Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials

SIGNIFICANCE AND USE
4.1 Equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns can only be addressed or are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
4.2 This guide is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use.  
4.3 This guide is intended to be generic and to apply to a wide range of equipment types and configurations.  
4.4 The term equipment  is used herein in a generic sense. See 3.2.6 for the definition.  
4.5 This service imposes stringent requirements on the quality and the integrity of the equipment, as follows:  
4.5.1 Leak tightness is required. This implies containment of liquids at all times, and retention of vapors and gases by means of vessel design, or through means of engineered provisions or operational procedures, or both, that ensure the retention, collection, and treatment of vapors and off-gases when the vessel cannot be fabricated or operated with an air-tight vessel configuration. Radioactive materials must be contained.  
4.5.2 Equipment must be capable of withstanding rigorous chemical cleaning and decontamination procedures.  
4.5.3 Equipment must be designed and fabricated to remain dimensionally stable throughout its life cycle.  
4.5.4 Close fabrication tolerances are required to set nozzles and other datum points in known positions.  
4.5.5 Fabrication materials must be resistant to radiation damage, or materials subject to such damage must be shielded or placed so as to be readily replaceable.  
4.5.6 Smooth surface finishes are required. Irregularities that hide and retain radioactive particulates or oth...
SCOPE
1.1 Intent:  
1.1.1 This guide covers equipment used in shielded cell or canyon facilities for the processing of nuclear and radioactive materials. It is the intent of this guide to set down the conditions and practices that have been found necessary to ensure against or to minimize the failures and outages of equipment used under the subject circumstances.  
1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, and installation of equipment capable of meeting the stringent demands of operating, dependably and safely, in a nuclear processing environment that operators can neither see nor reach directly.  
1.1.3 This guide sets forth generalized criteria and guidelines for the design, fabrication, and installation of equipment used in this service. This service  includes the processing of radioactive wastes. Equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. In the type of shielded cell or canyon facility of interest to users of this guide, either the background radiation level remains high at all times or it is impractical to remove the process sources of radiation to facilitate in situ repairs or carry out maintenance procedures on equipment. The equipment is operated remotely, either with or without visual access to the equipment.  
1.2 Applicability:  
1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:
1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.
1.2.1.3 The material handled or processed must ...

General Information

Status
Published
Publication Date
30-Jun-2020
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.09 - Nuclear Processing

Relations

Effective Date
01-Jul-2020
Effective Date
01-Jan-2024
Effective Date
15-Jun-2014
Effective Date
15-Jan-2014
Effective Date
01-Jun-2013
Effective Date
01-May-2013
Effective Date
01-Nov-2010
Effective Date
01-Aug-2010
Effective Date
01-Feb-2010
Effective Date
15-Feb-2009
Effective Date
15-Nov-2008
Effective Date
15-Nov-2008
Effective Date
15-Sep-2008
Effective Date
10-May-2000
Effective Date
01-Jan-1992

Overview

ASTM C1217-00(2020) - Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials provides comprehensive guidelines for the design, fabrication, and installation of equipment used in shielded cell or canyon facilities. Developed by ASTM International, this standard addresses the unique challenges of processing nuclear and radioactive materials, particularly where direct access to equipment is limited due to radiation hazards. The guide supplements federal, state, and other relevant standards and regulations, highlighting the critical importance of equipment integrity, containment, and operability in nuclear environments.

Key Topics

  • Equipment Integrity & Operability: Emphasizes the necessity for robust design and fabrication practices to ensure long-term equipment integrity and reliable operation, especially under remote handling scenarios.
  • Containment Requirements: Specifies that equipment must maintain leak-tightness, ensuring that liquids, gases, and radioactive materials are contained at all times through appropriate vessel design and engineered features.
  • Decontamination & Cleaning: Equipment must withstand rigorous chemical cleaning procedures and allow for straightforward decontamination to minimize radioactive contamination.
  • Dimensional Stability & Precision: Close fabrication tolerances are required to maintain positional accuracy for critical connection points, enabling reliable installation and operation.
  • Material Selection: Materials used must be resistant to radiation damage or positioned for easy replacement if susceptible.
  • Smooth Surface Finishes: Smooth, defect-free surfaces are essential to avoid trapping radioactive particles, simplifying cleaning and inspection.
  • Remote Operation Design: Equipment should be operable with minimal direct human intervention, often relying on remote handling and monitoring systems.
  • Documentation & Quality Assurance: The guide mandates thorough documentation, quality assurance programs traceable to recognized standards, and proper storage of all design and testing records.

Applications

This standard is applicable to a wide range of equipment used for processing nuclear and radioactive materials, especially in environments that present significant radiation hazards, including:

  • Shielded Cell or Canyon Facilities: Where equipment is installed behind radiation shields and operated remotely due to exposure risks.
  • Radioactive Waste Processing: Encompassing waste concentration, encapsulation, canning, and incorporation into host materials such as glass, ceramics, metals, or concrete.
  • Ancillary and Support Systems: Including systems that are integral to the nuclear process configuration, even if not directly handling radioactive materials.
  • Long-Term and High-Risk Operations: Scenarios where the material processed poses significant hazards to personnel or the environment, or where regulatory accountability and strict containment are required.

By following ASTM C1217-00(2020), designers, engineers, and facility operators can mitigate failures or outages, ensure material containment, and maintain regulatory compliance. The standard's approach supports enhanced safety, operational efficiency, and environmental protection throughout the lifecycle of nuclear processing equipment.

Related Standards

This guide references and works in conjunction with several key industry and regulatory standards, including:

  • ASTM C859 - Terminology Relating to Nuclear Materials
  • ASME NQA-1 - Quality Assurance Requirements for Nuclear Facility Applications
  • Boiler and Pressure Vessel Code (ASME Section VIII)
  • ANSI/ANS 8.1 - Nuclear Criticality Safety in Operations with Fissile Materials Outside Reactors
  • NFPA 70 - National Electric Code
  • NEMA 250 - Enclosures for Electrical Equipment 1000 Volts Maximum
  • 10CFR50, Appendix B - Quality Assurance (U.S. Nuclear Regulatory Commission)
  • ANSI A14.3 - Ladders, Fixed Safety Requirements

Use of ASTM C1217-00(2020) ensures alignment with widely recognized nuclear safety and engineering practices, supporting process safety, regulatory acceptance, and operational continuity in nuclear and radioactive material processing facilities.

