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Design Considerations TS NOT MEASUREMENT SENSITIVE DOE-HDBK-1132-99 April 1999 Reaffirmed 2014 DOE HANDBOOK DESIGN CONSIDERATIONS U.S. Department of Energy AREA EDCN Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1132-99 February 2014 Table of Changes Page Paragraph Changed To Throughout Reference citations. Revised all reference citations throughout the Order to reflect current versions of the documents. Throughout Formatting Made editorial and formatting changes. xv 3 Please provide suggestions for Please provide suggestions for improvement and material for improvement and material for consideration for future revisions consideration for future revisions to to the DOE Office of the James O’Brien, DOE Environment, Safety and Health; Headquarters, Office of Nuclear attention: Rich Stark, DOE/EH-31 Safety I-6 7 Safety analyses define the Safety analyses define the functional requirements of the functional requirements of the design, such as the type and design, such as the type and severity of accident conditions severity of accident conditions to be that the confinement system must accommodated by the confinement accommodate. system. I-10 4 Equipment that must be located Equipment located within the within the enclosure should be enclosure should be designed to designed to allow for in-place allow for in-place maintenance maintenance and/or replacement. and/or replacement. I-12 11 Various types of removal and Deleted transfer systems are discussed in International Atomic Energy Agency (IAEA) Safety Series No. 30. I-35 1 Added NCRP Report No. 151, Structural Shielding Design and Evaluation for Megavoltage X- and Gamma-Ray Radiotherapy Facilities, provides guidance regarding shielding design and evaluation for mega voltage accelerator facilities. I-35 3 ANSI N13.2, Administrative Deleted Practices in Radiation Monitoring (A Guide for Management), provides guidance for administrative practices in radiation monitoring. I-36 2 ANSI N13.4, American National American National Standard Standard for the Specification of N13.49-2001 (R2011), Performance Portable X- or Gamma-Radiation and Documentation of Radiological Survey Instruments, provides Surveys, provides both specific and guidance on personnel general guidance for facilities using monitoring devices. radioactive material or machines producing radiation fields. DOE-HDBK-1132-99 February 2014 Table of Changes Page Paragraph Changed To I-39 6 Radiation monitoring, alarm, and Radiation monitoring, alarm, and warning systems that must warning systems required to function function during a loss of normal during a loss of normal power power should be provided with an should be provided with an emergency UPS (internal or external emergency on-line). UPS (internal or external on-line). I-49 2 Design of materials management Design of materials management and storage systems should and storage systems should attempt attempt to achieve inventory to achieve inventory extension to extension to the maximum extent the maximum extent possible; that possible; that is, to minimize the is, to minimize the frequency with frequency with which inventory which inventory and reconciliation must be taken and reconciled. are necessary. I-67 2 For outdoor applications, the For outdoor applications, the capacity must also include capacity should also include maximum predicted precipitation. maximum predicted precipitation. I-90 2 For alloyed metals, however, For alloyed metals, however, additional consideration must be additional consideration should be given to the possible leaching of given to the possible leaching of impurities from the alloyed metal, impurities from the alloyed metal, even at normal room even at normal room temperatures temperatures and pressures. and pressures. I-97 2 In reality, these are the things In reality, these are the things that that designers must designers need to accommodate. accommodate. I-104 3 Because the true leakage rates of Because the true leakage rates of most tritium gloveboxes can most tritium gloveboxes can generally be certified to be no generally be certified to be no more more than 10-2 to 10-3 cm3/sec, than 10-2 to 10-3 cm3/sec, the the ingress of air into the box ingress of air into the box environment is a problem that environment is a problem to be must constantly be addressed. addressed. I-105 1 Because one of the undesired Because one of the undesired impurities will always include impurities will always include tritium tritium (as T2, HT, and/or HTO), (as T2, HT, and/or HTO), the the cleanup systems must always cleanup systems should remove remove free tritium from the free tritium from the glovebox gases. glovebox gases. I-106 1 Independent of the scale of the Independent of the scale of the operation, the tritium removal operation, the tritium removal systems used for these types of systems used for these types of containment systems must be containment systems should be capable of a very high rate of capable of a very high rate of throughput, and they should be throughput, and they should be examined with great care prior to examined with great care prior to selecting the containment selecting the containment systems systems for use. for use. DOE-HDBK-1132-99 February 2014 Table of Changes Page Paragraph Changed To I-110 1 When cleanup systems have to When cleanup systems have to run run for relatively long periods of for relatively long periods of time, time, leakage rates into and out leakage rates into and out of the of the glovebox in question, and glovebox in question, and leakage leakage rates into and out of the rates into and out of the cleanup cleanup system tend to become system tend to become additional additional factors that must be factors to consider in the overall considered in the overall design design of the facility. of the facility. I-119 3 In many instances, an existing In many instances, an existing DOE DOE facility that must be facility that needs decontamination decontaminated and and decommissioning does not decommissioned does not have a have a D&D plan and procedures in D&D plan and procedures in place that were implemented in the place that were implemented in original facility design. the original facility design. I-136 7 Each of these documents Each of these documents contains contains the technical the technical specifications for specifications that the wastes acceptance of their vitrified high- produced must meet for level waste into the repository. acceptance of their vitrified high- level waste into the repository. II-1 7 Certain aspects of the Certain aspects of the arrangement arrangement and layout, such as and layout, such as egress and egress and access, must satisfy access, are required to satisfy the the building code or local code building code or local code requirements. requirements. II-23 1 When arranged horizontally, a When arranged horizontally, a minimum distance of 30 inches minimum distance of 30 inches shall be provided along one side should be provided along one side of each tray run to allow for of each tray run to allow for installation and maintenance. installation and maintenance. II-23 1 When arranged vertically (trays When arranged vertically (trays above each other) cable trays above each other) cable trays shall have a minimum vertical should have a minimum vertical spacing of 16 inches for trays spacing of 16 inches for trays which which have a 3-inch loading have a 3-inch loading depth and 17 depth and 17 inches for trays inches for trays which have a 4-inch which have a 4-inch loading loading depth to allow for depth to allow for maintenance maintenance and installation and to and installation and to permit the permit the use of cable pulling use of cable pulling equipment equipment when required. when required. DOE-HDBK-1132-99 This document is available on the Department of Energy Technical Standards Program Web page at http://www.hss.doe.gov/nuclearsafety/ns/techstds/ ii DOE-HDBK-1132-99 TABLE OF CONTENTS PARAGRAPH PAGE ACRONYMS AND ABBREVIATIONS ............................................................................ ix FOREWORD ................................................................................................................ xiii PART I: DESIGN CONSIDERATIONS INTRODUCTION ......................................................................................................... I-1 REFERENCES ............................................................................................................ I-3 SECTION 1: SYSTEMS ............................................................................................... I-6 1.1 CONFINEMENT SYSTEMS ............................................................................. I-6 1.1.1 Introduction and Scope .................................................................... I-6 1.1.2 General Considerations ................................................................... I-7 1.1.3 Primary Confinement System .......................................................... I-8 1.1.4 Secondary Confinement ................................................................ I-12 1.1.5 Tertiary Confinement ..................................................................... I-14 1.1.6 Confinement Ventilation Systems .................................................. I-14 1.2 CONFINEMENT SYSTEM DESIGN ASPECTS BY FACILITY TYPE ............ I-19 1.2.1 Plutonium Processing and Handling Facilities and Plutonium Storage Facilities ..........................................................................
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