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ASTM C992-89(1997)

(Specification)

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components in a pool environment, or both.  
1.2 The materials systems described herein shall be functional for their service life in the operating environment of a nuclear reactor spent-fuel pool.  
1.3 A number of acceptable boron-based absorbing materials combinations are currently available while others are being developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and identifies parameters a buyer should specify to satisfy a unique or particular requirement.  
1.4 Compliance with this specification does not relieve the seller or the buyer from obligation to conform to applicable federal regulations governing the storage of nuclear fuel.

General Information

Status
Historical
Publication Date
09-May-1997
ICS
27.120.01 - Nuclear energy in general
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.03 - Neutron Absorber Materials Specifications
Current Stage
Ref Project

Relations

Replaced By
ASTM C992-06 - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
Effective Date
15-Feb-2006
Referred By
ASTM C1187-20a - Standard Guide for Establishing Surveillance Test Program for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment
Effective Date
10-May-1997

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ASTM C992-89(1997) - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage RacksASTM C992-89(1997) - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
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ASTM C992-89(1997) - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
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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
Designation: C 992 – 89 (Reapproved 1997)
Standard Specification for
Boron-Based Neutron Absorbing Material Systems for Use
in Nuclear Spent Fuel Storage Racks
This standard is issued under the fixed designation C 992; 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. Scope ANSI-ASME NQA-1 Quality Assurance Program Require-
ments for Nuclear Facilities
1.1 This specification defines criteria for boron-based neu-
2.3 U. S. Government Documents:
tron absorbing material systems used in racks for storage of
Title 10, CFR, Energy Part 50 (10CFR50) Licensing of
nuclear light water reactor (LWR) spent-fuel assemblies or
Production and Utilization Facilities
disassembled components in a pool environment, or both.
Title 10, CFR, Energy Part 72 (10CFR72) Licensing Re-
1.2 The materials systems described herein shall be func-
quirements for the Storage of Spent Fuel in an Indepen-
tional for their service life in the operating environment of a
dent Spent Fuel Storage Installation (ISFSI)
nuclear reactor spent-fuel pool.
1.3 A number of acceptable boron-based absorbing materi-
3. Terminology
als combinations are currently available while others are being
3.1 Definitions of Terms Specific to This Standard:
developed for use in the future. This specification defines
3.1.1 Terms shall be defined in accordance with Terminol-
criteria essential and applicable to all materials combinations
ogy C 859 except as defined as follows:
and identifies parameters a buyer should specify to satisfy a
3.1.2 buyer—the organization issuing the purchase order.
unique or particular requirement.
3.1.3 individual piece—a discrete section of neutron ab-
1.4 Compliance with this specification does not relieve the
sorber material whose individual dimensions conform to those
seller or the buyer from obligation to conform to applicable
in the purchase specification.
federal regulations governing the storage of nuclear fuel.
3.1.4 irradiation—the neutron, beta and gamma fluxes,
2. Referenced Documents from spent-fuel assemblies in a water-filled spent fuel pool.
3.1.5 production batch—a group of neutron-absorbing ma-
2.1 ASTM Standards:
terial pieces produced in a continuous production period, all of
A 240 Specification for Heat-Resisting Chromium and
which can be shown to have the same chemical composition,
Chromium-Nickel Stainless Steel Plate, Sheet, and Strip
physical, and nuclear properties within specification limits.
for Pressure Vessels
3.1.6 seller—the neutron absorbing system manufacturer.
B 209 Specification for Aluminum and Aluminum Alloy
3.1.7 service life—theperiodoftimeforwhichpropertiesof
Sheet and Plate
the neutron-absorbing material system are expected to remain
C 750 Specification for Nuclear-Grade Boron Carbide Pow-
in compliance with the contract requirements which relate to
der
4 chemical and physical integrity.
C 859 Terminology Relating to Nuclear Materials
3.1.8 supplier—any outside source of raw materials and
E 105 Practice for Probability Sampling of Materials
6 services used by the seller.
2.2 ANSI Standards:
ANSI 45.2.2 Packaging, Shipping, Receiving, Storage and
4. Ordering Information
Handling of Items for Nuclear Power Plants
4.1 The buyer should specify the following environmental
conditions to which the neutron absorbing material system
shall be exposed:
This specification is under the jurisdiction of ASTM Committee C-26 on
4.1.1 Total service life of the neutron absorbing material
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on
system (considered forty years unless otherwise specified),
Neutron Absorber Materials Specifications.
4.1.2 Dose rate and maximum integrated irradiation over
Current edition approved May 26, 1989. Published July 1989. Originally
published as C 992 – 83. Last previous edition C 992 – 83. the total service life of the neutron absorbing material system,
Annual Book of ASTM Standards, Vol 01.03.
and
Annual Book of ASTM Standards, Vol 02.02.
Annual Book of ASTM Standards, Vol 12.01.
Annual Book of ASTM Standards, Vol 14.02.
6 7
Available from theAmerican National Standards Institute, 11W. 42nd St., 13th Available from Superintendent of Documents, U. S. Government Printing
Floor, New York, NY 10036. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C 992
4.1.3 Chemical and thermal environment of the water in the 5.4 Boron Loss—Thelossofboronthroughanydegradation
spent fuel pool in which the neutron absorbing material system mechanisms such as leaching, neutron capture, out-gassing,
will be located. chemical interaction, radiation, etc., shall not lower the boron
4.2 The buyer shall specify the following physical and content below the allowable limits within the stated service life
(see Section 6.1.1).
chemical properties of the neutron absorbing material system,
including retained samples or in-use sampling coupons: 5.5 It is recommended that in-service surveillance tests be
performed to monitor maintenance of the boron areal density.
4.2.1 Total quantity of individual pieces required,
It is further recommended that these tests determine both
4.2.2 Physicaldimensionsofeachindividualpiecerequired,
physical and performance characteristics. The physical tests
and physical form limitations including flatness, camber, bow,
should determine at least the size, weight, density, and surface
etc.,
appearances. The performance tests should determine at least
4.2.3 Boron content of the neutron absorbing material
the strength and neutron attenuation capabilities. The test
systemexpressedintermsofgramsofisotopicB-10percm of
samplesshouldbepositionedtomaximizetheirradiationdoses
surface area or by weight percent, and
the samples will receive during each exposure period. The
4.2.4 Applicable tolerances for each dimension or property.
beforeandafterexposuretestresultsmustbecomparedforany
4.2.5 Material specifications for the components of the
unfavorable changes in the physical or performance character-
neutron absorbing material system shall be in accordance with
istics.
Specifications A 240, B 209, and C 750, if applicable.
4.3 In addition to the properties of 4.2, the buyer shall
6. Test Documentation
specify the following system properties as required by the
specific spent fuel storage rack design:
6.1 The seller shall provide to the buyer documentation of
4.3.1 Structural properties for the neutron absorbing mate- tests performed on the neutron absorbing material system
rial system, if required, and demonstrating compliance with the specifications.
4.3.2 Limitations on gas evolution, product cleanliness, or 6.1.1 The tests to demonstrate compliance to 5.4 shall be
accelerated tests to be performed whenever possible b
...

