ML18025B158

Official Exhibit - NRC-006C-MA-CM01 - Northwest Medical Isotopes, LLC, Construction Permit Application - PSAR, NWMI-2013-021, Rev. 3, Chapter 3 (Sep. 2017)

ML18025B158
Person / Time
Site:	Northwest Medical Isotopes
Issue date:	09/30/2017
From:	NRC/OGC
To:	NRC/OCM
SECY RAS
References
50-609-CP, Construction Permit Mndtry Hrg, RAS 54181
Download: ML18025B158 (98)

Text

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• Chapter 3.0 -Design of Structures, Systems, and Components Prepared by: Construction Permit Application for Radioisotope Production Facility NWMl-2013-021, Rev. 3 September 2017 Northwest Medical Isotopes, LLC 815 NW gth Ave , Suite 256 Corvallis , Oregon 97330 This page intentionally left blank.

"NWMI ...*.. ..* .. .*.* .. *.*. NOmfWUT MfOICAL ISOTOPES NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Chapter 3.0 -Design of Structures, Systems, and Components Construction Permit Application for Radioisotope Production Facility NWMl-2013-021, Rev. 3 Date Published:

September 5 , 2017 Document Number. NWMl-2013-021 I Revision Number. 3 Title: Chapter 3.0 -Design of Structures, Systems and Components Construction Permit Application for Radioisotope Production Facility Approved by: Carolyn Haass Signature:

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• NOlmfWEST MEDtCAl lSOTOf"ES Rev Date 0 6/29/2015 1 6/26/2017 2 8/5/2017 3 9/5/2017 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components REVISION HISTORY Reason for Revision Revised By Initial Application Not required Incorporate changes based on responses to NRC C. Haass Requests for Additional Information Modifications based on ACRS input C. Haass Incorporate final comments from NRC Staff and ACRS; C. Haass full document revision NWMI ..**.. * . NORTMWEST MEOtcAL tSOlDPH NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components This page intentionally left blank.

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• NORTHWUT MEDICAi. ISOTOPES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components CONTENTS 3.0 DESIGN OF STRUCTURES , SYSTEMS , AND COMPONENTS

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................................... 3-1 3 .1 Design Criteria .........................................

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.................................. 3-4 3.1.1 Radioisotope Production Facility Structures , System s, and Components

............ 3-4 3.1.2 Code of Federal Regulation s .........................

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3-8 3.1.3 U.S. Nuclear Regulatory Commission

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............... 3-8 3.1.4 Other Federal Regulation s, Guideline s, and Standards ...................................... 3-10 3.1.5 Local Government Documents

.......................................................................... 3-10 3.1.6 Di s covery Ridge/Univer s ity of Mi s souri ...........................................................

3-11 3 .1. 7 Codes and Standards

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........................... 3-12 3.2 Meteorological Damage .....................................................

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................................ 3-24 3.2.l CombinationsofLoads

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.......................... 3-25 3.2.1.1 Nuclear Safety-Related Structures , System s, and Components

........ 3-26 3.2.1.2 Commercial a nd Nuclear Non-Safety-Rel a ted Structure s, Systems , and Component s ...........................................................

..... 3-26 3.2.2 Combinations for Serviceability Bas e d Acceptance Criteria ........................

..... 3-27 3.2.3 Normal Loads ..................................

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...................... 3-27 3.2.4 Wind Loading ....................

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......... 3-30 3.2.4.1 Wind Load ......................................................................

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........ 3-30 3.2.4.2 Tornado Loading ............................................................................

... 3-30 3.2.4.3 Effect of Failure of Structures, Systems , or Component s Not Designed for Tornado Load s ............................................................... 3-32 3.2.5 Rain , Snow , and Ice Loading .................................................................

............ 3-33 3.2.5.1 Rain Loads ..........................................................

.............................. 3-33 3.2.5.2 Snow Load .......................................................

................................. 3-33 3.2.5.3 Atmospheric Ice Load ..........................

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................................ 3-35 3.2.6 Operating Thermal/Self-Straining Load s ...........................................................

3-35 3.2.7 Operating Pipe Reaction Loads .......................................................................... 3-35 3.2.8 External Hazards ...................

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........................ 3-3 5 3.3 Wat e r Damage ..................................

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................................. 3-36 3.3. J Flood Protection

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............... 3-36 3.3.1.1 Flood Protection Measure s for Structure s, Sy s tems , and Component s .................................

...................................................... 3-36 3.3.1.2 Flood Protection from External Sources ..........................

.................. 3-37 3.3.1.3 Compartment Flooding from Fire Protection Discharge

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3-3 8 3.3.1.4 Compartment Flooding from Postulated Component Failures ........... 3-38 3 .3 .1.5 Permanent Dewatering System .............................

............................. 3-3 8 3.3.1.6 Structural De s ign for Flooding ............................................

.............. 3-3 8 3.4 Seismic Damage ..........................................

..................................................................... 3-39 3.4. l Seismic Input .......................

............................................................................... 3-39 3.4.1.1 Design Response Spectra .................................................................. 3-39 3 .4.1.2 Method of Analysis ........................

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............... 3-40 3.4.2 Seismic Qualification of Subsystems a nd Equipment

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............... 3-41 3.4.2.1 Qualification by Analysis .................................................................. 3-41 3 .4.2.2 Qualification by Testing ................

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.......... 3-42 3 .4.3 Seismic Instrumentation

..................................................................................... 3-42 3.4.3.1 Location and Description

.................................................................. 3-43 3.4.3.2 Operability and Characteri s tics ................................

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• NOITHWUT MEOtCAl ISOTOP£S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components 3.5 Systems and Components

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... 3-44 3.5.1 General Design Basis Information

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.................................................... 3-44 3.5.1.1 Classification of Systems and Components Important to Safety ........ 3-44 3 .5 .1.2 Classification D efinitions

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................................ 3-44 3 .5 .1.3 Nuclear Safety Classifications for Structures , Systems, and Components

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.................................... 3-45 3.5.2 Radioisotope Production Facility ............................

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3-47 3.5.2.1 System Classification

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3-53 3.5.2.2 Classification of Systems and Components Important to Safety ...... 3-53 3.5.2.3 Design Basis Functions , Values, and Criteria ....................

............... 3-55 3.5.2.4 System Functions/Safety Functions

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3-55 3.5.2.5 Systems and Components

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3-55 3.5.2.6 Qualification Methods ..............................................

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3-56 3.5.2.7 Radioisotope Production Facility Specific System De sign Basis Functions and Values ........................................

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3-56 3.6 References

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• NOflTHWUT MEOtCAl ISOTOPH NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-1. Table 3-2. Table 3-3. Table 3-4. Table 3-5. Table 3-6. Table 3-7. Table 3-8. Table 3-9. Table 3-10. Table 3-11. Table 3-12. Table 3-13. Table 3-14. Table 3-15. Table 3-16. Table 3-17. Table 3-18. Table 3-19. Table 3-20. Table 3-21. Table 3-22. Table 3-23. Table 3-24. Table 3-25. TABLES List of System and Associated Systems and Construction Permit Application Crosswalk (2 pages) ..........................

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............... 3-4 Summary of Items Relied on for Safety Identified by Accident Analyses (3 pages) ............................................

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............. 3-5 Relevant U.S. Nuclear Regulatory Commis s ion Guidance (3 pages) .............................. 3-8 Other Federal Regulations , Guidelines , and Standards

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.................................. 3-10 Local Government Documents (2 pages) ............

........................................................... 3-11 Discovery Ridge/University of Missouri Requirements

................................................ 3-11 Design Codes and Standards ( 12 pages) ........................................................................ 3-12 Load Symbol Definitions (2 pages) ............................................................................... 3-24 Load Combinations for Strength Based Acceptance Criteria, Nuclear Safety-Related ........................................................................................................................... 3-26 Load Combinations for Strength Base Acceptance Criteria , Commercial

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3-27 Load Combinations for Serviceability Based Acceptance Criteria ................................ 3-27 Lateral Earth Pressure Loads ......................................................................................... 3-28 Floor Live Loads .......................................................

..................................................... 3-29 Crane Load Criteria ....................................................................................................... 3-29 Wind Loading Criteria ..................................

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.............................. 3-30 De s ign-Basi s Tornado Field Characteristics

.................................................................. 3-31 Design-Basis Tornado Missile Spectrum ....................................

................................... 3-32 Rain Load Criteria .................................

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.................................................... 3-33 Snow Load Criteria .......................

................................................................................. 3-34 Extreme Winter Precipitation Load Criteria .................................................................. 3-34 Atmospheric Ice Load Criteria ................

....................................................................... 3-35 Design Criteria Requirements ( 4 pages) ............................................................

............ 3-48 System Classifications

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............................................................. 3-53 System Safety and Seismic Classification and Associated Quality Level Group (2 pages) .......................

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................. 3-53 Likelihood Index Limit Guideline s ................................................................................ 3-54 3-iii

... ;. NWMI ...... .. *.. .... .. .. .. * * ! NOmfWUT MlDlCAL lSOTOPU NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components TERMS Acronyms and Abbreviations 99 Mo molybdenum-99 AASHTO American Association of State Highway and Transportation Officials ACGIH American Conference on Governmental Industrial Hygienists ACI American Concrete Institute AHRI Air Conditioning, Heating and Refrigeration Institute AISC American Institute of Steel Construction ALARA as low as reasonably achievable AMCA Air Movement and Control Association ANS American Nuclear Society ANSI American National Standards Institute ASCE American Society of Civil Engineers ASHRAE American Society of Heating , Refrigeration , and Air-Conditioning Engineers ASME American Society of Mechanical Engineers ASNT American Society for Nondestructive Testing ASTM American Society for Testing and Materials A WS American Welding Society BMS building management system CDC Centers for Disease Control and Prevention CFR Code of Federal Regulations CRR Collected Rules and Regulations CSR Missouri Code of State Regulations Discovery Ridge Discovery Ridge Research Park DBE design basis event DBEQ design basis earthquake DOE U.S. Department of Energy EIA Electronic Industries Alliance ESF engineered safety feature FEMA Federal Emergency Management Agency FPC facility process control FSAR final safety analysis report H z hydrogen gas HR hydrometeorological report HV AC heating , ventilation , and air conditioning l&C instrumentation and control IAEA International Atomic Energy Agency IBC International Building Code ICC International Code Council ICC-ES International Code Council Evaluation Service IEEE Institute of Electrical and Electronics Engineers IES Illuminating Engineering Society IFC International Fire Code IROFS items relied on for safety ISA International Society of Automation ISG Interim Staff Guidance IX ion exchange LEU low enriched uranium MDNR Missouri Department of Natural Resources Mo molybdenum 3-iv MO DOT MRI MU MURR NECA NEMA NEP NESHAP NETA NFPA NIOSH NOAA NRC NS NSR NWMI NWS PMF PMP PMWP QA QAPP RCA RPF SEP SMACNA SNM SR SSC TIA U.S. UL UPS USGS Units o c O f µ cm cm 2 ft ft 2 ft 3 g gal hp hr m. in.2 kg NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Mi s souri Department of Transportation mean recurrence interval University of Missouri University of Missouri Research Reactor National Electrical Contractors Association National Electrical Manufacturers Association normal electrical power National Emissions Standards for Hazardous Air Pollutants InterNational Electrical Testing Association National Fire Protection Association National Institute for Occupational Safety and Health National Oceanic and Atmospheric Administration U.S. Nuclear Regulatory Commission non-seismic non-safety-related Northwest Medical Isotopes , LLC National Weather Service probable maximum flood probable maximum precipitation probable maximum winter precipitation quality assura n ce quality assura n ce progra m p l an radiologically controlled area Radioisotope Production Facility standby electrical power Sheet Metal and Air Conditioning Contractors National Association special nuclear material safety related structures , systems and components Telecommunications Industry Association United States Underwriters Laboratory uninterruptible power supply U.S. Geological Survey degrees Celsius degrees Fahrenheit micron centimeter square centimeters feet square feet cubic feet acceleration of gravity gallon horsepower hour inch square inch kilogram 3-v

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• NOfl111WHT MEDICAL lSOTDP£S kip km kW L lb !bf m m 2 nu mi 2 mm MT rad sec NWMl-2 0 13-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components thousand pounds-force kilometer kilowatt liter pound pound-force meter square meter mile square mile minute metric ton absorbed radiation dose second 3-vi 3.0 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components DESIGN OF STRUCTURES, SYSTEMS, AND COMPONENTS This chapter identifies and describes the principal architectural and engineering design criteria for the facility structures, systems and components (SSC) for the Northwest Medical Isotopes , LLC (NWMI) Radioisotope Production Facility (RPF). The information presented emphasizes the safety and protective functions and related design features that help provide defense-in-depth against the uncontrolled release of radioactive material to the environment.

The bases for the design criteria for some of the systems discussed in this chapter are developed in other chapters of the Construction Permit Application and are appropriately cross-referenced , when required. NWMI's RPF design is based on applicable standards, guides, codes, and criteria and provides reasonable assurance that the RPF SSCs, including e lectr omechanical systems, are: * * * * * *

• Built and will function as designed and required by the analyses in Chapter 13.0 , "Acc ident Analysis" Built to have acceptable protection of the pub li c health and safety and environment from radiological risks (e.g., radioactive materials , exposure) resulting from operations Protected against potential meteorological damage Protected against potential hydrological (water) damage Protected against seismic damage Provided surveillance activities and technical specifications required to respond to or mitigate consequences of seismic damage Based on technical specifications developed to ensure that safety-related functions of electromechanical systems and components will be operable and protect the health and safety of workers, the public, and environment The design of the RPF and SSCs are based on defense-in-depth practices. The NRC defines design-in-depth as the following:

An approach to d es igning and operating nuclear facilities that pr eve nts and mitigat es accidents that release radiation or ha zardous material s. The k ey is c r eati ng multipl e independent and redundant layers of defense to compensate for pot entia l human and mechanical failures so that no single la yer, no matter how robust, is exclus iv e l y relied upon. D efe nse in depth includes the use of access contro ls , physical barri ers, redundant and diver se key safety functions, and emergency response measur es. Defense-in-depth is a design philosophy , applied from the outset and through completion of the design , that is based on providing successive levels of protection such that health and safety are not wholly dependent on any single element of the design, construction, maintenance, or operation of the facility.

The net effect of incorporating defense-in-depth practices is a conservatively designed facility and systems that exhibit higher tolerances to failures and external challenges.

The risk insights obtained through performance of accident ana l ysis can then be used to supplement the final design by focusing attention on the prevention and mitigation of the higher risk potential accidents. 3-1 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components This application to the U.S. Nuclear Regulatory Commission (NRC) seeks to obtain a license for a production facility under Title 10 , Code of Fed e ral R egu lation s (CFR), Part 50 (10 CFR 50), "Domestic Licen s ing of Production and Utilization Facilities

." Embedded in the 10 CFR 50-licensed facility will be severa l activities su bject to 10 CFR 70, "Domestic Licensing of Special Nucle a r Material ," to receive , po ssess, use , and transfer special nuclear material (SNM) and 10 CFR 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material ," to process and transport molybdenum-99 (99 Mo) for medical applications. Thjs IO CFR 50 li cense ap plic ation for the RPF follows the guidance in NUREG-1537 , Guidelines for Pr eparing and R eview ing Applications for the Li ce n sing of Non Pow e r R e actors -Format and Content, that encompasses activ itie s regulated under different NRC requirements (e.g., l 0 CFR 70 and 10 CFR 30), in accordance with 10 CFR 50.31 , "Co mbining Applications," and 10 CFR 50.32 , "E limination of Repetition." The NRC has determjned that a radioisotope separation and processing facility , which a l so conducts separation of SNM , will be considered a production facility and as such , will be subject to licensing under 10 CFR 50. The operation of the NWMI RPF will primarily be focused on the disa sse mbly of irradiated low-enriched uranium (LEU) target s, separation a nd purification of fission product 99 Mo , and the recycle of LEU that i s licen se d under I 0 CF R 50. RPF operations will also include the fabrication of LEU targets, which will be l icen se d under 10 CFR 70. The se targets will be s hipped to NWMI's network of research or test reactors for irradiation (considered a connected action) and returned to the RPF for processing. The LEU used for the production of LEU target materials will be obtained from the U.S. Dep art ment of Energy (DOE) and from LEU reclaimed from processing the irradiated tar ge t s. NWMI's licensin g approach for the RPF define s the following unit processes and areas that fall under the following NRC regulations

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• I 0 CFR 50, " Domestic Licensing of Production and Utilization Facilities" Target receipt and di sasse mbly system Target dissolution syste m Mol y bd e num (Mo) recovery and purification system Uranium recovery and recycle system Waste management system Associated l aboratory and support a reas I 0 CFR 70, "Domestic Licensing of Specia l Nuclear Materia l" Target fabrication system Fresh LEU (from DO E) receipt area Associat e d laboratory and support areas 10 CFR 30 , " Rules of General Applicability to Domestic Licensing of Byproduct Material" Any byproduct materials produced or extracted in the RPF Design information for the complete range of normal operating conditions for various facility systems is provided throughout the Construction Perrrut App li cation , and includes the following. *

• RPF-specific design criteria (e.g., codes and sta ndards , NRC guidelines) for SSCs are provided in Sections 3.1. NRC general de s ign criteria and associated app li cability to the RPF SSCs are addressed in Section 3.5. 3-2

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• NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components RPF description is presented in Chapter 4.0, " Radioi soto pe Production Facility De scri ption." Postulated initiating events and credible accidents th at form the design basis for the SSCs are discussed in Chapter 13.0. Potential hazards and credible accidents that could be encountered in the RPF during operations involving SNM, irradiated and unirrradiated , Mo recovery and purification , uranium recovery and recycle , waste management , and/or the use of hazardou s chemicals relative to the se radiochemical processes that form the ba ses for the SSCs loc a ted in the RPF , are discussed in Chapter 13.0. Design redundancy ofSSCs to protect agai n s t unsafe conditions with respect to single failures of engineered safety features (ESF) and control systems are described in Chapter 6.0, "Engi neered Safety Features," and Chapter 7.0, "Instrumentation and Control System," respectively. ESFs are described in Chapter 6.0, and the administrative controls are discussed in Chapter 14.0 , "T echnical Specifications

." Quality s tandards commensurate with the safety functions and potential ri sks that were used in the design of the SS Cs are described in Table 3-7 (Section 3 .1. 7). Hydrological design bases describing the mo s t severe predicted hydrological events during the life of the facility are provided in Chapter 2.0, " Site Characteristics

," Section 2.4. Design criteria for facility SSCs to withstand the mo st severe predicted hydrological events during the lifetime of the facility are provided in Section 3.3. Seismic design bases for the facility are provided in Chapter 2.0 , Section 2.5. Seismic design criteria for the facility SSCs are provided in Section 3.4. Analyses concerning function, reliability , and maintainability of SSCs are described throughout the Construction Permit Application. Meteorological design ba ses describing the most seve re weather extremes predicted to occur during the life of the facility are provid e d in Chapter 2.0 , Section 2.3. Design criteria for facility SSCs to withstand the most severe weather extremes predicted to occur during the life of the facility are provided in Section 3.2. Potential conditions or other items that will be probable subjects of technical specifications associated with the RPF structures and design features are discussed in Chapter 14.0. 3-3

..... NWMI *::**::* ..*... ' "NCNITNWUT MEOtCAUSOTOP'f.S 3.1 DESIGN CRITERIA NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Section 3.1 describes the design criteria applied to the RPF and SSCs within the facility. The principal design criteria for a production facility establish the necessary design, fabrication , construction, testing , and performance requirements for SSCs important to safety (i.e., those that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of workers and the public). The systems associated with the RPF are identified. Those items relied on for safety (IROFS) are identified in Chapters 6.0 and 13.0. Requirements are derived from:

• Code of Federal Regulations

• U.S. Nuclear Regulatory Commission

• Federal regulations , guidelines, and standards Local government regulations and requirements

• Discovery Ridge Research Park (Discovery Ridge) covenants University of Missouri System (MU) requirements

• Other codes and standards 3.1.1 Radioisotope Production Facility Structures, Systems, and Components Table 3-1 lists the RPF systems and identifies the RPF material accountability area and the Construction Permit Application reference chapter that provides the associated detailed system descriptions.

Table 3-1. List of System and Associated Systems and Construction Permit Application Crosswalk (2 pages) Primary structure and associated systems Construction Permit Application reference (primary references)

Radioisotope Production Facility (RPF -primary structure)

IO CFR 70" Target fabrication 10 CFR sob Target receipt and disassembly Target dissolution Molybdenum recovery and purification Uranium recovery and recycle Waste handling Criticality accident alarm Radiation monitoring Normal electrical power Standby electrical power Process vessel ventilation Facility ventilation Fire protection Plant and instrument air Emergency purge gas Gas supply Chapter 4.0 , Sections 4.l.3.1and4.4 Chapter 4.0, Section 4. l .3.2, 4.3.2 , and 4.3.3 Chapter 4.0 , Sections 4.1.3.3 and 4.3.4 Chapter 4.0 , Sections 4.1.3.4 and 4.3.5 Chapter 4.0 , Sections 4.1.3.5 and 4.3.6 Chapter 4.0, Section 4.l.3.6; Chapter 9.0, Section 9.7.2 Chapter 6.0 , Section 6.3.3.1; Chapter 7.0 , Section 7.3.7 Chapter 7.0, Section 7.6; C h apter 11.0, Section 11.1.4 3-4 Chapter 8.0 , Section 8.1 Chapter 8.0, Section 8.2 Chapter 9.0 , Section 9.1 Chapter 9.0, Section 9.1 Chapter 9.0 , Section 9.3 Chapter 9.0, Section 9.7.l Chapter 6.0 , Section 6.2.1.7.5 Chapter 9.0, Section 9.7.1

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• NO<<THWUTMEl>>CALISOTOf'U NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-1. List of System and Associated Systems and Construction Permit Application Crosswalk (2 pages) Primary structure and associated systems Process chilled water Facility chilled water Facility heated water Process stream Demineralized water Chemical supply Biological shie ld Facility process control Construction Permit Application reference (primary references)

C hapt er 9.0, Section 9.7.1 Chapter 9.0, Section 9.7.1 Chapter 9.0 , Section 9.7.1 Chapter 9.0, Section 9.7.1 Chapter 9.0 , Section 9.7.1 Chapter 9.0, Section 9.7.4 Chapter 4.0 , Sect i on 4.2 Chapter 7.0, Section 7.2.3

• 10 CFR 70 , " Dom e st i c Licensing of Specia l Nuclear Material ," C o d e of F e d e ral R egu lation s , Office o f the Federa l Register, a s amended. b 10 CFR 50 , "Domestic Licensing of Production and Ut ili z ation Facilities

," Co d e of F e d e ral R e gulation s , Office of th e Federal Register , a s amended. In addit ion to Table 3-2 , NWMI-2015-LIST-003 , NWMI Radioisotop e Produ c tion Facility Master Equipm e nt List, provides a s umm ary of the RPF systems , components , and equipment used in the RPF design. Table 3-2 provides a summary of the IROFS identified by the accident analyses in Chapter 13.0 , and a crosswalk to where the IROFS are described in the Construction Permit Application. Chapter 13.0 a l so provides the associated detailed descriptions.