Buy Documents

Guide

ASTM C1217-00(2020) - Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials

English language (19 pages)
sale 15% off
sale 15% off

Get Certified

Connect with accredited certification bodies for this standard

DNV

DNV is an independent assurance and risk management provider.

NA Norway Verified

Lloyd's Register

Lloyd's Register is a global professional services organisation specialising in engineering and technology.

UKAS United Kingdom Verified

DNV Energy Systems

Energy and renewable energy certification.

NA Norway Verified

Sponsored listings

Frequently Asked Questions

ASTM C1217-00(2020) is a guide published by ASTM International. Its full title is "Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials". This standard covers: SIGNIFICANCE AND USE 4.1 Equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns can only be addressed or are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions. 4.2 This guide is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use. 4.3 This guide is intended to be generic and to apply to a wide range of equipment types and configurations. 4.4 The term equipment is used herein in a generic sense. See 3.2.6 for the definition. 4.5 This service imposes stringent requirements on the quality and the integrity of the equipment, as follows: 4.5.1 Leak tightness is required. This implies containment of liquids at all times, and retention of vapors and gases by means of vessel design, or through means of engineered provisions or operational procedures, or both, that ensure the retention, collection, and treatment of vapors and off-gases when the vessel cannot be fabricated or operated with an air-tight vessel configuration. Radioactive materials must be contained. 4.5.2 Equipment must be capable of withstanding rigorous chemical cleaning and decontamination procedures. 4.5.3 Equipment must be designed and fabricated to remain dimensionally stable throughout its life cycle. 4.5.4 Close fabrication tolerances are required to set nozzles and other datum points in known positions. 4.5.5 Fabrication materials must be resistant to radiation damage, or materials subject to such damage must be shielded or placed so as to be readily replaceable. 4.5.6 Smooth surface finishes are required. Irregularities that hide and retain radioactive particulates or oth... SCOPE 1.1 Intent: 1.1.1 This guide covers equipment used in shielded cell or canyon facilities for the processing of nuclear and radioactive materials. It is the intent of this guide to set down the conditions and practices that have been found necessary to ensure against or to minimize the failures and outages of equipment used under the subject circumstances. 1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, and installation of equipment capable of meeting the stringent demands of operating, dependably and safely, in a nuclear processing environment that operators can neither see nor reach directly. 1.1.3 This guide sets forth generalized criteria and guidelines for the design, fabrication, and installation of equipment used in this service. This service includes the processing of radioactive wastes. Equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. In the type of shielded cell or canyon facility of interest to users of this guide, either the background radiation level remains high at all times or it is impractical to remove the process sources of radiation to facilitate in situ repairs or carry out maintenance procedures on equipment. The equipment is operated remotely, either with or without visual access to the equipment. 1.2 Applicability: 1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions: 1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment. 1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded. 1.2.1.3 The material handled or processed must ...

SIGNIFICANCE AND USE 4.1 Equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns can only be addressed or are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions. 4.2 This guide is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use. 4.3 This guide is intended to be generic and to apply to a wide range of equipment types and configurations. 4.4 The term equipment is used herein in a generic sense. See 3.2.6 for the definition. 4.5 This service imposes stringent requirements on the quality and the integrity of the equipment, as follows: 4.5.1 Leak tightness is required. This implies containment of liquids at all times, and retention of vapors and gases by means of vessel design, or through means of engineered provisions or operational procedures, or both, that ensure the retention, collection, and treatment of vapors and off-gases when the vessel cannot be fabricated or operated with an air-tight vessel configuration. Radioactive materials must be contained. 4.5.2 Equipment must be capable of withstanding rigorous chemical cleaning and decontamination procedures. 4.5.3 Equipment must be designed and fabricated to remain dimensionally stable throughout its life cycle. 4.5.4 Close fabrication tolerances are required to set nozzles and other datum points in known positions. 4.5.5 Fabrication materials must be resistant to radiation damage, or materials subject to such damage must be shielded or placed so as to be readily replaceable. 4.5.6 Smooth surface finishes are required. Irregularities that hide and retain radioactive particulates or oth... SCOPE 1.1 Intent: 1.1.1 This guide covers equipment used in shielded cell or canyon facilities for the processing of nuclear and radioactive materials. It is the intent of this guide to set down the conditions and practices that have been found necessary to ensure against or to minimize the failures and outages of equipment used under the subject circumstances. 1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, and installation of equipment capable of meeting the stringent demands of operating, dependably and safely, in a nuclear processing environment that operators can neither see nor reach directly. 1.1.3 This guide sets forth generalized criteria and guidelines for the design, fabrication, and installation of equipment used in this service. This service includes the processing of radioactive wastes. Equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. In the type of shielded cell or canyon facility of interest to users of this guide, either the background radiation level remains high at all times or it is impractical to remove the process sources of radiation to facilitate in situ repairs or carry out maintenance procedures on equipment. The equipment is operated remotely, either with or without visual access to the equipment. 1.2 Applicability: 1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions: 1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment. 1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded. 1.2.1.3 The material handled or processed must ...

ASTM C1217-00(2020) is classified under the following ICS (International Classification for Standards) categories: 27.120.30 - Fissile materials and nuclear fuel technology. The ICS classification helps identify the subject area and facilitates finding related standards.

ASTM C1217-00(2020) has the following relationships with other standards: It is inter standard links to ASTM C1217-00(2012), ASTM C859-24, ASTM C859-14a, ASTM C859-14, ASTM C859-13a, ASTM C859-13, ASTM C859-10b, ASTM C859-10a, ASTM C859-10, ASTM C859-09, ASTM D5144-08e1, ASTM D5144-08, ASTM C859-08, ASTM D5144-00, ASTM C859-92b. Understanding these relationships helps ensure you are using the most current and applicable version of the standard.

ASTM C1217-00(2020) is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.

