iTeh StandardsiTeh Standards
EURUSD
Your shopping cart is empty.
ASTM

ASTM D3843-00

(Practice)

Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

SIGNIFICANCE AND USE
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 D 5144, will perform satisfactorily in service.
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 owner, 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 D 5144,  shall be identified, quantified, and documented.
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 owner’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 practice 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 does not purport to address all of the safety problems, 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.

General Information

Status
Historical
Publication Date
09-Aug-2000
ICS
27.120.01 - Nuclear energy in general
Technical Committee
D33 - Protective Coating and Lining Work for Power Generation Facilities
Drafting Committee
D33.04 - Quality Systems and Inspection
Current Stage
Ref Project

Relations

Replaced By
ASTM D3843-00(2008) - Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities
Effective Date
01-Nov-2008
Referred By
ASTM D5498-12a(2018) - Standard Guide for Developing a Training Program for Personnel Performing Coating and Lining Work Inspection for Nuclear Facilities
Effective Date
10-Aug-2000
Referred By
ASTM D4286-08(2021) - Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities
Effective Date
10-Aug-2000
Referred By
ASTM D4538-21 - Standard Terminology Relating to Protective Coating and Lining Work for Power Generation Facilities
Effective Date
10-Aug-2000
Referred By
ASTM D5144-08(2021) - Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
Effective Date
10-Aug-2000

Buy Standard

ASTM D3843-00 - Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear FacilitiesASTM D3843-00 - Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities
PreviousNext
Standard
ASTM D3843-00 - Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities
English language
3 pages
sale 15% off
Preview
sale 15% off
Preview

