis for simulating radioactive contamination consistent with processes used to evaluate decontamination. The methods described provide a “loose-type” radiological or surrogate contamination on nonporous surfaces; these methods provide a surface contamination that may be easily removed by brushing or flushing with water.  
1.2 This practice is intended for nonporous surfaces such as stainless steel, aluminum, glass, laminates, and epoxy painted surfaces. Preparation of porous substrates is not addressed, although similar methodologies may be used. A different practice is employed using Practice E3190, to produce “fixed” contamination.  
1.3 The chemical simulants shall not include nor generate toxic byproducts as defined by U.S. Occupational Safety and Health Administration (OSHA) during preparation, application, or removal under normal conditions. A Safety Data Sheet (SDS) shall be provided so that appropriate personal protective equipment (PPE) can be selected.  
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed.  
4.2 In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1757 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook.6  
4.3 This decommissioning plan will be developed to serve as the executive document that describes the objectives of the decommissioning program and identifies and defines the elements necessary to accomplish the program.  
4.4 A detailed implementation plan describing how the objectives of the decommissioning plan will be met should be prepared. Some of the documents or implementation plans that may be required to support the overall decommissioning program include an engineering plan; a cost, schedule, and financing plan (10 CFR 140 and 170); a field implementation plan; a health and safety plan (29 CFR 1910.120, Guide E1167); a quality assurance plan (10 CFR 50.59 and 10 CFR 830.120); an emergency plan; an environmental monitoring plan (Guide E1819); a radiological protection plan (10 CFR 20, 10 CFR 835, Guide E1167); and a physical security plan (10 CFR 73). These implementation plans shall be separate from and consistent with the decommissioning plan.
SCOPE
1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC), Agreement State license, under Department of Energy (DOE) orders, or whose operation was overseen by another federal, state, or local agency.  
1.2 The guide applies to the preparation and content of the decommissioning plan document itself.  
1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide.  
Note 1: Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing the optimum methods for decontamination and decommissioning, and estimating the resulting waste volumes and personnel exposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or deriving the above information.  
5.2 Information on the proposed decommissioning methods, waste volumes, and estimated personnel radiation exposures can be used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This information may be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a function of the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.
SCOPE
1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses:  
1.1.1 the data quality objective for characterization as an initial step in decommissioning planning.  
1.1.2 sampling methods,  
1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and  
1.1.4 essential documentation of the characterization information.  
1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.3 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The purpose of this guide is to provide the user information and guidance for preparation of a plan for the surveillance and maintenance of nuclear facilities that have been deactivated and are awaiting D&D.  
4.1.1 This document provides guidance for performing S&M in a way that will ensure worker and public safety, while also addressing stakeholder requirements.  
4.1.2 Use of this guide helps standardize the basic requirements for S&M of nuclear facilities.  
4.2 Use of this guide helps ensure that the S&M plan addresses the significant activities and actions necessary to maintain these facilities in a safe and stable condition until they can be decommissioned.
SCOPE
1.1 This guide outlines a method for developing a Surveillance and Maintenance (S&M) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (D&D).  
1.2 The primary concerns for S&M are related to (1) animal intrusion, (2) structural integrity degradation,  (3) water in-leakage, (4) contamination migration, (5) unauthorized personnel entry, and (6) theft/intrusion. This document is intended to serve as a guide only, and is not intended to modify existing regulations.  
1.3 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed.  
5.2 Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.
SCOPE
1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.  
1.2 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 A waste management plan based on the contents of this guide will provide for the successful identification of potential waste streams anticipated from decommissioning activities, and provide a clear and concise methodology for the handling of identified waste from generation to final disposition.  
4.2 The waste management plan will identify the general waste types, characterization, packaging, transportation, disposal, and quality assurance requirements for potential waste streams.
SCOPE
1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal.  
1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations.  
1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams.  
1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.  
4.2 Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.  
4.3 Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.  
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.  
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:  
1.3.1 alpha  
1.3.2 beta (electrons)  
1.3.3 gamma  
1.3.4 characteristic x-rays  
1.3.5 The measurement of neutron emissions is not included as part of this standard.  
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.  
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.  
1.6 Non-SI units are used and appropriate for this guide as they are industry standard. Mathematical equivalents may be provided in parentheses.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 A program based on this guide will provide assurance to all concerned that the appropriate elements of radiation safety have been included to protect workers, the general public, and the environment in proximity to the decommissioning activities.  
4.2 Implementation of such a program will provide assurance to those agencies responsible for review or audit of the decommissioning project that the requirements for radiation protection have been addressed.
SCOPE
1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations.  
1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project.  
1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan.  
1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations.  
1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project.  
1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project.  
Note 1: If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site.  
1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation.  
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.9 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The purpose of this guide is to define the elements of a radiological protection training program that will enable a radiation worker, upon completion of training, to achieve the following:  
4.1.1 Understand the relative health and safety risks associated with the types and levels of radiation that may be encountered during the work assignment in radiologically controlled areas,  
4.1.2 Complete the forms and records necessary to be permitted to function as a radiation worker,  
4.1.3 Practice the necessary monitoring and contamination control techniques to minimize exposure to radiation or radioactive materials, or both, and  
4.1.4 Practice work habits that will minimize the impact of radiation or radioactive materials, or both, upon the workplace and surrounding environments.  
