Project Design Criteria Document

Project Design Criteria Document1. Project Design Criteria DocumentBSCChange HistoryComplete only applicable items.2. QA: QAPage v of 2703.DI: 000-3DR-MGR0-00100-000-007Project Design Criteria Document7. Revision No:8. Description of Change:Section 7.0, Preclosure Safety Analysis Criteria, has been added to this revision of the Project Design Criteria document.The resolutions to Criteria/Basis Change Notices 000-3DR-MGR0-00100-000-005-CBCN001 through CBCN012 was incorporatedinto this revision of the Project Design Criteria document.007This revision is a major re-write. No annotations of changes are used. The Project Design Criteria document was revised toincorporate CBCN-001 thru CBCN-017 and the addition of Regulatory Guidance Agreements (RGAs) that are applicable to therepository design. Deleted Appendix A and Appendix B of the PDC (Sections 9 and 10 respectively) since they were replace by the(RGAs). Approximately 100 RGAs were incorporated in the applicable sections of the PDC. Made editorial and other non technical corrections. References were updated to later revision as necessary.The following Criteria/Basis Change Notices were incorporated into this revision of the PDC:000-3DR-MGR0-00100-000-000-CBCN001 - Added heliport location design criteria in Section 4.2.5.000-3DR-MGR0-00100-000-000-CBCN002 - Added design criteria for clearances and setback for security purposes in Section4.2.1.5.000-3DR-MGR0-00100-000-000-CBCN003 - Revised wording of Section 4.9.5 to correctly address water well criteria.000-3DR-MGR0-00100-000-000-CBCN004 - Revised Section 1.7 to incorporate IEEE/ASTM SI-10-2002 in response toCondition Report (CR) action 6657-005.000-3DR-MGR0-00100-000-000-CBCN005 - Revised Sections 5.2, 5.5, and 5.7 to incorporate ASME NQA-1-2004 as the latestversion of the QA requirement to supplement the QMD. Although the CBCN requires incorporation of ASME NQA-1-2004, BSChas elected to utilize the ASME NQA-1-2000 version.000-3DR-MGR0-00100-000-000-CBCN006 - Revised Section 6.1.10.2.3 in response to CR 9975. The necessary wording fromNUREG-0800 is now included in the criteria. Other document changes for CR 9975 are not included in this CBCN.000-3DR-MGR0-00100-000-000-CBCN007 - Revised PDC Section 6.1.10.1.1 in response to Condition Report (CR) 9623. ThisCBCN incorporates 800-IED-MGR0-00701-000-00A in Section 6.1.10.1.1, and by inclusion incorporates the associated DTN.000-3DR-MGR0-00100-000-000-CBCN008 - Revised Sections 4.2.13.5, 6.1.1, 6.1.3, 6.1.6, and 6.1.7 in response to ConditionReport (CR) 9623. This CBCN incorporates 100-IED-WHS0-00201-000-00A and 800-IED-MGR0-00505-000-00A in the affectedsections of the PDC, and by inclusion incorporates the associated DTN.000-3DR-MGR0-00100-000-000-CBCN009 - Revised Section 4.3.3.1 in response to Condition Report (CR) action 9877-001.Corrected typographical error for switchyard voltage from 13.8 kV to 138 kV000-3DR-MGR0-00100-000-000-CBCN010 - Revised PDC to incorporate TMRB-2004-051. Section 4.10.3.7 was revised toinclude the radiation classification zone chart.000-3DR-MGR0-00100-000-000-CBCN011 - Replaced Sections 4.2.11.5.3 and 4.2.13.2.4 reference to ANSI/AISC 2005 [DIRS176320] with the previously referenced ANSI/AISC 1989 [DIRS 159157].000-3DR-MGR0-00100-000-000-CBCN012 - Revised PDC Section 4.6.2.6.2 and added new criteria (Section 4.6.2.4.6) inresponse to Condition Report (CR) 10376.000-3DR-MGR0-00100-000-000-CBCN013 - Added ASME NUM-1-2004 [DIRS 180437] code for jib crane in Section 4.8.1.2.4.000-3DR-MGR0-00100-000-000-CBCN014 - Incorporate Regulatory Guidance Agreement (RGA) REG-CRW-RG-000010,Agreement for Regulatory Guide 1.12, Rev. 0 into the Sections 4.6.1.13 and 4.6.3.4.000-3DR-MGR0-00100-000-000-CBCN015 - Revised PDC Sections 5.1.1 and 5.1.2 to include by reference the Waste PackageComponent Methodology Report, 000-30R-WIS0-00100-000-002, in response to CR action 10202-001.000-3DR-MGR0-00100-000-000-CBCN016 - Revised Sections 4.2.12, 4.2.13, 4.9.1, 4.10.2, and 4.12.2 in response to ConditionReports (CRs) 10501, 10514, 10685, and 10688.000-3DR-MGR0-00100-000-000-CBCN017 - Revised Sections 4.2.11, 4.2.12, 4.3.7, 4.6.1, and 4.9.2 to incorporate the EmergencyResponse Facilities (ERF) functions as provided in Regulatory Guidance Agreement REG-CRW-RG-000455, Agreement forNUREG-0696, Functional Criteria for Emergency Response Facilities – Final Report.000-3DR-MGR0-00100-000-007Page v of 270October 2007