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: C1217 − 00 (Reapproved 2020)
Standard Guide for
Design of Equipment for Processing Nuclear and
Radioactive Materials
This standard is issued under the fixed designation C1217; 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 1.2.1.3 The material handled or processed must be retained,
contained, and confined within known bounds for reasons of
1.1 Intent:
accountability or to minimize the spread of radioactive con-
1.1.1 This guide covers equipment used in shielded cell or
tamination.
canyon facilities for the processing of nuclear and radioactive
1.2.1.4 Thematerialshandledorprocessedmustbekeptand
materials. It is the intent of this guide to set down the
maintained within one or more of the following conditions:
conditions and practices that have been found necessary to
(1)In a specific geometric array or configuration, and
ensure against or to minimize the failures and outages of
(2)Withinarangeofconditionsthathavebeendetermined
equipment used under the subject circumstances.
to be a critically safe set of conditions for that piece of
1.1.2 It is intended that this guide record the principles and
equipment, that is:
caveatsthatexperiencehasshowntobeessentialtothedesign,
(a)In a given and specified operational position where
fabrication, and installation of equipment capable of meeting
adjacent nuclear criticality interaction conditions are known
the stringent demands of operating, dependably and safely, in
and unchanging,
anuclearprocessingenvironmentthatoperatorscanneithersee
(b)For a given and specified set or range of operating
nor reach directly.
conditions, and
1.1.3 This guide sets forth generalized criteria and guide-
(c)For a given and specified process.
lines for the design, fabrication, and installation of equipment
1.2.1.5 The equipment can neither be accessed directly for
used in this service. This service includes the processing of
purposes of operation or maintenance, nor can the equipment
radioactive wastes. Equipment is placed behind radiation
be viewed directly, for example, without intervening shielded
shieldwallsandcannotbedirectlyaccessedbytheoperatorsor
viewing windows, periscopes, or a television monitoring sys-
by maintenance personnel because of the radiation exposure
tem.
hazards. In the type of shielded cell or canyon facility of
interest to users of this guide, either the background radiation 1.2.2 Thisguideisintendedtobeapplicabletothedesignof
levelremainshighatalltimesoritisimpracticaltoremovethe equipment for the processing of materials containing uranium
process sources of radiation to facilitate in situ repairs or carry and transuranium elements in any physical form under the
out maintenance procedures on equipment. The equipment is following conditions:
operated remotely, either with or without visual access to the
1.2.2.1 Such materials constitute an unacceptable radiation
equipment.
hazard to the operators and maintenance personnel,
1.2.2.2 Theneedexistsfortheconfinementofthein-process
1.2 Applicability:
material, of dusts and particulates, or of vapors and gases
1.2.1 This guide is intended to be applicable to equipment
arising or resulting from the handling and processing of such
used under one or more of the following conditions:
materials, and
1.2.1.1 The materials handled or processed constitute a
1.2.2.3 Any of the conditions cited in 1.2.1 apply.
significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-
1.2.3 This guide is intended to apply to the design,
term life cycle (for example, in excess of two years), but fabrication, and installation of ancillary and support services
equipment intended for use over a shorter life cycle is not equipment under the following conditions:
excluded.
1.2.3.1 Such equipment is installed in shielded cell or
canyon environments, or
1.2.3.2 Such equipment is an integral part of an in-cell
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
Cycle and is the direct responsibility of Subcommittee C26.09 on Nuclear
processingequipmentconfiguration,oranauxiliarycomponent
Processing.
or system thereof, even though an equipment item or system
CurrenteditionapprovedJuly1,2020.PublishedJuly2020.Originallyapproved
may not directly hold or contain nuclear or radioactive mate-
in 2000. Last previous edition approved in 2012 as C1217 – 00 (2012). DOI:
10.1520/C1217-00R20. rials under normal processing conditions.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1217 − 00 (2020)
NOTE 1—Upsets, accidents, or certain emergency conditions may be
1.4 This international standard was developed in accor-
specified (and thus required) design considerations, but not necessarily
dance with internationally recognized principles on standard-
acceptable or normal operating circumstances under this definition.
ization established in the Decision on Principles for the
1.2.4 This guide is intended to apply to the design and
Development of International Standards, Guides and Recom-
fabrication of any and all types of equipment for radioactive
mendations issued by the World Trade Organization Technical
wastes processing when any of the conditions cited in 1.2.1
Barriers to Trade (TBT) Committee.
apply. This would include equipment for waste concentration;
for incorporation of wastes in selected host materials or 2. Referenced Documents
matrices;andforthefixation,encapsulation,orcanningofsuch
2.1 Industry and National Consensus Standards—
wastes. It is intended to apply to all such wastes, regardless of
Nationally recognized industry and consensus standards appli-
the product waste composition or form. The product radioac-
cable in whole or in part to the design, fabrication, and
tive waste may have a glass, ceramic, metallic, concrete,
installation of equipment are referenced throughout this guide
bituminous, or other type of host material or matrices
and include the following:
(composition), and may be in pelletized, solid, or granular
2.2 ASTM Standards:
form.
C859Terminology Relating to Nuclear Materials
1.3 User Caveats:
D5144Guide for Use of Protective Coating Standards in
1.3.1 This guide does not purport to address all of the safety
Nuclear Power Plants
concerns, if any, associated with its use. It is the responsibility 3
2.3 ANSI Standards:
of the user of this guide to establish appropriate safety and
ANS GlossaryofTermsinNuclearScienceandTechnology
health practices and determine the applicability of regulatory
(ANS Glossary)
limitations prior to use.
ANSI/ANS8.1NuclearCriticalitySafetyinOperationswith
1.3.2 (Warning—This guide pertains to equipment used in
Fissile Materials Outside Reactors
and for the handling and processing of nuclear and radioactive
ANSI A14.3Ladders, Fixed Safety Requirements
materials. These operations are known to be hazardous for a 4
2.4 ASME Standards:
variety of reasons, one being chemical toxicity.)
Boiler and Pressure Vessel CodeSection VIII
1.3.3 This guide is not a substitute for applied engineering
ASME NQA1QualityAssurance Requirements for Nuclear
skills. Its purpose is to provide guidance.
Facility Applications
1.3.3.1 The guidance set forth in this guide relating to
ASME NOG-1Rules for Construction of Overhead Gantry
design of equipment is intended only to alert designers and
Cranes (Top-Running Bridge, Multiple Girder)
