ASTM C1217-00(2012)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
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Designation: C1217 − 00 (Reapproved 2012)
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
materials. It is the intent of this guide to set down the 1.2.1.4 Thematerialshandledorprocessedmustbekeptand
conditions and practices that have been found necessary to
maintained within one or more of the following conditions:
ensure against or to minimize the failures and outages of
(1)In a specific geometric array or configuration, and
equipment used under the subject circumstances.
(2)Withinarangeofconditionsthathavebeendetermined
1.1.2 It is intended that this guide record the principles and
to be a critically safe set of conditions for that piece of
caveatsthatexperiencehasshowntobeessentialtothedesign,
equipment, that is, 1) in a given and specified operational
fabrication, and installation of equipment capable of meeting
position where adjacent nuclear criticality interaction condi-
the stringent demands of operating, dependably and safely, in
tions are known and unchanging, 2) for a given and specified
anuclearprocessingenvironmentthatoperatorscanneithersee
set or range of operating conditions, and 3) for a given and
nor reach directly.
specified process.
1.1.3 This guide sets forth generalized criteria and guide-
1.2.1.5 The equipment can neither be accessed directly for
lines for the design, fabrication, and installation of equipment
purposes of operation or maintenance, nor can the equipment
used in this service. This service includes the processing of
be viewed directly, for example, without intervening shielded
radioactive wastes. Equipment is placed behind radiation
viewing windows, periscopes, or a television monitoring sys-
shieldwallsandcannotbedirectlyaccessedbytheoperatorsor
tem.
by maintenance personnel because of the radiation exposure
1.2.2 Thisguideisintendedtobeapplicabletothedesignof
hazards. In the type of shielded cell or canyon facility of
equipment for the processing of materials containing uranium
interest to users of this guide, either the background radiation
levelremainshighatalltimesoritisimpracticaltoremovethe and transuranium elements in any physical form under the
following conditions:
process sources of radiation to facilitate in situ repairs or carry
out maintenance procedures on equipment. The equipment is
1.2.2.1 Such materials constitute an unacceptable radiation
operated remotely, either with or without visual access to the
hazard to the operators and maintenance personnel,
equipment.
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.
1.2.3 This guide is intended to apply to the design,
1.2.1.2 The equipment will generally be used over a long-
fabrication, and installation of ancillary and support services
term life cycle (for example, in excess of two years), but
equipment under the following conditions:
equipment intended for use over a shorter life cycle is not
1.2.3.1 Such equipment is installed in shielded cell or
excluded.
canyon environments, or
1 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
Current edition approved June 1, 2012 Published June 2012 . Originally
may not directly hold or contain nuclear or radioactive mate-
approvedin2000.Lastpreviouseditionapprovedin2006asC1217–00(2006).DOI:
10.1520/C1217-00R12. rials under normal processing conditions.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1217 − 00 (2012)
NOTE 1—Upsets, accidents, or certain emergency conditions may be
2. Referenced Documents
specified (and thus required) design considerations, but not necessarily
2.1 Industry and National Consensus Standards—
acceptable or normal operating circumstances under this definition.
Nationally recognized industry and consensus standards appli-
1.2.4 This guide is intended to apply to the design and
cable in whole or in part to the design, fabrication, and
fabrication of any and all types of equipment for radioactive
installation of equipment are referenced throughout this guide
wastes processing when any of the conditions cited in 1.2.1
and include the following:
apply. This would include equipment for waste concentration;
2.2 ASTM Standards:
for incorporation of wastes in selected host materials or
C859Terminology Relating to Nuclear Materials
matrices;andforthefixation,encapsulation,orcanningofsuch
D5144Guide for Use of Protective Coating Standards in
wastes. It is intended to apply to all such wastes, regardless of
Nuclear Power Plants
the product waste composition or form. The product radioac-
2.3 ANSI Standards:
tive waste may have a glass, ceramic, metallic, concrete,
ANSI/ANS8.1NuclearCriticalitySafetyinOperationswith
bituminous, or other type of host material or matrices
Fissile Materials Outside Reactors
(composition), and may be in pelletized, solid, or granular
ANS GlossaryofTermsinNuclearScienceandTechnology
form.