Table 3-2 a l so identifies whether the IROFS are co n sidered ESFs or administrative controls. Additiona l IROFS may be identified (or the current IROFS modified) during the RPF final design and development of the Operating License Application. Table 3-2. Summary of Items Relied on for Safety Identified by Accident Analyses (3 pages) IROFS Construction Permit Application designator Descriptor ESF AC crosswalk (primary references)

RS-01 Hot cell liquid confinement boundary RS-02 Reserved* RS-03 Hot cell seco nd ary confinement boundary RS-04 Hot cell shielding boundary RS-05 Reserved* RS-06 Reserved* RS-07 Reserved* RS-08 Sample and analysis of low-dose waste tank dose rate prior to transfer outside the hot cell shielded boundary 3-5 ,/ ,/ ,/ Chapter 6.0 , Sections 6.2.1.1 -6.2.1.6 Chapter 1 3.0 , Section 13.2.2.8 C h apter 6.0 , Sections 6.2.1.1 -6.2.1.6 C h apter 13.0 , Sections 13.2.2.8 , 1 3.2.3.8 Chapter 6.0, Sections 6.2.1.1 -6.2.1.6 Chapter 13.0, Sections 13.2.2.8, 13.2.4.8 Chapter 13.0 , Section 13.2.7.1

..... : NWMI ...... ..* .. ........ *. ' * * ! . NORTHWUT MfDfCAl tsOTOf'fJ NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-2. Summary of Items Relied on for Safety Identified by Accident Anal y ses (3 pages) IROFS Construction Permit Application designator Descriptor ESF AC crosswalk (primary references)

R S-0 9 Prim ary off gas r e li ef syste m ./ C h a pt e r 6.0 , Sec ti o n 6.2.1.7 C h a pt e r 13.0 , Sec t io n 13.2.3.8 RS-10 Active radiation monitoring and isolation of ./ Chapter 6.0 , Sect i on 6.2.1.7 low-dose waste transfer Chapter 13.0 , Section 13.2.7.1 RS-11 R eserve d* RS-12 Ca s k containment sampling prior to closure ./ Chapter 13.0 , Section 13.2.7.1 lid removal R S-1 3 Cask l oca l ve ntil a ti o n d urin g cl os ur e lid ./ C h a pt e r 6.0 , Sectio n 6.2.1.7 r e m ova l a nd d oc kin g pr e p ara ti o n s C h a p ter 1 3.0 , Sec t io n 1 3.2.7.1 RS-14 Reserved* R S-1 5 Cas k doc kin g p o rt e n a blin g se n so r C h a pt e r 6.0 , Sec t io n 6.2.1.7 C h a pt er 13.0 , Sec t io n 1 3.2.7.1 C S-01 Reserv e d* CS-02 M ass a nd b a tch h a ndlin g limit s for ur a nium C h ap t e r 13.0 , Sectio n 1 3.2.7.2 m e t a l , ura nium o xid es , ta r gets , a nd l a b oratory sa mple o ut s id e pro cess sys t e m s CS-03 Interaction control spacing provided by ./ Chapter 13.0 , Section 13.2.7.2 admini s trative control CS-04 Int e r act i o n c ontrol s p aci n g pro v id ed b y ./ C h a pt e r 6.0 , Sect i o n 6.3.1.2 p assive l y d es ign e d fi x tur es a nd wo rk s t a ti o n C h a pt e r 1 3.0 , Sect i o n 1 3.2.7.2 pl aceme n t CS-05 Container batch volume limit ./ Chapter 13.0 , Section 13.2.7.2 CS-0 6 P e n cil t a nk , vesse l , o r piping s a fe geo m e tr y ./ C h a pt e r 6.0 , Sec ti o n 6.3.1.2 c on fine m ent u s ing t h e di a m e t e r of t a nk s , C h a pt e r 1 3.0 , Sect i o n 1 3.2.4.8 vesse l s , o r pipin g CS-07 Pencil tank and vessel spacing control using ./ Chapter 6.0, Section 6.3.1.2 fixed interaction spacing of individual tanks Chapter 13.0 , Section 13.2.2.8 or vessels CS-0 8 Fl oo r a nd s ump geo m etry co ntrol of s l a b ./ C h a pt e r 6.0 , Sectio n 6.3.1.2 d e pth , s ump di a m eter or d e p t h for fl oo r s pill C h a pt e r 1 3.0 , Sectio n 1 3.2.2.8 c ont ainme nt b e rm s CS-09 Double-wall piping ./ Chapter 6.0 , Section 6.2. l. 7 Chapter 13.0 , Section 13.2.2.8 CS-IO C lo se d safe ge om etry h e atin g or coo l i n g l oo p ./ C hapt e r 6.0 , Sec ti o n 6.3.1.2 w ith m o ni to ring a nd a l a rm C h a pt e r 13.0 , Sect i o n 13.2.4.8 CS-11 Simple overflow to normally empty safe ./ Chapter 6.0 , Section 6.3.1.2 geometry tank with l eve l alarm Chapter 13.0 , Section 13.2.7.2 CS-1 2 Cond e n s in g pot or seal p o t in v entil a tion ve nt ./ C h a pt e r 6.0 , Sect i o n 6.3.1.2 lin e C h a pt er 13.0 , S e c t ion 1 3.2.7.2 CS-13 Simple overflow to normally empty safe ./ Chapter 6.0 , Section 6.3.1.2 geometry floor with level alarm in the hot cell Chapter 13.0 , Section 13.2.7.2 containment boundary 3-6

... ;. NWMI ...... .. ... ........ *. NOITHWESTMEDtCAllSOTOHI NWMl-2013-021, Rev. 3 Chapter 3.0 -Design o f Structures, Systems and Components Table 3-2. Summary of Items Relied on for Safety Identified by Accident Analyses (3 pages) IROFS Construction Permit Application designator Descriptor ESF AC crosswalk (primary references)

CS-14 Active discharge monitoring and isolation

,/ Chapter 6.0 , Section 6.3.1.2 Chapter 13.0 , Section 13.2.7.2 CS-15 Independent active discharge monitoring and ,/ Chapter 6.0, Section 6.3.1.2 isolation Chapter 13.0, Section 13.2.7.2 CS-16 Sampling and analysis of uranium mass or ,/ Chapter 13.0 , Section 13.2.7.2 concentration prior to discharge or disposal CS-17 Independent sampling and analysis of ,/ Chapter 13.0, Section 13.2.7.2 uranium concentration prior to discharge or disposal CS-18 Backflow prevention device ,/ Chapter 6.0 , Sections 6.2.1. 7 and 6.3.1.2 Chapter 13.0 , Section 13.2.4.8 CS-19 Safe-geometry day tanks ,/ Chapter 6.0, Section 6.3.1.2 Chapter 13.0 , Section 13.2.4.8 CS-20 Evaporator or concentrator condensate

,/ Chapter 6.0 , Section 6.3.1.2 monitoring Chapter 13.0 , Section 13.2.4.8 CS-21 Visual inspection of accessible surfaces for ,/ Chapter 13.0, Section 13.2.7.2 foreign debris CS-22 Gram estimator survey of accessible surfaces ,/ Chapter 13.0, Section 13.2.7.2 for gamma activity CS-23 Nondestructive assay of items with ,/ Chapter 13.0, Section 13.2.7.2 inaccessible surfaces CS-24 Independent nondestructive assay of items ,/ Chapter 13.0 , Section 13.2.7.2 with inaccessible surfaces CS-25 Target housing weighing prior to disposal ,/ Chapter 13.0, Section 13.2.7.2 CS-26 Proces s ing component safe volume ,/ Chapter 6.0 , Section 6.3.1.2 confinement Chapter 13.0 , Section 13.2.7.2 CS-27 Closed heating or cooling loop with ,/ Chapter 6.0, Section 6.3.1.2 monitoring and alarm Chapter 13.0 , Section 13.2.4.8 FS-01 Enhanced lift procedure

,/ Chapter 13.0 , Section 13.2.2.8 and 13.2.7.1 FS-02 Overhead cranes ,/ Chapter 13.0, Section 13.2.7.3 FS-03 Proce ss vessel emergency purge system ,/ Chapter 6.0 , Section 6.2.1. 7 Chapter 13.0 , Section 13.2.7.3 FS-04 Irradiated target cask lifting fixture ,/ Chapter 6.0, Section 6.2.1. 7 Chapter 13.0, Section 13.2.6.5 FS-05 Exhaust stack height ,/ Chapter 6.0 , Section 6.2.1.7 Chapter 13.0 , Section 13.2.7.3

• Reserved -IROFS designator currently unassign e d. AC admini s trative control. IROFS item s relied on for safe t y. ESF = engineered safe ty featur e. 3-7 NWM I ...... ' * . NOtmfWEST MEDICAL tsOTOPH NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.1.2 Code of Federal Regulations NWMI-DRD-2013-030, NWMI Radioisotope Production Facility Design Requirements Document, summarizes the CFR design inputs (in whole or in part) for the RPF, which in cl ude the following:

• * * * * * * * * * * * *

• 3.1.3 10 CFR 20 , " Standards for Protection Against Radiation" 10 CFR 30 , " Rules of General Applicability to Domestic Licensing of Byp roduct Material" 10 CFR 50 , " Domestic Licensing of Production and Utilization Facilities" 10 CFR 70 , " Domestic Licensing of Special Nuclear Material" 10 CFR 71 , " Energy: Packaging and Transportation of Radioactive Material" 10 CFR 73, " Physical Protection of Plants and Materials" 10 CFR 74, " Material Control and Accounting of Special Nuclear Material" I 0 CFR 851 , " Worker Safety and Health Program" 21 CFR 210 , "Current Good Manufacturing Practice in Manufacturing , Processing , Packaging , or Holding of Drugs' 21 CFR 211 , "Current Good Manufacturing Practice for Finished Pharmaceutical s" 29 CFR 1910 , "Occupational Safety and Health Standards" 40 CFR 61 , " National Emissions Standard s for Hazardous Air Pollutants (NESHAP)" 40 CFR 63 , " NESHAP for Source Categories" 40 CFR 141 , "National Primary Drinking Water Regulations" U.S. Nuclear Regulatory Commission Table 3-3 lists the NRC design inputs for the RPF identified in NWMI-DRD-2013-030. The RPF system design descriptions identify the specific requirements for that system produced by each appl i cable reference.

Table 3-3. Relevant U.S. Nuclear Regulatory Commission Gui d ance (3 pages) CFRa Title Docket Number: Final Int e rim Staff Guidan ce Augm e nting N UREG-153 7, " Guid e lin es fo r Pr e parin g and NRC-2011-0135 R e vi ew in g Appli c ations for th e Li ce nsin g of Non-Pow e r R e a c tor s," Part s 1 and 2,fo r (NRC , 2012) Li ce n s in g Radioisotop e Pr o du c tion Fa c iliti e s and Aqu e ou s Homo ge n e ou s R e a c tors NRC Regulatory Guides -Power Reactors (Division

1) Regulatory Guide 1.29 S e i s mi c D e sign Clas s ifi c ation Regulatory Guide 1.53 Application of the Single-Failure Criterion to Safety Systems , 2003 (R2011) Regulatory Guide 1.60 D es i g n R es pon se Sp ec tra for S e i s mi c D es i g n of Nucl e ar P owe r Plant s, 2014 Regulatory Guide 1.61 Damping Values of Seismic Design of Nuclear Power Plants Regulatory Guide 1.76 D es i g n Basi s Tornado and Tornado Mis s il es for Nucl e ar Pow e r Plants , 2007 Regulatory Guide 1.92 Combining Modal Responses and Spatial Components in Se i smic Response Analysis Regulatory Guide 1.97 Crit e ria for Ac c id e nt Monitoring Instrum e ntation for Nucl e ar Pow e r Plan t s , 2006 (R2013) Regulatory Guide 1.100 Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants, 2009 Regulatory Guide I . I 02 Flood Prot ec tion for Nucl e ar Pow e r Plant s Regulatory Guide 1.122 Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components 3-8

......... *. ..... ;. NWMI .... .... .. '

• NORTHWEST MEDICAl. ISOTOPE.S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-3. Relevant U.S. Nuclear Regulatory Commission Guidance (3 pages) CFR 3 Title Regulatory Guide 1.152 Criteria for Use of Computers in Safety Systems of Nuclear Power Plants, 2011 Regulatory Guide 1.166 Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post Earthquake Actions, 1997 Regulatory Guide 1.167 Restart of a Nuclear Power Plant Shut down by a Seismic Event, 1997 Regulatory Guide 1.208 Performance Based Approach to Define the Site-Specific Earthquake Ground Motion, 2007 NRC Regulatory Guides -Fuels and Materials Facilities (Division

3) Regulatory Guide 3.3 Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Regulatory Guide 3.6 Regulatory Guide 3. JO Regulatory Guide 3 .18 Regulatory Guide 3.20 Plutonium Processing and Fuel Fabrication Plants, 1974 (R2013) Content of Technical Specification for Fuel Reprocessing Plants, 1973 (R2013) Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants, 1973 (R2013) Confinement Barri ers and Systems for Fuel R ep ro cessing Plants, 1974 (R2013) Process Offgas Systems for Fuel Reprocessing Plants, 1974 (R2013) Regulatory Guide 3.71 Nuclear Criticality Safety Standards for Fuels and Mat erials Facilities, 2010 NRC Regulatory Guides -Materials and Plant Protection (Division

5) Regulatory Guide 5.7 Regulatory Guide 5 .12 Regulatory Guide 5.27 Regulatory Guide 5.44 Regulatory Guide 5.57 Regulatory Guide 5.65 Entry/Exit Control for Protected Areas, Vital Areas , and Material Access Areas, May 1980 (R2010) General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials, 1973 (R2010) Special Nuclear Material Doorway Monitors, 1974 Perimeter Intrusion Alarm Systems, 1997 (R2010) Shipping and Receiving Control of Strategic Special Nuclear Material, 1980 Vital Area Access Control , Protection of Physical Security Equipment, and Key and Lock Controls, 1986 (R2010) Regulatory Guide 5.71 Cyber Security Programs for Nuclear Fa c ilities, 2010 NUREG-0700, Human-System Interface Design Review Guidelines NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, LWR Edition Section 2.3.l Section 2.3.2 Section 3.3.1 Section 3.3.2 Section 3.7.1 Section 3.7.2 Section 3.7.3 "Regional Climatology," Rev. 3, March 2007 " Local Climatology," Rev. 3 , March 2007 "Wind Loading," Rev. 3, March 2007 "Tornado Loading," Rev. 3, March 2007 "Seismic Design Parameters," March 2007 "Seismic System Analysis," Rev. 4, September 2013 "Seismic Subsystem Analysis," Rev. 4, September 2013 NUREG-1513, Integrated Safety Analysis Guidance Document NUREG-1520, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility Part 3, Appendix D Natural Hazard Phenomena" NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors -Format and Content, Part 1 3-9

..... ;:.NWMI ..**.. ..* .... ....

• f!K>fl0fWfSTMEOICALtsOTOP£ S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-3. Relevant U.S. Nuclear Regulatory Commission Guidance (3 pages) CFR 3 Title NUREGICR-4604, Statistical Methods for Nuclear Material Management NUREGICR-6410, Nuclear Fuel Cycle Facility Accident Analysis Handbook Process hazard analysis "Development of Quantitative Risk Analyses" NUREGICR-6463, Review Guidelines on Software Languages for Use in Nuclear Power Plant Safety Systems -Final Report NUREGICR-6698 , Guide for Validation of Nuclear Criticality Safety Calculational Methodology

• Co mplete refer e n ces are provid ed in Section 3.6. 3.1.4 Other Federal Regulations, Guidelines, and Standards Table 3-4 lists other Federal design inputs for the RPF (NWMI-DRD-2013-030).

The RPF system design descriptions identify the specific requirements for that system produced by each applicable reference.

Table 3-4. Other Federal Regulations, Guidelines, and Standards Reference*

Title Federal Emergency Management Agency (FEMA) N I A " National Flood Insurance Program, Flood Insurance Rat e Map, Boone County, Missouri and Incorporated Areas" National Oceanic and Atmospheric Administration (NOAA) Hydrometeorological Probable Maximum Precipitation Estimates, U nit ed States East of the 105th Meridian Report No. 51 Hydrometeorological Application of Probable Maximum Precipitation Estimates, United States East of the J05th Report No. 52 Meridian Hydrometeorologic a l Seasonal Variation of JO-Squar e-M il e Probable Maximum Precipitation Estimates , United Report No. 53 States East of th e 105th Meridian U.S. Geological Survey (USGS) N I A "2 008 U.S. Geological Survey National Seismic Hazard Maps" Open-File Report 2008-1128 Documentation for the 2008 Update of the United States National Seismic Hazard Maps Centers for Disease Control and Prevention (CDC) NIOSH 2003-136 Guidance for Filtration and Air-Cleaning Systems to Protect Building Environments from Airborne Chemical, Biological, and Radiological Attacks

• Co mplete reference s are provided in Section 3.6 CDC FEMA NIOSH Centers for Di sease Control and Pre vent ion. NOAA Federal E mergency Management Agency. National In s titute for Occupational Safety and USGS Health. 3.1.5 Local Government Documents National Oceanic and Atmospheric Administration.

U.S. Geological Survey. Table 3-5 lists the design inputs for the RPF from the State of Missouri , City of Columbia, and Boone County government sources (NWMI-DRD-20 13-030). The RPF system design descriptions identify the specific requirements for that system produced by each applicable reference.

3-10 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-5. Local Government Documents (2 pages) Reference a Title Missouri Code of State Regulations (CSR), Title 10 10 CSR 10-6.01 Ambient Air Quality Standards Missouri CSR, Title 20 2 0 CSR 2030-2.040(1)

Eva luation Criteria for Building De s ign Missouri Department of Transportation (MODOT) Standards and Specifications Missouri Department of Natural Resources (MDNR) Missouri State Adopted International Code Council (ICC) Building Code Set 2012 Boone County Building Code City of Columbia, Missouri, Code of Ordinances Article II -Building and Fire Codes Section 6-16 , Adopt e d Building Code Section 6-17, Amendments Section 9-21 Section 9-22 Building Code Fire Code Fire Code

• Com pl e t e references a r e pro vided in Section 3.6 CS R Code of State R egulations. I CC = Int e rn atio n a l Co d e Co un c il. 3.1.6 Discovery Ridge/University of Missouri MDNR MO DOT Missouri Department of atural R eso ur ces. Missouri Department of Transportation.

Table 3-6 lists the MU sys tem requirements and Di sc overy Ridge covenant s design input s for the RPF identified in NWMI-DRD-2013-030. The RPF sys tem de s ign description s identify the s p ec ific requirements for that sys tem produced by each applicable refer e nce. Table 3-6. Discovery Ridge/University of Missouri Requirements Requirements Reference section/requirement a C i vi l D esign and construction of the civ il sys t em i s regu l ated by th e NRC as r e quir ed b y Di sc o very Rid ge/MU. Collected Rules and Regulations (CRR) Structura l C RR Section 70.060.1 , "C odes and Standards" -Adopts ICC codes University of Missouri, Consultant Procedures and Design Guidelines E l ectr i ca l Section 2.4.2, " Buildin g Codes and Standards for U ni vers it y Fac ilitie s" HV AC CPDG Division 23 , "Heat ing, Ventilating, and Air-Conditioning (HVAC)" In st rumentation Sectio n 2.4.2, " Building Codes and Standa rd s for Un i ve r sity Facilities" a nd Co ntrols Planning CPDG Section 2.4 , "Planning, Design and Contract Document Development Guidelines for Master Construction Delivery Method" Plumbing CPDG Division 22, " Plumbing" Process Section 2.4.2, " Building Codes and Standards for University Facilities" University of Missouri , Facilities Management Poli cy and Pro ce dure s Manual Electrical Chapter 2, " Design and Construction Polic y" 3-11 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-6. Discovery Ridge/University of Missouri Requirements Requirements Reference section/requirement

• Instrumentation Chapter 2 , " Design and Construction Policy" and Controls Structural Section 3.A, Refers to CRR 70.060 for the Basic Building Code Section 3.0, Refers to the University Building Adopted Codes for currently adopted codes University Building Adopted Codes IMC-2012 International Mechanical Code Structural Adopts IBC 2012

• C omplete refer e nc es are provid e d in Section 3.6 C RR Colle c t e d Rule s and R e gulation s. !B C Int e rn a tion a l Buildin g Co d e. I CC = Intern a ti o n a l C ode Co uncil. 3.1.7 Codes and Standards MU NR C Univer s ity of Mi ss ouri. U.S. Nu c l e ar R eg ul a tory C ommis s ion. Table 3-7 lists design inputs for the RPF identified in NWMI-DRD-2013-030.