Project Design Criteria DocumentINTENTIONALLY LEFT BLANK000-3DR-MGR0-00100-000-007Page vi of 270October 2007

Project Design Criteria DocumentContents1Introduction11.1Purpose and Scope11.2Regulatory Guidance Document Applicability11.3U.S. Department Of Energy Directives Applicability21.4National Codes And Standards Applicability21.5Quality Assurance31.6Safety Classifications31.7Units of Measure32Acronyms And Abbreviations53Definitions94Facility Design Criteria11General Design Criteria114.1.1Facilities Requiring Sanitation Services114.1.2Potential Explosives Storage Facilities114.1.3Energy Conservation114.1.4Life Cycle Cost Criteria and Methodology124.1.5Additional Sustainable Design Criteria124.1.6Waste Prevention, Recycling, and Federal Acquisition164.1.7American National Standard Institute Standards164.1.8Environmental Protection164.1.9Level of Design and Operational Information184.1.10Defining Condition Classification of Spent Nuclear Fuel184.1.11Cleanliness Requirements19Civil/Structural/Architectural Design Criteria194.2.1Civil Site Development194.2.2Civil Earthwork224.2.3Civil Roadways, Parking Areas, Walkways, and Open Areas224.2.4Civil Railroad Design244.2.5Civil Heliport Design244.2.6Civil Sanitary Sewer System254.2.7Civil Storm Drainage System264.2.8Not Used274.2.9Civil Utilities27Additional Civil Design ge vii of 270October 2007

Project Design Criteria Document4.2.11Structural Surface Design Criteria314.2.12Architectural Design Criteria454.2.13Subsurface Structural Design Criteria63Electrical Design Criteria704.3.1General Electrical Design Criteria704.3.2Emergency Electrical Power Design Criteria874.3.3Switchyard and Transmission Design Criteria894.3.4Normal Electrical Power Design Criteria904.3.5Safeguards and Security Design Criteria904.3.6Electrical Support Design Criteria934.3.7Communication Design Criteria934.3.8Important to Safety Electrical984.4Not Used984.5Geotechnical Design Criteria984.5.1Applicable Codes and Standards984.5.2Ground Support Design Criteria994.34.6Instrument And Control Design Criteria1024.6.1Digital Control and Management Information and Non-ITS ProcessControl System Design Criteria1024.6.2Radiation/Radiological Monitoring Design Criteria1084.6.3Environmental/Meteorological Design Criteria1124.6.4General Instrumentation Design Criteria1164.6.5Deleted1254.7Not Used1254.8Mechanical Handling125Mechanical Handling Design Criteria125Mechanical Design Criteria1294.9.1Fire Protection Design Criteria1294.9.2Surface Heating, Ventilation, and Air Conditioning System DesignCriteria1454.9.3Subsurface Ventilation Design Criteria1554.9.4Site-Generated Radioactive Waste Management Design Criteria1584.9.5Plant Services System Design Criteria1624.9.6Plant Heating and Cooling System Design Criteria1694.9.7Cask / TAD / Waste Package / Pool Process Systems Design Criteria1724.9.8Site-Generated Non-Radioactive Waste Management Design Criteria1784.10Nuclear Design Criteria1814.10.1Nuclear Engineering Design Criteria1814.10.2Criticality Design Criteria1854.10.3As Low As is Reasonably Achievable Design Criteria1894.8.14.9000-3DR-MGR0-00100-000-007Page viii of 270October 2007