engineers to those features, conditions, and procedures that 5
2.5 Federal Regulations:
have been found necessary or highly desirable to the acquisi-
10CFR50,Appendix B, Quality Assurance
tion of reliable equipment for the subject service conditions.
29CFR1910Occupational Safety and Health Standards
1.3.3.2 The guidance set forth results from discoveries of
2.6 National Electrical Manufacturers Association (NEMA)
conditions, practices, features, or lack of features that were
Standard:
found to be sources of operational or maintenance trouble, or
NEMA250Enclosures for Electrical Equipment 1000 Volts
causes of failure.
Maximum (Type 4)
1.3.4 It is often necessary to maintain the materials being
2.7 National Fire Protection Association (NFPA) Standard:
processed within specific chemical composition or concentra-
NFPA 70National Electric Code
tion ranges, or both. When such constraints apply, it may also
be necessary to create and maintain a specific geometric array
3. Terminology
to minimize the chances of a nuclear criticality incident.
3.1 Definitions:
Designers and engineers are referred to other standards for
3.1.1 The terminology employed in this guide conforms
additional guidance when such requirements apply.
with industry practice insofar as practicable.
1.3.5 Equipment usage intent, service conditions, size and
configuration, plus the configuration and features of the oper-
ating and maintenance environments have an influence on
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
equipment design.Therefore, not all of the criteria, conditions,
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
caveats, or features would be applicable to every equipment
the ASTM website.
item.
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
1.3.6 It is intended that equipment designed, fabricated,
4th Floor, New York, NY 10036, http://www.ansi.org.
procured, or obtained by transfer or adaptation and re-use of Available from American Society of Mechanical Engineers (ASME), ASME
International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
existingequipment,andinstalledinaccordancewiththisguide
www.asme.org.
meet or exceed statutory, regulatory, and safety requirements
Available from U.S. Government Printing Office, Superintendent of
for that equipment under the applicable operating and service
Documents, 732 N. Capitol St., NW, Washington, DC 20401-0001, http://
www.access.gpo.gov.
conditions.
Available from National Electrical Manufacturers Association (NEMA), 1300
1.3.7 This guide does not supersede federal or state
N. 17th St., Suite 900, Arlington, VA 22209, http://www.nema.org.
regulations, or both, and codes applicable to equipment under
Available from National Fire Protection Association (NFPA), 1 Batterymarch
any conditions. Park, Quincy, MA 02169-7471, http://www.nfpa.org.
C1217 − 00 (2020)
3.1.2 For definitions of terms used in this guide, refer to sponsibilities and rights (or specified portions thereof) by way
Terminology C859 and ANS Glossary. of contractual arrangement(s) with the legal owner of the
3.2 Definitions of Terms Specific to This Standard: facilities.
3.2.1 The terms defined below are of a restricted nature,
specifically applicable to this guide. 4. Significance and Use
3.2.2 accident—an unplanned event that could result in
4.1 Equipment operability and long-term integrity are con-
unacceptable levels of any of the following: (1) equipment
cerns that originate during the design and fabrication se-
damage, (2) injury to personnel, (3) downtime or outage, (4)
quences. Such concerns can only be addressed or are most
releaseofhazardousmaterials(radioactiveornon-radioactive),
efficiently addressed during one or the other of these stages.
(5) radiation exposure to personnel, or (6) criticality.
Equipment operability and integrity can be compromised
3.2.3 accountability—the keeping of detailed records on,
duringhandlingandinstallationsequences.Forthisreason,the
and the responsibility, on the part of operations personnel and
subject equipment should be handled and installed under
plant management, of being accountable for the amounts of
closely controlled and supervised conditions.
specialnuclearmaterialsenteringandleavingaplant,avessel,
4.2 This guide is intended as a supplement to other
or a defined processing step.
standards, and to federal and state regulations, codes, and
3.2.4 datum connection points—those locations on equip-
criteria applicable to the design of equipment intended for this
mentwhereseparateauxiliaryequipmentitemssuchaspumps,
use.
agitators,columns,condensers,andotherseparatelyremovable
4.3 This guide is intended to be generic and to apply to a
equipment pieces are mounted, or where process, service,
wide range of equipment types and configurations.
instrumentation, or electrical jumper connections are made.
4.4 The term equipment is used herein in a generic sense.
3.2.4.1 Discussion—These datum connection points are po-
See 3.2.6 for the definition.
sitioned by dimensioning from (theoretically) perfectly placed
base X, Y, and Z datum planes; for example, such points or
4.5 This service imposes stringent requirements on the
locations are dimensionally located by three-plane coordinate
quality and the integrity of the equipment, as follows:
dimensions. Datum connection points are the loci of position-
4.5.1 Leak tightness is required. This implies containment
ing elements such as dowels, trunnions, trunnion guides, and
of liquids at all times, and retention of vapors and gases by
such other devices or elements that serve to align, position, or
means of vessel design, or through means of engineered
locate equipment in a precise position or array, or which serve
provisions or operational procedures, or both, that ensure the
as a point for the connection or placement of other compo-
retention, collection, and treatment of vapors and off-gases
nents.
when the vessel cannot be fabricated or operated with an
3.2.5 engineering responsibility—an obligation to perform air-tight vessel configuration. Radioactive materials must be
engineering design activities assigned to a specified organiza- contained.
tion.
4.5.2 Equipment must be capable of withstanding rigorous
chemical cleaning and decontamination procedures.
3.2.6 geometrically favorable—equipment having set
4.5.3 Equipment must be designed and fabricated to remain
dimensions, and a shape or a layout configuration, that pro-
dimensionally stable throughout its life cycle.
vides assurance that a criticality incident cannot occur in the
4.5.4 Closefabricationtolerancesarerequiredtosetnozzles
equipment or system under a given set of circumstances or
and other datum points in known positions.
conditions.
4.5.5 Fabrication materials must be resistant to radiation
3.2.6.1 Discussion—The given set of conditions or circum-
damage, or materials subject to such damage must be shielded
stances requires that the isotopic composition, form,
or placed so as to be readily replaceable.
concentration, and density of fissile materials in the equipment
4.5.6 Smooth surface finishes are required. Irregularities
or system will not violate those assumed and used for the
that hide and retain radioactive particulates or other adherent
preparation of the criticality analysis, and that those variables
contamination must be eliminated.