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
Designation:D3843–00
Standard Practice for
Quality Assurance for Protective Coatings Applied to
Nuclear Facilities
This standard is issued under the fixed designation D 3843; 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 2.4 Code of Federal Regulations:
10 CFR 50 , Appendix B: Title 10, Chapter 1, Energy, Part
1.1 This practice provides a common basis for, and specifi-
50, Domestic Licensing of Production and Utilization
cally comprises quality assurance requirements applicable to,
Facilities, Appendix B, Quality Assurance Criteria for
safety-relatedprotectivecoatingworkinCoatingServiceLevel
Nuclear Power Plants and Fuel Reprocessing Plants
I areas of nuclear facilities as defined in Guide D 5144.
10 CFR 21 Reporting of Defects and Noncompliances
1.2 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
3. Terminology
responsibility of the user of this standard to establish appro-
3.1 Definitions of Terms Specific to This Standard:
priate safety and health practices and determine the applica-
3.1.1 certification, n—the written documentation of the
bility of regulatory limitations prior to use.
qualification of personnel or material.
2. Referenced Documents 3.1.2 coating applicator, n—an organization or individual
responsible for applying a protective or decorative coating
2.1 ASTM Standards:
system.
D 4227 PracticeforQualificationofCoatingApplicatorsfor
3.1.3 coating manufacturer, n—an organization responsible
Application of Coatings to Concrete Surfaces
for manufacturing coating materials.
D 4228 PracticeforQualificationofCoatingApplicatorsfor
3.1.4 coating system, n—a polymeric protective film con-
Application of Coatings to Steel Surfaces
sisting of one or more coats, applied in a predetermined order
D 4537 Guide for Establishing Procedures to Qualify and
by prescribed methods.
Certify Personnel Performing Coating Work Inspection in
3.1.5 coating work, n—an all-inclusive term to define all
Nuclear Facilities
operations required to accomplish a complete coating job. The
D 5144 Guide for Use of Protective Coating Standards in
term shall be construed to include materials, equipment, labor,
Nuclear Power Plants
preparation of surfaces, control of ambient conditions, appli-
2.2 ANSI Standards:
cation and repair of coating systems, and inspection.
N45.2 Quality Assurance Program Requirements for
3.1.6 Code of Federal Regulations (CFR), n—the rules and
Nuclear Power Plants
regulations of the United States Federal Government.The code
NQA-1 (86) Quality Assurance Program Requirements for
is subdivided into titles, with Title 10 (10 CFR) applying to
Nuclear Facilities
energy.
2.3 ASME Standard:
3.1.7 paintings/coatings/linings, n—essentially synony-
NQA-1 (89) Quality Assurance Program Requirements for
4 mous terms for liquid-applied materials consisting of pigments
Nuclear Facilities
and fillers bound in a resin matrix, which dry or cure to form
a thin, continuous protective or decorative film. “Linings”
This practice is under the jurisdiction of ASTM Committee D33 on Protective
indicate an immersion environment.
Coating and Lining Work for Power Generation Facilities and is the direct
3.1.8 deviation, n—a departure of a characteristic from
responsibility of D33.04 on Quality Systems and Inspection.
established procedures or from specified requirements.
Current edition approved Aug. 10, 2000. Published October 2000. Originally
approved in 1980. Last previous edition approved in 1993 as D 3843 – 93.
3.1.9 documentation, n—any written or pictorial informa-
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
tion describing, defining, specifying, reporting, or certifying
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
activities, requirements, procedures, or results.
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website.
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
4th Floor, New York, NY 10036, http://www.ansi.org.
4 5
Available from American Society of Mechanical Engineers (ASME), ASME AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
International Headquarters, Three Park Ave., New York, NY 10016-5990, http:// 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
www.asme.org. www.access.gpo.gov.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
D3843–00
3.1.10 inspection, n—a phase of quality control which by tions are discovered during any phase of the coating work
means of examination, observation, or measurement deter- activity, a nonconformance report shall be completed either by
mines the conformance of materials, supplies, components, the owner, vendor, or owner’s designee. The owner or the
parts, appurtenances, systems, processes, or structures to pre- owner’s designee shall approve the disposition of the noncon-
determined quality requirements. formance report in accordance with the owner’s quality assur-
3.1.11 inspection agency, n—apersonorpersonsauthorized ance program.
by the owner or owner’s designee to verify and attest conform-
NOTE 1—Notification of the Nuclear Regulatory Commission (NRC) is
ance of the coating work.
required by 10 CFR 21 for certain types of defects and noncompliances.
3.1.12 nonconformance, n—a deficiency in characteristic,
5.4 Safety-related coating work shall be governed by pro-
documentation, or procedure that renders the quality of an item
grammatic and procedural quality provisions that ensure that
unacceptable or indeterminate. Examples of nonconformances
the requirements of 10 CFR 50, Appendix B as defined are
include: physical defects, test failures, incorrect or inadequate
satisfied. Guidance in this regard is available in ANSI N45.2
documentation, or deviation from prescribed processing, in-
and ASME NQA-1. Refer, also, to EPRI TR-109937.
spection, or test procedures.
3.1.13 owner, n—the person, group, company, or corpora-
6. Control of Selection and Qualification of Coating
tion who has or will have the license for the facility or
Materials
installation.
3.1.14 owner’s designee, n—a person or persons authorized
6.1 All qualifications of coating materials shall meet the
by the owner to act in his behalf.
applicable standards referenced in Guide D 5144 to the extent
3.1.15 vendor, n—any individual or organization who fur-
definedbytheownerortheowner’sdesigneeindesigncriteria,
nishes items or service to a procurement document.
safety analysis reports, quality assurance program, or other
controlling documents.
4. Significance and Use
6.2 The coating manufacturer shall furnish recommended
4.1 Quality assurance, as covered by this practice, com-
surfacepreparationandapplicationproceduresforeachcoating
prises all those planned and systematic actions necessary to
systemoneachsubstrateascoveredbytheprojectspecification
provideadequateconfidencethatsafety-relatedcoatingworkin
includingpreviouslycoatedsurfacesasapplicable.Thecoating
nuclear facilities as defined in Guide D 5144, will perform
manufacturer shall also furnish recommended storage condi-
satisfactorily in service.
tions for each coating material specified.
4.2 It is not practical to impose all the requirements of this
practice on certain specific items that require only a small
7. Control of Coating Manufacturing
quantity of coating material. The owner, consistent with his
7.1 The coating manufacturer shall maintain a Quality
formal Quality Assurance Program, may accept affidavits of
Assurance Program and shall provide adequate documentation
compliance or certification attesting to the quality of a shop or
to show that the quality of a given coating system as supplied
field coating for such items. If required by licensing commit-
is the same composition as (within owner approved manufac-
ment; safety-related coatings that are
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.

This May Also Interest You

ASTM
ASTM D3843-16(2021)e1(Practice)
Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

SIGNIFICANCE AND USE
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.