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Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
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Standard Guide for Establishing and Maintaining a Quality Assurance Program for Analytical Laboratories Within the Nuclear Industry

SIGNIFICANCE AND USE
4.1 The mission of an analytical laboratory is to provide quality analyses on nuclear fuel cycle materials. An analytical laboratory QA program is comprised of planned and systematic actions needed to provide confidence that this mission is conducted in an acceptable and consistent manner.  
4.2 The analytical laboratories involved in the analysis of nuclear fuel cycle materials are required to implement a documented QA program. Regulatory agencies may mandate some form of control requirements for all or a part of a laboratory's operation. A documented QA program is also necessary for those laboratory operations required to comply with ASME NQA-1 or ISO/IEC 17025, or the requirements of many accreditation bodies. Even when not mandated, laboratory QA programs should be established as a sound and scientific technical practice. This guide provides guidance for establishing and maintaining a QA program to control those analytical operations vital to ensuring the quality of chemical analyses.  
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FIG. 1 Essential Elements of Analytical Laboratory Quality Assurance System  
4.5 Althoug...
SCOPE
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4.1 Quality assurance, as covered by this practice, comprises all those planned and systematic actions necessary to provide adequate confidence that safety-related coating work in nuclear facilities as defined in Guide D5144, will perform satisfactorily in service.  
4.2 It is not practical to impose all the requirements of this practice on certain specific items that require only a small quantity of coating material. The licensee, consistent with his formal Quality Assurance Program, may accept affidavits of compliance or certification attesting to the quality of a shop or field coating for such items. If required by licensing commitment; safety-related coatings that are not qualified or for which the quantification basis is indeterminate as defined in Guide D5144, shall be identified, quantified, and documented.  
4.3 This practice may be incorporated in a project specification by direct reference or may be used to provide guidelines for the quality assurance program for coatings, on the basis of the licensee’s requirements. Effective use of this practice may also require the incorporation of applicable sections in project specifications for coatings on concrete, steel, equipment, and other related items.
SCOPE
1.1 This standard replaces ANSI N101.4 and provides a common basis for, and specifically comprises quality assurance requirements applicable to, safety-related protective coating work in Coating Service Level I areas of nuclear facilities as defined in Guide D5144.  
1.2 This standard meets the requirements of ANSI N101.4 while also recognizing advancements in technology and industry practices since transfer to ASTM responsibility for updating, rewriting, and issuing replacement standards to ANSI N101.4.  
1.3 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 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.

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ASTM
ASTM E1034-95(2020)(Specification)
Standard Specification for Nuclear Facility Transient Worker Records

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.  
4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).  
4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.  
1.2 This specification applies to records to be used for in-processing only.  
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).  
1.4 This specification doesPresident Barack Obama eulogy at John Lewis funeral not reduce any regulatory requirement for records retention at a licensed nuclear facility.  
Note 1: Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the 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 does not alter the required content of records needed for in-processing of nuclear facility transient workers.
Note 2: This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).  
1.5 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.

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ASTM
ASTM E2216-02(2020)(Guide)
Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
1.4 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.

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