ASTM E1281-89(2005)
(Guide)Standard Guide for Nuclear Facility Decommissioning Plans
Standard Guide for Nuclear Facility Decommissioning Plans
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.
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Standards Content (Sample)
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Designation:E1281–89 (Reapproved 2005)
Standard Guide for
Nuclear Facility Decommissioning Plans
This standard is issued under the fixed designation E1281; 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 (´) indicates an editorial change since the last revision or reapproval.
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 E1034 Specification for Nuclear Facility Transient Worker
Records
1.1 This guide applies to decommissioning plans for any
E1167 Guide for Radiation Protection Program for Decom-
nuclear facility whose operation was (is) governed by Nuclear
missioning Operations
Regulatory Commission (NRC) orAgreement State license, or
E1168 Guide for Radiological Protection Training for
under Department of Energy (DOE) orders.
Nuclear Facility Workers
1.2 The guide applies to the preparation and content of the
2.2 Code of Federal Regulations:
decommissioning plan document itself.
10 CFR 19 Notices, Instructions and Reports to Workers;
1.3 The detailed description and development of implemen-
Inspections
tation plans identified in Section 4 is outside the scope of this
10 CFR 20 Standards for Protection Against Radiation
guide.
10 CFR 30 Rules of General Applicability to Domestic
NOTE 1—Nuclear facilities operated by the U.S. DOE are not licensed
Licensing of Byproduct Material
by the U.S. NRC, nor are other nuclear facilities which may come under
10 CFR 40 Domestic Licensing of Source Material
the control of the U.S. Department of Defense or individual agreement
10 CFR 50 Domestic Licensing of Production and Utiliza-
states. The references in this guide to licensee, U.S. NRC Regulatory
tion Facilities
guides, and Title 10 of the U.S. Code of Federal Regulations are to imply
10 CFR 51 Licensing and Regulatory Policy and Proce-
appropriate alternative nomenclature with respect to DOE, DOD, or
agreement state nuclear facilities. This distinction should not alter the
dures for Environmental Protection
content of decommissioning plans for nuclear facilities.
10CFR70 DomesticLicensingofSpecialNuclearMaterial
10 CFR 71 Packaging of Radioactive Material for Trans-
1.4 This standard does not purport to address all of the
port and Transportation of Radioactive Materials Under
safety concerns, if any, associated with its use. It is the
Certain Conditions
responsibility of the user of this standard to establish appro-
10 CFR 73 Physical Protection Requirements
priate safety and health practices and determine the applica-
10 CFR 140 Financial Protection Requirements
bility of regulatory limitations prior to use.
10 CFR 150 Exemption and Continued RegulatoryAuthor-
2. Referenced Documents
ity in Agreement States Under Section 274
2.1 ASTM Standards: 10 CFR 170 Fees and Facilities and Material Licenses and
Other Regulatory Services Under the Atomic Energy Act
of 1954, as Amended
40 CFR 190 Environmental Radiation Protection Standards
This guide is under the jurisdiction of Committee E10 on Nuclear Technology
and Applications and is the direct responsibility of Subcommittee E10.03 on
for Nuclear Power Operations
Radiological Protection for Decontamination and Decommissioning of Nuclear
40 CFR 191 Environmental Radiation Protection Standards
Facilities and Components.
for Management and Disposal of Spent Nuclear Fuel,
Current edition approved Aug. 1, 2005. Published August 2005. Originally
´1
High Level Waste and Transuranic Waste
approved in 1989. Last previous edition approved in 1996 as E1281-89(1996) .
DOI: 10.1520/E1281-89R05.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on Available from Superintendent of Documents, U.S. Government Printing
the ASTM website. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E1281–89 (2005)
40 CFR 192 Health and Environmental Protection for (or were) used to produce, process, or store radioactive
Uranium and Thorium Mill Tailings materials. Some examples are nuclear reactors (power, test, or
49 CFR 170 Hazardous Materials Regulations—DOT to research), fuel fabrication plants, fuel reprocessing plants,
190 uranium/thorium mills, UF-6 production and enrichment
2.3 Nuclear Regulatory Commission Standards: plants, radiochemical laboratories, and radioactive waste dis-
NRC Regulatory Guide 1.86, Termination of Operating posal sites.
Licenses for Nuclear Power Plants 3.1.6 safe storage, n—consists of placing and maintaining
NUREG-1727 NMSS Decommissioning Standard Review the facility in protective storage. Initial safe storage operations
Plan (NRC 2000) would consist of general plant decontamination activities,
Regulatory Guide 1.179 Standard Format and Content for radiation surveys, the processing and removal of radioactive
License Termination Plans for Nuclear Power Reactors waste materials, securing a possession-only license, and the
(NRC 1999) implementation of security, surveillance, and maintenance
2.4 Department of Energy Standard: plans for the delay period. Decommissioning is completed by
DOE Order 5820.2 Radioactive Waste Management, Chap- dismantling following the protective storage period. The addi-
ter V, Decontamination and Decommissioning of Surplus tional activities initiated after 30 or more years would be
Facilities essentiallythesameasthosedescribedforentombment,except
that there would be more systems removed after safe storage
3. Terminology
than after entombment.
3.1 Definitions of Terms Specific to This Standard:
4. Significance and Use
3.1.1 decommission, vt—to remove a nuclear facility safely
4.1 The standardization of decommissioning plans will
from service and reduce residual radioactivity to levels that
provide the nuclear facility owner with a greater assurance that
permit release of the property or facility for unrestricted use
all basic planning elements and requirements have been
and termination of any applicable license(s).
identified, examined, and addressed.