will remain within conservatively chosen limits, and that
4.5.7 Equipment must be capable of being operated virtu-
nuclear criticality interaction conditions will be within some
ally unattended, unseen, and trouble-free over long periods.
permitted, pre-set range.
4.6 It is assumed that the radiation hazards, combined with
3.2.7 jumpers—the pipe line, electrical service, or instru-
the need for confinement and containment, will necessitate a
mentation service connector assemblies that span the gap
shielded enclosure cell equipped for some degree of remote
between nozzles or connection points on the canyon or
handling and processing capability in the transuranic materials
cell-mounted equipment and (1) nozzles or connection points
handling, processing, or machining operations (see 1.2.2).
on adjacent or nearby vessels, or (2) service nozzles or
connectorpointsontheinteriorsidesofthecellorshieldwalls.
4.7 Equipment intended for use in the processing and
3.2.8 owner-operator—the firm having either legal owner- incorporation of radioactive wastes in host composites or
ship responsibilities and rights for the nuclear and radioactive matrices may operate at high temperatures and pressures and
materialshandling/processingfacilitywheresubjectequipment may require engineered provisions for the removal of large
is to be installed or used, or both, or the firm that has accepted heat loads under normal and emergency conditions. The
all management, engineering, operation, and maintenance re- chemicalcorrosionanderosionconditionsencounteredinthese
C1217 − 00 (2020)
processes tend to be extremely severe, placing emphasis on 4.10.2.7 Decommissioning—Decommissioning of equip-
design for containment integrity. ment. (See qualification in 4.10.3.)
4.10.2.8 Nuclear Criticality Safety—Design for nuclear
4.8 Maintenance records from the plant or from a plant
criticality safety. (See qualification in 4.10.3.)
having a similar processing mission may be available for
4.10.3 Given the foregoing non-applicability statement, this
reference. If available and accessible, these records may offer
guide may be selectively applied to laboratory, research and
valuable insight with regard to the causes, frequency, and type
development, and semi-works equipment when equipment
of failure experienced for the type and class of equipment
integrity, materials containment, and the need for ease of
being designed and engineered.
cleaning are prime design considerations, where it is deemed
4.9 The constraints cited herein are intended to help the
essential to safety, or when it is otherwise justifiable. Also,
engineer establish conditions aimed toward the following:
many of the design criteria, guidelines, and caveats set forth
4.9.1 Enhancing radioactive materials containment
herein will have applicability to certain equipment items and
integrity,
auxiliaries to be found in a reactor facility environment.
4.9.2 Minimizing the loss of in-process materials or the
Guidance provided herein relative to equipment features and
spread of hazardous radioactive contaminants,
provisions that minimize the retention of radioactive contami-
4.9.3 Minimizing equipment blemishes or faults that pro-
nation in any form, and that facilitate cleanup and
mote the adherence or retention of radiation sources,
decontamination, will generally satisfy the potential need for
4.9.4 Facilitating the ease and safety of decontamination
equipment cleanup associated with the eventual decommis-
and maintenance sequences, and
sioning and disposal of the equipment. Specific guidance is
4.9.5 Reducing the failure frequency rate for all types and provided in instances where design, fabrication, or integrity
classes of equipment used in this service.
considerationsareessentialtothepreservationofconditionsor
dimensions necessary to meet pre-determined and specified
4.10 Exclusions:
nuclear safety requirements.
4.10.1 In general, this guide is not intended to apply when
the conditions set forth in 1.2.1 are irrelevant to the design of
5. Quality Assurance and Quality Requirements
equipment or systems.
4.10.2 Given the conditioned exceptions set forth in 4.10.3, 5.1 Quality Assurance (QA):
this guide is not intended to apply to the following: 5.1.1 The owner-operator should have an approved QA
program that is traceable to the criteria cited in applicable
4.10.2.1 Operations—Operation of equipment or facilities.
portions of 10CFR50, Appendix B. The QA program should
4.10.2.2 Uranium Ore Mining—Equipment or facilities as-
alsomeettherequirementsofandbeinaccordancewithASME
sociated with the mining of uranium ore.
NQA-1.
4.10.2.3 Uranium/Plutonium/Heavy or Reactive Metals
Processing Equipment—Equipment for the processing, ma-
NOTE2—Theabove-referenceddocumentsaregeneralinformatanddo
chining and handling of uranium, plutonium, or other trans-
not serve as a procedure, instruction, or QA plan or program specific to
any one piece or class of equipment, or to any one task associated with
uranic materials in metallic or other forms such as solutions,
equipment design, fabrication, and installation.
slurries,powders,orpelletswhentheradiationexposurelevels
are minimal, or when such operations are carried out in hoods
5.1.2 Eachsub-contractorengineeringfirmandeachvendor
or glove boxes and do not require massive radiation shield
involved in equipment design, fabrication, inspection, testing,
walls or enclosures. (See 1.2.2.)
and installation should have a QA program traceable to both
4.10.2.4 Laboratory/Research and Development/Semiworks the criteria of 10CFR50, Appendix B and the requirements of
Equipment—Equipmentfortheabovenamedfacilities.Theuse
the owner-operator’s QA program.
of this guide in an unrestricted manner would result in
5.1.2.1 The vendors or sub-contractor firms should be re-
equipment that is over-designed and costly for the above
quired to submit their QA programs to the owner-operator
service conditions. (See qualification in 4.10.3.)
client for review and acceptance prior to initiating firm design
4.10.2.5 Ancillary and Support Services—Equipment and and engineering work, and before materials procurement and
facilities designed for ancillary and service facilities that are fabrication commences.
located and installed outside shield walls, in spaces that are 5.1.3 An individual QA plan, specifically applicable to the
directly accessible for purposes of operation, maintenance and
subject equipment (or service), should be prepared early in the
repair. (Note, however, the exception stated in 1.2.3.) conceptual design stage, and implemented throughout the
4.10.2.6 Nuclear (Fission) Reactors and Auxiliaries design, fabrication, inspection, and installation phases for the
Thereof—Design of nuclear fission reactor vessels and auxil- equipment.Complete,definitive,andspecificqualityassurance
iary components and systems used in, or associated with, methods and procedures should be delineated in this QAplan.
power reactor facilities or to nuclear reactors and auxiliaries The document should be controlled, numbered, or otherwise
intended for any other use or purpose. This guide does not identifiable to facilitate its being referenced in other docu-
apply to any equipment item or complex where the primary ments.Whereappropriate,referencetotheQAPlanshould: (1)
