ASTM E1281-15(R2021) pdf free download

ASTM E1281-15(R2021) pdf free download.Standard Guide for Nuclear Facility Decommissioning Plans
1. 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 ofEnergy (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 implemen- tation plans identified in Section 4 is outside the scope of this guide. N OTE 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 ofFederal 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 appro- priate safety, health, and environmental practices and deter- mine the applicability ofregulatory limitations prior to use. 1.5 This international standard was developed in accor- dance with internationally recognized principles on standard- ization established in the Decision on Principles for the Development of International Standards, Guides and Recom- mendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
3. Terminology
3.1 Definitions ofTerms Specific to This Standard: 3.1.1 decommission, vt—to remove a nuclear facility safely from service and reduce residual radioactivity to levels that permit release of the property or facility for unrestricted use and termination of any applicable license(s). 3.1.2 decontamination, n—those activities employed to re- duce the levels of (radioactive) contamination in or on structures, equipment, materials, and personnel. 3.1.3 dismantlement, n—the alternative in which the equipment, structures, and portions of a facility and site containing radioactive contaminants are removed or decon- taminated to a level that permits the property to be released for unrestricted use shortly after cessation of operations. 3.1.4 entombment, n—consists of placing the facility into protective storage. Initial entombment activities consist of removing the balance of plant contaminated components, systems, and structures from the site and sealing all the remaining contaminated and activated plant components and systems within the entombment boundary. This structure pro- vides for containment of the entire radioactive inventory remaining on site during the entombment period. Other initial activities would consist of processing and removing radioac- tive waste, securing a possession-only license, and implement- ing security and surveillance plans for the delay period. Decommissioning is completed by either radioactive decay to unrestricted use levels or by dismantlement to unrestricted use levels. If dismantlement were selected following entombment, additional activities would be initiated after 30 or more years and would consist ofradiation surveys, removal ofthe entomb- ment structure and materials within it, processing and removal of any remaining solid and liquid radioactive wastes, and restoring/releasing the site for unrestricted use.3.1.5 nuclearfacility, n—a facility whose operations involve (or involved) radioactive materials in such form or quantity that a radiological hazard potentially exists to the employees or the general public. Included are facilities that are (or were) used to produce, process, or store radioactive materials. Some examples are nuclear reactors (power, test, or research), fuel fabrication plants, fuel reprocessing plants, uranium/thorium mills, UF-6 production and enrichment plants, radiochemical laboratories, and radioactive waste disposal sites. 3.1.6 safe storage, n—consists of placing and maintaining the facility in protective storage. Initial safe storage operations would consist of general plant decontamination activities, radiation surveys, the processing and removal of radioactive waste materials, securing a possession-only license, and the implementation of security, surveillance, and maintenance plans for the delay period. Decommissioning is completed by dismantling following the protective storage period. The addi- tional activities initiated after 30 or more years would be essentially the same as those described for entombment, except that there would be more systems removed after safe storage than after entombment.