4.2 The standardization of radiation worker radiological protection training provides the individual radiation worker with a greater assurance that the training received is adequate to minimize radiation exposure, to enable the worker to work safely in a radiologically controlled area, and to meet applicable regulations.  
4.3 The standardization of radiation worker radiological protection training prevents unnecessary retraining of radiation workers.  
4.4 This guide should be used as the basis for establishing a radiological protection training program for radiation workers at nuclear facilities.
SCOPE
1.1 This guide covers general recommendations with respect to standard work practices, procedures, and measurement methods for the radiological protection portion of health and safety training for radiation workers at nuclear facilities. This guide defines the elements of a training program for radiation workers consistent with the philosophy that occupational radiation exposure be kept as low as is reasonably achievable (ALARA). Regulatory agencies have statutory responsibilities to promulgate regulations applying to the training of workers exposed to radiation hazards. This guide shall not take precedence over any such regulations.  
1.2 This guide is intended to help ensure that the employer provides the radiation worker with radiological protection training that the worker needs to work safely in a radiologically controlled area and to maintain radiation exposure ALARA.  
1.3 The scope of radiological protection training shall be related to the duties and responsibilities of each radiation worker and shall be commensurate with potential radiological protection problems in the radiologically controlled area.  
1.4 This guide is also intended to provide guidance that will enable an evaluation of the effectiveness of the radiological protection training program toward achieving the purpose stated in Section 4.  
1.5 This guide does not cover the more detailed training requirements for radiation protection professionals or technicians.  
1.6 This guide provides reference to the type of radiological protecting training records that should be created, and recommends retention periods for radiological protection training records.  
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.8 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.  
4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).  
4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.  
1.2 This specification applies to records to be used for in-processing only.  
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).  
1.4 This specification doesPresident Barack Obama eulogy at John Lewis funeral not reduce any regulatory requirement for records retention at a licensed nuclear facility.  
Note 1: Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers.
Note 2: This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 This practice provides a protocol to compare different decontamination technologies with a standard contamination mechanism and analysis of subsequent decontamination factors/efficiencies.  
5.2 The use of this practice provides for the preparation of test coupons with a known amount of fixed radiological or surrogate contaminant on the surface.  
5.3 A standard test coupon is described and a list of potential spray equipment, contaminants, and contaminating solutions is provided within the procedure.  
5.4 This method describes a contamination simulation process that meets the requirements of testing performed (previously) by the U.S. Department of Energy and U.S. Environmental Protection Agency.
SCOPE
1.1 This practice is intended to provide a basis for simulating radioactive contamination consistent with processes used to evaluate decontamination. The methods described provide a “fixed-type” radiological or surrogate contamination on porous surfaces; these methods provide a surface contamination that is not easily removed by brushing or flushing with water.  
1.2 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.3 This practice is intended to be practiced primarily on porous surfaces such as concrete, marble, granite, grout, brick, tile, asphalt, vinyl floor tile, latex painted gypsum wall board and polyurethane coated wood. Preparation of non-porous substrates is not addressed, although similar methodology may be used.  
1.4 The chemical simulants shall not include nor generate toxic by-products as defined by U.S. Occupational Safety and Health Administration (OSHA) during preparation, application, or removal under normal conditions. A Safety Data Sheet shall be provided so that appropriate PPE can be selected.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SCOPE
1.1 This specification is intended to provide a basis for identification of non-removable permanent foaming fixatives as a long-term measure used to immobilize or isolate radioactive contamination, or both, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
6.1 Materials encountered during D&D may contain residual radioactivity varying in amounts from that in irradiated fuel to barely detectable quantities in or on building materials. It is clear that highly radioactive materials have to be disposed as radioactive waste pursuant to 10 CFR 60 and 10 CFR 61. Conversely, it is not reasonable to expend a disproportionate amount of resources to isolate materials that contain minute quantities of radioactive materials that will not cause even statistically measurable health effects.  
6.2 This guide provides a rationale and methodology for distinguishing between materials that contain sufficient radioactivity to warrant isolation of some type (such as storage awaiting decay, near-surface disposal, disposal with intruder protection, or placement in a deep repository) from materials with insignificant radioactive content. Materials with insignificant radioactive content can be recycled in the economy or disposed of in conventional (landfill) facilities without adverse health effects. Materials that meet the criteria identified in this guide are not simply excluded from regulation because they do not fall precisely in the regulatory scope. They are sufficiently free of radioactive material so that no further efforts at control are justified for radiation protection purposes. Therefore, the release of materials for unrestricted use in accordance with this guide meets the criteria for being an “as low as reasonably achievable” (ALARA) activity.  
6.3 For the purpose of this guide, the return of materials containing residual radioactivity to society without regulatory restrictions is referred to as “unrestricted release based on the absence of the credible potential for adverse health effects.” This guide asserts that materials recycled this way will have no statistically measurable health effects regardless of use. It does not guarantee that the materials are suitable for use in every possible application, for example, trace am...
SCOPE
1.1 This guide provides an approach for developing a basis for obtaining approval for release of bulk materials to be removed from a decontamination and decommissioning (D&D) or environmental remediation site from regulatory control. This would be addressed in the decommissioning plan (Guide E1281). Fig. 1 follows the logic described in the MARSAME for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as “candidate for release based on dose.”    
1.2 For purposes of this guide, bulk materials shall consist of, for example, building materials, concrete rubble, soils, and internally contaminated or activated equipment and facility components.  
1.3 This guide is intended to apply to those equipment and materials to be removed from the site for their disposition as opposed to real property (buildings and grounds) that are to remain.  
1.4 Warning—Breathing of asbestos dust is hazardous. Asbestos and asbestos products present demonstrated health risks for users and for those with whom they come into contact. In addition to other precautions, when working with asbestos products, minimize the dust that results. For information on the safe use of chrysoltile asbestos, refer to “Safe Use of Chrysotile Asbestos: A Manual on Preventive and Control Measures.”  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. For a specific hazard see 1.4.