equipment design considerations include the dissipation of appearonvesselorequipmentdrawingsordocuments,orboth,
fission heat, or where the removal of radioactive decay heat (2) be included in applicable fabrication specifications, (3) be
loads resulting from reactor shutdown is a necessity, or both. included in applicable purchase order or procurement
(See qualification in 4.10.3.) documents, (4) be included in specifications and procedures
C1217 − 00 (2020)
covering equipment inspection and testing, (5) be included in or presently applicable and specified design conditions,
procedures for the preparation and packaging of equipment for configuration, quality requirements, integrity, and other condi-
shipment,,and (6)beincludedinspecificationsandprocedures tions or requirements established for the equipment are
covering equipment installation. This should apply regardless contemplated, a documented effort should be made to review
of the origins of the drawings or documents. and clear changes through the individuals or group having
5.1.3.1 All specific QA instructions contained in the QA original or equivalent design and engineering responsibility.
All such changes themselves should be well documented as to
plan should indicate the tasks and responsibilities for which
any and all individuals, functions, or groups are to be held the reasons and the authorizations for making the changes.
5.2.5 Handling, packing, protection, shipping, storage, and
accountable.
installationofequipmentdestinedforserviceunderthesubject
5.1.4 The individual QAPlan should be written and applied
service conditions should be accomplished with and through
insuchamannerastoassignresponsibilitiesbothforperform-
the use of procedures and controls that have been included in
ing tasks, and for verifying adherence to QA Plan require-
eithertheQAprogramortheindividualQAplanspecifictothe
ments. If the responsibility for verifying specified QA
equipment, and which ensure that the quality and integrity of
inspections, examinations, analyses, and tests is wholly or
the equipment is not compromised or diminished.
partially delegated to equipment vendor or fabricator
organizations, rigid back-up verification procedures should be
5.3 Records Retention—All records of design, fabrication,
carried out.
inspection,andtestingshouldbepassedintothecustodyofthe
5.1.5 The owner-operator or responsible design and engi-
owner-operator. The records should be retained for the useful
neering organization should reserve the right to visit suppliers’
life of the equipment or system.
and fabricators’facilities to (1) perform audits or surveillance
5.3.1 All such records generated by sub-contractor design
activities, (2) witness specified operations, or (3) examine
andengineeringfirmsandbyequipmentvendorsorfabricators,
pertinent records. It may also propose changes to the QAPlan
or both, on and for the equipment should be furnished, for
and relevant procedures.
audit, to the organization having overall primary design and
engineeringresponsibility.Theretentionrequirementsforsuch
5.2 Quality Requirements:
records should be specified in writing.
5.2.1 The quality and integrity of methods, workmanship,
5.3.2 Such records should be available for audit purposes at
and materials associated with the design and fabrication,
any time during the period of their retention.
testing, and inspection of equipment or systems intended for
5.3.3 Vendors are cautioned to duplicate such records as
service under the subject conditions must be commensurate
may be prudent or necessary for their retention, and to protect
with calculated, known, or demonstrable needs. Such needs
and preserve such records with the utmost care until they are
arise from: (1) stated risks and hazards, whether known or
passed into the custody of the owner-operator.
perceived, associated with the handling and processing of
nuclear and radioactive materials, (2) basic physical and
6. General Requirements
chemical principles, and (3) applicable codes and regulations.
6.1 Design Caveat:
The originating organization for the design and engineering of
6.1.1 No equipment or components having a set perfor-
the equipment should determine such needs, and should then
mance function should be located in a nuclear and radioactive
document the calculations or rationale, or both, by which such
materialshandlingandprocessingenvironmentunlessthereare
needs were determined.
no safe, practicable, or cost effective alternatives, or combina-
5.2.2 The owner-operator, or alternatively the individual or
tions thereof. If the in-cell placement is not necessary, the
organization defining the service conditions and performance
subsequent decontamination and maintenance need is made
requirements for a piece of equipment or for a system should
much more difficult when operating equipment or functional
specify any and all conditions to be met. The individual or
components are placed in a remote-operated canyon or cell.
group should specify material requirements and determine the
6.1.2 The design of nuclear processing equipment shall
needforandspecifythetestsandinspectionrequirements,and
include provisions to minimize the release of radioactive
should establish or state the acceptance criteria by which
material from process vessels and equipment (including pipes
compliance is to be judged and recognized, and should state
or lines connecting to vessels or areas that are not normally
what records are required.
contaminated with radioactive material, such as cold reagent
5.2.3 The design and engineering records, including
tanks and instrument air) during normal and foreseeable
calculations, mathematical modeling, stress analysis, test
abnormal conditions of operation, maintenance, and decon-
results, and other engineering documents for equipment or
tamination.
systems intended for critical equipment or systems, as may be
adjudged by the owner-operator because of service conditions
6.2 Design Features and Constraints for Vessels:
should be cross-checked, verified, and authenticated by an
6.2.1 All equipment fabricated of stainless steel and alloy
independent analysis. Such analysis should be in accordance
materials and intended for use in this service should have a
with the applicable or specified portions of ASME NQA-1.
very smooth surface finish, one equivalent or superior to a
5.2.4 Modification of equipment, in any way and at any No. 2B bright mill finish as commercially supplied on high
stage of its life, might contribute to a subsequent failure if the qualityrolledsheetproducts.Thisappliestoallsurfaces,inside
design intent or capabilities of the equipment, or both, are andout,regardlessofthelocationororientation,orboth,ofthe
unknownormisunderstood.Ifanydeviationsfromtheoriginal surfaces.Theintentistodiscouragetheretentionofradioactive
C1217 − 00 (2020)
contaminants and to facilitate ease of decontamination. This figuration will be at known positions. The service connections
provision is also applicable to cast and forged items to the foracondenser,anagitator,orapumpmaybesixtofifteenfeet
extent that smooth surface finishes can be achieved at an
above its mounting flange on the base vessel. Any tilt or
acceptable cost level. distortion of the mounting flange can tilt, throw off, or
misposition the datum connection points on the auxiliary