Project Design Criteria Document4.10.4Control of Access to High Radiation Areas1944.10.5General Radiological Criteria196Offsite Interface Design Criteria1964.11.1Offsite Utility Interface Design Criteria1964.11.2Transportation Project Interface Design Criteria196Plant Design Criteria1964.12.1Nonmetallic Insulation for Stainless Steel1974.12.2Deleted1974.12.3Piping Design Criteria197Solar Power Station Design Criteria1974.114.124.135Waste Package And Components Design Criteria5.1198Waste Package Mechanical Design Criteria1985.1.1Structural Design Criteria1985.1.2Metallurgical Design Criteria1985.1.3Waste Package Thermal Design Criteria199Waste Package Fabrication Criteria199Waste Package QA Criteria200Waste Package Closure System Design Criteria2005.3.1Waste Package Closure System Equipment Design Criteria2005.3.2Waste Package Closure System Process Criteria2005.4Emplacement Pallet Design Criteria2015.5Emplacement Pallet Fabrication Criteria202Emplacement Pallet QA Criteria2035.6Drip Shield Design Criteria2035.7Drip Shield Fabrication Criteria203Drip Shield QA Criteria2045.25.2.15.35.5.15.7.16Site Specific Criteria6.1205Natural ent Temperature2076.1.7Humidity2076.1.8Frost Line2086.1.9Flood -MGR0-00100-000-007Page ix of 270October 2007

Project Design Criteria Document6.1.12Radon2126.1.13Silica Dust2126.1.14Rockfall2126.1.15Structural Geology213Thermal213Cladding Temperatures2136.26.2.17Preclosure Safety Analysis Criteria2147.1General Criteria for Repository Preclosure Safety Analysis2147.2Preclosure Period for Preclosure Safety Analysis2147.3Identification and Systematic Analysis of Hazards and EventSequences2147.3.1Identification and Systematic Analysis of Hazards and Initiating Events2157.3.2Comprehensive Identification of Potential Event Sequences2157.3.3Quantifying Initiating Event Frequency2167.3.4Initiating Event and Event Sequence Screening Analyses2167.3.5Quantification of Event Sequence Frequency216Reliability Modeling and Quantification2177.4.1Reliability Modeling and Quantification: Active Systems andComponents2177.4.2Reliability Modeling and Quantification: Passive Structures andComponents2187.4.3Dependent and Common Cause Failures2187.4.4Human Reliability Analysis2187.4.5Modeling for Active Components2197.5Treatment of Uncertainties and Sensitivity Analysis2197.6List of SSCs and Associated Failure Frequencies2207.7Event Sequences Leading to Criticality2207.8Calculation of Seismic Event Sequence Frequency2207.9Classification of ITS SSCs, Identification of Procedural SafetyControls, and Development of Nuclear Safety Design Bases2217.10Consequence Analyses for Exposure to Radiation from EventSequences2217.11Margins for Event Sequence Categorization and Consequence Analyses2227.12Assessment of Rail Equipment Maintenance Yard Risks2227.13Guidance in Support of Generally Accepted PCSA Methods2227.48References2248.1Documents Cited2248.2Codes, Standards, Regulations2358.3Source Data2678.4Output Constraints268000-3DR-MGR0-00100-000-007Page x of 270October 2007