ABSTRACT
This specification prescribes the performance criteria for strippable/removable coatings used in immobilizing radioactive contamination, minimizing worker exposure, and facilitating subsequent decontamination or protecting uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, tensile strength, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction) as well as the mechanical and chemical properties for strippable/removable coatings. The strippable/removable coating is intended to reduce: migration of the radioactive contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air and the airborne intake hazards of the contamination; and the spread of contamination as a result of external forces such as pedestrian traffic. The strippable/removable coating shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be readily applied to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the strippable/removable coating may include constituents that will physically or chemically bind and immobilize radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of strippable/removable materials used to immobilize radioactive contamination, minimize worker exposure, and facilitate subsequent decontamination or to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification prescribes the performance criteria for non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and protect uncontaminated areas against the spread of radioactive contamination. It covers the minimum performance requirements (shelf life, adhesion, abrasion resistance, dry/cure time, decontamination factor, airborne release fraction, respirable fraction, radiation resistance) as well as the mechanical and chemical properties for permanent coatings that are intended to immobilize dispersible radioactive contamination deposited on buildings and equipment as might result from anticipated to unanticipated events to include normal operating conditions, decommissioning, and radiological release. The coating is intended to reduce: migration of the contamination into or along buildings, equipment, and other surfaces; resuspension of contamination into the air; and the spread of contamination as a result of external forces such as pedestrian traffic. It shall: be applicable to both vertical and horizontal surfaces; work within a range of environmental and radiological conditions; and be applicable to both porous and nonporous materials such as concrete, wood, metal, ceramics, and plastics. Furthermore, the coating may include constituents that will physically or chemically bind and hold radioactive contamination.
SCOPE
1.1 This specification is intended to provide a basis for identification of non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed.  
4.2 In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1757 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook.6  
4.3 This decommissioning plan will be developed to serve as the executive document that describes the objectives of the decommissioning program and identifies and defines the elements necessary to accomplish the program.  
4.4 A detailed implementation plan describing how the objectives of the decommissioning plan will be met should be prepared. Some of the documents or implementation plans that may be required to support the overall decommissioning program include an engineering plan; a cost, schedule, and financing plan (10 CFR 140 and 170); a field implementation plan; a health and safety plan (29 CFR 1910.120, Guide E1167); a quality assurance plan (10 CFR 50.59 and 10 CFR 830.120); an emergency plan; an environmental monitoring plan (Guide E1819); a radiological protection plan (10 CFR 20, 10 CFR 835, Guide E1167); and a physical security plan (10 CFR 73). These implementation plans shall be separate from and consistent with the decommissioning plan.
SCOPE
1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC), Agreement State license, under Department of Energy (DOE) orders, or whose operation was overseen by another federal, state, or local agency.  
1.2 The guide applies to the preparation and content of the decommissioning plan document itself.  
1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide.  
Note 1: Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 A waste management plan based on the contents of this guide will provide for the successful identification of potential waste streams anticipated from decommissioning activities, and provide a clear and concise methodology for the handling of identified waste from generation to final disposition.  
4.2 The waste management plan will identify the general waste types, characterization, packaging, transportation, disposal, and quality assurance requirements for potential waste streams.
SCOPE
1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal.  
1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations.  
1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams.  
1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
5.1 Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed.  
5.2 Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.
SCOPE
1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