6.2.1.1 The surfaces should be free of gouges, scratches,
crevices, cracks (regardless of their origins, causes, or equipmentitemsothattheservicejumperscannotbeattached.
Equipment design based on a minimum adequate metal thick-
character),voids,weldripplesoroverlap,inaccessiblesurfaces
and pits that can capture and retain dirt, moisture, and ness for given design or operating temperature and pressure
particulate or deposited radioactive contaminants. conditions is not always acceptable for these reasons.
6.2.1.2 Equipment vendors and fabricators should be re- 6.2.5 An as-built record of the precise position of each of
quested to submit weld samples and surface finish samples
theconnectionandpositioningelements,forexample,the X, Y,
typical of those finishes they propose to supply for each piece
and Zpositioncoordinatesforeachnozzle,flange,dowel,bolt,
of equipment on which they are bidding. The purchase order
and dowel hole, should be taken and documented prior to the
specification should state surface finish requirements in terms
time the equipment is placed in its service location. The
of the samples submitted, or in terms that are readily
measurements recorded should include nozzle, flange, and
identifiable, achievable, and verifiable.
dowel tilt or cant, including degree and direction with respect
6.2.2 The inclusion of weep holes or vents in reinforcing to the nominal vessel centerlines and the vessel’s support base
pads and collars around flanged openings, nozzles, support
or legs. The placement accuracy and the alignment of dowels,
trunnions, or lift eyes is not permitted on equipment in this
flanges,andguideswithregardtoverticality,flatness,tilt,cant,
service, irrespective of code fabrication procedural require-
directionoftilt,orcant,shouldbewithinrequiredandspecified
ments.Allsuchspecialreinforcementpadsorcollarsshouldbe
tolerances. If the equipment is destined to operate at tempera-
seal welded around the entire perimeter of the pads or collars.
tures in excess of approximately 150 °C the measurements
This provision requires that the metal surfaces enclosed be
should be checked after the equipment has been cycled
absolutely clean and dry during fabrication.
betweenambientroomtemperatureandtheoperatingtempera-
6.2.3 Impact nut retention provisions such as collars are
ture two or three times so that any residual thermal distortion
generally required around bolt holes on the top flange face of will be accommodated.
flanged joints, when such connections are part of the equip-
6.2.6 All flanged openings and nozzles on equipment in-
ment design configuration. Such nut retention collars must
tended for liquids handling and processing should be placed at
have drain holes or slots that permit run-off and draining of
theextremetopofthevessel,oralternately,atalevelabovethe
liquids used during decontamination sequences.
maximum liquid fill level likely to be experienced during the
6.2.4 The thickness of material used for equipment is
operational cycles for the vessel.
critical to its ability to resist bending, flexing, and distortion.
6.2.6.1 A freeboard in the range of 15 to 20% should be
The dimensions of plate, structural members, pipe schedule or
provided for equipment used in non-boiling liquids processing
thickness, positioning members such as dowels, trunnions and
service. The freeboard may need to be increased beyond the
guides, and other elements of the equipment should be set at
suggested level if the equipment has a tall, thin configuration.
levels that will resist damage once the equipment has been
If the equipment has an overflow nozzle, the overflow nozzle
fabricated.Agenerousmetalthicknessallowancemayoftenbe
should be placed opposite the vent nozzle location to provide
justifiedonthebasisofpreventingdistortionanddamagetothe
for a vent air sweep across the vessel. The overflow nozzle
equipment while it is being transferred and handled during
shouldturndownandextendtowithinthreeinchesofthebase
shipment, or during installation in a remote-operated facility.
of the equipment to minimize splashing.
Adherence to this caution can result in a metal thickness over
6.2.6.2 The objective of high openings placement is to
and above that required to meet design basis and operational
create a vessel configuration that will minimize chances of
temperature and pressure conditions. Costs of the extra metal
accidental overflow and drainage or leakage of radioactive
areofminimalconcerncomparedwiththeassuranceofhaving
liquids, solutions, or slurries into the processing cell or canyon
a dimensionally stable piece of equipment.
in the event of gasket, seal, or jumper pipe failure.Accidental
6.2.4.1 Theprimeobjectiveofthecautionstatementin6.2.4
overfill of vessels is not common, but it has been known to
is to preserve the accuracy of placement of the nozzles, the
happen.
positioning dowels and trunnions, the guides and the datum
6.2.6.3 Anti-siphon protection should be incorporated into
base plates or support points, and such other elements of the
the design of the vessel or its jumper, or both, or connecting
equipment as may be necessary in order that when the
lines. Such protection is required to prevent accidental transfer
equipment is placed in its service position the connection
of liquids from the vessel to an unintended location. Such
points will be at known locations. This contributes to the
siphoning transfers can be caused by variable liquid levels in
attainment of leak-tight hookup of pipe jumpers for process
vessels, due to condensation and collapse of steam pressure in
and service connections, and secure connection of instrumen-
the lines of transfer jet or sparger connections, or from other
tation and electrical power supply jumpers. It also assures that
flange faces and positioning dowels and guides for the mount- causes. Equipment and facilities design must provide protec-
tion against transfer or suck-back of radioactive materials into
ing of auxiliaries such as agitators, pumps, condensers,
columns, and other components on the base equipment con- occupied operating areas.
C1217 − 00 (2020)
6.2.7 Gusseting and reinforcement for the support or stiff- 6.3.1 Jumpers should be configured to drain towards the
ening of flanged openings and nozzles, and for stiffening the vessel on the receiving end of the connection insofar as is
heads or shells of vessels, should be placed on the external practicable.
sides of the vessel to facilitate ease of cleanup and decontami- 6.3.2 Jumpers and lift bails or lift yokes should be config-
nation. Placement and configuration of the reinforcement
uredandbalancedsoastohanginaverticalandstableposition
gussets should not create liquid entrapment points. Placement when suspended from the hook on a lift hoist.
of reinforcement gusseting on the external side benefits cali-
6.3.2.1 Lift bails and lift yokes are low maintenance com-
bration accuracy for the vessel.
ponents that are seldom transferred into areas where adhering
6.2.8 Lift eyes or trunnions on vessels should be positioned
surfacecontaminationisathreattopersonnel.Thematerialsof
so as to be visible to the operator of the lifting equipment and
construction(Section7)andthesurfacefinishconstraints(6.2)
so as to be clear of all nozzles and openings on the vessel.The are much less stringent for such components. Two sets of lift
