ASTM E1281-89(1996)e1
(Guide)Standard Guide for Nuclear Facility Decommissioning Plans
Standard Guide for Nuclear Facility Decommissioning Plans
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.
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e1
Designation:E1281–89 (Reapproved 1996)
Standard Guide for
Nuclear Facility Decommissioning Plans
This standard is issued under the fixed designation E 1281; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
e NOTE—Keywords were added editorially in March 1996.
INTRODUCTION
As a nuclear facility approaches the end of its operational life, the operator should initiate final
preparations for decommissioning. As part of this program, a decommissioning plan should be
developed to comply with applicable federal and state requirements and regulations, as well as to
provide generic and detailed information relevant to decommissioning project planning.This standard
is a guideline for the preparation and content of the decommissioning plan.
1. Scope E 1167 Guide for Radiation Protection Program for Decom-
missioning Operations
1.1 This guide applies to decommissioning plans for any
E 1168 Guide for Radiological Protection Training for
nuclear facility whose operation was (is) governed by Nuclear
Nuclear Facility Workers
Regulatory Commission (NRC) orAgreement State license, or
2.2 Code of Federal Regulations:
under Department of Energy (DOE) orders.
10 CFR 19 Notices, Instructions and Reports to Workers;
1.2 The guide applies to the preparation and content of the
Inspections
decommissioning plan document itself.
10 CFR 20 Standards for Protection Against Radiation
1.3 The detailed description and development of implemen-
10 CFR 30 Rules of General Applicability to Domestic
tation plans identified in Section 4 is outside the scope of this
Licensing of Byproduct Material
guide.
10 CFR 40 Domestic Licensing of Source Material
NOTE 1—Nuclear facilities operated by the U.S. DOE are not licensed
10 CFR 50 Domestic Licensing of Production and Utiliza-
by the U.S. NRC, nor are other nuclear facilities which may come under
tion Facilities
the control of the U.S. Department of Defense or individual agreement
10 CFR51LicensingandRegulatoryPolicyandProcedures
states. The references in this guide to licensee, U.S. NRC Regulatory
for Environmental Protection
guides, and Title 10 of the U.S. Code of Federal Regulations are to imply
10 CFR 70 Domestic Licensing of Special Nuclear Material
appropriate alternative nomenclature with respect to DOE, DOD, or
agreement state nuclear facilities. This distinction should not alter the
10 CFR 71 Packaging of Radioactive Material forTransport
content of decommissioning plans for nuclear facilities.
and Transportation of Radioactive Materials Under Cer-
tain Conditions
1.4 This standard does not purport to address all of the
10 CFR 73 Physical Protection Requirements
safety concerns, if any, associated with its use. It is the
10 CFR 140 Financial Protection Requirements
responsibility of the user of this standard to establish appro-
10 CFR 150 Exemption and Continued Regulatory Author-
priate safety and health practices and determine the applica-
ity in Agreement States Under Section 274
bility of regulatory limitations prior to use.
10 CFR 170 Fees and Facilities and Material Licenses and
2. Referenced Documents
Other Regulatory Services Under the Atomic Energy Act
2.1 ASTM Standards: of 1954, as Amended
40 CFR 190 Environmental Radiation Protection Standards
E 1034 Specification for Nuclear Facility Transient Worker
Records for Nuclear Power Operations
40 CFR 191 Environmental Radiation Protection Standards
for Management and Disposal of Spent Nuclear Fuel,
High Level Waste and Transuranic Waste
This guide is under the jurisdiction of Committee E-10on Nuclear Technology
and Applications and is the direct responsibility of Subcommittee E10.03 on
Radiological Protection for Decontamination and Decommissioning of Nuclear
Facilities and Components.
Current edition approved March 6, 1989. Published May 1989. Available from Superintendent of Documents, U.S. Government Printing
Annual Book of ASTM Standards, Vol 12.02. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E1281
40 CFR 192 Health and Environmental Protection for Ura- uranium/thorium mills, UF-6 production and enrichment
nium and Thorium Mill Tailings plants, radiochemical laboratories, and radioactive waste dis-
posal sites.