SIGNIFICANCE AND USE
4.1 The purpose of this guide is to provide the user information and guidance for preparation of a plan for the surveillance and maintenance of nuclear facilities that have been deactivated and are awaiting D&D.  
4.1.1 This document provides guidance for performing S&M in a way that will ensure worker and public safety, while also addressing stakeholder requirements.  
4.1.2 Use of this guide helps standardize the basic requirements for S&M of nuclear facilities.  
4.2 Use of this guide helps ensure that the S&M plan addresses the significant activities and actions necessary to maintain these facilities in a safe and stable condition until they can be decommissioned.
SCOPE
1.1 This guide outlines a method for developing a Surveillance and Maintenance (S&M) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (D&D).  
1.2 The primary concerns for S&M are related to (1) animal intrusion, (2) structural integrity degradation,  (3) water in-leakage, (4) contamination migration, (5) unauthorized personnel entry, and (6) theft/intrusion. This document is intended to serve as a guide only, and is not intended to modify existing regulations.

SIGNIFICANCE AND USE
4.1 The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.  
4.2 Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.  
4.3 Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.  
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.  
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:  
1.3.1 alpha  
1.3.2 beta (electrons)  
1.3.3 gamma  
1.3.4 characteristic x-rays  
1.3.5 The measurement of neutron emissions is not included as part of this standard.  
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.  
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.  
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