  • Standard
    18 pages
    English language
    sale 15% off
ASTM
ASTM D8157-19(Guide)
Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants

SIGNIFICANCE AND USE
4.1 This guide presents concise guidance and approach to developing a test document for qualifying a coating for CSLI service, whether a new or existing coating. Guidance for evaluating existing qualification test data for applicability is presented in Guide D8104.  
4.2 The requirements for qualification testing can be found in Quality Assurance Criteria III (Design Control), IX (Control of Special Processes), and XI (Test Control) of 10 CFR 50, Appendix B, as implemented, respectively, by Requirements III, IX, and XI of NQA-1. A test document developed per this guide is intended to be compliant with these requirements.  
4.3 This guide implements the guidance provided in Guide D5144 for qualification of coatings for use in CSLI service. Additional guidance is provided in Regulatory Guide 1.54, Revisions 0 through 3, as may be invoked by the licensee.  
4.4 For plants with a license basis that predates the requirements of ANSI N5.12 and N101.2, this guide also is applicable. For these plants, the coatings or coating systems may be designated as acceptable, rather than qualified.  
4.5 All qualification testing shall comply with the licensee’s approved quality assurance program.
SCOPE
1.1 This guide provides an approach to identifying the need for and development of a test document to qualify coatings for Coating Service Level I (CSLI) service in nuclear power plants.  
1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings qualification test document, not to mandate a singular basis for all test documents. Variations or simplifications of the process described in this guide may be appropriate for any given operating or new construction nuclear power plant depending on its licensing commitments.  
1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
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.

  • Guide
    4 pages
    English language
    sale 15% off
ASTM
ASTM C1009-21(Guide)
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.  
4.3 Quality assurance programs are designed and implemented by organizations to assure that the quality requirements for a process, product or service will be fulfilled. The quality system is complementary to technical requirements that may be specific to a process or analytical method. Each laboratory should identify applicable program requirements and use standards to implement a quality program that meets the appropriate requirement. This guide may be used to develop and implement an analytical laboratory QA program. Other useful implementation standards and documents are listed in Section 2 and Appendix X1.  
4.4 The guides for QA in the analytical laboratory within the nuclear fuel cycle have been written to provide guidance for each of the major activities in the laboratory and are displayed in Fig. 1. The applicable standard for each subject is noted in the following sections.  
FIG. 1 Essential Elements of Analytical Laboratory Quality Assurance System  
4.5 Althoug...
SCOPE
1.1 This guide covers the establishment and maintenance of a quality assurance (QA) program for analytical laboratories within the nuclear industry. References to key elements of ASME NQA-1 and ISO/IEC 17025 provide guidance to the functional aspects of analytical laboratory operations. When implemented as recommended, the practices presented in this guide will provide a comprehensive QA program for the laboratory. The practices are grouped by functions, which constitute the basic elements of a laboratory QA program.  
1.2 The essential, basic elements of a laboratory QA program appear in the following order:    
Section  
Organization  
5  
Quality Assurance Program  
6  
Training and Qualification  
7  
Procedures  
8  
Laboratory Records  
9  
Control of Records  
10  
Management of Customer Requests and Commitments to Customers  
11  
Control of Procurement  
12  
Control of Measuring Equipment and Materials  
13  
Control of Measurements  
14  
Control of Nonconforming Work  
15  
Candidate Actions  
16  
Preventative Actions  
17  
1.3 Collection of samples and associated sampling procedures are outside the scope of this guide. The user may refer to sampling practices developed by Subcommittee C26.02.  
1.4 Nuclear laboratories are required to handle a variety of hazardous materials, including but not limited to radioactive samples and materials. The need for proper handling of these materials is discussed in 13.2.4. While this guide focuses on the nuclear laboratory QA program, proper handling of nuclear materials is essential for proper function of the QA program.  
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 Tra...

  • Guide
    12 pages
    English language
    sale 15% off
  • Guide
    12 pages
    English language
    sale 15% off
ASTM
ASTM D3843-16(2021)e1(Practice)
Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

SIGNIFICANCE AND USE
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.

