ASTM C1562-10(2018)
(Guide)Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
SIGNIFICANCE AND USE
5.1 Information is provided in this document and other referenced documents to assist the licensee and the licensor in analyzing the materials aspects of performance of SNF and DCSS components during extended storage. The effects of the service conditions of the first licensing period are reviewed in the license renewal process. These service conditions are highlighted and discussed in Annex A1 as factors that affect materials performance in an ISFSI. Emphasis is on the effects of time, temperature, radiation, and the environment on the condition of the SNF and the performance of components of ISFSI storage systems.
5.2 The storage of SNF that is irradiated under the regulations of 10 CFR Part 50 is governed by regulations in 10 CFR Part 72. Regulatory requirements for the subsequent geologic disposal of this SNF are presently given in 10 CFR Part 60, with specific requirements for the use of Yucca Mountain as a repository being given in the regulatory requirements of 10 CFR Part 63. Between the life-cycle phases of storage and disposal, SNF may be transported under the requirements of 10 CFR Part 71. Therefore, in storage, it is important to acknowledge the transport and disposal phases of the life cycle. In doing this, the materials properties that are important to these subsequent phases are to be considered in order to promote successful completion of these subsequent phases in the life cycle of SNF. Retrievability of SNF (or high-level radioactive waste) is set as a requirement in 10 CFR Part 72.122(g)(5) and 10 CFR Part 72.122(l). Care should be taken in operations conducted prior to disposal, for example, storage, transfer, and transport, to ensure that the SNF is not abused and that SNF assemblies will be retrievable, the protective value of the cladding is not degraded and remains capable of serving as an active barrier to radionuclide release during transfer and transport operations. It is possible that cladding could be altered during dry storage. The ...
SCOPE
1.1 Part of the total inventory of commercial spent nuclear fuel (SNF) is stored in dry cask storage systems (DCSS) under licenses granted by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this guide is to provide information to assist in supporting the renewal of these licenses, safely and without removal of the SNF from its licensed confinement, for periods beyond those governed by the term of the original license. This guide provides information on materials behavior under conditions that may be important to safety evaluations for the extended service of the renewal period. This guide is written for DCSS containing light water reactor (LWR) fuel that is clad in zirconium alloy material and stored in accordance with the Code of Federal Regulations (CFR), at an independent spent-fuel storage installation (ISFSI).2 The components of an ISFSI, addressed in this document, include the commercial SNF, canister, cask, and all parts of the storage installation including the ISFSI pad. The language of this guide is based, in part, on the requirements for a dry SNF storage license that is granted, by the U.S. Nuclear Regulatory Commission (NRC), for up to 20 years. Although government regulations may differ for various nations, the guidance on materials properties and behavior given here is expected to have broad applicability.
1.2 This guide addresses many of the factors affecting the time-dependent behavior of materials under ISFSI service [10 CFR Part 72.42]. These factors are those regarded to be important to performance, in license extension, beyond the currently licensed 20-year period. Examples of these factors are given in this guide and they include materials alterations or environmental conditions for components of an ISFSI system that, over time, could have significance related to safety. For purposes of this guide, a license period of an additional 20 to 80 years is assumed.
1.3 This guide address...
General Information
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Standards Content (Sample)
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.
Designation: C1562 − 10 (Reapproved 2018)
Standard Guide for
Evaluation of Materials Used in Extended Service of Interim
Spent Nuclear Fuel Dry Storage Systems
This standard is issued under the fixed designation C1562; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 1.3 Thisguideaddressesthedeterminationoftheconditions
of the spent fuel and storage cask materials at the end of the
1.1 Part of the total inventory of commercial spent nuclear
initial20-yearlicenseperiodastheresultofnormaleventsand
fuel (SNF) is stored in dry cask storage systems (DCSS) under
conditions. However, the guide also addresses the analysis of
licenses granted by the U.S. Nuclear Regulatory Commission
potentialspentfuelandcaskmaterialsdegradationastheresult
(NRC). The purpose of this guide is to provide information to
of off-normal, and accident-level events and conditions that
assist in supporting the renewal of these licenses, safely and
may occur during any period.