SIGNIFICANCE AND USE
5.1 Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing the optimum methods for decontamination and decommissioning, and estimating the resulting waste volumes and personnel exposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or deriving the above information.  
5.2 Information on the proposed decommissioning methods, waste volumes, and estimated personnel radiation exposures can be used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This information may be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a function of the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.
SCOPE
1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses:  
1.1.1 the data quality objective for characterization as an initial step in decommissioning planning.  
1.1.2 sampling methods,  
1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and  
1.1.4 essential documentation of the characterization information.  
1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 A program based on this guide will provide assurance to all concerned that the appropriate elements of radiation safety have been included to protect workers, the general public, and the environment in proximity to the decommissioning activities.  
4.2 Implementation of such a program will provide assurance to those agencies responsible for review or audit of the decommissioning project that the requirements for radiation protection have been addressed.
SCOPE
1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations.  
1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project.  
1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan.  
1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations.  
1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project.  
1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project.  
Note 1: If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site.  
1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation.  
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 The purpose of this guide is to define the elements of a radiological protection training program that will enable a radiation worker, upon completion of training, to achieve the following:  
4.1.1 Understand the relative health and safety risks associated with the types and levels of radiation that may be encountered during the work assignment in radiologically controlled areas,  
4.1.2 Complete the forms and records necessary to be permitted to function as a radiation worker,  
4.1.3 Practice the necessary monitoring and contamination control techniques to minimize exposure to radiation or radioactive materials, or both, and  
4.1.4 Practice work habits that will minimize the impact of radiation or radioactive materials, or both, upon the workplace and surrounding environments.  
4.2 The standardization of radiation worker radiological protection training provides the individual radiation worker with a greater assurance that the training received is adequate to minimize radiation exposure, to enable the worker to work safely in a radiologically controlled area, and to meet applicable regulations.  
4.3 The standardization of radiation worker radiological protection training prevents unnecessary retraining of radiation workers.  
4.4 This guide should be used as the basis for establishing a radiological protection training program for radiation workers at nuclear facilities.
SCOPE
1.1 This guide covers general recommendations with respect to standard work practices, procedures, and measurement methods for the radiological protection portion of health and safety training for radiation workers at nuclear facilities. This guide defines the elements of a training program for radiation workers consistent with the philosophy that occupational radiation exposure be kept as low as is reasonably achievable (ALARA). Regulatory agencies have statutory responsibilities to promulgate regulations applying to the training of workers exposed to radiation hazards. This guide shall not take precedence over any such regulations.  
1.2 This guide is intended to help ensure that the employer provides the radiation worker with radiological protection training that the worker needs to work safely in a radiologically controlled area and to maintain radiation exposure ALARA.  
1.3 The scope of radiological protection training shall be related to the duties and responsibilities of each radiation worker and shall be commensurate with potential radiological protection problems in the radiologically controlled area.  
1.4 This guide is also intended to provide guidance that will enable an evaluation of the effectiveness of the radiological protection training program toward achieving the purpose stated in Section 4.  
1.5 This guide does not cover the more detailed training requirements for radiation protection professionals or technicians.  
1.6 This guide provides reference to the type of radiological protecting training records that should be created, and recommends retention periods for radiological protection training records.  
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.  
4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).  
4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.  
1.2 This specification applies to records to be used for in-processing only.  
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).  
1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers. Note 2—This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).

SIGNIFICANCE AND USE
The purpose of this guide is to provide the user information and guidance for preparation of a plan for the surveillance and maintenance of nuclear facilities that have been deactivated and are awaiting D&D.
This document provides guidance for performing S&M in a way that will ensure worker and public safety, while also addressing stakeholder requirements.
Use of this guide helps standardize the basic requirements for S&M of nuclear facilities.
Use of this guide helps ensure that the S&M plan addresses the significant activities and actions necessary to maintain these facilities in a safe and stable condition until they can be decommissioned.
SCOPE
1.1 This guide outlines a method for developing a Surveillance and Maintenance (S&M) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (D&D).
1.2 The primary concerns for S&M are related to (1) animal intrusion, (2) structural integrity degradation, (3) water in-leakage, (4) contamination migration, (5) unauthorized personnel entry, and (6) theft/intrusion. This document is intended to serve as a guide only, and is not intended to modify existing regulations.

SIGNIFICANCE AND USE
Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed.
Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.
SCOPE
1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

SIGNIFICANCE AND USE
The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed.
In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1757 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook.
SCOPE
1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC) or Agreement State license, or under Department of Energy (DOE) orders.
1.2 The guide applies to the preparation and content of the decommissioning plan document itself.
1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide.
Note 1—Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
A waste management plan based on the contents of this guide will provide for the successful identification of potential waste streams anticipated from decommissioning activities, and provide a clear and concise methodology for the handling of identified waste from generation to final disposition.
The waste management plan will identify the general waste types, characterization, packaging, transportation, disposal, and quality assurance requirements for potential waste streams.
SCOPE
1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal.
1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations.
1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams.
1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
Materials encountered during D&D may contain residual radioactivity varying in amounts from that in irradiated fuel to barely detectable quantities in or on building materials. It is clear that highly radioactive materials have to be disposed as radioactive waste pursuant to 10 CFR 60 and 10 CFR 61. Conversely, it is not reasonable to expend a disproportionate amount of resources to isolate materials that contain minute quantities of radioactive materials that will not cause even statistically measurable health effects.
This guide provides a rationale and methodology for distinguishing between materials that contain sufficient radioactivity to warrant isolation of some type (storage awaiting decay, near-surface disposal, disposal with intruder protection, or placement in a deep repository) from materials with insignificant radioactive content. Materials with insignificant radioactive content can be recycled in the economy or disposed of in conventional (landfill) facilities without adverse health effects. Materials that meet the criteria identified in this guide are not simply excluded from regulation because they do not fall precisely in the regulatory scope. They are sufficiently free of radioactive material so that no further efforts at control are justified for radiation protection purposes. Therefore, the release of materials for unrestricted use in accordance with this guide meets the criteria for being an “as low as reasonably achievable” (ALARA) activity.
For the purpose of this guide, the return of materials containing residual radioactivity to society without regulatory restrictions is referred to as “unrestricted release based on the absence of the credible potential for adverse health effects.” This guide asserts that materials recycled this way will have no statistically measurable health effects regardless of use. It does not guarantee that the materials are suitable for use in every possible application, for example, trace amounts of radionuclides...
SCOPE
1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (D&D) from restricted use. This would be addressed in the decommissioning plan (E 1281). It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Fig. 1 shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as “candidate for release based on dose.”
1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects.
1.3 Surface contaminated objects are materials externally contaminated with radioactive material. Provisions already exist for their release for recycle if it can be shown that they meet applicable federal and state regulations for surface contamination. Regulatory Guide 1.86 and DOE Order 5400.5 specify the upper limits for radioactive surface contamination on material to be released for unrestricted use.
1.4 The release of material containing residual radioactive material (except for  226Ra) in bulk form (for example, soil or slightly activated metal) is based on the demonstration that the dose to a member of the public will be lower than a specified value (proposed by the petitioner or defined by regulation) for its intended use and lower than a second specified value via the most restrictive plausible scenario. The first proposed value should be lower than the second since the dose to any member of the public (via the intended use scenario) will almost certainly be realized, ...