The RPF sy stem design descriptions identify the specific requirements for that s ystem produced by each applicable reference. The Construction Pennit Application and associated preliminary design documents identify codes , standards, and other referenced documents that may be applicable to the RPF. The specific RPF design codes, standards, and other referenced documents , including exceptions or exemptions to the identified requirements , will be finalized in the RPF final design and provided to the NRC. In addition, the codes , standards , and referenced documents for the RPF safety SSC s that are needed to demonstrate compliance with regulatory requirement s will be identified and committed to in the Operating License Application. Table 3-7. Design Codes and Standards (12 pages) Document number" Document title American Concrete Institute (ACI) ACI 349 Code R equ ir e m e n ts fo r Nuclear Safety-R e l ated Conc r e t e Structu r es a n d Commen tm y, 2 01 3 American Institute of Stee l Construction (AISC) ANSU AISC N690 Specification for Safet y-R e l a t ed S t ee l Str u c t u r es for Nuclear Facilities , 2 01 2 Air Movement and Control Association (AMCA) AMCA Publication 201 Fans and Systems, 2002 (R201 l) AMCA Publication 2 03 ANSI/AMCA 210 AMCA Publication 211 AMCA Publication 311 Fi e ld P e rforman ce M e a s ur e m e nt of Fan S ys t e m s, 1990 (R201 l) Laboratory Methods for Testing Fans for Aerodynamic Performance Rating, 2007 C e rtifi e d Rating s Pr og ram -Produ c t Ratin g Manual for Fan A ir P e rforman ce, 2013 Certified Ratings Program -Product Rating Manual for Fan Sound Performance, 2006 (R2010) American Conference on Governmental Industrial Hygienists (ACGIH) ACGIH 2097 Industrial Ventilation

A Manual of Recommended Practice for Design, 2013 American Nationa l Standards Institute (ANSI) ANSI/ITSDF B56. I Safety Standard for Low lift and High Lift Trucks 3-12

.; .. ;. NWMI ...... ..* ... .*.* .. *.*. "NORTIIWEST llEOICAl.

ISOTOH:S Document number" NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title ANSI/IEEE C2 2012 National Ele c trical Safety Code (NESC), 2012 ANSI C84. l American National Standard for Electric Power Systems and Equipment

-Voltage Rating s (60 Hertz), 2011 ANSI Nl3 ser ie s Addresses radiation monitoring equipment ANSI N 13 .1 Sampling and Monitoring Releases of Airborne Radioactiv e Substances from the Stacks and Ducts of Nuclear Facilities 2011 ANSI N323D American National Standard for Installed Radiation Protection Instrumentation , 2002 ANSI/AIHA/ASSE Z9.5 Laboratory Ventilation, 2012 ANSI/NEMA Z535. I Safety Colors , 2006 (R201 I) ANSI/NEMA Z535.2 Environmental and Facility Safety Signs, 2011 ANSI/NEMA Z535.3 Criteria for Safety Symbols, 2011 ANSI/NEMA Z535.4 Product Safety Signs and Labels, 2011 ANSI/AMCA 204 Balance Quality and Vibration Levels for Fans, 2005 (R20 1 2) ANSI/AMCA 210 Laboratory Methods of Testing Fans for Aerodynamic Performance Rating , 2007 ANSI/ARRI Standard 390 Performance Rating of Single Package Vertical Air-Conditioners and Heat Pumps , 2003 ANSI/ARRI Standard 410 Forced-Circulation Air-Cooling and Air-Heating Coils, 2001 ANSI/ARRI Standard 430 Performance Rating of Centra l Station Air-Hand lin g Units, 2009 ANSI/ARRI Standard 850 P erformance Rating of Commercial and Industrial Air Filter Equipment, 2013 ANSI/HI 3.1-3.5 Rotary Pumps, 2008 ANSI N42. l 7B American National Standard Performance Specifications for Health Physics Instrum entation -Occupational Airborne Radioa ctivity Monitoring Instrumentation, 1989 ANSI N42. l 8 Specification and Performance of On-Site in strumentation for Continuously Monitoring Radioactivity in Effluents , 2004 ANSI/IEEE N320 American National Standard Performan ce Specifications for Rea ctor Emergency Radiological Monitoring Instrumentation , 1979 American Nuclear Society (ANS) ANSI/AN S-2.3 ANSI/ ANS-2.26 ANSI/ ANS-2.27 ANSI/ ANS-2.29 ANSI/ANS-6.4 Estimating Tornado, Hurricane, and Extreme Straight Line Wind Characteristics at Nuclear Facility Sites, 2011 Categorization of Nuclear Facility Structures , Systems , and Components for Seismi c Design, 2004 (R2010) Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments, 2008 Probabilistic Seismic Hazard Analysis, 2008 Nuclear Analysis and De sign of Concrete Radiation Shielding for Nuclear Power Plants, 2006 3-13

.;.-.;:.NWMI ..**.. ..* *.. .... .... .. NOATKWESTMEDICAUSOTOf'ES Document number* ANSI/ ANS-6.4.2 ANSI/ ANS-8.1 ANSl/ANS-8.3 ANSI/ ANS-8. 7 ANSI/ANS-8

.10 ANSI/ ANS-8.19 ANSI/ ANS-8.20 ANSI/ ANS-8.21 ANSI/ ANS-8.24 ANSl/ANS-10.4 ANSI/ ANS-10.5 ANSl/ANS-15

.17 ANSI/ ANS-40.3 7 ANSl/ANS-55.1 ANSI/ ANS-55.4 ANSl/ANS-55

.6 ANSI/ ANS-58.3 ANSI/ ANS-58.8 ANSI/ ANS-59.3 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title Sp ec ifi c ation for Radiation Shielding Materials , 2006 Nuclear Criticality Safety in Operations with Fissionab le Materials Outside Reactors, 1998 (R2007) (W2014) Criti c ally A c cid e nt A !arm S y stem , 1997 (R20 I 2) Nuclear Criticality Safety in the Storage of Fissile Materials, 1998 (R2007) Crit e ria for Nucl e ar Criti c ality Control in Operations with Shi e ldin g and Confin e m e nt , 1983 (R2005) Administrative Practices for Nuclear Criticality Safety, 1996 (R2014) Nucl e ar Criti c ali ty Saf ety Training , 1991 (R2005) Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors, 1995 (R2011) Validation of N e utr o n Transport M e thod s for Nucl e ar Criticality Saf e ty C al c ulations, 2007 (R2012) Verification and Validation of Non-Safety-Related Scientific and Engineering Computer Programs for the Nuclear Industry, 2008 A cc ommodating U se r N ee ds in Comput e r Program D e v e lopm e nt , 2006 (R2011) Fire Protection Program Criteria for Research Reactors, 1981 (R2000) (W2010) Mobil e Low-L e v e l Radioactiv e Wa s t e Pro c e s sing S ys t e ms , 2009 Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants, 1992 (R2009) Ga se ous Radioa c ti ve Wast e Pro ce s s in g S y st e ms for light Wat e r R eac tor Plants , 1993 (R2007) Liquid Radioactive Waste Processing System for Light Water Reactor Plants, 1993 (R2007) Ph ys i c al Prot ec tion for Nuclear Saf e ty-R e lat e d S ys t e ms and Compon e nts , 1992 (R2008) Time Response Design Criteria for Safety-Related Operator Actions, 1994 (R2008) N ucl e ar Saf e ty Crit e ria for Contr o l Air S y st e m s, 1992 (R2002) (W2012) Design Guides for Radioactive Material Handling Facilities and Equipment, Remote Systems Technology Division, 1988, Air Conditioning, Heating and Refrigeration Institute (AHRI) ANSl/AHRI Standard 365 Performan c e Ratin g of Comm e r c ial and Indu s trial U nitary Air-Conditioning Cond e n s ing Units , 2009 ANSI/ AHRI Standard 410 Forced-Circulation Air-Conditioning and Air-Heating Coils, 2001 American Society of Civil Engineers (ASCE) ASCE4 ASCE 7 ASCE43 Seismic Analysis of Safety-Related Nuclear Structures and Commentary, 2000 Minimum D e sign Load s for Building s and Oth e r Stru c tures , 2005 (R2010) Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, 2005 3-14

.. ;.-.; .. NWMI ..**.. ..* **: ........ *. .. NOfUlfWESTMEOICALISOTOPES Document number" ASCE Manual of Practice 37 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title D e sign and Constru c tion of Sanitary and Storm Sew e rs , 1969 American Society of Heating, Refrigeration and Air-Conditioning Engineers (ASHRAE) ANSI/ASHRAE Standard Safety Standard for R e frig e ration Sy s t e ms , 2013 15 ANSI/ASHRAE 51-07 Laboratory Methods of Testing Fans for Certified Aerodynamic Peiformance Rating, 2007 ANSI/ ASHRAE Standard 52.2 ANSI/ ASHRAE Standard 55 ANSI/ ASHRAE Standard 62.1 ASHRAE Standard 70 ANSl/ASHRAE/IES Standard 90.1 ANSl/ASHRAE 110 M e thod for Testing G e n e ral Ventilation Air Cl e aning D e vi ces for R e moval Effi c i e n cy by Particl e Si ze, 2007 Thermal Environmental Conditions for Human Occupancy, 2013 V e ntil a tion for A c ceptabl e Indoor Air Quali ty , 2010 Method of Testing the Performance of Air Outlets and Air Inlets, 2011 En e r gy Standard for Buildings E xce pt Low-Ris e R e sid e ntial Building s, 2010 Method of Testing Performance of Laboratory Fume Hoods, 1995 ANSI/ ASHRAE 111 M e asur e ment, Testing , Adjusting and Balancing of Building H e atin g, V e ntilation, Air-Conditioning and R e frig e ration S ys tems , 2008 American Society of Mechanical Engineers (ASME) ASME A 1 7 .1 Saf ety Cod e for El e vators and Es c alators, 201 3 ASME AG-1 Code on Nuclear Air and Gas Treatment, 2012 ASME Bl6.5 ASMEB20.l ASME B30.17 ASMEB30.20 ASME B31.3 ASME B31.9 ASME B31.12 ASMEB40.100 ASME B40.200 ASME Boiler and Pressure Vessel Code ASMEHST-1 ASMEN509 ASMEN510 ASMENQA-1 Pip e Flanges and Flan ge d Fittings: N PW 24, 2003 Safety Standard for Conveyors and Related Equipment , 2012 Ov e rh e ard and Gant ry Cranes (Top Running Brid ge , Sin g l e Gird e r, U nderhung Hoist), 2006 Below-the-Hook Lifting Devices , 2013 Pro cess Piping, 2014 Building Services Piping, 2011/2014 H y dro ge n Piping and Pip e lines , 2014 Pressure Gauges and Gauge Attachments, 2013 Th e rmometers , Dir ec t R e ading and R e mot e Reading , 2013 Section VIII Division 1, 2010/2013 Section IX P e rforman ce Standard for El e ctri c Chain Hoists , 2012 Nuclear Power Plant Air-Cleaning Units and Components , 2002 (R2008) T es ting of Nucl e ar Air-Tr e atm e nt S y st e ms , 2007 Quality Assurance Requirements for Nuclear Facility Applications, 2008 with la-2009 addenda 3-15

..... ;. NWMI ...... ..* .... .......... . NORTHWHTMEDICALISOTO..U Document number" NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title ASME QME-1 Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, 2012 American Society for Nondestructive Testing (ASNT) SNT-TC-lA R ecommended Practice No. SNT-TC-JA:

Personnel Qualification and Certification in Nondestructive Testing, 2011 American Society for Testing and Materials (ASTM) ASTM Cl055 ASTM Cl217 ASTM Cl533 ASTM Cl554 ASTM Cl572 ASTM Cl615 ASTM Cl661 ASTME493 Standard Guide for Heated System Surface Conditions that Produce Contact Burn Injuri es, 2003 (2014) Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials, 2000 Standard Guide for General Design Considerations for Hot Cell Equipment, 2015 Standard Guide for Materials Handling Equipment for Hot Cells, 2011 Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radi at ion Shielding Window Components for Remotely Operated Facilities, 20 I 0 Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities, 2010 Standard Guide for Viewing Systems for Remotely Operated Facilities, 2013 Standard Practice for Leaks Using the Mass Spectrometer Leak Detector in the Inside-Out Testing Mode, 2011 ASTM Fl471 Standard Test Method for Air Cleaning Performance of High-Effi ciency Particulate Air-Filter System, 2009 American Welding Society (A WS) AWS B2. l/B2. JM Specification for Welding Procedure and Performance Qualification, 2009 A WS D 1.1 I D 1.1 M Structural Welding Code -Steel , 2010 AWS Dl.3/Dl.3M AWS Dl.6/Dl.6M AWS D9.l/D9.IM AWSQCI Structural Welding Code -Sheet Steel, 2008 Structural Welding Code -Stainless Steel, 2007 Sheet Metal Welding Code, 2006 Standard for A WS Certification of Welding Inspectors, 2007 Centers for Disease Control and Prevention (CDC) -National Institute for Occupational Safety and Health (NIOSH) DHHS (NIOSH) Publication Guidance for Filtration and Air Cleaning Systems to Protect Building Environments No. 2003-136 from Airborne Chemical , Biological, and Radiological Attacks, 2003 Electronic Industries Alliance (EIA)/Telecommunications Industry Association (TIA) ANSl/TIA-568-C. l ANSl/TIA-568-C

.2 ANSl/TIA-568-C

.3 ANSl/TIA-569 ANSl/TIA-606 Commercial Building Telecommunications Cabling Standard, 2012 Balan ced Twisted-Pair T e lecommuni cat ion s Cabling and Components Standards, 2014 Optical Fiber Cabling and Components Standard, 2011 Telecommunications Pathways and Spaces, 2013 Administration Standard for Commercial Telecommunications Infrastructure, 2012 3-16

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• NOflTHWEST MEDICAL lSOlOPES NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document number a ANS I/TIA-607 ANSI/TIA-758-A International Code Council ICCA117.l IECC IMC IPC Document title Comm e r c ial Building G r o unding (Earthin g) and B o ndin g R e quir e m e nts for T e l eco mmuni c ation s, 2013 Customer-Owned Outside Plant Telecommunications Infrastructure Standard, 2004 Accessible and Usable Buildings and Facilities Standard , 2009 20i 2 Int e rnational En e r gy C on se rvation Cod e, Ma y 2011 20i 2 In ternatio nal Mechanical Code, June 2011 Int e rnational Plumbin g Cod e, April 2011 Institute of Electrical and Electronics Engineers (IEEE) IE E E 7-4.3.2 IEEE 141 IEEE 142 IEEE 24 1 IEEE 2 42 IEEE 308 IEEE 315 IEEE 323 IEEE 336 IEEE 338 IEE E 344 IEEE 3 79 IEEE 384 IEEE 399 IE E E 446 IEEE 493 Standard C rit e ria fo r Di g ital Comput e r s in Saf ety S ys t e m s of N ucl e a r Pow e r G e n e ratin g Station s, 2003 R ecomme nd ed Practice for E l ectric Power Distribution for Industrial Plants (Red B ook), 1993 (R1999) R ec omm e nd e d Pra c ti ce for Gr o undin g of Indu trial and Comm erc i a l Pow er S ys t e m s (Gr ee n Book), 2007 R ecommended Practice fo r E l ectric Power Systems in Com m e r c ial Buildings (Gray Book), 1990 (R1997) R ec omm e nd e d Pra c ti ce f o r Prot ec tion and C o ordination o f Indu s trial and Comm e rcia l Pow er S ys t e ms (Buff Book), 200 1 Standard Criteria for Cla s s J E Power Systems for Nuclear Power Generating Stations , 2012 Graphi c S y mbols for El ec tri c al and El ec troni c s Diagrams , 1 975 (RI 993) Standard for Qualifying C la ss i E Equipment for Nuclear Power Generati n g Stations, 2003 R ec omm e nd e d Pra c ti ce f o r i n s talla t i o n , In s p ec tion, a nd T es tin g/o r C la ss IE P owe r , Instrum e ntation , and C ontro l Equipm e nt at Nucl e ar Faciliti es, 2010 Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems, 2012 R ec omm e nd e d Pra c ti ce for S e i s mi c Qualifi c ation of C la ss i E Equipm e nt for N ucl e ar P o w e r G e n e r a tin g Station s , 2013 Standard Application of t h e Single-Failure Criterion to Nuclea r Power Generating Station Safety Systems , 2014 Standard Crit e ria for ind e p e nd e n ce of C l as s i E Equipm e nt and C ir c uits , 2008 R ecommended Pra ctice for Power Systems Analysis (Brown B ook), 1997 R ec omm e nd e d Pra c ti ce f o r Em e rg e n cy and Standb y Pow e r S y st e m s for Indu s trial and C omm e r c ial Appli c ation s (Orang e Book), 1995 (R2000) Re comme nd ed Pra ctice for the Design of R e liabl e Industrial and Commercial Power Systems (Gold Bo ok), 2007 3-17 Document number* IEEE 497 IEEE 5I9 IEEE 535 IEEE 577 IEEE 603 IEEE 650 IEEE 739 IEEE 828 IEEE 829 IEEE 902 IEEE 946 IEEE I012 IEEE 1015 IEEE 1023 IEEE 1028 IEEE 1046 IEEE 1050 IEEE I 100 IEEE I289 IEEE 1584 ANSI/IEEE C2 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title Standard Crit e ria for A c cid e nt Monitoring Instrum e ntation for N ucl e ar Pow e r G e n e rating Station s, 2010 Recommended Practice and Requirements for Harmonic Control in Electrica l Power Systems, 20I4 Standard for Qualifi c ation of Cla ss 1 E L e ad Stora ge Batt e ri e s for N ucl e ar Pow e r G e n e rating Station s, 2013 Standard Requirements for Reliability Ana l ysis in the Design and Operation of Safety Systems for Nuclear Facilities, 20I2 Standard Criteria for Saf e ty S y st e ms for Nuclear Pow e r G e n e ratin g Stations , 2009 Standard for Qualification of Class IE Static Battery Chargers and Inverters for Nuclear Power Generating Stations, 2006 R ec omm e nd e d Pra c ti ce for En e r gy Manag e m e nt in Industrial and Comm e rcial Fa c iliti e s (Bronze Book), 1995 (R2000) Standard for Configuration Management in Systems and Software Engineering, 20I2 Standard for Softwar e and S y st em T es t Do c um e ntation , 2008 Guide for Maintenance, Operation, and Safety of Industrial and Commercial Power Systems (Yellow Book), I 998 G e n e rating Station s, 2004 Standard Criteria for Software Verification and Validation, 20I2 R ec omm e nded Pra c ti ce Appl y in g Lo w-Voltag e Cir c uit Br e ak e r s Use d in Industrial and Comm e rcial Po wer S ys t e ms (Blu e Book), 2006 (C2007) Guide for the Application of Human Factors Engineering to Systems, Equipment, and F aci/ities of Nuclear Power Generating Stations, 2004 (R20 I 0) Standard for Softwar e R e vi e w s and Audit s, 2008 Application Guide for Distributed Digital Control and Monitoring/or Power Plants, 1991 (Rl996) Guid e for Instrumentation and Control Equipm e nt Grounding in G e n e rating Station s , 2004 Recommended Practice for Powering and Grounding Electronic Equipment (Emerald Book), 2005 Guid e for th e Appli c ation of Human Fa c tors Engin ee ring in th e D es ign of Comput e r-Based Monitoring and Control Displa y s for Nucl e ar Pow e r Generatin g Station s, 1998 (R2004) IEEE Guide for Performing Arc-Flash Hazard Calculations, 2002 201 2 Nationa l Electri c al Saf e ty Cod e (NESC), 2012 Illuminating Engineering Society of North America (IES) IES-20 I I Th e Lighting Handbook , 2011 ANSI/JES RP-I-I 2 American National Standard Practice for Office Lighting, 2012 3-18 "NWMI ...... .. .. ........ *. ' *!' NORTHWEST MEDtCAL ISOTOKS Document number" IES RP-7 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title Am e ri c an National Standard Pra c ti ce for Li g htin g Industrial Fa c ili t i es , 1991 (W2001) International Society of Automation (ISA) ANS I/ISA-5.1-2009 ISA-5.3-1983 ISA-5.4-1991 ISA-5.5-1985 ANS I/ISA-5.06.01-2007 ANSI/ISA 7.0.01-1996 ANS l/ISA-12.01.01-2013 ISA-18.1-1979 ISA-TR20.00

.0l-2 00 7 ISA-RP60.l-1990 ISA-67.01.01-2002 ANSl/ISA-67.04

.01-2006 1SA-RP67.04.02-2010 ANSI/ISA-75.05.01-2000 ANS I/TSA-82.03-19 88 ISA-TR84.00.04-201 l ISA-TR84.00.09-201 3 ISA-TR9 l.00.02-2003 ANS l/JSA-TR99.00.0l-2007 In s trum e n t ation S y mbol s and Id e ntifi ca tion , 2009 Graphic Symbols for Distributed Control/Shar e d Display Instrumentation , Logic , and Computer Systems , 1983 Instrum e nt Loop Dia g ram s , 1991 Graphic S y mbols for Process Displays, 1985 Fun c ti o nal R e quir e m e nt s Do c um e ntation f o r C ontr o l Software A ppli c a tion s, 2007 Quality Standard for Instrument Air D e finiti o n s and Inform a ti on P e rtainin g to El ec tri c al E quipm e nt in Hazardou s (Cla ss ifi e d) Lo c ation s, 2013 Annunciator Sequences and Sp e cifications , 1979 (R2004) Sp ecifica tion Form s fo r Pr oces s M e a s ur e m e nt and Co ntr o l In s trum e nt s Part 1: G e n e r a l C on s id e rati o n s U pdat e d with 27 n ew s p ecific ation form s in 2 004-2 006 and updat e d w ith 11 n ew s p e c ifi c ation f o rm s in 200 7 Control Center Facilities, 1990 Tran sd u ce r and Tran s mitt e r In s tallati o n for N ucl e a r Saf ety Appli c ati o n s , 2002 (R2007) Setpoints for Nuclear Safety-Relat e d Instrumentation , 2006 (R2011) M e th odo l og i es for th e D ete rmination of S e tpoints f or N ucl e ar Saf ety-R e lat e d In s trum e ntation, 2010 Control Valve Terminology , 2000 (R2005) Saf ety S tandard f o r E l ec tri c al and E l e c tro ni c T e s t , Me a s urin g , Co n tro llin g, and R e la ted E quipm e nt , 19 88 Part 1 Guideline for the Implementation of ANSI/ISA-84.00.01-2004