lift points must be readily accessible to the hoist hook used to
bails and lift yokes should be provided, one set being used and
lift and transport the vessel. If equipment design is such that a stored in the contaminated environment, and the other set used
lift yoke or lift bail suspended from the hoist hook is intended
to transfer equipment into and out of the contaminated envi-
orrequiredtoliftandtransportthevessel,theplacementofthe ronment.
lift points on the vessel shall be such as to allow the yoke or
6.4 Equipment Installation—General:
bail to be moved into the lift position with a minimum of
6.4.1 Equipment received on-site and stored while awaiting
interference.
installation in the cell or canyon environment should be stored
6.2.8.1 Lift eyes, lift bails, or trunnions should be attached
underconditionsthatpreservethedimensionalandoperational
to the main shell of the equipment, as opposed to being
integrity of the equipment.The equipment should be protected
attached to a heat transfer or insulation cover jacket.
from damage due to heat, moisture, sunlight, or corrosive
6.2.9 Equipment must be configured and balanced so as to
fumesormaterials.Theequipmentshouldalsobestoredunder
hang vertically and in a stable position when it is suspended
conditions that protect it from damage caused by transfer
from the hoist hook or lift bail or yoke. The constraints with
handling, dropped loads, flying debris, or vandalism.
regard to surface finish (see 6.2.1) apply to any ballast added
6.4.2 Allprecautionsshouldbetakentoensurethatmarking
for balancing cell or canyon equipment.
crayons, inks, paints, and labels having an unacceptable
6.2.10 Vessels designed to have a heat transfer jacket or
chloride content are not used on stainless steel equipment
those requiring insulation and an insulation jacket should be
components during storage or during test, transfer, handling,
subjected to a thorough inspection and to leak tightness and
and installation sequences. See 7.4 regarding chlorides and
weldintegritytestsbeforethejacketsareadded.Leaktightness
fluorides as causes of stress corrosion cracking.
and weld integrity tests for the jacket should be conducted
6.4.3 Equipment test, inspection, calibration, and checkout
separately.
sequences should be completed prior to equipment installation
6.2.11 The insulation (and the insulation jackets) on canyon
in the cell or canyon environment to the extent that this is
and cell equipment generally does not abut or cover nozzles,
practicable. Equipment should be immaculately clean and
openings, and lift eyes or trunnions, and does not extend to
empty when it is installed in place. To the extent required,
cover the top and bottom of the vessels. The insulation on
equipment openings should be sealed to exclude dusts and
canyon or cell equipment is most often provided to keep
moisture (and the introduction of apple cores, cigarette butts,
surface temperatures low and thus minimize thermal air
and other debris by vandals) during the interval between the
currents in the cell environment. The thermal efficiency of the
final cleaning of the equipment and the installation in place.
equipment is a secondary consideration.This latter generaliza-
Precautionsshouldbeincludedintheinstallationspecifications
tion does not apply in the case of furnaces, melters, and other
that call for the removal of all such temporary seals as a
equipment operating at temperatures in excess of 125 °C, or
near-final installation step.
where surfaces must be insulated for process reasons.
6.4.4 All equipment should be handled with extreme care
6.2.12 Insulation cover jackets should be configured to
during transfer handling and installation sequences to ensure
allow for the free draining of decontamination liquids. The
against collision damage and dimensional changes damage.
jackets should have a short tube connection or an alternative
Pumps,mixers,agitators,centrifuges,andotherrotatingequip-
provisiontoaccommodatevacuumleaktestingoftheenclosed
ment should be handled in such a manner as to preserve shaft
volume.
straightness and rotational balance. Equipment should be
6.2.13 Equipment design should be standardized to the
handled and moved in an upright position using the same type
extentpracticablesothatcommonauxiliariessuchasagitators,
of handling hooks, lift bails, and yokes as are to be employed
pumps, condensers, lift bails, lift yokes, and jumpers may also
in the canyon or cell maintenance procedures to the extent this
be standardized. In the context used here, standardized means
is practicable.
having common dimensions and configurations rather than
6.4.5 Installation sequences should be planned and se-
having duplicate performance characteristics, although those
quenced so that other equipment is not handled above and
too may be desirable. The purpose is to decrease design costs
around previously installed components to the extent practi-
and minimize maintenance problems and the need to store
cable. Personnel access to equipment previously installed
spare equipment items.
should be sharply limited and constantly supervised. Equip-
6.3 Design Constraints for Jumpers, Lift Bails, and Yokes: mentpreviouslyinstalledshouldnotbeusedtorest,support,or
C1217 − 00 (2020)
otherwise come into contact with other equipment or compo- for gasketing, sealing, lubrication, thermal insulation cements,
nents being installed. Equipment should not be walked on or wire insulation, coatings, adsorption (ion exchange) resins,
used as an access platform. materials, and other materials or components commonly used
inthisserviceandsusceptibletoradiationdegradationdamage.
Using this information as a guide, the performance of these
7. Materials of Construction
same materials under given radiation exposure conditions is
7.1 General Considerations for Metals and Alloys:
generally predictable within an acceptable margin for error.
7.1.1 It is highly desirable that corrosion resistant alloys or
References on sources of radiation degradation damage are
metals be used for all equipment in this service. Carbon steels,
provided in Appendix X2.
copper,aluminum,andotherreadilyoxidizedmaterialscapture
7.2.3 Materials subject to radiation degradation and related
and retain radioactive contaminants in the rust and corrosion
damage effects should be configured and placed so as to be
layers. The use of a Type 300 Series stainless steel such as
readilyandseparatelyremovable.Whenthisisnotpracticable,
corrosion released 304-Lstainless is suggested as a minimum.
these materials should be placed on removable components or
The constraint applies to all elements and components of the
sub-assemblies rather than on the larger or main equipment
equipment, even those not exposed to the process.
item to facilitate removal and replacement.
7.1.1.1 Theobjectiveofthisconstraintistofacilitateeaseof
7.2.4 Whentheuseofmaterialsandcomponentssusceptible
cleanup and decontamination. Rust and oxidation complicate
toradiationdamagedegradationandfailureisunavoidable,the
the decontamination effort, making it a difficult and time-
provision of a shield or placement of such materials or devices
consuming task. The radiation exposures of maintenance
...

Questions, Comments and Discussion

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

Loading comments...