SIGNIFICANCE AND USE
Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing the optimum methods for decontamination and decommissioning, and estimating the resulting waste volumes and personnel exposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or deriving the above information.
Information on the proposed decommissioning methods, waste volumes, and estimated personnel radiation exposures can be used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This information may be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a function of the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.
SCOPE
1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses:
1.1.1 the data quality objective for characterization as an initial step in decommissioning planning.
1.1.2 sampling methods,
1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and
1.1.4 essential documentation of the characterization information.
1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

SIGNIFICANCE AND USE
The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.

SIGNIFICANCE AND USE
The purpose of this guide is to define the elements of a radiological protection training program that will enable a radiation worker, upon completion of training, to achieve the following:
4.1.1 Understand the relative health and safety risks associated with the types and levels of radiation that may be encountered during the work assignment in radiologically controlled areas,
4.1.2 Complete the forms and records necessary to be permitted to function as a radiation worker,
4.1.3 Practice the necessary monitoring and contamination control techniques to minimize exposure to radiation or radioactive materials, or both, and
4.1.4 Practice work habits that will minimize the impact of radiation or radioactive materials, or both, upon the workplace and surrounding environments.
The standardization of radiation worker radiological protection training provides the individual radiation worker with a greater assurance that the training received is adequate to minimize radiation exposure, to enable the worker to work safely in a radiologically controlled area, and to meet applicable regulations.
The standardization of radiation worker radiological protection training prevents unnecessary retraining of radiation workers.
This guide should be used as the basis for establishing a radiological protection training program for radiation workers at nuclear facilities.
SCOPE
1.1 This guide covers general recommendations with respect to standard work practices, procedures, and measurement methods for the radiological protection portion of health and safety training for radiation workers at nuclear facilities. This guide defines the elements of a training program for radiation workers consistent with the philosophy that occupational radiation exposure be kept as low as is reasonably achievable (ALARA). Regulatory agencies have statutory responsibilities to promulgate regulations applying to the training of workers exposed to radiation hazards. This guide shall not take precedence over any such regulations.
1.2 This guide is intended to help ensure that the employer provides the radiation worker with radiological protection training that the worker needs to work safely in a radiologically controlled area and to maintain radiation exposure ALARA.
1.3 The scope of radiological protection training shall be related to the duties and responsibilities of each radiation worker and shall be commensurate with potential radiological protection problems in the radiologically controlled area.
1.4 This guide is also intended to provide guidance that will enable an evaluation of the effectiveness of the radiological protection training program toward achieving the purpose stated in Section 4.
1.5 This guide does not cover the more detailed training requirements for radiation protection professionals or technicians.
1.6 This guide provides reference to the type of radiological protecting training records that should be created, and recommends retention periods for radiological protection training records.
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
p>The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.
This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).
The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.
1.2 This specification applies to records to be used for in-processing only.
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).
1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility.  
Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers.  
Note 2—This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).