without removal of the SNF from its licensed confinement, for
periods beyond those governed by the term of the original
1.4 This guide provides information on materials behavior
license.This guide provides information on materials behavior
to support continuing compliance with the safety criteria,
under conditions that may be important to safety evaluations
which are part of the regulatory basis, for licensed storage of
for the extended service of the renewal period. This guide is
SNFatanISFSI.Thesafetyfunctionsaddressedanddiscussed
written for DCSS containing light water reactor (LWR) fuel
in this standard guide include thermal performance, radiologi-
that is clad in zirconium alloy material and stored in accor-
cal protection, confinement, sub-criticality, and retrievability.
dance with the Code of Federal Regulations (CFR), at an
The regulatory basis includes 10 CFR Part 72 and supporting
independent spent-fuel storage installation (ISFSI). The com-
regulatoryguidesoftheU.S.NuclearRegulatoryCommission.
ponents of an ISFSI, addressed in this document, include the
Therequirementssetforthinthesedocumentsindicatethatthe
commercial SNF, canister, cask, and all parts of the storage
installationincludingtheISFSIpad.Thelanguageofthisguide following items were considered in the original licensing
is based, in part, on the requirements for a dry SNF storage
decisions: properties of materials, design considerations for
license that is granted, by the U.S. Nuclear Regulatory Com-
normal and off-normal service, operational and natural events,
mission (NRC), for up to 20 years. Although government
and the bases for the original calculations. These items may
regulations may differ for various nations, the guidance on
require reconsideration of the safety-related arguments that
materials properties and behavior given here is expected to
demonstratehowthesystemscontinuetosatisfytheregulatory
have broad applicability.
requirements. Further, to ensure continued safe operation, the
1.2 This guide addresses many of the factors affecting the
performance of materials must be justified in relation to the
time-dependent behavior of materials under ISFSI service [10
effects of time, temperature, radiation field, and environmental
CFR Part 72.42]. These factors are those regarded to be
conditions of normal and off-normal service. Arguments for
important to performance, in license extension, beyond the
long-term performance must account for materials alterations
currently licensed 20-year period. Examples of these factors
(especially degradations) that are expected during the service
aregiveninthisguideandtheyincludematerialsalterationsor
periods, which include the periods of the initial license and of
environmental conditions for components of an ISFSI system
the license renewal. This guide pertains only to structures,
that, over time, could have significance related to safety. For
systems, and components important to safety during extended
purposes of this guide, a license period of an additional 20 to
storage period and during retrieval functions, including trans-
80 years is assumed.
port and transfer operations. Materials information that per-
tains to safety functions, including retrieval functions, is
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
pertinent to current regulations and to license renewal process,
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
High Level Waste.
andthisinformationisthefocusoftheguide.Thisguideisnot
Current edition approved Sept. 1, 2018. Published October 2018. Originally
intended to supplant the existing regulatory process.
approved in 2003. Last previous edition approved in 2010 as C1562–10. DOI:
10.1520/C1562-10R18.
