ASTM C1562-10
(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
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.
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 hydrogen ...
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). 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 addresses ...
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Designation: C1562 − 10
Standard Guide for
Evaluation of Materials Used in Extended Service of Interim
1
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 that, over time, could have significance related to safety. For
purposes of this guide, a license period of an additional 20 to
1.1 Part of the total inventory of commercial spent nuclear
80 years is assumed.
fuel (SNF) is stored in dry cask storage systems (DCSS) under
1.3 Thisguideaddressesthedeterminationoftheconditions
licenses granted by the U.S. Nuclear Regulatory Commission
of the spent fuel and storage cask materials at the end of the
(NRC). The purpose of this guide is to provide information to
initial20-yearlicenseperiodastheresultofnormaleventsand
assist in supporting the renewal of these licenses, safely and
conditions. However, the guide also addresses the analysis of
without removal of the SNF from its licensed confinement, for
potentialspentfuelandcaskmaterialsdegradationastheresult
periods beyond those governed by the term of the original
of off-normal, and accident-level events and conditions that
license.This guide provides information on materials behavior
may occur during any period.
under conditions that may be important to safety evaluations
for the extended service of the renewal period. This guide is
1.4 This guide provides information on materials behavior
written for DCSS containing light water reactor (LWR) fuel
to support continuing compliance with the safety criteria,
that is clad in zirconium alloy material and stored in accor-
which are part of the regulatory basis, for licensed storage of
dance with the Code of Federal Regulations (CFR), at an
SNFatanISFSI.Thesafetyfunctionsaddressedanddiscussed
2
independent spent-fuel storage installation (ISFSI). The com-
in this standard guide include thermal performance, radiologi-
ponents of an ISFSI, addressed in this document, include the
cal protection, confinement, sub-criticality, and retrievability.
commercial SNF, canister, cask, and all parts of the storage
The regulatory basis includes 10 CFR Part 72 and supporting
installationincludingtheISFSIpad.Thelanguageofthisguide
regulatoryguidesoftheU.S.NuclearRegulatoryCommission.
is based, in part, on the requirements for a dry SNF storage
Therequirementssetforthinthesedocumentsindicatethatthe
license that is granted, by the U.S. Nuclear Regulatory Com-
following items were considered in the original licensing
mission (NRC), for up to 20 years. Although government
decisions: properties of materials, design considerations for
regulations may differ for various nations, the guidance on
normal and off-normal service, operational and natural events,
materials properties and behavior given here is expected to
and the bases for the original calculations. These items may
have broad applicability.
require reconsideration of the safety-related arguments that
demonstratehowthesystemscontinuetosatisfytheregulatory
1.2 This guide addresses many of the factors affecting the
requirements. Further, to ensure continued safe operation, the
time-dependent behavior of materials under ISFSI service [10
performance of materials must be justified in relation to the
CFR Part 72.42]. These factors are those regarded to be
effects of time, temperature, radiation field, and environmental
important to performance, in license extension, beyond the
conditions of normal and off-normal service. Arguments for
currently licensed 20-year period. Examples of these factors
long-term performance must account for materials alterations
aregiveninthisguideandtheyincludematerialsalterationsor
(especially degradations) that are expected during the service
environmental conditions for components of an ISFSI system
periods, which include the periods of the initial license and of
the license renewal. This guide pertains only to structures,
1
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
systems, and components important to safety during extended
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
storage period and during retrieval functions, including trans-
High Level Waste.
port and transfer operations. Materials information that per-
Current edition approved Jan. 1, 2010. Published March 2010. Originally
ε2
approved in 2003. Last previous edition approved in 2003 as C1562–03 . DOI:
tains to safety functions, including retrieval functions, is
10.1520/C1562-10.
pertinent to current regulations and to license renewal
...
This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
´2
Designation:C1562–03 Designation: C1562 – 10
Standard Guide for
Evaluation of Materials Used in Extended Service of Interim
1
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. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1
´ NOTE—Editorial changes were made throughout in October 2004.
2
´ NOTE—Editorial changes were made in July 2007.
1. 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
containinglightwaterreactor(LWR)fuelthatiscladinzirconiumalloymaterialandstoredinaccordancewiththeCodeofFederal
2
Regulations (CFR), at an independent spent-fuel storage installation (ISFSI). 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-yearperiod.Examplesofthesefactorsaregiveninthisguideandtheyincludematerialsalterationsorenvironmentalconditions
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 addresses the determination of the conditions of the spent fuel and storage cask materials at the end of the initial
20-year license period as the result of normal events and conditions. However, the guide also addresses the analysis of potential
spent fuel and cask materials degradation as the result of off-normal, and accident-level events and conditions that may occur
during any period.
1.4 This guide provides information on materials behavior to support continuing compliance with the safety criteria, which are
part of the regulatory basis, for licensed storage of SNF at an ISFSI. The safety functions addressed and discussed in this standard
guide include thermal performance, radiological protection, confinement, sub-criticality, and retrievability. The regulatory basis
includes 10 CFR Part 72 and supporting regulatory guides of the U.S. Nuclear Regulatory Commission.The requirements set forth
in these documents indicate that the following items were considered in the original licensing decisions: properties of materials,
design considerations for normal and off-normal service, operational and natural events, and the bases for the original calculations.
These items may require reconsideration of the safety-related arguments that demonstrate how the systems continue to satisfy the
regulatory requirements. Further, to ensure continued safe operation, the performance of materials must be justified in relation to
the effects of time, temperature, radiation field, and environmental conditions of normal and off-normal service. Arguments for
long-term performance must account for materials alterations (especially degradations) that are expected during the service
periods, which include the periods of the initial license and of the license renewal. This guide pertains only to structures, systems,
and components important to safety during extended storage period and during retrieval functions, including transport and transfer
operations. Materials information that pertains to safet
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