SIGNIFICANCE AND USE
This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.
It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.
This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.
This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.
General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.
This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from which the analysis methodology and supporting data are taken.
1.3 Guide E 1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E 1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E 1760 and E 1278, and provides a more detailed approach for the release of concrete.

SIGNIFICANCE AND USE
A program based on this guide will provide assurance to all concerned that the appropriate elements of radiation safety have been included to protect workers, the general public, and the environment in proximity to the decommissioning activities.
Implementation of such a program will provide assurance to those agencies responsible for review or audit of the decommissioning project that the requirements for radiation protection have been addressed. RADIATION PROTECTION PROGRAM   Top
SCOPE
1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations.
1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project.
1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan.
1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations.
1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project.
1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project.
Note 1—If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site.  
1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation.
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed.
Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.
SCOPE
1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; ( 2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing DD activities and the reuse of the facility or area for other purposes.

SIGNIFICANCE AND USE
The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed.
In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1727 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook.6  
This decommissioning plan will be developed to serve as the executive document that describes the objectives of the decommissioning program and identifies and defines the elements necessary to accomplish the program.
A detailed implementation plan describing how the objectives of the decommissioning plan will be met should be prepared. Some of the documents or implementation plans that may be required to support the overall decommissioning program include an engineering plan; a cost, schedule, and financing plan; a field implementation plan; a health and safety plan; a quality assurance plan (for example, Guide E 1167); an emergency plan; an environmental report; a radiological protection plan; and a physical security plan. These implementation plans shall be separate from and consistent with the decommissioning plan.
SCOPE
1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC) or Agreement State license, or under Department of Energy (DOE) orders.
1.2 The guide applies to the preparation and content of the decommissioning plan document itself.
1.3 The detailed description and development of implementation plans identified in Section is outside the scope of this guide.
Note 1—Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities.
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
A waste management plan based on the contents of this guide will provide for the successful identification of potential waste streams anticipated from decommissioning activities, and provide a clear and concise methodology for the handling of identified waste from generation to final disposition.
The waste management plan will identify the general waste types, characterization, packaging, transportation, disposal, and quality assurance requirements for potential waste streams.
SCOPE
1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal.
1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations.
1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams.
1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SCOPE
1.1 This guide outlines a method for developing a Surveillance and Maintenance (SM) plan for inactive nuclear facilities. It describes the steps and activities necessary to prevent loss or release of radioactive or hazardous materials, and to minimize physical risks between the deactivation phase and the start of facility decontamination and decommissioning (DD).
1.2 The primary concerns for SM are related to (1) animal intrusion, (2) structural integrity degradation, (3) water in-leakage, (4) contamination migration, (5) unauthorized personnel entry, and (6) theft/intrusion. This document is intended to serve as a guide only, and is not intended to modify existing regulations.

SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, ( 2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.
1.2 This standard guide is based on the "Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites," (Arnish, J. et.al., 2000) from which the analysis methodology and supporting data are taken.
1.3 Guide E 1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E 1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E 1760 and E 1278, and provides a more detailed approach for the release of concrete.

SIGNIFICANCE AND USE
The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities.
Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area at the completion of decommissioning activities.
SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.
1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.
1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:
1.3.1 alpha
1.3.2 beta (electrons)
1.3.3 gamma
1.3.4 characteristic x-rays
1.3.5 The measurement of neutron emissions is not included as part of this standard.
1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.
1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.

SIGNIFICANCE AND USE
Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing the optimum methods for decontamination and decommissioning, and estimating the resulting waste volumes and personnel exposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or deriving the above information.
Information on the proposed decommissioning methods, waste volumes, and estimated personnel radiation exposures can be used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This information may be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a function of the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.
SCOPE
1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses:  
1.1.1 the data quality objective for characterization as an initial step in decommissioning planing.  
1.1.2 sampling methods,  
1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and  
1.1.4 essential documentation of the characterization information.  
1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SCOPE
1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses:  
1.1.1 the data quality objective for characterization as an initial step in decommissioning planing.  
1.1.2 sampling methods,  
1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and  
1.1.4 essential documentation of the characterization information.  
1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SCOPE
1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from firther regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.

SCOPE
1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: 1- Development of an environmental baseline prior to commencement of decommissioning activities; 2- Determination of release paths from site activities and their associated exposure pathways in the environment; and 3- Selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.