(/EC 61511), 2011 S ec uri ty Co unt e rm e a s ur es R e lat e d to Saf ety in s t r um e nt ed S ys t e m s (S IS}, 2013 Criti c ality Classification Guideline for Instrum e ntation , 2003 S ec ur ity T ec hnolo g i es fo r Indu s trial A u to mation an d Co ntrol S ys t ems , 2007 International Atomic Energy Agency (IAEA) IAEA-TECDOC-1 2 50 S e i s mi c D e si g n C onsid e ration s of N ucl e ar Fu e l Cy cl e Fa c iliti es , 2001 IAEA-TECDOC-1347 Consid e ration of External Events in the Design of Nuclear Facilities Other Than Nuclear Power Plants , With Emphasis on Earthquakes, 2003 IAEA-TECDOC-1430 Rad io i so top e Handlin g Fa c iliti e s and Automation of Radioi so top e Pr o du c tion , 2004 International Code Council (ICC) IBC 2012 IFC 2012 International Building C ode , 201 2 International Fire Code , 2012 3-19 Document number" NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title IMC 2012 Int e rnational M ec hani c al Cod e, 2012 International Code Council Evaluation Service (ICC-ES) ICC-ES AC156 "Acceptance Criteria for Seismic Certification by Shake-Table Testing of Nonstructural Components

," 2010 National Electrical Contractors Association (NECA) NECA I NECA90 NECA 100 NECA 101 NEC A/AA 104 NECA/NEMA 105 NECA 111 NECA 120 NECA202 NECA230 NECAIFOA 301 NECA 331 NECA400 NECA402 NECA/EGSA 404 NECA407 NECA408 NECA409 NECA 410 NECA 411 NECA420 NECA430 NECA/IESNA 500 NECA/IESNA 501 NECA/IESNA 502 NECAIBICSI 568 Standard Pra c ti c e of G o od Workman s hip in El ec tri c al Con s tru c ti o n , 2010 Recommended Practice for Commissioning Building Electrical Systems (ANSI), 2009 S y mb o l s f o r El ec tri c al C on s tru c tion Drawing s (AN SI), 2013 Standard for Installing Steel Conduits (Rigid, IMC, EMT) (ANSI), 2013 Standard for Installing A luminum Building Wir e and Cabl e (AN SI), 2012 Standard for Installing Metal Cable Tray Systems (ANSI), 2007 Standard for Installing N onm e talli c Ra cew a y s (RN C, E N T, LF NC) (AN SI), 2003 Standard for Installing Armored Cable (Type AC) and Metal-Clad Cable (Type MC) (ANSI), 2013 Standard for Installing and Maintaining Industrial H e at Tra c in g S ys t e ms (ANS!), 2013 Standard for Selecting, Installing, and Maintaining Electric Motors and Motor Controllers (ANSI), 2010 Standard for In s tallin g and T es tin g F i b e r Opti cs , 2009 Standard for Building and Service Entrance Grounding and Bonding, 2009 Standard for In s tallin g and Maintainin g S w it c hb o ard s (A NS!), 2007 Standard for Installing and Maintaining Motor Control Centers (ANSI), 2007 Standard for Installin g G e n e rat o r S e t s (AN SI), 2014 Recommended Practice for Installing and Maintaining Pane/boards (ANSI), 2009 Standard for Installin g and Maintaining Bu s wa ys (A NSI), 2009 Standard for Installing and Maintaining Dry-Type Transformers (ANSI), 2009 Standard for In s tallin g and Maintainin g Liquid-Fill e d Tran s f o rm e r s (AN SI), 201 3 Standard for Installing and Maintaining Uninterruptible Power Supplies (UPS) (ANSI), 2006 Standard for Fu se A ppli c ations (AN SI), 2014 Standard for Installing Medium-Voltage Metal-Clad Switchgear (ANSI), 2006 R ec omm e nd e d Pra c ti ce for In s talling Indoor Li g hting S ys t e m s (AN SI), 2006 Recommended Practice for Installing Exterior Lighting Systems (ANSI), 2006 R ec omm e nded Pra c ti ce for Installing Industrial Lightin g S y st e m s (ANSI), 2006 Standard for Installing Building Telecommunications Cabling (ANSI), 2006 3-20 "NWMI .... ** .... .... 0

• NOllTMWmM£0fW ISOTOPES Document number" NECA/NCSCB 600 NECAINEMA 605 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title R ecommended Pra ctice for In sta llin g and Maintaining Medium-Voltage Cable (ANSI), 2014 Installing Underground Nonmetallic Utility Duct (ANSI), 2005 National Electrical Manufacturers Association (NEMA) NEMAMG-1 Motors and Generators , 2009 InterNational Electrical Testing Association (NETA) ANSI/NETA ATS-2013 ANSI/NET A ETT-20 I 0 ANSI/NET A MTS-2011 Standard for Acceptance Testing Specifications for Electrical Power Distribution Equipment and Systems, 2013 Standard for Certification of Electrical T est in g T echnicians, 20 I 0 Maintenance Testing Spe c ifications for Electrical Power Distribution Equipment and Systems, 2011 National Fire Protection Association (NFPA) NFP A I Fire Code, 2015 NFPA2 NFPA4 NFPA 10 NFPA 13 NFPA 14 NFPA20 NFPA22 NFPA24 NFPA 25 NFPA30 NFPA 37 NFPA45 NFPA 55 NFPA68 NFPA 69 NFPA 70 NFPA 70B NFPA 70E NFPA 72 NFPA 75 NFPA 79 NFPA80 H ydrogen Technologies Code, 20 I I Standard for Integrated Fire Protection and Life Safety System Testing, 2015 Standard for Portabl e Fire Extinguishers, 2013 Standard for the Installation of Sprinkler Systems, 2013 Standard for the In sta llation of Standpipe and Ho se Syste m s, 2013 Standard for the Installation of Stationary Pumps for Fire Protection, 2013 Standard for Water Tanks for Pri vate Fire Prot ection, 2013 Standard for the Installation of Private Fire Service Mains and Their Appurtenances, 2013 Standard for th e In spection, T esting, and Maintenance of Water-Based Fire Protection Systems, 2014 Flammable and Combustible Liquids Code, 2015 Standard for th e In sta llation and Use of Stationary Com bu st ion Engines and Gas Turbines, 2015 Standard on Fire Protection for Laboratories Using Chemicals, 2015 Compressed Gases and Cryoge ni c Fluids Code, 2013 Standard on Explosion Protection by Dejlagration Venting, 2013 Standard on Explosion Prevention Systems, 2014 National Electrical Code (NEC), 2014 R ecomme nded Pra ctice for Electrical Equipment Maintenance, 2013 Standard for Electrical Safety in the Workplace, 2015 Nationa l Fire Alarm and Signaling Code, 2013 Standard for the Fire Protection of Information Technology Equipment, 2013 Electrical Standard for Indu stri al Machinery, 2015 Standard for Fire Door s and Other Opening Protectives, 2013 3-21

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• NORTHWEST MEOtcAl lSOTOftES Document number* NFPA 80A NFPA 86 NFPA 86C NFPA90A NFPA 90B NFPA 91 NFPA 92 NFPA92A NFPA 92B NFPA lOIB NFPA 105 NFPA 110 NFPAlll NFPA 170 NFPA 204 NFPA220 NFPA 221 NFPA262 NFPA 297 NFPA329 NFPA400 NFPA496 NFPA497 NFPA 704 NFPA 730 NFPA 731 NFPA 780 NFPA 791 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-7. Design Codes and Standards (12 pages) Document title R ecomme nded Practice for Protection of Buildings from Exterior Fire Exposures , 2012 Standard/or Ovens and Furnaces, 2015 Standard/or Indu stria l Furnaces Using a Special Pro ce ssing Atmosphere , 1999 Standard/or the Installation of Air-Conditioning and Ventilating System, 2015 Standard/or the In sta ll ation of Warm Air H eati n g and Air-Conditioning Systems , 2015 Standard/or Exhaust Systems for Air Conveying of Vapors, Gases , Mists, and Noncombustible Particulate Solids, 2015 Standard for Smoke Contro l Systems, 2012 Standard for Smoke-Control Systems Utilizing Barriers and Pressure Differences, 2009 Standard for Smok e Management Systems in Mall s, Atria , and Larg e Spaces , 2009 Code for Means of Egress for Buildings and Structures , 2002 (W-Next Edition) Standard for the In stallation of Smoke Door Assemblies and Other Opening Protectives, 2013 Standard for Emergency and Standby Power Systems , 2013 Standard on Stored Electrical Energy Emergency and Standby Power Systems, 2013 Standard for Fire Safety and Emergency Symbols, 2012 Standard/or Smoke and H eat V e nting , 2012 Standard on Types of Building Construction, 2015 Standard for Hi gh Challenge Fire Walls , Fire Walls, and Fire Barrier Walls , 2015 Standard Method of Test for Flame Travel and Smoke of Wires and Cables for Use in Air-Handling Spaces , 2015 Guide on Prin c ipl es and Practices/or Communications Systems, 1995 Recommended Practice for Handling Releases of Flammable and Combustible Liquids and Gases, 2015 Hazardous Materials Code, 2013 Standard for Purged and Pressurized Enclosures for Electrical Equ i pment, 2013 R ecommended Practice for the Classification of Flammable Liquids , Gases, or Vapors and of Ha za rdou s (Classified)

Locations for E l ect ri ca l In stallatio ns in Chemica l Pro cess Areas, 2012 Standard System for the Identification of the Hazards of Materials for Emergency Response, 2012 Guide for Premis es Security , 2014 Standard for the Installation of Electronic Premises Security Systems, 2015 Standard for the In sta llation of Lightning Prote ction Systems, 2014 Recommended Practice and Procedures for Unlabeled Electrical Equipment Evaluation, 201 3-22

.... ; NWMI *::**:;;. ...... NORllfWUT MEDICAL tsOTOffS NWMl-2013-0 21, Rev. 3 Chapter 3.0 -Design of Structures , Systems and C o mp o nents Table 3-7. Design Codes and Standards (12 pages) Document number* Document title NFPA 8 01 Standard for Fire Protection for Facilities Handlin g Radioactive Materials, 2014 Sheet Metal a nd Air Conditio n ing Contractors National Association (SMACNA) National Oceanic and Atmospheric Admi n istration (NOAA) NOAA Atlas 14 Precipitation-Frequenc y Atlas of the United States, Vol. 8 Version 2.0, 2013 SMACNA 1143 HVAC Air Du ct Leakage Test, 1985 SMACNA 1520 Round Industrial Du c t Construction Standard, 1999 SMACNA 1922 R ectangu lar Indu strial Duct Construction Standard , 2004 SMACNA 1966 HVAC Duct Construction Standard-Me tal and Flexible, 2006 SMACNA-2006 HVAC Systems Duct Design , 2006 ANSUSMACNA 001-2008 Seismic Restraint Manual: Guidelines for Mechanical Systems, 2008 U.S. Weather Bureau Technical Paper No. 40 Rainfall Frequency Atlas of the United States for Durations from 30 Minutes to 24 Hours and Return Periods from 1 to JOO Years, 1963 Underwriters Laboratory, Inc. (UL) Federal Specifications UL 181 UL499 UL555 UL 586 UL900 UL 1995 Standard for Factory-Made Air Ducts and Connectors, 2013 Standard for Electric H eat in g Appliances, 2014 Standard for Fire Damp e rs, 2006 Standard for High Efficiency, Parti culate, Air Filter Units, 2009 Standard for Air Filter Units, 2004 H eating and Cooling Equipment, 2011

• Co mplete refer ences are pro v id ed in Section 3.6 ACGIH American Co nf e r e n ce on Governmental I AEA International Atomic E ner gy Age ncy. Indu strial H yg i e ni sts. I CC internation al Code Co un c il. ACI American Co ncr ete In s titute. I CC-ES Int e rnation al Co d e Co uncil Eva luation Service. AHRI Air Con ditioning , He a tin g and Refrigerati o n IE EE Institute of E lectri ca l and Electronics Engineers.

Institute. JES llluminating E n g in ee rin g Society. AISC American In s titute of Steel Construction. ISA Internation al Society of Automation. AMCA Air Movement a nd Control Association.

NECA National Electrical Co ntractor s Association.

ANS American Nuclear Society. NEMA National Electrica l Manufacturers Association. ANSI American Nat ional Standards In s titut e. NETA InterNation a l E le ctrica l Testing Association.

ASCE American Society of Civil E n g in eers. NFPA National Fire Protection Association.

ASHRAE American Society of Heating , R ef rigerati on NIOSH National Institute for Occupational Safety and and A ir-Co nditioning E n gi neer s. Health. ASME American Society of Mechanical Engineers.

NOAA National Oceanic a nd Atmospheric ASNT American Society for Nondestructive Administration Te sting. SMACNA Sheet Metal and Air Co nditionin g Contractors ASTM American Society for Testing and Material s. National Association.

AWS American Welding Society. TIA Te l ecommunications Indu s try Association.

CDC Ce nters for Disease Co ntrol and Prevention. UL Underwriters Laboratory.

E IA Electronic Indu st ries Alliance. 3-23

.... ;. NWMI ...... .. .. .... .... .. ' *.* . NOmlWEIHIEOtCAl ISOTOl'l.S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.2 METEOROLOGICAL DAMAGE RPF meteorological accidents with radiological consequences are evaluated in NWMI-2015-SAFETY-Ol l , Evaluation of Natural Ph e nom e non and Man-Mad e Ev e nts on Safety Featur e s a nd It e m s Relied on for Safety. The basis for the structural design ofthe RPF is described in NWMI-2013-043 , NWMJ Radioisotope Produ c tion Fa c ili ty Structural D e sign Ba s is. Updates and development of technical specifications associated with the meteoro logica l design of the RPF SSCs will be provided in Chapter 14.0 as part of the Operating License Application.

The demands on structural elements due to applied loads are evaluated using the criteria and methodology discussed below. The effect of each load case is determined separately, and total demand is determined by combining the load effects using the load combinations for evaluating strength and eva l uating the serviceability criteria given below. Four categories ofload cases are used: normal , severe environmental, extreme e nvironmental , and abnormal loads. The definition of each load is the following:

• * *

• Normal loads are loads that are expected to be encountered during normal plant operations and shutdown , and load due to natural hazard phenomena likely to be encountered during the service life of the facility. Severe environmental loads are loads that may be encountered infreq ue ntly during the service life of the facility.

Extreme environmental loads are loads that are credible but are highly improbable to occur during the service life of the facility.

Abnormal loads are loads generated by a postulated high-energy pipe break accident used as a design basis. Definitions of load case symbols are provided in Table 3-8. Table 3-8. Load Symbol Definitions (2 pages) Symbol Definition Norma l Load Cases D Dead loads due to the weight of the structural elements, fixed-position equipment , and other permanent appurtenant items; weight of crane trolley and bridge F Load due to fluids with well-defined pre s sures and maximum heights H Load due to lateral earth pressure, groundwater pressure, or pressure of bulk materials L Live load due to occupancy and moveable equipment , including impact L, Rooflive load C c r Rated capacity of crane (will include the maximum wheel load s of the crane and the vertical, lateral , and longitudinal forces induced by the moving crane) S Snow load as stipulated in ASCE 7* for risk category IV facilities R Rain load T 0 Self-staining load, thermal effects, and loads during normal operating, startup, or shutdown conditions, based on the most critical transient or steady-state condition 3-24 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-8. Load Symbol Definitions (2 pages) Symbol Definition Ro Pip e r eac tion s durin g n o rm a l operatin g , s tartup , or s hutdo w n c onditi o n s , b ase d on th e mo s t criti ca l tran s i e nt o r s t ea d y-s t ate c ondition Severe Environmental Load Cases D; W e i g ht of i ce F a Flood load W L o ad due t o w ind p ress ur e W a Load based on serviceability wind speed W; Wind-o n-ic e E o Where required as part of the design basis , loads generated by the operating basis earthquake, as defined in 10 CFR 50 ,b Appendix S , " Earthquake Engineering Criteria for Nuclear Power Plants ," or as specified by the authority having jurisdiction Extreme Environmental Load Cases S , Weight of the 48-hour probable maximum winter precipitation s uperimposed on S W , L o ad s ge n e r a t ed by t he s p ec ifi ed d es i gn b as i s t o rn a d o , includin g wi nd pr ess ur es , pr es s ur e diff e r e nt ia l s , a nd torn a d o-b o rn e mi ss il es , as d e fin e d i n NU RE G-0 8 00 ,c o r as s p ec i fied b y the authorit y h av in g juri s di c tion E ss Loads generated by the safe shutdown , or design basis earthquake , as defined in 10 CFR 50 , b Appendix S , or as specified by the authority having jurisdiction Abnormal Load Cases P a Maximum differential pressure load generated by the postulated accident Ra Pip e an d e quipm e nt r eac tion s ge n e rat ed b y th e po s tul a ted accid e nt , includin g R o T a Thermal loads generated by the postulated accident , including T 0 Y j Jet impin ge m e nt lo a d ge n e rat ed by t h e p os tul a t e d acc id e nt Y m Missile impact load , such as pipe whip generated by or during the postulated accident Y , Lo a ds o n the s tru c tur e ge n e rated b y th e r eac tion o f th e broken hi g h-e n e r gy pip e du r in g the po s tul a t e d ac c id e nt

• ASCE 7 , M i n i mum D es i gn L oad s f o r B u ildin g s a n d Ot h e r Str u c t ur es , Am e ric a n Soc i ety of C i v il E n g in ee r s , R es t o n , V ir g ini a , 20 05 (R2 0 1 0). b I 0 CF R 5 0 , " D o m est i c Li ce n s in g of P ro du c ti o n and U tili za ti o n Faci l i t ies ," Co d e of F e d e ral R eg u l ati o n s, O ffice of th e Fe d eral R eg i s t e r , a s am e nd e d. c NURE G-0 800 , Sta n d a r d R e v i ew P l a n for t h e R ev i ew o f Saf ety A na l ys i s R e po rt s f o r N u cle a r P owe r Plant s, LWR E dit io n , U.S. N u c l ear R egu l a t ory Commi ss i o n , O ffice of N u c l e ar M a t e r ia l Safety and Safeguar d s , W a s hin g to n , D.C., 1 987. 3.2.1 Combinations of Loads Load combination s u s ed for evaluating s trength and s ervice a bility ar e giv e n in the following subsection

s. Combinations for s tr e n g th-ba s ed acc e pt a nce crit e ri a are g i v en for both nuclear s afety-r e l a t e d SSCs and for commercial SSC s. 3-25 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components 3.2.1.1 N u clear Safety-Related Structures, Systems, and Components For nuclear safety-related SSCs , the loading combinations from ACI 349 , Cod e R e quir e m e nts for Nucl e ar Saf ety-Related Con c r e t e Stru c tur es and Comm e ntary , are used. The load combinations from ACI 349 are essentially identical to the combination from ANSI/ AISC N690 , Sp e cifi c ation for Saf ety-R e lated St ee l Stru c tures for Nucl e ar Fa c iliti e s. Table 3-9 presents nuclear safety-related SSC loads. In addition, the load combination for extreme winter precipitation load (S,) takes DC/COL-ISG-007 , Int e rim Staff Guidan ce on Ass ess m e nt of Normal and Extr e m e Wint e r Pr ec ipitation Load s on th e Roofs of Sei s mi c Cat egory I Stru c tur es , guidance into account. Table 3-9. Load Com b inations for Stre n gth Base d Accepta n ce Criteria, N u clear Safety-Re l ated Combination Norma l Loa d Combinat i ons l.4(D + F + R,,) +To l .2(D + F + T 0 + R,,) + l .6 (L + H) + l .4C c r + 0.5(L, or S or R) l .2(D + F + R,,) + 0.8(L + H) + l .4Ccr + l .6(Lr or S or R) Severe Environmental Load Combinations l.2(D + F + R,,) + 1.6(L + H + E o) 1.2(D + F + R,,) + 1.6(L + H + W) Ext r e me E n v ir o n me n t al and A b nor m a l Lo ad Co mbin a ti o n s D + F + 0.8L + Cc r + H +T o+ R,, + E ss D + F+ 0.8L+ H +To+ R,,+ W, D + F + 0.8L + Ccr + H +T a+ Ra+ l.2P a D + F + 0.8L + H + T. +Ra+ Pa+ Y, + Y j + y m + E ss D + F + 0.8L + C c r + H +T o+ R,, + S, *HHG+ ANSl/AISC N690b (9-1) (NB2-l) (9-2) (NB2-2) (9-3) (NB2-3) (9-4) (NB2-4) (9-5) (NB2-5) (9-6) (NB2-6) (9-7) (NB2-7) (9-8) (NB2-8) (9-9) (NB2-9) a A C I 349 , C o d e R eq uir e m e nt s fo r N ucl e ar Saf ety-R e l at e d Co n c r e t e St ru c tur es and Co mm e nta1 y, Am e ri c an Concret e In s titute , Farmington Hill s , Michi g an , 2 01 3. h ANS V AISC N69 0 , Sp ec ifi c ati o n fo r S af ety-R e lat e d S t ee l S tru c tu r e s for N ucl e ar Fa c ili ti es, Am e ri c an In s titute of St ee l Co n s truction , Chica g o , Illinoi s , Janu a ry 3 1 , 2 012. 3.2.1.2 Commercia l a nd Nuclear No n-Safety-Re l ate d Structu r es, Systems, a nd Compo n ents For commercial and nuclear non-safety-related SSCs , the loading combinations from American Society of Ci v il Engineers (ASCE) 7 , Chapter 2 are used. When the loading includes earthquake effects, the special sei s mic load combinations are taken from ASCE 7 , Minimum D e sign Load s for Buildin gs and Oth e r Stru c tur e s, Chapter 12. The basic load combinations for the strength design of commercial type and safety-related nuclear SSCs are given in Table 3-10. The combinations listed a r e obtained from the 2012 International Building Code (IBC) and ASCE 7. The crane live load case (C cr) is separated from other live loads in the combinations for design purposes. 3-26