1.5 This international standard was developed in accor-
In general fuels of higher burnup (>45 MWd/kgU) and MOX fuels are not
dance with internationally recognized principles on standard-
included in this guide. Guidance for these fuels are expected to be included in an
Annex to be written later. ization established in the Decision on Principles for the
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1562 − 10 (2018)
Development of International Standards, Guides and Recom- ACI 349-00Code Requirements for Nuclear Safety Related
mendations issued by the World Trade Organization Technical Concrete Structures
Barriers to Trade (TBT) Committee. ACI 359-01 Code for Concrete Reactor Vessels and
Containments, also designated asASME Boiler and Pres-
2. Referenced Documents
sure Vessel Code, Section III, Div 2, Code for Concrete
Reactor Vessels and Containments
2.1 ASTM Standards:
2.5 ANSI Documents:
C33/C33MSpecification for Concrete Aggregates
ANSI/ANS-6.4-1985Guidelines on the Nuclear Analysis
C227 Test Method for Potential Alkali Reactivity of
and Design of Concrete Radiation Shielding for Nuclear
Cement-Aggregate Combinations (Mortar-Bar Method)
Power Plants
C295/C295MGuide for Petrographic Examination of Ag-
ANSI/ANS-57.9Design Criteria for an Independent Spent
gregates for Concrete
Fuel Storage Installation (Dry Storage Type)
C859Terminology Relating to Nuclear Materials
ANSI/ANS-57.10DesignCriteriaforConsolidationofLWR
C1174PracticeforEvaluationoftheLong-TermBehaviorof
Spent Fuel
Materials Used in Engineered Barrier Systems (EBS) for
2.6 Other Documents:
Geological Disposal of High-Level Radioactive Waste
ASME-B&PV Sect III-Div 2 (2001)Code for Concrete
2.2 Government Documents:
Reactor Vessels and Containments
10 CFR Part 50Domestic Licensing of Production and
EPRI-1994Class I Structures License Renewal Industry
Utilization Facilities
Report; Revision 1, TR-103842, July 1994
10 CFR Part 60Disposal of High Level Radioactive Wastes
in Geologic Repositories
3. Terminology
10 CFR Part 63Disposal of High Level Radioactive Wastes
3.1 The terminology of Terminology C859 applies to this
in a Proposed Geologic Repository in Yucca Mountain
document except as given below.
10 CFR Part 71Packaging and Transport of Radioactive
Materials
3.2 Definitions of Terms Specific to This Standard:
10CFRPart72LicensingRequirementsfortheIndependent
3.2.1 accident-level events or conditions—theextremelevel
Storage of Spent Nuclear Fuel and High-Level Radioac-
of an event or condition for which there is a specified
tive Waste
resistance, limit of response, and requirement for a given level
2.3 NUREG Standards:
of continuing capability, which exceed “off-normal” events or
NUREG-1536Standard Review Plan for Dry Storage Cask
conditions. They include both design basis accidents and
Systems, January 1997
design-basis for natural phenomena events and conditions.
NUREG-1567Standard Review Plan for Spent Fuel Dry
NUREG-1536, NUREG-1567
Storage Facilities, Report, January 1998
NOTE 1—Specific accident conditions to be addressed have been
NUREG-1571Information Handbook on Independent Spent
evaluated for each dry cask storage system (DCSS) and are documented
Fuel Storage Installations
in a Safety Analysis Report for that system.
NUREG/CR-6407Classification of Transportation Packag-
3.2.2 alteration mode—a particular form of alteration, for
ing and Dry Spent Fuel Storage System Components
example, general corrosion, passivation. C1174
According to Importance to Safety, February, 1996, INEL
3.2.3 ASTM guide—a compendium of information or series
Report 95/0551
ofoptionsthatdoesnotrecommendaspecificcourseofaction.
ISG-1Interim Staff Guidance Number 1, U.S. NRC, Spent
3.2.4 canister—in a dry cask storage system (DCSS) for
Fuel Project Office
spent nuclear fuel, a metal cylinder that is sealed at both ends
2.4 American Concrete Institute Standards:
and is used to perform the function of confinement, while a
ACI 201.2R-97Guide to Durable Concrete
separate overpack performs the functions of shielding and
ACI 209R-97Prediction of Creep, Shrinkage and Tempera-
protection of the canister from the effects of impact loading.
ture Effects in Concrete Structures
ACI 301-99Building Code Requirements for Reinforced
3.2.5 cask—in a dry cask storage system (DCSS) for spent
Concrete
nuclear fuel, a stand-alone device that performs the functions
ACI 318-02Building Code Requirements for Reinforced
of confinement, radiological shielding, and physical protection
Concrete
of spent fuel during normal, off-normal, and accident
conditions. NUREG-1571
3.2.6 certificate of compliance—in a dry cask storage sys-
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 tem (DCSS) for spent nuclear fuel, a certificate issued by the
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website.
4 7
AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments, Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:// 4th Floor, New York, NY 10036, http://www.ansi.org.
www.access.gpo.gov. Available from American Society of Mechanical Engineers (ASME), ASME
Available from National Technical Information Service (NTIS), 5285 Port International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
Royal Rd., Springfield, VA 22161, http://www.ntis.gov. www.asme.org.