Project Design Criteria Page xi of 270October 2007

Project Design Criteria Document1 Introduction1.1 Purpose and ScopeThe Project Design Criteria Document (PDC) provides the design criteria necessary to support the development ofpreliminary and detailed design for all repository structures, systems, and components (SSCs). The PDC satisfiesrequirement 3.2.1.K of the Civilian Radioactive Waste Management System Requirements Document (CRD),DOE/RW-0406 [DIRS 176715] as flowed down through requirement 3.1.1.R of the Monitored GeologicRepository Systems Requirements Document (MGR-RD), YMP/CM-0026 (DOE 2006 [DIRS 177491]), whichrequires that all repository SSCs be designed in accordance with applicable industry codes, standards, engineeringprinciples, and practices.The PDC identifies the appropriate codes and standards for all repository SSCs, including those that are associatedwith safety categories (items important to safety [ITS] and important to waste isolation [ITWI]) as determined fromthe 000-3DR-MGR0-00300-000-001, Basis of Design for the TAD Canister-Based Repository Design Concept(BOD) (BSC 2007 [DIRS 182131]). As the design evolves, the PDC will be revised in accordance with theevolving design and safety categories for repository systems as provided in changes to the BOD. The BODclassifications will not be repeated or referenced in this document. As the design evolves, application of specificsections of these codes and standards for particular applications will be determined during the design process andused in the development of design products.The PDC is organized along traditional discipline lines and comprised of sections that contain general designcriteria or generic discipline design criteria, design load combinations, design acceptance limits, design load cases,site conditions, and applicable codes, standards, and regulations for each discipline in Engineering.The PDC provides constraints to the design in the form of applicable codes, standards, and regulatory guidancepositions. The Requirements Management Program, RQ-DIR-10, Figure 1, Section 4.1 provides an explanation ofthe requirements management program flowdown.1.2 Regulatory Guidance Document ApplicabilityThe U.S. Nuclear Regulatory Commission (NRC) requires, in 10 CFR 63.21(c)(2), Energy: Disposal of HighLevel Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada [DIRS 180319], that the safetyanalysis report (SAR) include information relative to codes and standards that the U.S. Department of Energy(DOE) proposes to apply to the design and construction of the geologic repository operations area (GROA). Thisdocument provides the information relative to codes and standards for inclusion of reference in the SAR for therepository.Design engineers will use the codes, standards, regulatory guides, and technical reports stated in this document.Changes to those documents used herein will be addressed, as necessary, in future revisions during the designprocess and will be approved by the Engineering Manager. This document will provide the code of record for theidentified NRC regulated activities and repository facilities and systems.NRC regulatory guidance documents, such as regulatory guides, interim staff guidance, and technical reports(NUREGs), provide guidance to licensees and applicants on implementing specific parts of the NRC regulations,techniques used by the NRC staff in evaluating specific problems or postulated accidents, and data needed by thestaff in its review of applications for permits or licenses.The selection of regulatory guides, interim staff guidance, and NUREGs, previously provided in Appendix A, wasbased on applicability to support the development of design products. Appendix A has been deleted and thedocumentation of the rationale for selecting the guidance documents are co-located with the criterion in the body ofthe PDC. A formal screening of a majority of the regulatory guidance documents has been conducted inaccordance with licensing procedure LS-PRO-3005, Regulatory Guidance Agreements (RGAs). Additionalscreening will eventually address the remaining documents with RGAs as well as updating the initial screening ofregulatory positions as design progresses.Many regulatory guides are written for other NRC licensed activities, but very few have been specifically writtenfor Yucca Mountain. Some regulatory guides, codes, and standards have been identified in the Yucca MountainReview Plan Final Report, NUREG-1804 (NRC 2003 [DIRS 163274]). The RGA agreement for NUREG 1804,000-3DR-MGR0-00100-000-007Page 1 of 270October 2007