..... ; .. NWMI ..*... ..* *.. .*.* .. *:. .. NOMTMWESTMEOICALISOTOP£S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-10. Load Combinations for Strength Base Acceptance Criteria, Commercial Combination Basic Load Combinations l.4(D +F) l .2(D + F) + l .6(L + Ccr + H) + 0.5(L, or Sor R) l.2(D + F) + l.6(L, or Sor R) + l .6H + l/1(L + Ccr) or 0.5W] 1.2(D + F) + I.OW+ f 1(L +C c ,)+ 1.6H + 0.5(L, or Sor R) l.2(D + F) + I.OE+ f 1(L + C c r) + l.6H + f2S 0.9D+ I.OW+ l.6H 0.9(D + F) + I .OE+ l .6H Load Combinations, including Flood Load l.2D + (0.5W + I.OF a)+ L + 0.5(L, or Sor R) 0.9D + (0.5W + I .OF a) Load Combinations, incl u ding Atmospheric Ice Where: l .2D + l .6L +(0.2Di + 0.5S) l.2D + L +(Di+ Wi + 0.5S) 0.9 D +(Di+ Wi) fl = 0.5 for other live lo a d s. IBC* (16-1) (16-2) (16-3) (16-4) (16-5) (16-6) (16-7) §1605.2.l §1605.2.1 §1605.2.1 §1605.2.1 §1605.2.1 f2 = 0.7 for flat roof co nfiguration s, w hich do not s h ed s no w, and 0.2 for other roof configurations a IBC 2012 , Int ernatio nal Building Code , Int e rnati ona l Co d e Co un cil , In c., Washington D.C. ASCE 7b 2 3 4 5 6 7 §2.3.3.2 §2.3.3.2 §2.3.4.1 §2.3.4.2 §2.3.4.3 b ASCE 7 , Minimum D es i gn Loads for Buildings and Other Struc tu res, American Society of C ivil Enginee r s, R es ton , Virginia , 2 010. 3.2.2 Combinations for Serviceability Based Acceptance Criteria Based on ASCE 7, Appendix C Commentary , the load combinations given in Table 3-11 are u se d when evaluating se rviceability ba se d acceptance criteria. 3.2.3 Normal Loads The RPF is required to resist load s due to: * *

• Operating conditions of the systems and components within th e RPF Normal a nd seve re natural phenomena hazards , remaining operational to maintain life-safety and safety-related SS Cs Extreme natural phenomena hazards , maintaining life-safety and safetyre l ated SSCs Table 3-11. Load Combinations for Serviceability Based Acceptance Criteria Combination Short-Term Effects D+L D + 0.5S ASCE7 (CC-la) (CC-lb) Cree p , Sett l ement and Similar Long-Term of Permanent Effects D + 0.5L Drift of Walls an d Frames D+0.5L+ W a Seismic Drift Per ASCE 7 , Section 12.8.6 (CC-2) (CC-3) a Appendix C, Co mm e nt ary, of ASCE 7 , M i nimu m Design Loads for Buildings and Oth e r Struc tur es, American Society o f Civ il E ngin eers , R es ton , Virginia , 20 13. 3-27

..... ; .. NWMI ...... ..* ... ........ * . . * *

• NORTHWEST MEOfCAl ISOTOPH NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Structural loads are due to the following:

• * *

• Self-weight of building materials and SSCs Occupanc y and normal use of the RPF Off-normal conditions and accidents Natural phenomena ha zar ds Section 3.1 describ es the structural discipline so urce requirem e nts for the se criteria. Struc t ural load criteria are summarized below. Site-specific natural phenomena hazard criteria are based on the physical location of the RPF given in Chapter 2.0 , Sections 2.3 and 2.5. 3.2.3.1.1 Dead Loads Dead loads consist of the weight of all material s of construction comprising th e building , including walls, floors , roofs , ceilings , confinement doors , stairways, built-in partitions, wall and floor finishes, and cladding. Dead lo a d s also con s i s t of the weight of fixed equipment, including the weight of cranes. The density of all interconnections (e.g., heating , ventilation, and air conditioning

[HV AC] ductwork , conduits , cable trays , and piping) between equipment will be conservatively estimated and included in the final design for dead load for fixtures attached to ceilings or anchored to floors in the RPF. 3.2.3.1.2 Lateral Earth and Ground Water Pressure Loads Lateral earth and groundwater pres s ure loads are lateral pressures due to the weight of adjacent soil and groundwater, respectively. The design lateral earth load is a function of the composition of the soil. The Discovery Ridge Pha se 1 Environmental Assessment (Terracon , 201 la) indicates that the s oils present are clayey gravels consistent with the Unified Soil Classification "GC." In addition, the assessment indicate s that expansive soils are present. Chapter 2.0, Section 2.5.3 presents additional on-site soil information. The design lateral earth pressure load for the RPF is ba se d on ASCE 7 , Table 3 .2.1, and h as been augmented to account for the expansive soils (e.g., surcharge load is applied to account for the weight of the facility above the soils adjacent to the tank hot cell). The design groundwater depth is estimated to be approximately 5.5 meters (m) (18 feet [ft]) ground surface and will be verified pending final geotechnical inve stiga tion. Additional information is presented in Chapter 2.0 , Section 2.4.2. The lateral earth pressure load s for the RPF are presented in Table 3-12. Table 3-12. Lateral E arth Pressure Loads Element Value Base design lateral soil load 45 lb/ft 2 per ft Design lateral load (expansive increase) 60 lb/ft 2 per ft R efe r e nc e: Table 3.2-1 of ASCE 7 , Minimum D e s i g n Loads for Buildings and Oth er Structures , Americ an Society of C i vil E ngine ers , Re s ton , Virginia, 2013. 3-28

........... .... ;. NWMI .......... . ! . NOATHWHT M£00CA1. tSOTons NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.2.3.1.3 Live Loads Floor Live Load Live loads are produced by the use and occupancy of the RPF , and as such, different live load magnitudes are appropriate for different areas of the facility.

Design floor loads provided in Table 3-13 are based on ASCE 7, Sections 4.3 and 4.4 , and Section C4.3 Commentary.

During the structural analysis, unknown loads (e.g., hot cell roof in Table 3-13) will have a conservative value assumed and marked with "(HOLD)." As the design matures, the actual values will be inserted in the analysis and the HOLDs removed. Final design media cannot be issued if there are HOLDs identified. The facility live loads will be established during the completion of the final facility design and provided as part of the Operating License Application.

Roof Live Load Table 3-13. Floor Live Loads Description Uniform Concentrated Production area 250 lb/ft 2 3 , 000 lb Hot cell roof TBD TBD Cover block laydown TBD TBD Mechanical rooms 200 lb/ft 2 2 , 000 lb Laboratory I 00 lb/ft 2 2 , 000 lb Office 50 lb/ft 2 2 , 000 lb Office partitions 20 lb/ft 2 Corridors I 00 lb/ft 2 Truck bay Per AASHTO Based on Sections 4.3 , 4.4 , a nd C 4.3 Commentary of ASCE 7 , Minimum Design L oads for Buildings and Other Structures , American Soc iety of C ivil Eng ine e r s , R eston, Virginia, 2013. AASHTO TBD American Association of State Highway and Transportation Officials.

to be det ermine d. The minimum roof live load (Lr) prescribed by the City of Columbia is 20 pounds (lb)/square foot (ft 2), non-reducible (Ordnance No. 21804, Section 6-17). Snow loads (e.g., normal and extreme rain-on-snow) are discussed separately in Section 3.2.5.2. Crane Loads The design basis crane load criteria are given in Table 3-14 and are based on a preliminary quote provided in NWMI-2015-SDD-001 , RPF Facility SDD. The crane de s ign is to run a top-running bridge crane with a remotely operated, powered bridge and hoist. The crane design basis will be refined in the final design and Operating License Application to account for the following:

• ASCE 7, Chapter 3 -Include weights of crane and runway beams in dead loads Table 3-14. Crane Load Criteria Element Crane capacity Crane weight (with hoists) Bridge weight Hoist and trolley weight Wheel load (static) Value 75 ton (150 kip) 69,990 lbf 62,330 !bf 7,660 !bf 54.3 kip

• ASCE 7, Chapter 4 -Increase wheel load by 25 percent to account for vertical impact *

• ASCE 7, Chapter 4 -Determine lateral force by multiplying sum of hoist and trolley weight and rated capacity of crane by 20 percent ASCE 7 , Chapter 4 -Determine longitudinal force by multiplying the wheel load by 10 percent 3-29

.; ... ; .. NWMI ...... .. **: .... .... .. . ! . NORTKW£ST MEDICAl ISOTOns NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems a n d Components 3.2.4 Wind Loading 3.2.4.1 Wind Load PerNUREG-1537, Section 2.3.1, "General and Local Climate,

wind loads will be based on the 100-year return period wind speed. In addition , based on NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Section 3.3.1, the wind speed will be transformed to equivalent pressure per ASCE 7-05. For RPF SSCs per current applicable 2012 IBC guidance, ASCE 7-10 is used for this transformation of wind speed to equivalent pressure.

From Table 1.5-1 of ASCE 7-10 and based on use and occupancy of the RPF, a Risk Category IV is assigned to RPF SSCs. Figure 26.5-lB for a Risk Category IV building of ASCE 7-10 is used to obtai n the basic wind speed for the RPF site. The mean recurrence interval (MRI) of the basic wind speed for Risk Category IV buildings is 1 , 700 years. Since the MRI stipulated in ASCE 7-10 is more stringent than NUREG-1537 100-year wind speeds , wind loads will be determined in accordance with ASCE 7-10, Chapters 26 throug h 30, as applicable, for a Risk Category IV building. The surface roughness surrounding RFP SSCs is currently Surface Category C, which in turn indicates Exposure Category C for the RFP per ASCE 7-10. The RPF main building is an enclosed building. The wind loading criteria are provided in Table 3-15. The basic wind speed given in Table 3-15 is a 3-second (sec) gust wind speed at 10 m (33 ft) aboveground for Exposure Category C and Risk Category IV. The wind loading criteria will be updated in the Operating License Application. 3.2.4.2 Tornado Loading Table 3-15. Wind Loading Criteria Element Basic wind speed , V Exposure category Enclosure classification Risk category Value 193.1 km/hr (120 mi/hr) c Enclosed IV Source: ASC E 7-10, Minimum D es ign Loads f o r Building s and Oth e r Stru c tur es , American Society of Civil E ngineers , Reston , Vir g inia , 2010. Tornado loads are a combination of tornado wind effects, atmospheric pres s ure change, and generated missile impact effects and are discussed separately in the following sections. NUREG-1520, Standard Review Plan for the R e vi e w of a License Application for a Fuel C y cle Facility , Part 3, Appendix D , states that an annual exceedance probability of 10-5 may need to be considered.

The maximum tornado wind speed from NRC Regulatory Guide 1. 76 , Design-Basis Tornado and Tornado Mis s il es for Nuclear Pow e r Plant s, for Region I , has an annual exceedance probability of 1 0-7 that is s ignifi cantly lower than the target probability stated in NUREG-1520. For the RPF preliminary safety analysis report, the maximum tornado wind speed from NRC Regulatory Guide 1.76 for Region I will be used. The tornado load criteria will be updated by using tornado loadin g in accordance with 10-5 annual probability of exceedance in the Operating License Application.

3-30 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.2.4.2.1 Maximum Tornado Wind Speed Tornado wind field characteristics used to calculate tornado wind pressures on the RPF are provided in Table 3-16 per NRC Regulatory Guide 1. 76. The maximum tornado wind speed has two components

translational and rotational.

The maximum total tornado wind speed is the sum of these two components and is applied to the RPF building from each direction separately. Based on NUREG-0800, Section 3.3.2, ASCE 7-05 may be used to transform maximum tornado wind speed to equivalent pressure. Table 3-16. Design-Basis Tornado Field Characteristics Description Tornado region Maximum wind speed Translational speed Radius of maximum rotational speed Pressure drop , t.P Value Region I 370.l km/hr (230 mi/hr) 74.0 km/hr (46 mi/hr) 45.7 m (150 ft) (1.2 lb/in.2) Source: NRC Regulatory Guide I. 76 , D es i g n-Ba s is Tornado and Tornado Missil e s for N uclear Pow e r Plants , Rev. I , U.S. Nuclear Regulatory Commi ss ion , Washington , D.C., March 2007. For RPF SSCs per current applicable 2012 IBC guidance , Chapters 26 and 27 of ASCE 7-10 is used for this transformation of tornado wind speed to equivalent pressure. From Table 1.5-1 of ASCE 7-10 and based on use and occupancy of the RPF, a Risk Category IV is assigned to RPF SSCs. Per NUREG-800 , Section 3.3.2 , tornado wind speed is assumed not to vary with the height aboveground.

Additional information is provided in Chapter 2.0, Section 2.3.1.5 , and Chapter 13.0 , Section 13.2.6.1. 3.2.4.2.2 Atmospheric Pressure Change NRC Regulatory Guide 1.76 provides guidance for determining the pressure drop and the rate of pressure drop caused by the passing of a tornado. Depending on the final design of the RPF building and whether it is enclosed (unvented) or partially enclosed (vented structure), the procedures outlined in NUREG-800 Section 3.3.2 will be used to account for atmospheric pressure change effects. At the preliminary stage of the design, the RPF building is known not to be open. The value for atmospheric pressure drop , corresponding to the design-basis tornado is given in Table 3-16. 3.2.4.2.3 High Straight-Line Winds Similar to the tornado , high straight-line winds can also damage the facility structure, which in tum can lead to damage to SSCs relied on for safety. This evaluation demonstrates how the facility design addressed straight-line winds with a return interval of 100 years or more, as required by building codes. The RPF is designed as a Risk Category IV structure, a standard industrial facility with equivalent chemical hazards , in accordance with ASCE 7. The return frequency of the basic (design) wind speed for Risk Category IV structures is 5.88 x l0-4/year (MRI= 1,700 year). The provisions of ASCE 7 , when used with companion standards such as American Concrete Institute (ACI) 318 , Building Code Requirements for Structural Con c r e te , and American Institute of Steel Construction (AISC) 360 , Specification for Structural Steel Buildings , are written to achieve the target maximum annual probabilities of established in ASCE 7. The highest maximum probability of failure targeted for Risk Category JV structures is 5.0 x 10-6. 3.2.4.2.4 Tornado-Generated Missile Impact Effects The missile is assumed rigid in this analysis for maximum penetration.

Note that in Columbia, Missouri , the location of the University of Missouri Research Reactor (MURR) facility , the expected speed of tornado missiles is larger than the expected speed of any hurricane-generated missiles at the same annual frequency of exceedance (NUREG/CR-7005, T e chnical Basis for Regulatory Guidance on Design-Basis Hurricane Wind Spe e ds for Nuclear Power Plant s). 3-31 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems a n d Components Tornado-generated missile impact effects are based on the standard de sign missile s pectrum from NRC Regulatory Guide 1.76 and are presented in Table 3-17. In addition, wind velocities in excess of 34 m/sec (75 mi/hr) are capable of generating missiles from objects lying within the path of the tornado wind and from the debris of nearby damaged s tructures per Regulatory Guide I. 76. The se requirements are considered more severe than the characteristics from DOE-STD-I 020, Natural Ph enome na Ha zards D e sign and Evaluation Crit e ria for D e partment of En e rgy Faciliti es, that are cited in NUREG-1520, Section 3. The recommended RPF roof and wall system de s ign criteria are also taken from DOE-STD-1020 , Table 3-4. Description Automobile Pipe Steel Sphere Table 3-17. Design-Basis Tornado Missile Spectrum M,i¢fMijM 4 , 000 lb 287 lb 0.14 7 lb Dimensions 16.4 ft x 6.6 ft x 4.3 ft 6.625 in. diameter x 15 ft long 1.0 in. diameter Horizontal velocity 92 mi/hr 92 mi/hr 18 mi/hr Vertical velocity 62 mi/hr 62 mi/hr 12 mi/hr Sou rc e: NRC Regulatory Guide 1.76 , D esign-Ba sis T o rnad o and T o rnad o Mi ss il es fo r N ucl e ar P ower Pla n ts , U.S. Nuclear R egu latory Commissio n , Wa s hington , D.C., March 2 007. The impact-type missile , an automobile is limited to a height of no more than 9.1 m (30 ft) above-grade. Structural wall openings are subjected to the impact ofa 0.25 centimeters (cm) (I-inch [in.]) diameter steel sphere. The vertical ve locities are taken as 0.67 of the horizontal velocity. For an automobile and pipe missile , a normal impact is assumed. The tornado load criteria will be updated by using tornado loading in ac cordance with I 0-5 annual probability of exceedance in the Operating Lice n se Application and accordingly , the de s ign-basis tornado missile s pectrum will also be updated. Note that in Columbia, Missouri , the location of the MURR facility, the expected s peed of tornado missiles is larger than the expected speed of any hurricane-generated mi ssi le s at the same annual frequency of exceedance (NUREG/CR-7005). 3.2.4.2.5 Combined Tornado Load Effects After tornado-generated wind pressure effects , atmospheric pressure change effects and missile impact effects are determined

the combination thereof will be established in accordance with procedures outlined n NUREG-800, Section 3.3.2. The effect of atmospheric pressure drop by itself will be considered , and the total effects of wind pressure and missile impact effect s with one-half of the atmospheric pressure drop effects will be considered jointly. 3.2.4.3 Effect of Failure of Structures, Systems, or Components Not Designed for Tornado Loads SSCs , in which failure during a tornado event could affect the s afety-related portions of the RPF , are either designed to

*

• Resist the tornado loading or the effect on the safety-related structures from the failure of these SSCs Be bounded by the tornado missile or aircraft impact evaluations The effects and mitigations of failure of SSCs not designed for tornado loads will be developed during final design and the Operating License Application. 3-32

.... ; NWMI *::**:-:-* NOlmlWESTMEDfCALISOTOPEI 3.2.5 Rain, Snow, and Ice Loading 3.2.5.1 Rain Loads NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components From the National Weather Service (NWS)/National Oceanic and Atmospheric Administration (NOAA) Hydrometeorological Report No. 51, Probable Maximum Precipitation Estimates, United States East of the 105th Meridian , the probable maximum precipitation (PMP) is defined as "theoretical greatest depth of precipitation for a given duration that is physically possible over a particular drainage area at a certain time of year." Per NUREG-1 537 , Section 2.3.1 , "General and Loca l C limat e," rain loads will be based on the estimate of the weig ht of the 48-hour (hr) probab l e maximum precipitation , as specified by the U.S. Geological Survey. This rain load estimate is compared with the loc al building code rain load (i.e., ASCE 7-10), and the greater value is used in design of the RPF roof. The roof of the RPF is designed to prevent rainwater from accumulating on the roof. In accorda nc e with 2012 IBC and ASCE 7-10, the roof structure is designed to safely support the weight ofrainwater accumulation with the primary drainage system blocked and the secondary drainage system at it s design flow rate when subjected to a rainfall intensity based on the 48-hr probable maximum precipitation.

Rain loads are determined by the amou nt of water that can accum ulat e on the undeflected building roof if the primary drainage system becomes blocked (static head), plus a uniform depth of water above the inlet of the secondary drainage system at its design flow (hydrau lic head). The rain load criteria are determined per ASCE 7-10, Chapter 8 , and are provided in Table 3-1 8. Table 3-18. Rain Load Criteria Element Static head Hydraulic head Rainfall intensity Value 5 cm (2-in) TBD 3. 14 in./hr" a NOAA Atlas 14 , Pr e cipitati o n-Fr e qu e n cy A tla s of th e Un i t e d Stat es, Volume 8 , Ver s ion 2.0: Midwe s tern State s, Nationa l Oceanic and Atmo s pheric Admini s tration , Si l v er Sprin g , Mary l and , 2013. TBD = to be determined.

The hydraulic head is dependent on the roof drain size , roof area drained , and the rainfa ll inte n sity. The rainfall inte n sity used to determine the hydrauli c head i s taken from NOAA Atlas 14 , Pr ec Fr e qu e n cy At l as of th e United Stat e s , web tool for the 100-year storm , 1-hr duration. The rain load criteria wi ll be updated in the Operating License App li cation. 3.2.5.2 Snow Load Per the gu idanc e in DC/COL-ISG-007 , two types of s now lo ad are cons id ered: normal snow load and the extreme winter precipitation lo ad. The normal snow load will be included in normal load com bin ation s given below. Per the guidance in the DC/COL-I SG-007, the extreme winter precipitation load is included in the extreme environme nt a l lo ad combinations. The snow load criteria will be updated in the Operating License Application.

