ASTM C1562-03e1

Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems

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 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 safety functions, including retrie...

General Information

• Status: Historical
• Publication Date: 09-Feb-2003
• ICS: 27.120.01 - Nuclear energy in general
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.13 - Spent Fuel and High Level Waste

Relations

• Replaces: ASTM C1562-03 - Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
• Effective Date: 10-Feb-2003
• Replaced By: ASTM C1562-03e2 - Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
• Effective Date: 10-Feb-2003
• Referred By: ASTM C1553-21 - Standard Guide for Drying of Spent Nuclear Fuel
• Effective Date: 10-Feb-2003

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
e1
Designation: C 1562 – 03
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 C 1562; 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.
1
e NOTE—Editorial changes were made throughout in March 2004.
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
initial 20-year license period as the result of normal events and
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
1.4 This guide provides information on materials behavior
for the extended service of the renewal period. This guide is
to support continuing compliance with the safety criteria,
written for DCSS containing light water reactor (LWR) fuel
which are part of the regulatory basis, for licensed storage of
that is clad in zirconium alloy material and stored in accor-
SNF at an ISFSI.The safety functions addressed and discussed
dance with the Code of Federal Regulations (CFR), at an
2
in this standard guide include thermal performance, radiologi-
independent spent-fuel storage installation (ISFSI) . The com-
cal protection, confinement, sub-criticality, and retrievability.
ponents of an ISFSI, addressed in this document, include the
The regulatory basis includes 10 CFR Part 72 and supporting
commercial SNF, canister, cask, and all parts of the storage
regulatory guides of the U.S. Nuclear Regulatory Commission.
installationincludingtheISFSIpad.Thelanguageofthisguide
The requirements set forth in these documents indicate that the
is based, in part, on the requirements for a dry SNF storage
following items were considered in the original licensing
license that is granted, by the U.S. Nuclear Regulatory Com-
decisions: properties of materials, design considerations for
mission (NRC), for up to 20 years. Although government
normal and off-normal service, operational and natural events,
regulations may differ for various nations, the guidance on
and the bases for the original calculations. These items may
materials properties and behavior given here is expected to
require reconsideration of the safety-related arguments that
have broad applicability.
demonstrate how the systems continue to satisfy the regulatory
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
are given in this guide and they include materials alterations or
(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
systems, and components important to safety during extended
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
CycleandisthedirectresponsibilityofSubcommitteeC26.13onRepositoryWaste.
storage period and during retrieval functions, including trans-
Current edition approved Feb. 10, 2003. Published March 2003.
port and transfer operations. Materials information that per-
2
In general fuels of higher burrup (> 45 MWd/kgU) and MOX fuels are not
tains to safety functions, including retrieval func
...