(ANS Glossary)
1.3 User Caveats:
ANSI A14.3Ladders, Fixed Safety Requirements
1.3.1 This standard does not purport to address all of the
2.4 ASME Standard:
safety concerns, if any, associated with its use. It is the
Boiler and Pressure Vessel Code, Section VIII
responsibility of the user of this standard to establish appro-
ASME NQA1QualityAssurance Requirements for Nuclear
priate safety and health practices and determine the applica-
Facility Applications
bility of regulatory limitations prior to use.
ASME NOG-1,Rules for Construction of Overhead Gantry
NOTE2—Warning:Thisstandardpertainstoequipmentusedinandfor
Cranes (Top-Running Bridge, Multiple Girder)
the handling and processing of nuclear and radioactive materials. These
2.5 Federal Regulations:
operations are known to be hazardous for a variety of reasons, one being
10CFR50,Appendix B, Quality Assurance
chemical toxicity.
29CFR1910,Occupational Safety and Health Standards
1.3.2 This standard is not a substitute for applied engineer-
2.6 National Electrical Manufacturers Association (NEMA)
ing skills. Its purpose is to provide guidance. 6
Standards:
1.3.2.1 The guidance set forth in this standard relating to
NEMA250Enclosures for Electrical Equipment 1000 Volts
design of equipment is intended only to alert designers and
Maximum (Type 4)
engineers to those features, conditions, and procedures that
2.7 National Fire Protection Association (NFPA) Stan-
have been found necessary or highly desirable to the acquisi- 7
dards:
tion of reliable equipment for the subject service conditions.
NFPA 70,National Electric Code
1.3.2.2 The guidance set forth results from discoveries of
conditions, practices, features, or lack of features that were
3. Terminology
found to be sources of operational or maintenance trouble, or
3.1 Definitions:
causes of failure.
3.1.1 The terminology employed in this guide conforms
1.3.3 It is often necessary to maintain the materials being
with industry practice insofar as practicable.
processed within specific chemical composition or concentra-
3.1.2 For definitions of terms used in this guide, refer to
tion ranges, or both. When such constraints apply, it may also
Terminology C859 and ANS Glossary.
be necessary to create and maintain a specific geometric array
3.2 Definitions of Terms Specific to This Standard:
to minimize the chances of a nuclear criticality incident.
3.2.1 The terms defined below are of a restricted nature,
Designers and engineers are referred to other standards for
specifically applicable to this guide.
additional guidance when such requirements apply.
3.2.2 accident—an unplanned event that could result in
1.3.4 Equipment usage intent, service conditions, size and
unacceptable levels of any of the following: (1) equipment
configuration, plus the configuration and features of the oper-
damage, (2) injury to personnel, (3) downtime or outage, (4)
ating and maintenance environments have an influence on
equipment design.Therefore, not all of the criteria, conditions,
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
caveats, or features would be applicable to every equipment
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
item.
Standards volume information, refer to the standard’s Document Summary page on
1.3.5 It is intended that equipment designed, fabricated,
the ASTM website.
nd th
procured, or obtained by transfer or adaptation and re-use of Available fromAmerican National Standards Institute, 11 W. 42 St., 13 Fl.,
New York, NY 10036.
existing equipment, and installed in accord with the standard
Available fromAmerican Society of Mechanical Engineers, 3 ParkAve., New
meet or exceed statutory, regulatory, and safety requirements
York, NY 10016.
for that equipment under the applicable operating and service
Available from U.S. Government Printing Office, Superintendent of
Documents, Mail Stop SSOP, Washington, DC 20402-9328.
conditions.
Available from Global Engineering Co., 15 Inverness Way, Englewood, CO
1.3.6 This standard does not supersede federal or state
80112.
regulations, or both, and codes applicable to equipment under
Available from National Fire Protection Agency (NFPA), One Batterymarch
any conditions. Park, Quincy, MA 02269.
C1217 − 00 (2012)
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
duringhandlingandinstallationsequences.Forthisreason,the
3.2.3 accountability—the keeping of detailed records on,
subject equipment should be handled and installed under
andtheresponsibility—onthepartofoperationspersonneland
closely controlled and supervised conditions.
plant management—of being accountable for the amounts of
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
criteria applicable to the design of equipment intended for this
3.2.4 datum connection points—those locations on equip-
use.
mentwhereseparateauxiliaryequipmentitemssuchaspumps,
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
air-tight vessel configuration. Radioactive materials must be
3.2.5 engineering responsibility—an obligation to perform
contained.
engineering design activities assigned to a specified organiza-
4.5.2 Equipment must be capable of withstanding rigorous
tion.
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
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