3.2.5.2.1 Normal Snow Load PerNUREG-1537 , Sectio n 2.3.1 and DC/COL-ISG-007, the normal snow load is the 100-year ground snow, modified using the procedures of ASCE 7 to determine the roof s no w load, including snow drifting. The 100-year ground snow load is calcu lated by factori n g the ground snow load stip ulat ed in t h e City of Columbia Code of Ordinances amendments (City of Co lumbia , 20 14) a nd IBC 2012 a nd is eq uivalent to the mapped ground snow load from Figure 7-1 of ASCE 7. This information is determined using the conversion factor provided in ASCE 7 , Table C7-3. 3-33 NWM I ...... *

• NORTHWEST MEDtcAL ISOTOH.I NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components The expos ur e factor provided in ASCE 7, Table 7-2 , for partially exposed roof in terrain category C is similar with the exposure u sed for determining wind loads. Since the RPF does not fall into any of the special cases indicated in ASCE 7, Table 7-3, the thermal factor is ass um ed to be 1.0. The importa n ce factor is taken to be unity from ASCE 7-10 , Table 1.5-2, for the RPF , which is designated Risk Category IV. Snow load criteria are s umm arized in Table 3-19. 3.2.5.2.2 Extreme Winter Precipitation Load Table 3-19. Snow Load Criteria Element Mapped ground snow l oad (50-year) Conversion factor, 100-year to 50-year Design ground snow l oad, p g (JOO-year) Expos ure factor (Ce) Thermal factor (C,) Importance factor 't1!11* *20 lb/ft 2 b0.82 24.4 lb/ft 2 I.Ob I.O b I.Ob a C ity of Co lumbia , " City of Co lumbi a Code of Ordinances," www.gocolumbiamo

.com/Council

/Code _of_ Ordinances

_PDF/, accessed September 8, 20 I 4. b ASCE 7 , Minimum D es ign Loads for Buildings and Oth e r Stru c tur es , American Society of Civi l Engineers , Reston, Virginia , 2013. Per NUREG-1537 , Section 2.3.1 and DC/COL-I SG-007 , the extreme winter precipitation l oad is the normal s now lo ad as presented in Section 3.2.5.2.1 , plus the liquid weight of the 48-hr probable maximum winter precipitation (PMWP). The 48-hr PMWP is determined from the NOAA/NWS Hydrometeorological Report (HR) 53 , Seasonal Variation of Mile Probable Maximum Pre cipitatio n Estimates, United States East of the 105th Meridian, for a 10-mi 2 area. HR 53 gives month PMP estimates for six 24-and 72-hr durations.

Based on the example of variation of PMP depths given in HR 53, Figure 46 , the 48-hr PMP is lin ear l y interpolated from the 24-and 72-hr PMP depths and gives a PMWP of 51.8 c m (20.4 in.). However, using the NOAA web tool for Co lu mbia (NOAA, 2017), a two-day ( 48-hr) average 100-year rain is 22.2 cm (8.73 in.) precipitation. The months of December , January , Fe bru ary, and March were used to determine the PMWP. In addition, using HR 53, Figu r es 26 through 45 , Table 3-20. Ex treme Winter Precip i tation Load Crite r ia Element 24-hr , I O-mi 2 PMWP 72-hr, 10-mi 2 PMWP 48-hr, 1 O-mi 2 PMWP (interpo l ated) Weight of 48-hr PMWP Value 46.7 cm (1 8.2 in.)* 56.9 cm (22.5 in.)* 22.2 cm (8.73 in.)b 106 lb/ft 2 a NWS/NOAA HR 53 , Seasona l Variation of JO-Squar e-Mile Probabl e Maximum Pr ec ipitation Estimat es , United Stat es East of th e 1 05th Meridian , National Oceanic and Atmospheric Administration , Silver Spring , Maryland , I 980. b NOAA , 2017 , " NOAA At l as 14 Point Precip it ation Frequency Estimates: Mo," http s://hdsc.nw s.noa a.gov/hdsc/pfd s/ pfd s_map_cont.htrnl?bkmrk=rno , Nationa l Oceanic and Atmospheric Administration , Si l ver Spring , Maryla nd , accessed 20 1 7. PMWP probable maximum winter precipitation.

the PMWP was determined to occur in the month of March. The PMWP criteria are given in Table 3-20. Winter weat h er events since 1 996 in Boone Cou n ty, Missouri, are provided in Chapter 2.0, Table 2-36. 3-3 4 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.2.5.3 Atmospheric Ice Load For SSCs to be considered sensitive to ice , the ice thickness and concurrent wind loads are determined using the procedures in ASCE 7, Chapter 10. Consistent with the requirements for snow and wind loads, the mapped values are converted to 100-year values using the MRI multipliers given in ASCE 7 , Table Cl0-1. Criteria for ice loading are given in Table 3-21. 3.2.6 Operating ThermaUSelf-Straining Loads Table 3-21. Atmospheric Ice Load Criteria Element Ice thickne ss (50-year) Concurrent wind speed Ice thickness MRI multiplier Wind speed MRI multiplier Importance factor Value* 2.54 cm (1 in.) 64.4 km/hr (40 mi/hr) 1.25 1.00 1.00

• ASCE 7, Minim um D esign Loads for Buildin gs and Oth e r Structures, American Society of Civi l E ngin eers, Reston, Virginia , 2013. MRI = mean recurrence interval.

Th e operating thermal/self-straining loads will be evaluated in the Operating License Application.

The se loads will be consistent with the requirements of ACI 349 or ANSl/AISC N690 , as applicable to the material of construction.

3.2. 7 Operating Pipe Reaction Loads The operating pip e reaction loads will be evaluated in the Operating License Application.

These load s will be consistent with the requirem e nt s of applicable American Society of Mechanical Engi neers (ASME) B31 , Standards of Pressur e Piping, codes. 3.2.8 External Hazards External hazards include aircraft impact , external ex plosions , and external fire. The RPF is a production facility , as opposed to a nuclear power reactor , as s uch 10 CFR 50.150(a)(3) is interpreted to mean that the requirement for the aircraft impact assessment is not applicable to this facility.

Sources of accidental external explosions have been considered and were found to not be an accident of concern. The RPF is constructed of robu s t , noncombu stib le material s, and adequate se tback s from transportation routes and land scap ing consisting of fire fuels are provided s uch that externals fires are not an accident of concern. 3-35 3.3 WATER DAMAGE NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components This section identifies the requirements and guidance for the water damage design of the RPF SSCs. NUREG-15 20 and ASCE 7 , Chapter 5 , provide guidance on flood protection o f nuclear safety-related SSCs. Updates and development of technical specifications associated with the water damage design of the RPF SSCs wi ll be provided in Chapter 14.0 as part of the Operating Licen se App li cation. 3.3.1 Flood Protection This s ub sec tion discusses the flood protection measures that are applicable to safety-re l ated SSCs for both external flooding and postulated flooding from failures of facility components containing liquid. A compliance review will be conducted of the as-bui lt design against the assumptions and requirements that are the basis of the flood evaluation presented below. Additional information is presented in Chapter 2.0 , Section 2.4.3 and Chapter 13.0 , Section 13.2.6.4.

This as-built evaluation will be documented in a flood analysis report and be part of the Operating License Application.

3.3.l.1 Flood Protection Measures for Structures, Systems, and Components 3.3.1.1.1 Flooding from Precipitation Events Regional flooding from large precipitation events raising the water level s of local streams and rivers to above the 500-year flood level can have an adverse impact on the structure and SSCs within. These impacts include the structural damage from water and the damage to power supplies and instrument control systems for SSCs relied on for safety. The infiltration of flood water into the facil i ty could cause the failure of moderation control requirements and lead to an accidental nuclea r criticality. Direct damage or impairment of SSCs could also be caused by flooding in the facility.

The site will be graded to direct the st ormwater from localized downpours with a rainfall intensity for the 100-year storm for a I-hr duration around and away from the RPF. Thus , no flooding from local downpours is expected based on sta ndard industrial de s ign. Rainwater that falls on the waste management truck ramp and accumulates in the trench drain has low to no consequence for radiological , chemical , and criticality hazard s. Situated on a ridge , the RPF will be located above the 500-year flood plain according to the flood insurance rate map for Boone County , Missouri , Panel 295 (FEMA, 2011). The site is above the elevation of the nearest bodies of water (two small ponds and a lake), and no dam s are located upstream on the local streams. This data conservatively provides a 2 x I 0-3 year return frequency flood , which can be considered an unlikely event according to performance criteria.

Howe ver, the site is located at an elevation of 248.4 m (815 ft), and the 500-year flood plain starts at an elevation of 231.6 m (760 ft), or 16.8 m (55 ft) below the site. Since the site, located only 6.1 m (20 ft) below the neare st high point on a ridge (relative to the local topography), is well above the beginning of the 500-year flood plain, and i s considered a dry s ite , the probable maximum flood from regional flooding is considered h i ghly unlikel y , without further evaluation.

1 1 The recommended sta ndard for determining the probabl y maximum flood , ANS 2.8, D e t er mining Desi g n Ba s i s Flooding at P owe r R e a c tor Sit es, ha s been withdrawn.

3-36 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components P e r NUREG-1520 , Sec tion 3.2.3.4(1)(c), and ASCE 7 , C hapte r 5 , flood lo a d s will b e ba sed on the water l eve l of the 100-year flood (one percent probabili ty of excee danc e p er year). Th e facility has been det ermi n e d to b e above both the 100-year and the 500-year flood plain. Chapter 2 , Section 2.4.3, pro vides a ddition al detail for flood protection measures. Po stu l ate d floodin g from component fa ilur es in the building compartments wi ll b e prevented from adversely affecting plant safety or posing any h aza rd to th e public. Exterior or access openings and p e n etrat ion s into the RPF will be a bo ve the m ax imum po st ul ated floodin g l eve l. Th erefore, flood lo ads are cons id e red hi ghly unlik e l y and are not considered d es i gn loads. 3.3.1.1.2 Flooding from Inadvertent Discharge of Fire Protection System Water D esig n of fire s uppr essio n systems using water (e.g., automatic spr inkJ ers, hose sta tion s) includes e l ements s uch as the gra ding and c h a nn e lin g of floors, ra i s in g of e quipm ent mounts a b ove floors , s h e l ving a nd floor drains , and other passive means. Th ese features w ill ensure s u ffic i e nt capac ity for gravity-driven collection and d rainage of th e maximum water discharge rate a nd duration to av oid lo ca li zed floodin g and resulting water damage to e quipm e nt wit hin the area. In addition, particularly se n s it ive sys tem s and co mpon e nt s, whether electrical , optical, mechanical and/or chemical , are typi ca ll y prot ecte d within enclos ur es d esigned for the a n ticipate d a dv erse e nvironm enta l co nditi ons res ultin g from th ese types of water discharges.

If cr iti ca l for safety , th ese wate r-se n sit i ve syste m s and compo n e nt s will be installed within the a ppropri ate severe e n viron m e nt-rat e d enclos ur es in acco rdanc e with the relevant indu stry sta ndard (s) (e.g., National E l ectr ic a l Manufacturers Association

[N EMA] e ncl osure s tandard s). Selection of specific fire s uppr ession sys tem s for fac ility location s will be gui ded by r ecomme ndation s in relevant industry standa rds (e.g., NFPA 8 01 , Standard for Fire Protection for Faci liti es Handling R adioactive Materials) a nd will depend on the l eve l of fire h azards at those locations , as determined from th e fina l facility a nd process systems d es i g n s. These final detailed d es ign s wi ll includ e any facility d esign e l e m e nts a nd sensitive e quipm ent protection m eas ur es de e med necessary for addressing the maximum in adverte nt rate and duration of water di sc har ges from the fire protection syste m s. Th e fina l comprehensive facility de s ign , a l ong with co mmitm e nt s to d esign codes , stan d a rds , a nd ot h er referenced docum ents (including any exceptions or exemptio n s to th e identified requirements), will be i dentifi ed and provided as part of the Operating Lic e nse Application.

3.3.1.2 F lood Protection from External Sources Safety-related components locat ed below-grade will b e prot ected u s in g th e hardened prot ectio n approach.

The safety-re l a t ed syste m s and components wi ll be protected from external wate r dama ge by bein g enc l osed in a reinforced co n crete safety-related str u cture. Th e RPF will h ave the fo llo wing c h aracteris tic s: * *

• Exte rior safety-r e l a ted wa ll s b e low-gr ade w ill b e 0.61 m (2-ft) thick minimum Water s top s will be pro v id ed in a ll construction joints below-grade Waterproof coat ing will be a ppli e d to external s urfac es below-grade and as required a bov e-grade Roof s will be designed to prevent poolin g of l arge amounts of water in accordance with R egu lato ry Gui de 1.10 2, Flood Protection for Nuclear Pow er Plant s W aterproofi ng of foundations and wa ll s of safety-related s tructur es belo w-grade will b e acco mpli s h e d prim a r i l y by the u se of water stops at ex pan s ion a nd construction joint s. In a ddition to water stops, waterproofing of the RPF will b e provided to protect th e ex t erna l s urfa ces from ex po s ure to water. Th e l eve l above the RP F first l eve l where wa t erproofing i s to b e u se d will b e d etermi n ed in the Operating Li cense Application. 3-37 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components The flood protection measures that are described above will also guard against flooding from the rupture of the on-site fire protection water storage tank (if future design development determines that a fire protection storage tank is necessary). Any flash flooding that may result from tank rupture will drain away from the RPF and thereby cause no damage to facility equipment.

3.3.l.3 Compartment Flooding from Fire Protection Discharge The total discharge from the failure of fire protection piping consists of the combined volume from any sprinkler and hose systems. The sprinkler system , if used , is capable of delivering a water density of 20 gallons per minute (gal/min)

(76 liters per minute [L/min]) over a 139 m 2 (1 , 500 ft2) design area; therefore , the sprinkler system is calculated to have a flow rate of 1 , 136 L/min (300 gal/min). The hose stream will be a manually operated fire hose capable of delivering up to 946 L/min (250 gal/min). In accordance with NFPA 801 , Section 5.10 , the credible volume of discharge is sized for the suppression system operating for a duration of 30 min. The design of water-sensitive , safety-related equipment will ensure that potential flooding from sprinkler discharge will not adversely affect the safety features. For example , equipment may be raised from the floor sufficiently such that the potential flooding due to sprinkler discharge will not impact the criticality analyses. Outside of the radiologically controlled area (RCA), as defined in Chapter 11.0, "Radiation Protection and Waste Management

," there is limited water discharge from fire protection systems. Any sensitive , safety-related equipment will be installed above the floor slab at-grade to ensure that the equipment remain s above the flooded floor during sprinkler discharge.

3.3.l.4 Compartment Flooding from Postulated Component Failures Piping , vessels , and tanks with flooding potential in the safety-related portions of the RPF will be seismically qualified. Water-sen s itive , safety-related equipment will be raised above the floor. The depth of water on the floor will be minimized by using available floor space to spread the flood water and limiting the water volumes. Analyses of the worst flooding due to pipe and tank failure s and their consequences will be developed in the Operating License Application. 3.3.1.4.1 Potential Failure of Fire Protection Piping The total discharg e from the operation of the fire protection system bounds the potential water collection due to the potential failure of the fire protection piping. 3.3.1.5 Permanent Dewatering System There is no permanent dewatering system provided for the flood design. 3.3.1.6 Structural Design for Flooding Since the design PMP elevation is at the finished plant-grade and the probable maximum flood (PMF) elevation is approximately 6.1 m (20 ft) below-grade , there is no dynamic force due to precipitation or flooding.

The lateral surcharge pressure on the s tructures due to the design PMP water le v el is calculated and does not govern the design of the below-grade walls. The load from buildup of water due to discharge of the fire protection system in the RCA i s supported by slabs-on-grade , with the exception of the mezzanine floor. Drainage is provided for the second level in the RCA to ensure that the second level slab is not significantly loaded. The second level slab is designed to a live load of 610 kilograms (kg)/m 2 (125 lb/ft 2); therefore , the slab is capable of withstanding any temporary water collection that may occur while water is draining from that floor. 3-38 3.4 SEISMIC DAMAGE NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Seismic analysis criteria used for the RPF will conform to IAEA-TECDOC-134 7, Consideration of External Event s in the Design of Nuclear Facilities Other Than Nuclear Pow e r Plants , with Emphasis on Earthquakes. This report provides requirements and guidance for the seismic design of nuclear facilities other than nuclear power plants. NUREG-0800 and other NRC Regulatory Guides provide additional detailed guidance for the seismic analysis and design of the RPF. Additional information is provided in Chapter 2.0, Section 2.5.4 , and Chapter 13.0 , Section 13.2.6.5. Updates and development of technical specifications associated with the seismic damage design of the RPF SSCs will be provided in Chapter 14.0 as part of the Operating License Application.

3.4.1 Seismic Input 3.4.1.1 Design Response Spectra Safe-Shutdown Earthquake The NRC has recommended using Regulatory Guide 1.60 , D e sign Respon se Sp ec tra for S e i s mic D es ign of Nuclear Power Plants , for radioisotopes production facilities (e.g., 10 CFR 50). NWMI will use a spectrum anchored to 0.20 g peak ground acceleration for the RPF design basis. Regulatory Guide 1.60 is not indexed to any specific soil type , with its frequency content sufficiently broad to cover all soil types. Therefore , soil type for the RPF will not be a parameter used to determine the RPF's design response spectra. The composition of soil in which the RPF is embedded will be included in the interaction analysis as part of the building response analysis. This information will be provided in the final safety analysis report (FSAR) as part of Operating License Application.

This peak ground acceleration matches that of the University of Missouri Research Reactor (Adams, 2016) and the Calloway Nuclear Generating Station , which both are within 80.5 km (50 mi) of the RPF , as suggested by the NRC staff during the November 10 , 2016 Public Meeting. The analysis procedure develops ground motion acceleration time histories that match or exceed the Regulatory Guide 1.60 spectrum as input to the building finite e l ement model. Structural damping will follow the recommendations of Regulatory Guide 1.61 , Damping Valu es for Seismi c D es ign of Nucl e ar Power Plant s, which range from about 3 to 7 percent. Response spectra corresponding to the recommended damping values of Regulatory Guide 1.61 will be used to derive seismic loads. Damping varies depending on the type of SSC. Structural damping will follow Regulatory Guide 1.61 guidance (ranging from about 3 to 7 percent).

Plotting response spectra at 5 percent damping for purposes of illustration is a convention within the nuclear industry , but for analysis lo ads , damping will vary depending on the earthquake level (operating basis earthquake or safe-shutdown earthquake) and the type of SSC. Soil-Structure Interaction and Dynamic Soil Pressures The structure is supported on a shallow foundation system on stiff competent soils. The Phase 1 Assessment (Terracon , 201 la/b) stated the site is classified as Site Class C. Prescribed in ASCE 7, Table 20.3-1 , the typical shear wave ve lo cities for the soi l s present at the site are 1,200 to 2 , 500 ft/sec. Typical practice is to define competent soi l as having a shear wave ve locity greater than 1,000 ft/sec. The analysis of the RPF building structure to the safe shutdown earthquake will include the effects of a structure interaction. Dynamic soil pressures were determined using ASCE 4 , S e ismi c Anal y sis of R e lat e d Nuclear Stru c tur e s and Commentar y, Section 3.5.3.2 , and applied to the earth retaining walls in the hot cell area. 3-39 Operating Basis Earthquake NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components For preliminary de sign, the operating basis earthquake was selected to be one-third the safe-shutdown earthquake defined previously (based on Regulatory Guide 1.61 ). Since this option was selected, explicit design and analysis of the facility structure for the operating basis earthquake ground-motion is not required.

3.4.1.2 Method of Analysis The effect of loads other than earthquake-indu ced (seismic) loads is determined by static analysis methods in accordance with ASCE 7 and the fundamental principles of engineering.

Seismic analysis of SSCs will be performed by either equivalent-static methods or dynamic analysis methods in accordance with ASCE 4 and ASCE 43 , Seismic Design Criteria for Structures, Systems, and Components in Nuclear Fa cili ties. The equivalent-static and dynamic seismic analysis methods are discussed below. 3.4.1.2.1 Equivalent-Static Analysis Equivalent

-static seis mic analysis of commercial type structure will be performed in accordance with ASCE 7 , Section 12.8. Direction of Seismic Loading Design of IROFS will consider seismic load s in all three directions using a combination of the-s um-of-squared or 100/40/40 methodologies per Regulatory Guide 1.92 , Combining Modal Respon ses and Spatial Components in Seismic Respon se Analysis.

The 100/40/40 methodology will be used in the development of the final RPF design and included as part of the Operating License Application.

3.4.1.2.2 Dynamic and Static Ana l ysis Dynamic analyses are only used for the evaluation of RPF structural components. A static analysis will be completed during final design by using a combination of static load computations to ensure the SSCs remain in place and intact , and a combination of existing shake table test data and existing earthquake experience to ensure that the equipment functions following the earthquake.

The analysis of related structures may be either completed by the: *

• Linear-elastic response spectra method performed in accordance with ASCE 4 , Section 3.2.3.1 , and ASCE 43 , Section 3.2.2 Linear-elastic time history method performed in accordance with ASC E 4 , Section 3.2.2, and ASCE 43 , Section 3.2.2 Damping -The damping values used for dynamic analysis for the structural system considered will be taken from Regulatory Guide 1.61. Inelastic energy adsorption factors and damping values used for the analysis of nuclear safety-related structures will be se l ected from ASCE 43 , Table 5-1. Modeling -Finite element models will only be used for the RPF building structures.

The mesh for plate e l ements and member nodes will be se lect ed to provide adequate discretization and distribution of the mass. Further , the aspect ratio of plate elements will be limited to no greater than 4: 1 to ensure accurate analysis results. 3-40 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Direction of seismic loading -Three orthogonal directions of seismic loading are used in the RPF design, two horizontal and one vertical.

The modal components of the dynamic analysis and the spatial components of response analysis are combined as described below. *

• 3.4.2 Modal combinations -The structure of the RPF is designed to be relatively stiff , and components are combined using the comp l ete quadratic combination method. Spatial component combinations

-Spatial components are calculated separately and combined using the square-root-sum-of-the-squares method to determine the combined earthquake effect and resulting demands. Seismic Qualification of Subsystems and Equipment This subsection discusses the methods by which the RPF systems and components are qualified to ensure functional integrity.