Project Design Criteria DocumentREG-CRW-RG-000399 (BSC 2007 [DIRS 182359]), was "Adopted with Clarification". Even though the RGA didnot identify Engineering as being impacted, NUREG-1804 is referred to throughout the PDC. The RGA will berevised to add Engineering as an impacted organization.Any of the referenced documents that are not being used for repository design were previously detailed inAppendix B. Since the RGAs identify the applicability of the regulatory guides, codes, and standards, Appendix Bhas been deleted. Only those regulatory guides, codes, and standards that are identified as applicable are includedin the PDC. The RGAs are located in the associated rationale statement.1.3 U.S. Department Of Energy Directives ApplicabilityDOE HQ O 250.1-1998, Civilian Radioactive Waste Management Facilities -- Exemption from DepartmentalDirectives (DOE 1998 [DIRS 159140]), provides for the exemption of Office of Civilian Radioactive WasteManagement (OCRWM) facilities from certain DOE directives. The exemption applies to DOE directives thatoverlap or duplicate requirements of the NRC regarding radiation protection, nuclear safety (ITS and ITWI) for theYucca Mountain Project (YMP), including quality assurance, safeguards and security of nuclear material in thedesign, construction, operation, and decommissioning of radioactive waste (OCRWM) facilities. Exemptionsapply to requirements in directives that overlap or duplicate NRC requirements and ensure the precedence of NRCrequirements.OCRWM facilities include structures, equipment, systems, processes, or activities associated with the acceptance,transportation, storage, and disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) pursuantto the Nuclear Waste Policy Act of 1982 [DIRS 101681] and NRC regulations, where applicable. Examplesinclude interim storage structures and technologies, repository facility structures, and waste acceptance andtransportation activities.Exemptions do not apply to requirements for which the NRC defers to the DOE or does not exercise regulatoryjurisdiction. DOE directives that provide criteria applicable to the non-nuclear portion of the repository facilitywill be addressed per the Bechtel SAIC Company, LLC (BSC) contract.Applicable DOE guidance documents (Guide, Handbooks, and Standards) are used in sections of the PDC.1.4 National Codes And Standards ApplicabilityDOE O 252.1, Technical Standards Program [DIRS 159139], requires the use of voluntary consensus standards bythe DOE in a manner consistent with National Technology Transfer and Advancement Act of 1995, Public Law104-113, 110 Stat. 775 [DIRS 159251], and OMB Circular No. A-119, Federal Participation in the Developmentand Use of Voluntary Consensus Standards and in Conformity Assessment Activities [DIRS 159250].Consensus standards are the product of a standards developing organization operating with openness, balance ofinterests, due process, an appeals process, and a consensus that represents general agreement but not necessarilyunanimity.The integration of national codes and standards into the NRC regulatory process is achieved through:(a) incorporating codes and standards by reference in regulations(b) endorsing codes and standards in regulatory guides as acceptable methods for implementing regulation(c) referencing of codes and standards as a technical basis in standard review plans, technical specifications,generic communications, and inspection manuals.Although (a) is the prime example of a mandatory requirement, (b) and (c) are the primary mechanisms forallowing voluntary use of consensus standards by licensees.Regulation 10 CFR 63 does not provide prescriptive design criteria; instead it allows the DOE to develop designcriteria and demonstrate their appropriateness. Therefore, the DOE has flexibility to use any codes, standards, andmethodologies it demonstrates to be applicable and appropriate in the repository design.When codes or standards are in conflict with each other, the specific issue will be presented to the appropriatemanager for resolution. The design authority can authorize interim changes in the PDC for use until the nextrevision.000-3DR-MGR0-00100-000-007Page 2 of 270October 2007

Project Design Criteria Document1.5 Quality AssuranceThe PDC is written in accordance with EG-PRO-3DP-G04B-00001, Design Criteria, and is subject to therequirements of Quality Management Directive (QMD) QA-DIR-10 (BSC 2007 [DIRS 180474]).1.6 Safety ClassificationsSafety classifications for SSCs are documented in the 000-3DR-MGR0-00300-000-001, Basis of Design for theTAD Canister-Based Repository Design Concept (BOD) (BSC 2007 [DIRS 182131]). The BOD classificationswill not be repeated or referenced in this document.1.7 Units of MeasureUnits of measure to be used in the design, fabrication, construction, testing, and operation of the procured items forthe repository shall be in English units in accordance with IEEE Std 260.1-2004, IEEE Standard Letter Symbolsfor Units of Measurement (SI units, Customary Inch-Pound Units, and Certain Other Units) [DIRS 176341]. Thisincludes surface facilities, subsurface facilities, waste packages, and other SSCs. Units of measurement that arecurrently stated in this document as metric units may remain as such, and converted to English units, as necessary.All conversions of metric units to English units shall utilize Annexes A and B of IEEE/ASTM SI-10-2002,American National Standard for Use of the International System of Units (SI): The Modern Metric System [DIRS177651], (factors and rules, respectively). Supporting calculations or analyses, such as those for waste packages,may be performed in SI units but the design output must be performed in English units.Values should be rounded to an equal or greater number of significant figures as the value to be converted usingstandard procedures. Therefore, conversion factors are not the limit on accuracy in the calculation. Convertedvalues should be rounded to the same number of significant figures as the original quoted value. In the cases whereonly two significant figures are given in the source, only two significant figures should be provided. In such a case,it may appear as though there is a significant arithmeti

Project Design Criteria Document. The entire Project Design Criteria document is being revised (per Section 5.6 (2) ofLP-3.25Q-BSC, Rev. I, ICN 2, Design Criteria) to incorporate additional design criteria, codes and standards, etc., th