49 CFR 170 Hazardous Materials Regulations—DOT to
3.1.6 safe storage, n—consists of placing and maintaining
the facility in protective storage. Initial safe storage operations
2.3 Nuclear Regulatory Commission Standard:
would consist of general plant decontamination activities,
NRC Regulatory Guide 1.86, Termination of Operating
radiation surveys, the processing and removal of radioactive
Licenses for Nuclear Power Plants
waste materials, securing a possession-only license, and the
2.4 Department of Energy Standard:
implementation of security, surveillance, and maintenance
DOE Order 5820.2 Radioactive Waste Management, Chap-
plans for the delay period. Decommissioning is completed by
ter V, Decontamination and Decommissioning of Surplus
dismantling following the protective storage period. The addi-
Facilities
tional activities initiated after 30 or more years would be
essentially the same as those described for entombment, except
3. Terminology
that there would be more systems removed after safe storage
3.1 Definitions of Terms Specific to This Standard:
than after entombment.
3.1.1 decommission, vt—to remove a nuclear facility safely
from service and reduce residual radioactivity to levels that
4. Significance and Use
permit release of the property or facility for unrestricted use
4.1 The standardization of decommissioning plans will
and termination of any applicable license(s).
provide the nuclear facility owner with a greater assurance that
3.1.2 decontamination, n—those activities employed to re-
all basic planning elements and requirements have been
duce the levels of (radioactive) contamination in or on struc-
identified, examined, and addressed.
tures, equipment, materials, and personnel.
4.2 In applying the guidance contained in this standard, the
3.1.3 dismantlement, n—the alternative in which the equip-
nuclear facility owner will address the significant subject areas
ment, structures, and portions of a facility and site containing
necessary to describe a comprehensive decommissioning plan.
radioactive contaminants are removed or decontaminated to a
4.3 This decommissioning plan will be developed to serve
level that permits the property to be released for unrestricted
as the executive document that describes the objectives of the
use shortly after cessation of operations.
decommissioning program and identifies and defines the ele-
3.1.4 entombment, n—consists of placing the facility into
ments necessary to accomplish the program.
protective storage. Initial entombment activities consist of
4.4 A detailed implementation plan describing how the
removing the balance of plant contaminated components,
objectives of the decommissioning plan will be met should be
systems, and structures from the site and sealing all the
prepared. Some of the documents or implementation plans that
remaining contaminated and activated plant components and
may be required to support the overall decommissioning
systems within the entombment boundary. This structure pro-
program include an engineering plan; a cost, schedule, and
vides for containment of the entire radioactive inventory
financing plan; a field implementation plan; a health and safety
remaining on site during the entombment period. Other initial
plan; a quality assurance plan (for example, Guide E 1167); an
activities would consist of processing and removing radioac-
emergency plan; an environmental report; a radiological pro-
tive waste, securing a possession-only license, and implement-
tection plan; and a physical security plan. These implementa-
ing security and surveillance plans for the delay period.
tion plans shall be separate from and consistent with the
Decommissioning is completed by either radioactive decay to
decommissioning plan.
unrestricted use levels or by dismantlement to unrestricted use
levels. If dismantlement were selected following entombment,
5. Elements of the Decommissioning Plan
additional activities would be initiated after 30 or more years
5.1 The plan should identify and describe the major ele-
andwouldconsistofradiationsurveys,removaloftheentomb-
ment structure and materials within it, processing and removal ments of the decommissioning program. These elements
of any remaining solid and liquid radioactive wastes, and should be addressed in their approximate chronological order
restoring/releasing the site for unrestricted use. and should be expanded to provide descriptive information and
3.1.5 nuclear facility, n—a facility whose operations in- details.
volve (or involved) radioactive materials in such form or 5.2 The following are provided as typical decommissioning
quantity that a radiological hazard potentially exists to the elements for some types of nuclear facilities:
employees or the general public. Included are facilities that are 5.2.1 Facility description,
(or were) used to produce, process, or store radioactive
5.2.2 Operating history, and
materials. Some examples are nuclear reactors (power, test, or
5.2.3 Adescription of the history of operation at the nuclear
research), fuel fabrication plants, fuel reprocessing plants,
facility should be included to provide general information and
an indication of the scope of effort required for decommission-
ing.This description should include the initial construction and
licensing history, the operating record, and a summary of all
Available from Nuclear Regulatory Commission, Public Document Room,
operating events that could affect decommissioning activities
1717 H St., N.W., Washington, DC 20555.
(such as spills or releases of radioactive or contaminated
Available from Dept. of Energy, National Technical Information Service, U.S.