Based on the characteristics and complexities of the subsystem or equipment, seismic qualification will be done by a combination of static load computations to ensure that the SSCs remain in place and intact, and a combination of existing shake table test data and existing earthquake experience to ensure that the equipment functions fo llo wing the earthquake. 3.4.2.1 Qualification by Analysis NWMI will define specific acceptable qualification methods in the procurement packages to demonstrate seismic qualifications.

Seismic qualification of IROFS will include three options of: ( 1) calculations and verification that the main structural components of the SSC can withstand the seismic loads derived from the in-structure floor response spectra at the damping va lu e derived from Regulatory Guide 1.61, (2) reference to available shake table testing that demonstrates the seismic capacity of the SSC or of multiple similar items, and (3) demonstration of the seismic capacity through the performance of the type of SSC in actual earthquakes.

3.4.2.1.1 Equivalent Static Analysis The equivalent static analysis of nuclear safety-related subsystems and equipment is performed in accordance ASCE 43, Section 8.2.1.1. The equivalent static analysis of subsystems and equipment that are not relied on for nuclear safety but are designated as a component of a seismic system per IBC 2012 , Chapter 17, is performed in accordance with ASCE 7, Chapter 13. 3.4.2.1.2 Static Analysis The static analysis of non-structural, safety-related subsystems and equipment is performed in accordance ASCE 4, Section 3.2.3.1 , and ASCE 43, Section 8.2.1.2. A portion ofthe seismic qualification process will involve simple static analysis of the main structura l elements (anchorage and primary framing) of IROFS components, using seismic loads from in-structure response spectra derived from the RPF building structure dynamic response analysis. In-structure response spectra are determined using ASCE 4 , Section 3 .4.2, and NRC Regulatory Guide 1.122 , D e v e lopment of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components.

In-structure floor response spectra will be developed through a finite element model of the RPF building using an artificial time history that matches or envelops the Regulatory Guide 1.60 spectrum at a peak ground acceleration=

0.20 g. 3-41

.; .. ;. NWMI ..*... .. .. . .......... ' * ." NOATKWEST ME D IOO ISOTOPES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.4.2.2 Qualification by Testing NWMI will define specific acceptable qualification methods in the procurement packages to demonstrate seismic qualifications. Seismic qualification ofIROFS will include three options of: (1) calculations and verification that the main structural components of the SSC can withstand the seismic loads derived from the in-st ructure floor response s pectra at the damping value derived from Regulatory Guide 1.61 , (2) reference to available shake table testing that demonstrates the seismic capacity of the SSC or of multiple similar items , and (3) demonstration of the seismic capacity through the performance of the type of SSC in actual earthquakes.

Per NRC Regulatory Guide 1.100 , Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants: *

• Active mechanical equipment relied on for or important to nuclear safe ty will be required to be seismically qualified in accordance with Regulatory Guide 1.100. Active electrical equipment important to or relied on for nuclear safety will be required to be seismically qualified in accordance with IEEE 344, IEEE Standard for S eis mi c Qualification of Equipment for Nuclear Power Generating Stations.

Sub sys tems and equipment not relied on for nuclear safety but designated as a component of a seismic system per IBC 2012, Chapter 17, will be required.

Existing databases of past shake table tests will be used , such as the Office of Statewide Health Planning and Development database provided by the state of California. These tests have typically been done based on the ICC-ES AC156 , "Acceptance Criteria for Seismic Certification by Shake-Table Testing ofNonstructural Components," spectrum.

The capacity of the standard support design for overhead fixtures mounted above RPF IROFS will be checked to ensure that the supports can withstand the seismic loads derived from the floor spectra (e.g., remain stable during and after postulated earthquake effects) of the attachment floor slab. This information will be provided in the FSAR as part of the Operating License Application.

The RPF seismic design will also include a check to ensure that pounding or sway impact will not occur between adjacent fixtures (e.g., rattle space). Estimates of the maximum displacement of any fixture can be derived from the appropriate floor response spectrum and an estimate of the fixture's lowest response frequency. This information will be provided as part of the Operating License Application.

3.4.3 Seismic Instrumentation Seismic recording instrumentation wi ll be triaxial digital systems that record accelerations versus time accurate l y for periods between 0 and 10 sec. Recorders will have rechargeable batteries suc h that if there is a loss of power , recording will s till occur. All instrumentation will be housed in appropriate weather and creature-proofed enclosures.

As a minimum , one recorder should be located in the free-field mounted on rock or competent ground generally representative of the s ite. In addition, at sites classified as Seismic Design Category D , E, or Fin accordance with ASCE 7 , Chapter 11 , using Occupancy Category IV, recorders will be located and attached to the foundations and roofs of the RPF and in the control room. The systems will have the capability to produce motion time histories. Re s ponse spectra will be computed separately.

The purpose of the instrumentation is to (1) permit a comparison of measured responses of C-1 structures and selected components with predetermined results of analyses that predict when damage might occur, (2) permit facility operators to understand the possible extent of damage within the facility immediately following an earthquake , and (3) be able to determine when an safe-shutdown eart hquake event has occurred that would require the emptying of the tank(s) for inspection as specified in NFPA 59A , Standard for the Production , Storage, and Handling of Liqu efie d Natural Gas, Section 4.l .3.6(c). 3-42

.; .. ;. NWMI ...*.. .. .. .... * *

• NOftTNWEST MEDtcAl ISOTOP'ES NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Seismic instrumentation for the RPF site is not an IROFS; it provides no safety function and is therefore not "safety-related

." Altho u gh the s eismic recorders have no safety function , they must be designed to withstand any credible level of shaking to ensure that the ground motion would be recorded in the hi ghly unlikely event of an earthquake. This capabi li ty requires verificat i o n of adequate capacity from the manufacturer (e.g., prior shake table tests of their product line), provision of adequate anchorage (e.g., manufacturer-provided anc hor specifications to ensure accurate recordings), and a check for seism i c interaction ha zards such as water s pray or falling fixtures.

With these design features , the instrumentation would be treated as if it were safety-r e l ated QL-2. Additional information on seismic instruction wi ll be provided as part of the Operating License Application. 3.4.3.1 Location and Description Seismic instrumentation i s installed for structural monitoring.

The seismic instrumentation consists of so lid-s tate digital , tri-axia l strong motion recorders located in the free-field , at the structure base , and at the roofof the RPF. 3.4.3.2 Operabilit y and Characteristics The seismic in strumentation operates during all modes of RPF operat i ons. The maintenance an d repair procedures provide for keeping the maximum number of in struments in service during RPF operation s. The instrumentation insta ll ation design in c lud es provisions for in-service testing. The instruments se l ected are capable of in-place functiona l testing and periodic cha nn el checks during normal faci li ty operation.

3-4 3 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components 3.5 SYSTEMS AND COMPONENTS Certain systems and components of the RPF are considered important to safety because they perform safety functions during normal operations or are required to prevent or mitigate the consequences of abnormal operational transients or accidents.

This section summarizes the design basis for design , construction , and operating characteristics of safety-r e l ated SSCs of the RPF. 3.5.1 General Design Basis Information 3.5.1.1 Classification of Systems and Components Important to Safety The RPF systems and co mponent s wi ll be classified according to their importance to safety, quality l evels, and seismic c l ass. The g uid ance used in developing these classifications during preliminary design with the support ofregulatory guidance reviews , hazards and operability ana l ysis, accident analysis, integrated safety ana l ysis, and national consensus code requirements is presented below. The RPF systems identified in Table 3-1 a nd their associated subsystems and components are discussed in the subsect ion s that fo llow. 3.5.1.2 Classification Definitions The definitions used in the classification of SSCs include the followi n g. In accorda nc e with I 0 CFR 50.2 , " Definitions," design basis refers to information that identifies the specific functions to be performed by an SSC of a facility and the specific values or ranges of values chosen for controlling parameters as reference bounds for design. These values may be: *

• Restraints derived from genera ll y accepted state-of-the-art practices for achieving functio nal goals Requirements derived from ana ly sis (e.g., calcu l ation, experiments) of t he effects of a postulated acc ident for w hi c h a SSC must meet its functional goals These reference bounds are to include the bounding conditions under which SSCs must perform design basis functions and may be derived from normal operation or any accident or events for which SSCs are required to function , including anticipated operational occurrences , design basis acc ident s, externa l events, natural phenomena, and other events spec ificall y addressed in the regulations.

Design basis accident is a postulated accident that a nuclear faci lity must be designed and built to withstand, without loss to the SSCs necessary to ens ur e public health and safety. Design basis event (DBE) is an event that is a cond ition of normal operation (inclu din g anticipated operational occurrences), a de sign basis accident, an external event, or natural phenomena for which the facility must be designed so that the safety-re lat ed functions are ac hi evable. Design basis accidents and transients are those DBEs that are accidents and transients and are postulated in the safety analyses. The de s ign ba sis acci d ents and transients are used in the design of the facility to es tabli sh acceptab l e performance requirements for SSCs. Single failure is considered a random failure and ca n include an initiating event (e.g., component failure , natural phenomenon , externa l man-made h azard) or consequential fa ilur es. Mechanical, instrumentation , and electrical systems a nd components required to perform their intended safety function in the eve nt of a single fai lure are designed to include s ufficient redundancy and independence.

This type of design verifies that a single failure of any active component does not result in a lo ss of the capabil i ty of the system to perform its safety functions.

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.; .. ; NWMI ...*.. ..* .. .... .... .. NOlmfWESTMEOICAl ISOTOPES NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Mechanical, instrumentation , and electrica l systems and components are designed to ensure that a single failure, in conjunction with an initiating event, does not result in the lo ss of the RPF's ability to perform it s int ende d safety function. Design techniques suc h as physical separat ion , functional diversity, diver sity in compo nent design , and principles of operation , will b e used to the extent necessary to protect against a sing l e failure. An initiating event is a sing l e occurrence , including its consequential effects , that places the RPF (or some portion) in an abnorma l conditio n. An initiating event and its resulting consequences are not considered a single failure. Active components are devices characterized by an expected significant change of state or discernible mech anica l motion in response to an imposed demand on the system or operation requirements (e.g., switc h es, circuit breakers , relays, valves , pressure sw it ches, motors, dampers , pumps , and analog met ers). An active compone nt failure is a failure of the component to complete its intended safety function(s) on demand. Passive components are devices characterized by an expected negligible change of state or negligible m echanical motion in response to an imposed design basis l oad demand on the system. Defense-in-depth is an approach to designing and operating nuclear facilitie s that prevents and mitigates accidents that relea se radiation or hazardous material through the c reation of multiple independent and redundant layers of defense to compensate for potential hum an and mechanical failures so that no single l ayer, no matter ho w robust, i s exclusively relied on. Defense-in-depth includes the use of access controls, physical barriers, redundant and div erse key safety functions, and emerge ncy response mea s ur es. The RPF structure and system designs a re ba sed on defense-in-depth practi ces. Th e RPF design incorporates:

• *

• Preference for e n gi n eered controls over admi ni s trati ve co ntrols Independence to avoid common mode failures Other features that enhance safety by reducing challenges to safety-r elated components and systems Safety-related systems and components identified in this section are described in C h apters 4.0; 5.0 , "Coo lant Systems;" 6.0; 7.0; 8.0, "E lectric al Power Systems;" a nd 9.0, "A uxiliary Systems," as appropriate. 3.5.1.3 Nuclear Safety Classifications for Structures, Systems, and Components SSCs in the RPF are c la ssified as safety-re lat ed and non-safety-related.

The safety-re lat ed SSCs include IROFS to meet the performance requirement of 10 CFR 70.6 1 and other safety-r e lat ed SSCs to meet the r equireme nt s of 10 CFR 20. The purpose of this section i s to classify SSCs according to the safety function being performed.

In additio n , de sign requirements will be plac ed on SSCs to ensure the proper performance of their safety function, when required.

• Safety-related i s a classification applied to items relied on to remain functional during or following a postulated DBE to ensure the: Int egrity of the faci li ty infrastructure Capability to sh ut down the facility and maint ain it in a safe shutdow n condition 3-45

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• *

• Capability to prevent or mitigate the consequences of postulated accidents identified through accident analyses that could result in potential offsite and worker exposures comparable to the applicable guideline exposures set forth in 10 CFR 70.6l(b), 10 CFR 70.6 l (c), and 10 CFR 70.61 (d) Operation of the facility without undue risk to the health and safety of workers , the public, and the environment to meet 10 CFR 20 normal release or exposure limits for radiation doses and applicable limits for chemical exposures Safety-related IROFS -SSCs identified through accident analyses that are required to meet the performance requirements of 10 CFR 70.6l(b), 10 CFR 70.61(c), and 1 0 CFR 70.6l(d) (Table 3-2). Safety-related Non-IROFS

-SSCs that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of workers, the public , and environment , and includes SSCs to meet 10 CFR 20 normal release or exposure limits. Non-safety-related

-SSCs related to the production and delivery of products or services that are not in the above safety classifications 3.5.1.3.1 Quality Group Classifications for Structures, Systems, and Components The assignment of safety-related classification and use of codes and standards conforms to the requirements NWMI's Quality Assurance Program Plan (QAPP) for the development of a Quality Group classification and the use of codes and standards.

The classification system provides a recognizable means of identifying the extent to which SSCs are related to safety-related and seismic requirements, including ANS nuclear safety classifications , NRC quality groups , ASME Code Section III classifications , seismic categories , and other applicable industry standards , as shown in Table 3-7. Quality assurance (QA) requirements are defined in the NWMI QAPP (Chapter 12.0 , "Conduct of Operations," Appendix C). The definitions of QA Levels 1 , 2 , and 3 are provided below. QA Level 1 will implement the full measure of the QAPP and will be applied to IROFS. I ROFS are QA Level 1 items in which failure or malfunction could directly result in a condition that adversely affects workers, the public , and/or environment , as described in 10 CFR 70.61. The failure of a s i ngle QA Level 1 item could result in a high or intermediate consequence.

The failure of a QA Level 2 item, in conjunction with the failure of an additional item , could result in a high or intermediate consequence. All building and structural IROFS associated with credible external events are QA Level 1. QA Level 1 items also include those attributes of items that could interact with IROFS due to a seismic event and result in high or intermediate consequences , as described in 10 CFR 70.61. Examples include:

• Items to prevent nuclear criticality accidents (e.g., preventive controls and measures to ensure that under normal and credible abnormal conditions , all nuclear processes are subcritical)

• Items credited to withstand credible design-bases external events (e.g., seismic, w i nd)

• Items to prevent degradation of structural integrity (e.g., failure or malfunction of facility)

QA Level 2 will be applied to non-QA Level 1 safety SSCs. The QA program is important to the acceptability and suitability of the item or service to perform as specified. Acceptance methods shall be specified (including acceptance and other applicable performance criteria), documented , a nd verified before use of the item or service. Some of the required characteristics may be examined less rigorously than for QA Level 1. Examples of QA Level 2 items include:

• SSCs to meet 10 CFR 20 normal release or exposure limits 3-46 NWM I ...... * ! . NOIUHW£ST MlDtcAl ISOTOf'ES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components

• *

• Fire protection systems Safeguards and security systems Material control and accountability systems QA Level 3 will include non-safety-related quality activities performed by NWMI that are deemed necessary to ensure the manufacture and delivery of highly reliable product s and services to meet or exceed customer expectations and requirements.

QA Level 3 items include those items that are not classified as QA Level I or QA Level 2. QA Level 3 item s are controlled in accordance with standard commercial practice s. These quality activities are embodied in NWMI's QAPP and will be further specified in the Operating License Application, and when necessary.

3.5.1.3.2 Seismic Classification for Structures, Systems, and Components SSCs identified as IROFS will be designed to satisfy the general seismic criteria to withstand the effects of natural phenomena (e.g., earthquakes, tomados , hurricanes , floods) without loss of capability to perform their safety functions.

ASCE 7, Chapter 11 , sets forth the criteria to which the plant design bases demonstrate the capability to function during and after vibratory ground-m otion associated with the shutdown earthquake conditions. The seismic classification methodology used for the RPF complies with the preceding criteria, and with the recommendations stated in Regulatory Guide 1.29 , Seismi c Design Classification.

The methodology classifies SSCs into three categories:

seismic Category I (C-1), seismic Category II (C-11), and seismic (NS). Seismic C-1 applies to both functionality and integrity, while C-11 applies only to integrity. SSCs located in the proximity ofIROFS, the failure of which during a safe-shutdown earthquake could result in loss of function of IROFS , are designated as C-11. Specifically:

• C-1 applies to IROFS. C-1 also applies to those SSCs required to support shutdown of the RPF and maintain the facility in a safe shutdown condition C-11 applies to SSCs designed to prevent collapse under the safe-shutdown earthquake.

SSCs are classified as C-11 to preclude structural failure during a safe-shutdown earthquake, or where interaction with C-1 items cou ld degrade the functioning of a safety-related SSC to an unacceptable level or could result in an incapacitating injury to occupants of the main control room.

• NS SSCs are those that are not classified seismic C-1 or C-11. 3.5.2 Radioisotope Production Facility Systems and components within the RPF are presented in Section 3.5.1. The RPF design basis evaluated the general design criteria from 10 CFR 70.64 , " Requirements for New Facilities or New Processes at Existing Facilities." This evaluation is presented in Table 3-22. These general design criteria provide a rational basis from which to initiate design but are not mandatory. There are some cases where conformance to a particular criterion is not directly measurable. For each of the criteria, a specific assessment of the RPF design is made , and a complete li st of references is included to identify where detailed design information pertinent to each criterion is treated. The Chapter 13.0 accident sequences for credible events define the DBE. The safety-related parameter limits ensure that the associated design basis is met for the events presented in Chapter 13.0. 3-47

.... ;. NWMI ..*... ..* .. ........ *. ' ". NOtmfWUT MEOtCAU$GTOH.S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems a n d Components Table 3-22. Design Criteria Requirements (4 pages) Design criteria and description Application and compl i ance IO CFR 70.64, "Requirements for New Facilities or New Processes at Existing Facilities"" Quality standards and records

• Develop and implement design in accordance with management measures to ensure that IROFS are a vailable and reliable to perform their function when needed.

• Maintain appropriate record s of these items by or under the control of the licensee throughout the life of the facility. N atural phenomena ha z ards P rov id e fo r ad e qu a t e p ro t ec ti o n aga in s t n a tur a l phenom e n a, w i t h co n s id era ti o n o f th e mo s t s e ve r e d oc um e nt e d hi s t o ri ca l e vent s for the s it e.

• SSCs important to safety will be designed , fabric a ted , erected , te s ted, operated , and maintained to quality standards commensurate with the importance of the safety functions to be performed. Where generall y recognized codes and standard s are used, they will be identified and ev a luated to determine their applicability , adequacy , and s ufficiency and will be supplemented or modified as necessary to en s ure a quality product in keeping with the required s afety function.

• NWM J's QAPP w ill be established a n d imp l emente d to provide ade qu ate ass u rance that SSCs satisfactori l y p e r fo r m thei r safety f un ctions.

• A pp ro pr iate records of desig n , fa bri cat i o n. erec t ion , a n d t esting of SSCs i m p orta n t to safety w ill be mainta in ed by o r under co n tro l of NWMI for t h e li fe of RPF.

• NWMI will us e a graduated QAPP that links quality cla s sification and associated documentation to s afety clas s ification and to the manufacturing and delivery of highly reliable products and equipment.

• The NWMI QAPP will provide detail s of the procedure s to be applied , including quality and safety level classification

s.

• SSC s imp o rt a nt t o sa f e ty w ill b e d es i g n e d , fa b rica t e d , e r ec t ed , tes t e d , op e rat e d , a nd m a int ai n ed t o qu a lity stan d ar d s co mm e n s ur a te w ith th e im po rtan ce of th e sa fety fun c ti o n s t o b e p e r fo rm e d. Wh e r e ge n era ll y r ecog ni ze d co d es and s t a nd a rd s are u se d , th ey w ill b e id e ntifi e d a nd ev a lu a t ed t o d e t e rmin e th e ir a pplic a bilit y, a d e qu acy, a nd s uffi c i e ncy a nd w ill b e s uppl e m e n te d or m o difi e d as n e c essary to e n s ure a quali ty produ c t in k ee pin g with th e r e qu i r e d safe ty funct io n.

• T h e d es i gn ba s i s fo r th ese SSCs w ill in c lud e: -A pp ro p riate co n s id e rati o n of th e mo s t seve r e n a tur a l ph e n o m e na t h at h ave b een hi s t o ri ca ll y r e p o rt e d fo r th e RPF s it e and s urr ou nding a r ea , i n cluding s uffi c i e n t m arg in for limit e d acc u racy , qu a nti ty, and p e ri o d of tim e fo r w hi c h hi s tori ca l d a t a h as b ee n acc umul a t e d -A pprop r i a t e co mbin a ti o n s of n a tur a l ph e n o m e na e ff e ct s dur ing norm a l a nd a ccid e n t opera tin g co ndi t i o n s -Imp o rt a n ce of the s a fe t y fun c tion s to b e p erforme d

• S p e cifi c RP F d es i g n c rit e ria a nd N R C ge n era l des i g n c rit e ria a r e di sc u sse d in S ec ti o ns 3.1 and 3.5, r es p ec ti ve l y. 3-48 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-22. Design Criteria Requirements (4 pages) Design criteria and description Application and compliance Fire protection Provide for adequate protection against fires and explosions E nvironmental and dynamic effects Pro vide fo r a d e quat e p rotec tion from e n viro nmental conditions and dynami c e ff ects assoc i a ted with norma l operations , maint e n a n ce , testing, and po s tul a t ed ac cident s th at co uld le ad to l oss of safe ty functi o n s Chemical protection Provide fo r adequate protection against chemical risks produced from licen sed material , facility conditions that affect the safety of licensed material, and hazardous chemicals produced from licen se d material Emerge nc y capability Pro vide fo r e mer ge n cy capa bility t o m a int a in co ntr ol of:

• Licensed material a nd ha za rdou s c h e micals produc ed from li censed m ate ri a l

• Evac u a tion of o n-site p e r so nn e l

• On-site e mer ge n cy faci liti es and serv i ces that facilitate t h e u se of ava il a bl e off-sit e services

• SSCs important to safety will be design ed and located throughout the RPF to minimize , consistent with other safety requirement s, the prob abi lity and effect of fires and explosions.