6 9
AvailablefromAmericanConcreteInstitute(ACI),P.O.Box9094,Farmington Available from Electric Power Research Institute (EPRI), 3512 HillviewAve.,
Hills, MI 48333-9094, http://www.aci-int.org. Palo Alto, CA 94304–1395.
C1562 − 10 (2018)
U.S. Nuclear Regulatory Commission (NRC) to the designer/ thereisacorrespondingmaximumspecifiedresistance,limitof
vendorofaspecificcaskmodelthatmeetstherequirementsset response, or requirement for a given level of continuing
forth in 10 CFR Part 72.236. capability. NUREG-1536
3.2.7 confinement—in a dry cask storage system (DCSS) for
NOTE 3—Specific off-normal conditions to be addressed have been
evaluated for each licensed DCSS and are documented in a Safety
spent nuclear fuel, the ability to prevent the release of
Analysis Report for that system.
radioactive substances into the environment. NUREG-1571
3.2.18 radiation shielding—in a dry cask storage system
3.2.8 confinement systems—in a dry cask storage system
(DCSS) for spent nuclear fuel, barriers to radiation, which are
(DCSS) for spent nuclear fuel, the assembly of components of
designed to meet the requirements of 10 CFR Parts 72.104(a),
thepackagingintendedtoretaintheradioactivematerialduring
and 72.106(b), and 72.128(a.2).
storage. These may include the cladding, storage system shell,
3.2.19 retrievability—in a dry cask storage system (DCSS)
bottom and lid, penetration covers, the closure welds or seals
for spent nuclear fuel, the ability to remove spent nuclear fuel
and bolts and other components. NUREG-1536
from storage for further processing or disposal. 10 CFR Part
3.2.9 criticality—in a dry cask storage system (DCSS) for
72.122 (1)
spent nuclear fuel, the condition wherein a system or medium
3.2.20 safety analysis report (SAR)—in a dry cask storage
is capable of sustaining a nuclear chain reaction. C859
system (DCSS) for spent nuclear fuel, the document that is
3.2.10 degradation—any change in the properties of a
supplied by a DCSS vendor or site-specific independent spent
material that adversely affects the behavior of that material;
fuel storage installation (ISFSI) applicant to the U.S. Nuclear
adverse alteration. C1174
Regulatory Commission (NRC) for analysis and confirming
3.2.11 degraded cladding—in spent nuclear fuel, cladding
calculations (review and approval). NUREG-1571
material that by visual inspection appears to be structurally
3.2.21 safetyevaluationreport(SER)—inadrycaskstorage
deformed or damaged to an extent that special handling is
system (DCSS) for spent nuclear fuel, the document that the
expected to be required. See ISG-1 for damaged fuel.
U.S. Nuclear Regulatory Commission (NRC) publishes after
3.2.12 dry cask storage system (DCSS)—in nuclear waste review of a Safety Analysis Report (SAR). NUREG-1571
management, a set of components that performs the functions
3.2.22 service conditions—in a dry cask storage system
of confinement, radiological shielding, and physical protection
(DCSS) for spent nuclear fuel, the time of service,
of spent nuclear fuel during normal, off-normal, and accident
temperatures, environmental conditions, radiation, and
conditions. Examples would include canister-based systems
loading, etc. that a component experiences during storage.
withtheirmetalorconcreteoverpackorvault,oranintegrated
3.2.23 spent nuclear fuel (SNF), spent fuel—nuclear fuel
cask.
that has undergone at least one year of decay since being used
3.2.13 dry storage—in nuclear waste management,thestor-
as a source of energy in a power reactor, and has not been
age of spent nuclear fuel after removal of the water from the
separated into its constituent elements by reprocessing.
fuel,claddingandallcomponentsofadrycaskstoragesystem,
NUREG-1571
and after the atmosphere has been replaced with an inert
NOTE 4—In this guide, only commercial light water reactor SNF that is
atmosphere.
clad in zirconium alloy material and has been removed from service is
considered.
3.2.14 independent spent fuel storage installation (ISFSI)—
any compl
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