  • Standard
    18 pages
    English language
    sale 15% off
ASTM
ASTM C1210-21(Guide)
Standard Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within Nuclear Industry

SIGNIFICANCE AND USE
4.1 A laboratory quality assurance program is an essential program for laboratories within the nuclear industry. Guide C1009 provides guidance for establishing a quality assurance program for an analytical laboratory within the nuclear industry. This guide deals with the control of measurements aspect of the laboratory quality assurance program. Fig. 1 shows the relationship of measurement control with other essential aspects of a laboratory quality assurance program.
FIG. 1 Quality Assurance of Analytical Laboratory Data  
4.2 The fundamental purposes of a measurement control program are to provide the with-use  assurance (real-time control) that a measurement system is performing satisfactorily and to provide the data necessary to quantify measurement system performance. The with-use  assurance is usually provided through the satisfactory analysis of quality control samples (reference value either known or unknown to the analyst). The data necessary to quantify measurement system performance is usually provided through the analysis of quality control samples or the duplicate analysis of process samples, or both. In addition to the analyses of quality control samples, the laboratory quality control program should address (1) the preparation and verification of standards and reagents, (2) data analysis procedures and documentation, (3) calibration and calibration procedures, (4) measurement method qualification, (5) analyst qualification, and (6) other general program considerations. Other elements of laboratory quality assurance also impact the laboratory quality control program. These elements or requirements include (1) chemical analysis procedures and procedure control, (2) records storage and retrieval requirements, (3) internal audit requirements, (4) organizational considerations, and (5) training/qualification requirements. To the extent possible, this standard will deal primarily with quality control requirements rather than overall quality assurance re...
SCOPE
1.1 This guide provides guidance for establishing and maintaining a measurement system quality control program. Guidance is provided for general program considerations, preparation of quality control samples, analysis of quality control samples, quality control data analysis, analyst qualification, measurement system calibration, measurement method qualification, and measurement system maintenance.  
1.2 This guidance is provided in the following sections:    
Section  
General Quality Control Program Considerations  
5  
Quality Control Samples  
6  
Analysis of Quality Control Samples  
7  
Quality Control Data Analysis  
8  
Analyst Qualification  
9  
Measurement System Calibration  
10  
Qualification of Measurement Methods and Systems  
11  
Measurement System Maintenance  
12  
1.3 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.

  • Guide
    7 pages
    English language
    sale 15% off
  • Guide
    7 pages
    English language
    sale 15% off
ASTM
ASTM C992-20a(Specification)
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.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
1.6 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.  
1.7 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.

  • Technical specification
    4 pages
    English language
    sale 15% off
  • Technical specification
    4 pages
    English language
    sale 15% off
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.

  • Guide
    15 pages
    English language
    sale 15% off
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.

  • Technical specification
    5 pages
    English language
    sale 15% off
ASTM
ASTM D8157-19(Guide)
Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants

SIGNIFICANCE AND USE
4.1 This guide presents concise guidance and approach to developing a test document for qualifying a coating for CSLI service, whether a new or existing coating. Guidance for evaluating existing qualification test data for applicability is presented in Guide D8104.  
4.2 The requirements for qualification testing can be found in Quality Assurance Criteria III (Design Control), IX (Control of Special Processes), and XI (Test Control) of 10 CFR 50, Appendix B, as implemented, respectively, by Requirements III, IX, and XI of NQA-1. A test document developed per this guide is intended to be compliant with these requirements.  
4.3 This guide implements the guidance provided in Guide D5144 for qualification of coatings for use in CSLI service. Additional guidance is provided in Regulatory Guide 1.54, Revisions 0 through 3, as may be invoked by the licensee.  
4.4 For plants with a license basis that predates the requirements of ANSI N5.12 and N101.2, this guide also is applicable. For these plants, the coatings or coating systems may be designated as acceptable, rather than qualified.  
4.5 All qualification testing shall comply with the licensee’s approved quality assurance program.
SCOPE
1.1 This guide provides an approach to identifying the need for and development of a test document to qualify coatings for Coating Service Level I (CSLI) service in nuclear power plants.  
1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings qualification test document, not to mandate a singular basis for all test documents. Variations or simplifications of the process described in this guide may be appropriate for any given operating or new construction nuclear power plant depending on its licensing commitments.  
1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
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.

  • Guide
    4 pages
    English language
    sale 15% off
ASTM
ASTM C1562-10(2018)(Guide)
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...

  • Guide
    26 pages
    English language
    sale 15% off