3.1.2 decontamination, n—those activities employed to re-
4.2 In applying the guidance contained in this standard, the
duce the levels of (radioactive) contamination in or on struc-
nuclear facility owner will address the significant subject areas
tures, equipment, materials, and personnel.
necessary to describe a comprehensive decommissioning plan.
3.1.3 dismantlement, n—the alternative in which the equip-
Additional guidance on the planning of decommissioning
ment, structures, and portions of a facility and site containing
projects, and the preparation of decommissioning plans can be
radioactive contaminants are removed or decontaminated to a
found in such references as NUREG-1727 on decommission-
level that permits the property to be released for unrestricted
ing standard review plans, and Regulatory Guide 1.179 on the
use shortly after cessation of operations.
format and content of license termination plans. Recent new
3.1.4 entombment, n—consists of placing the facility into
guidance on all aspects of decommissioning is contained in an
protective storage. Initial entombment activities consist of
ASME publication titled The Decommissioning Handbook.
removing the balance of plant contaminated components,
4.3 This decommissioning plan will be developed to serve
systems, and structures from the site and sealing all the
as the executive document that describes the objectives of the
remaining contaminated and activated plant components and
decommissioning program and identifies and defines the ele-
systems within the entombment boundary. This structure pro-
ments necessary to accomplish the program.
vides for containment of the entire radioactive inventory
4.4 A detailed implementation plan describing how the
remaining on site during the entombment period. Other initial
objectives of the decommissioning plan will be met should be
activities would consist of processing and removing radioac-
prepared. Some of the documents or implementation plans that
tive waste, securing a possession-only license, and implement-
may be required to support the overall decommissioning
ing security and surveillance plans for the delay period.
program include an engineering plan; a cost, schedule, and
Decommissioning is completed by either radioactive decay to
financing plan; a field implementation plan; a health and safety
unrestricted use levels or by dismantlement to unrestricted use
plan; a quality assurance plan (for example, Guide E1167); an
levels. If dismantlement were selected following entombment,
emergency plan; an environmental report; a radiological pro-
additional activities would be initiated after 30 or more years
tection plan; and a physical security plan. These implementa-
andwouldconsistofradiationsurveys,removaloftheentomb-
tion plans shall be separate from and consistent with the
ment structure and materials within it, processing and removal
decommissioning plan.
of any remaining solid and liquid radioactive wastes, and
restoring/releasing the site for unrestricted use.
5. Elements of the Decommissioning Plan
3.1.5 nuclear facility, n—a facility whose operations in-
5.1 The plan should identify and describe the major ele-
volve (or involved) radioactive materials in such form or
ments of the decommissioning program. These elements
quantity that a radiological hazard potentially exists to the
should be addressed in their approximate chronological order
employees or the general public. Included are facilities that are
and should be expanded to provide descriptive information and
details.
Available from Nuclear Regulatory Commission, Public Document Room,
1717 H St., N.W., Washington, DC 20555.
5 6
Available from Dept. of Energy, National Technical Information Service, U.S. Taboas,A. L., Moghissi,A.A., and LaGuardia, T. S., Eds.,ASME, Three Park
Dept. of Commerce, Springfield, VA 22161. Ave., New York, NY, 2004.
E1281–89 (2005)
5.2 The following are provided as typical decommissioning subcontractors. When safe storage or entombment alternatives
elements for some types of nuclear facilities: areselected,thentheorganizationandresponsibilitiesstructure
5.2.1 Facility description, for the protected storage and delayed dismantlement phases of
5.2.2 Operating history, and the program should be provided as well.
5.2.3 Adescription of the history of operation at the nuclear
9. Program Schedule and Cost
facility should be included to provide general information and
an indication of the scope of effort required for decommission-
9.1 Major Milestone Schedule—The plan should include
ing.Thisdescriptionshouldincludetheinitialconstructionand
decommissioningscheduleinformation.Identificationofmajor
licensing history, the operating record, and a summary of all
decommissioning phase start and finish dates as well as major
operating events that could affect decommissioning activities
decommissioning task milestones should be addressed. A
(such as spills or releases of radioactive or contaminated
figure or chart as well as a written explanation should be
materials).
provided. A logic diagram may be included to depict the
sequence of activities.
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
analysis reports may be provided in appendices or by refer-
decommissioning program. A typical list of decommissioning
ence. Plant characteristics that should be addressed include a
activities is presented in Appendix X1.
general plant description, a plant structures description, and a
10.2 The plan should include a concise description of how
plant systems description. Radiological and hazardous material
these major activities will be carried out in a manner that
characteristics of the nuclear facility shall be included as well.
protects the worker and public health and safety. Persons or
The radionuclide inventory for the facility should be presented
organizations responsible for each activity should be desig-
with all of the major contributors identified and quantified.
nated.
Environmental radiological characteristics of the site should be
discussed.
11. Facility Modification
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
should be stated concisely. The selected or proposed decom-
removal of structures and systems) need not be addressed
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
facility should be provided when applicable, that is, when the
acaskhandling/stagingfacility.Theamountofdetailnecessary
safe storage or entombment alternatives are selected, and when
will vary, depending on the type of modification. In general,
a surveillance/maintenance period is proposed for the facility.
however, the information should be adequate to describe the
7.3 Cleanup criteria should be stated herein, such as NRC
extent and purpose of the modification, including the decom-
Regulatory Guide 1.86, or other specific federal and stat
...
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