Dept. of Commerce, Springfield, VA 22161. materials).
E1281
6. Characterization 9.2 Cost Estimate—Asummary of the detailed, site-specific
decommissioning cost estimate should be provided. A copy of
6.1 Adescription of the entire nuclear facility to be decom-
the detailed cost estimate may be referenced or provided as an
missioned should be provided including results of a radiation
appendix.
survey prior to initiation of other decommissioning activities.
Site characteristics that should be addressed include topogra-
10. Decommissioning Activities
phy, soils and geology, hydrology, seismology, demography,
and meteorology. Specific details such as those found in safety 10.1 The plan should address the major activities of the
decommissioning program. A typical list of decommissioning
analysis reports may be provided in appendices or by refer-
ence. Plant characteristics that should be addressed include a activities is presented in Appendix X1.
10.2 The plan should include a concise description of how
general plant description, a plant structures description, and a
these major activities will be carried out in a manner that
plant systems description. Radiological and hazardous material
protects the worker and public health and safety. Persons or
characteristics of the nuclear facility shall be included as well.
organizations responsible for each activity should be desig-
The radionuclide inventory for the facility should be presented
nated.
with all of the major contributors identified and quantified.
Environmental radiological characteristics of the site should be
11. Facility Modification
discussed.
11.1 The plan should identify major additions to the facility
7. Program Objectives
in support of decommissioning operations. Changes to the
7.1 The objective(s) of the decommissioning program facility resulting from decommissioning activities (such as
removal of structures and systems) need not be addressed
should be stated concisely. The selected or proposed decom-
missioning alternative (dismantlement, safe storage followed herein.
by dismantlement, or entombment to unrestricted use levels) 11.2 Examples of major facility modifications to be identi-
shall be included as a minimum. fied include additions of a waste processing facility, a waste
7.2 A qualitative description of any interim status of the staging/storage facility, a water cleanup/clarification facility, or
acaskhandling/stagingfacility.Theamountofdetailnecessary
facility should be provided when applicable, that is, when the
safe storage or entombment alternatives are selected, and when will vary, depending on the type of modification. In general,
however, the information should be adequate to describe the
a surveillance/maintenance period is proposed for the facility.
7.3 Cleanup criteria should be stated herein, such as NRC extent and purpose of the modification, including the decom-
missioning of these modifications. Detailed design and analyti-
Regulatory Guide 1.86, or other specific federal and state
requirements. Termination survey requirements should be as cal information may be provided as appendices.
detailed in 13.5.
12. Waste Management
7.4 The interim and ultimate desired status of all facility
licenses should be discussed. For facilities where the unre-
12.1 Radioactive Materials—Anticipated types, quantities,
stricted release criteria will be achieved without a planned and
and dose rate ranges of radioactive waste materials should be
significant delay period, this should be stated. For this case, an
identified. Projected dispositions of these materials should also
ongoing surveillance/maintenance program will not be neces-
be identified with respect to packaging, interim storage, trans-
sary.
portation, and disposal.
12.2 Radioactive Hazardous Materials—Anticipated types,
8. Program Management and Administration
quantities, and dose rate ranges of radioactive hazardous
8.1 The decommissioning plan should include a description materials should be identified. Expected dispositions of these
of the organization and responsibilities with respect to the materials should also be identified with respect to treatment,
overall program.The discussion should address the decommis- packaging, interim storage, transportation, and disposal.
sioning project team, decommissioning manpower; worker 12.3 Hazardous Materials—Anticipated types and quanti-
health and safety training (for example, Specification E 1034 ties of hazardous waste materials should be identified. Ex-
pected dispositions of
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