• Noncombustible and heat re sistant materials will be u se d wherever practical throughout the RPF , particularly in location s suc h as confinement and the control room.

• Fire det ectio n and s uppres sion systems of appropriate capacity an d capability will be provided and designed to minimize the adverse effects of fires on SSCs important to safety.

• Firefighting syste ms will be de signe d to ensure that their rupture or inadvertent operation doe s not significantly impair the safety capability of these SSCs.

• Where neces sary, within zoned areas or where criticality and access are an i ss u e , required systems will be manually initi ated by operations after review ofa detection sig nal.

• RPF frre protection system will be design ed s uch that a failure of any component will not impair the ability of safety-related SSCs to safely shut down and isolat e the RPF or limit the release of radioactivity to provide reasonable assurance that the public will b e protected from radiological risks resultin g from RPF operations

• RPF fire protection system will be de s igned to provide rea sonable assurance that the public will be protected from radiological risks re s ulting from RPF operation s (e.g., failure of any component will not impair the ability of safety-re lated SSCs to safe ly s hutdown and i so late the RPF or limit the relea se of radioactivity).

• Chapters 6.0 and 9.0 provide additional information.

• SSCs import a nt t o sa f e t y are d es ign ed t o accommodate effects of , and to b e co mp a tible wit h , th e e n v ironm e ntal co nditi o n s ass ociat e d with n o rmal operation , m a int enance , testing , a nd postulated acc id e nt s. Du e to l ow t empera ture a nd pr ess ur e RP F processes , d ynamic e ff ec t s du e t o pipe rupture a nd di sc har g in g fluids a r e n ot a ppli ca bl e t o the RP F.

• Chemical protection in the RPF will be provided by confinement isolation s ystems , liquid retention features , and use of ap propriate per s onal protective equipment.

• Chapter 6.0, Section 6.2.1 , provides additional information.

• E m e r ge n cy p roce dur es will b e d eve l o p e d a nd maintained fo r the RPF t o co ntr o l SNM a nd h azar d o us c h e mi ca l s produced from the SNM.

• A pr e limin ary E m e r ge n cy Pr epare dn ess P l a n i s provided in C h ap t er 1 2.0 , A pp e ndi x B. 3-49

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• NOllTKWHT MlOICAL lSOTOPES NWMl-2 0 13-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Table 3-22. Design Criteria Requirements (4 pages) Design criteria and description Application and compliance Utility services Provide for continued operation of e s s ential utility service s In s p e ction , testing , and maintenance P rovi d e fo r a dequ a t e i n s p ec ti o n , t es t ing , a n d m a int e n a n ce of IR OFS to e n s ur e ava il a bility a nd r e li a b i li ty t o p e rf o rm t h e ir fun c tion wh en n ee d e d Criticality control Provide for criticality control , including adherence to the double-contingency principle Instrum e ntation and control Th e d es i gn mu s t p rov id e fo r inclu s i o n of I&C sys t e m s to monit o r an d co ntrol th e b e h av i o r o f item s r e li e d o n for sa fet y.

• The RPF is designed for passive, s afe shutdown and to prev e nt uncontrolled release of radioactive material if normal electric power is interrupted or lost.

• A standby diesel generator will be provided for asset protection of selected RPF systems.

• Uninterruptable power supplies will automatically provide power to systems that support the safety functions protecting workers and the public.

• A combination ofuninterruptable power supplies and a standby electrical power system will provide emergency electrical power to the RPF. A 1 , 000 kW (1 , 341 hp) diesel generator will provide facility electric power.

• Chapter 8.0 , Section 8.2 provides additional information.

• Th e RPF i s d es i g n e d t o provid e access a nd co nt ro l s for t es tin g , m a int e nan ce , a n d in s p ec ti o n of sa f ety-r e l a t e d SSCs, as n ee d e d , throu g h o ut th e RP F.

• C h a pt e r s 4.0 , 6.0 , 7.0 , an d 9.0 p rov ide a dditi o n al in fo rm a tion.

• The RPF design will provide adequate protection against critical i ty hazards related to the storage , handling , and processing of SNM , which will be accomplished by: -Including equipment , facilities , and procedures t o protect worker and public health and to minimize danger to life or property -Ensuring that the design provides for criticality control , including adherenc e to the double-contingency principle

-Incorporating a criticality monitoring and alarm system into the facility design

• Compliance with the requirements of criticality control , including adherence to the double-contingency principle , are described in detail in Chapter 6.0 , Section 6.3.

• RPF SNM p rocesses w ill be e ncl ose d pr e d o mina te l y b y h o t ce lls a nd g lo ve b ox d es i g n s exce pt for th e tar ge t fa bri ca tion ar ea.

• Th e FP C s y s t e m will pro v ide m o nitorin g and co ntrol of safe t y-r e l a t e d c ompon e nt s a nd pro cess sys t e m s within th e RP F.

• Th e BMS (a s ub set o f th e FP C sys t e m) w i ll m o nit o r th e RP F vent il a tion sys t e m and m ec hani ca l utility sys t e m s.

• ESF sys t e m s wi ll o p era t e ind e p e nd e ntl y fro m th e F P C sys t e m o r BMS. E a c h ESF sa f e t y fun ct i o n will u se hard-w ir e d an a l og co n t rol s/int e rlock s t o prot e ct w ork er s, th e publi c , and e nvironm e nt. Th e ES F param e t e rs a nd alarm fun c tion s will b e int eg rated int o and monitor ed b y th e FP C sys t em o r BMS.

• RPF d es i gns are ba se d on d efe n se-in-d e pth pr ac ti ces and in corpora te a pr e f e r e n ce fo r e n g in e er e d co ntrol s o ve r a dmini s t ra tiv e co ntr o l s, ind e p e nd e n ce to av o id co mm on m o d e fa ilur es , and in co rp o rate o th er fea tur es th a t e nh ance safe t y b y r e ducing c h a ll e n ges t o safe ty-r e l a t e d co mp o n e nt s and sys t e m s.

• Th e FP C sys t e m w ill pro v id e th e c a p a bility t o m o nitor and c ont ro l the b e h av i o r of sa fety-r e l a t e d SSCs. Th e s e sys t e ms e n s ure a d e qu a te s a fe ty of p ro c ess and utili ty se rvice op era tion s in c o nne c tion with their sa f e ty function. Co ntrol s are pro v id e d to m a int a in th ese v ari a bl es and sys t e m s wi thin th e pr esc rib e d o p e rating ran ges und e r a ll norm a l c onditi o n s.

• Th e FP C sys t e m i s d es i g n ed t o fa il to a sa f e-s t a te o r t o ass ume a s t a te d e mon s tr a t e d to b e acce ptabl e if c onditions s u ch a s l oss o f s i g n a l , lo ss o f e n e r gy or m o ti ve p owe r , or adv e r se e nvir o nm e nts a r e ex peri e nc e d.

• C h a pt e r 7.0 p rov id es addition a l I&C s y s t e m inform a tion. Sa fe t y-r e lated SS Cs a r e d es cribed in Sec tion 3.5 a nd C hapt e r s 4.0 , 5.0 , 6.0 , 7.0 , and 8.0. 3-50

..... :. NWMI ...... ..* *.. ........ *. NORTHWEST MEDICAL ISOTOPES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-22. Design Criteria Requirements (4 pages) Design criteria and description Application and compliance Defense-in-depthh Base facility and system design and facility layout on defense-in-depth practices. The design must incorporate, to the extent practicable

• Defense-in-depth is a design philosophy that NWMI has applied from the beginning of the project and will continue through completion ofa design that is based on providing successive levels of protection such that health and safety are not wholly dependent on any single element of the design , construction, maintenance, or operation of the RPF.

• Preference for the selection of engineered controls over administrative controls to increase overall system reliability

• NWMI's risk insights obtained through performance of the accident analysis will be used to supplement the final design by focusing attention on the prevention and mitigation of the higher risk potential accidents.

• Chapter 6.0 and 13.0 provide additional information.

• Features that enhance safety by reducing challenges to IROFS

• 10 CFR 70.64, " Requirements for New Facilities or New Processes at Ex i st in g Facilities," Code of F e deral Regulations , Office of the Federal Register, as amended. b As used in 10 CFR 70.64 , requirements for new facilities or new processes at existing fac ilities , defense-in-depth practices means a design philosophy, applied from the outset and through completion of th e design , that is based on providing s ucc essive level s of protection s uch that health and safety will not be wholly dependent on any s ingle element of the design , construction , maint enance, or operation of the facility.

The net effec t of incorporating defense-in-depth pra ctices is a conservatively designed facility and system that will exhibit greater tolerance to failures and externa l challenges. BMS CFR ESF FPC l&C IROFS buildin g management system. Code of Federal Regulations.

engineered safety feature. facility process control. instrumentation and control. items relied on for safety. NRC NWMI QAPP RPF SNM SSC U.S. Nuclear Regulatory Commiss ion. Nort hwe st Medical Isotop es , LLC. quality assurance program plan. Radioisotope Production Facility.

specia l nuclear material.

structures , systems, and components.

The criteria are generic in nature and subject to a variety of interpretations; however, they also establish a proven basis from which to provide for and assess the safety of the RPF and develop principal design criteria.

The general design criteria establish the necessary design, fabrication, construction , testing, and performance requirements for SSCs important to safety (i.e., SSCs that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of workers , the public, and environment).

Safety-related SSCs that are determined to have safety significance for the RPF will be designed, fabricated , erected , and tested as required by the NWMI QAPP, described in Chapter 12.0 , Appendix C. In addition, appropriate records of the design , fabrication, erection, procurement, te s ting , and operations ofSSCs will be maintained throughout the life of the plant. The RPF design addresses the following:

• * * * * * *

• Radiologic a l and chemical protection Natural phenomena hazards Fire protection Environmental and dynamic effects Emergency capability (e.g., licensed material, hazardous chemicals, evacuation of on-site personnel, on-site emergency facilities

/off-site emergency facilities)

Utility services Inspection , testing, and maintenance Criticality safety 3-51

• .**.-.* .. ..... ; .. NWMI ........ *. * *. * ! . NORTKWEST MEDtcAL ISOTOPU *

• Instrumentation and controls Defense-in-depth NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Safety-related systems and components will be qualified using the applicable guidance in the Institute of Electrical and Electronics Engineers (IEEE) Standard IEEE 323, IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations.

The qualification of each safety-related system or component needs to demonstrate the ability perform the associated safety function: *

• Under environmental and dynamic service conditions in which they are required to function For the length of time the function is required Additionally, non-safety-related components and systems will be qualified to withstand env i ronmental stress caused by environmental and dynamic service conditions under which their failure c o uld prevent satisfactory accomplishment of the safety-related functions. The RPF instrumentation and control (l&C) system (also known as the facility process co n trol [FPC] system) will provide monitoring and contro l of the process systems within the RPF that are significant to safety over anticipated ranges for normal operations and abnormal operations. The FPC system will perform as the overall production process controller.

This system will monitor and contro l the process instrumented functions within the RPF , including monitoring of process fluid transfers an d controlled inter-equipment pump transfers of process fluids. The FPC system will also ensure that process and utility systems operate in accordance wi t h their safety function. Controls will be provided to maintain variab l es and systems within the prescribed operating ranges under all normal conditions.

In addition, the FPC system is designed to fail into a safe state or to assume a state demonstrated to be acceptable if conditions such as loss of signal, lo ss of e n ergy or motive power, or adverse environments are experienced. The building management system (BMS) (a subset of the FPC system) will monitor the RPF ventilation system and mechanical utility systems. The BMS primary functions will be to monitor the facility ventilation system and monitor and control (turn on and off) the mechanical utility systems. ESF systems will operate independently from the FPC system or BMS. Each ESF safety function will use hard-wired analog controls/interlocks to protect workers, the public, and environment.

The ESF parameters and alarm functions will be integrated into and monitored by the FPC system or BMS. The fire protection system will have its own central alarm panel. The fire protection system will report the status of the fire protection equipment to the centra l alarm station and the RPF control room. This integrated control system will be isolated from safety-r elated components consistent with IEEE 279, Criteria for Protection Systems for Nuclear Power Generating Stations.

In addition, the RPF is designed to meet IEEE 603 , Standard Criteria for Saf ety Systems for Nuclear Power Generating Stations, for separation and isolation of safety-related systems and components. Chapter 7.0 provides additiona l details on the integrated control system. 3-52 NWMI ...*.. .. ... .... .... .. * *

• NORTHWEST MEOfCAl lSOTOPf.S 3.5.2.1 System Classification The RPF is classified as a non-reactor nuclear production facility per 10 CFR 50. In addition, a portion of the RPF will fabricate LEU targets , similar to fuel fabrication per 10 CFR 70. Due to the nature of the work performed within facility, a hazardous occupancy applies. Table 3-23 provides the RPF classification for hazards occupancy , construction, risk, and seismic design categories.

3.5.2.2 C l assification of Systems and Components Important to Safety RPF SSCs , including their foundations and NWMl-2013-0 21, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Table 3-23. System Classifications Classification description Hazard category Occupancy type Construction type Risk category Seismic design category Classification Intermediate hazard Mixed, A-2 , B, F-1 , H-3 and H-4 11-B IV c Source NRC IBC 2012* IBC 2012* ASCE 7b ASCE 7 b * !BC 2012 , " International Buildin g Code ," as amended , International Code Council , Inc., Washington , D.C., February 2012. b ASCE 7 , Minimum D e sign Load s for Buildin gs and Other Stru c tur e s , American Society of Civil En g ineer s, Re s ton , Virginia , 201 3. NR C = U.S. Nuclear Regulatory Commi ss ion. supports , designed to remain functional in the event of a DBE are designated as C-I. SSCs designated IROFS are also classified as C-I. SSCs co-located with C-I systems are reviewed and supported in accordance with II over I criteria.

This avoids any unacceptable interactions between SSCs. C-1 structures should be designed using dynamic analysis procedures, or when justified , equivalent static procedures using both horizontal and vertical input ground motions. For dynamic analyses, either response spectra or time history analyses approaches may be used. Dynamic analysis should be performed in accordance with the procedures of ASCE 4 , with the exception of the damping limitations presented in Section 3.4.1. Table 3-24 lists the RPF SSCs and associated safety and seismic classifications and quality level group for the top-level systems. Subsystems within these systems may be identified with lower safety classifications. For example , the day tanks of the chemical supply system are IROFS , while the rest of the chemical supply system is classified as safety-related or not-safety-related.

Table 3-24. System Safety and Seismic Classification and Associated Quality Level Group (2 pages) System name (code) Facility structure (RPF) Target fabrication (TF) Target receipt and disassembly (TD) Target dissolution (DS) Mo recovery and purification (MR) Uranium recovery and recycle (UR) Waste handling (WH) Criticality accident alarm (CA) Radiation monitoring (RM) Standby electrical power (SEP) Normal electrical power (NEP) Highest safety classification*

IROFS IROFS IROFS IROFS IROFS IROFS IROFS IROFS IROFS IROFS SR 3-53 Seismic classificationb C-1 C-1 C-1 C-I C-1 C-1 C-1 C-1 C-1 C-I C-1 Quality level group QL-1 QL-1 QL-1 QL-1 QL-1 QL-1 QL-1 QL-1 QL-1 QL-1 QL-1

...... ;. NWMI ...... ..* .. . ........ * .

• NORTHWEST M£01CAL ISOTOnS NWMl-2013-021, Rev. 3 Chapte r 3.0 -Design of Structures, Systems and Components Table 3-24. System Safety and Seismic Classification and Associated Quality Level Group (2 pages) System name (code) Process vessel ventilation (PVV) Facility ventilation (FV)c Fire protection (FP) Plant and instrument air (PA) Emergency purge gas (PG) Gas supply (GS) Process chilled water (PCW) Facility chilled water (FCW) Facility heated water (HW) Process steam Demineralized water (DW) Chemical supply (CS) Biological shield (BS) Facility process control (FPC) Highest safety classificationa IROFS IROFS SR NSR IROFS NSR IROFS NSR NSR IROFS NSR IROFS IROFS SR Seismic classificationb C-1 C-1/II C-II C-II C-1 C-II C-1 C-II C-II C-I C-II C-I C-I C-II Quality level group QL-1 QL-1/2 QL-2 QL-2 QL-1 QL-2 QL-1 QL-2 QL-2 QL-1 QL-2 QL-1 QL-1 QL-2

• Safety classification accounts for highest classification in the system. Systems that are classified as safety-related may include both safety-related and non-safety-related components. Only safety-related components will be used to satisfy the safety functions of the system , whereas non-safety-related components can be used to perform non-safety functions.

For example, there are non-safety-related components , such as fans , within the safety-related ventilation systems that perform safety-related functions. b Seismic category may be locally revised to account for II over I design criteria and to eliminate potential system degradation due to seismic interactions.

c Ventilation zone classifications vary-Ventilation Zone I and II are considered safety-related, C-I and QL-1; Ventilation Zone III and IV are considered non-safety-related , C-II and QL-2. IROFS = items relied on for safety. RPF = Radioisotope Production Facility.

= safety-related (not IROFS). NSR = non-safety re l ated. SR SSCs that must maintain structural integrity post-DBE, but are not required to remain functional are C-11. All other SSCs that have no specific NRC-regulated requirements are designed to l ocal jurisdictional requirements for structural integrity and are C-III. All C-I SSCs are analyzed under the loading conditions of the DBE and consider margins of safety appropriate for that earthquake.

The margin of safety provided for safety-class SSCs for the DBE are sufficient to ensure that their design functions are not put at risk. Table 3-25 presents the likelihood index limit guide l ines and associated event frequency and risk index limits. Table 3-25. Likelihood Index Limit G u idelines Likely normal facility process condition Not unlike l y (frequent facility process condition)

Unlikely (infrequent facility process condition)

Highly unlikely (limiting facility process condition)

D!!.11 Event frequency limits 4 Multiple events per year > or= 0 3 More than 10-4 per event, per year >-4 <O 2 Between I 0-4 and 10-5 per event, -4 to 5 per year Less than 10-5 per event, per year < -5 3-5 4

..... ;. NWMI ...... ..* ... .*.* .. *.* . . NORTifWESlMEDICAl.ISOTOPES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.5.2.3 Design Basis Functions, Values, and Criteria The design basi s for syste ms a nd components required for safe operation and s hutdown of the RPF are established in three categories, which are described below. The preliminary design basis functions and values for each m ajo r system are provided in th e following s ub sec tion s. Design Basis Functions

• License conditions, order s, or technical spec ification s Functions credited in the safety analysis to e nsure safe shutdown of the facility is achieved and maintained , prevent potential accidents, or mitigate the potential consequences of accidents that could result in consequences greater than applicable NRC exposure guidelines Design Basis Values *

• Va lu es or ranges of values of controlling parameters established as reference bound s for RPF design to meet design basis function requirements Va lue s may be established by an NRC requirement, derived from or confirmed by the safety analysis, or selected by the designer from an applicable code, standard, or guidance document Design Basis Criteria

• Code-driven requirements established for the RPF fall into seven categories, including fabrication , construction , operations, testing, inspection , performance , and qual ity * *

• Codes include national consensus codes, national standards, and national guidance documents Design of safety-related systems (including protection systems) is consistent with IEEE 379 , Standard Application of th e Single-F ailure Criterion to Nuclear Power Generating Station Safety Systems, and Regulatory Guide 1.53 , Application of th e Single-Failure Criterion to Nu clear Pow er Plant Prot ec tion Systems Protection sys tem is designed to provide two or three channels for each protective sys tems and functions and two logic train circuits: Redundant channels and trains w i ll be electrically i so lat e d and physically separated in areas outside of the RPF control room Redundant design will not prevent protective action at the system l eve l 3.5.2.4 System Functions/Safety Functions The NWMI RPF will provide protection against natural phenomena hazards for the personnel , SNM, and systems within the facility.

The facility will a lso provide protection against operational and accident hazards to personnel and the public. Table 3-2 lists the IROFS defined by the preliminary hazards analysis.

3.5.2.5 Systems and Components 3.5.2.5.1 Mechanical RPF C-1 mechanical equipment and components (ident ifi ed in Table 3-24) will be qualified for operation under the design basis earthquake (DBEQ) seismic conditions by prototype testing , operating experience, or appropriate analysis. The C-1 mechanical equipment is also designed to withstand loadin gs due to the DBEQ, vibrational loadings transmitted through piping , and operational vibratory lo ading, such as floor vibration due to other operating equipment, without loss offunction or fluid boundary. This analysis considers the natural frequency of the operating equipment , the floor response spectra at the equipment location , and lo adings transmitted to the equipment and the equipment anchorage.

3-55

..... ;. NWMI ...... .. .. .......... "NORTHW£STMEDICALISOTOPES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems a n d Components The qualification documents and all supporting analysis and test reports will be maintained as part of the permanent plant record in accordance with the requirements of the NWMI QAPP. The safety-related equipment and components within the RPF will be required to function during normal operations and during and following DBEs. This equipment will be capable of functioning in the RPF environmenta l conditions associated with normal operations and design basis accidents.

Certain systems and components used in the ESF systems will be located in a controlled environment.

This controlled environment is considered an integral part of the ESF systems. 3.5.2.5.2 Instrumentation and Electrical C-1 instrumentation and electrical equipment (identified in Table 3-24) is designed to resist and withstand the effects of the postulated DBEQ without functional impairment.

The equipment will remain operable during and after a DBEQ. The magnitude and frequency of the DBEQ l oadings that each component experiences will be determined by its location within the RPF. In-structure response curves at various building elevations will be developed to support design. The equipment (e.g., b a tteries and instrument racks, contro l consoles) has test data, operating experience, and/or calculations to substantiate the ability of the components and systems to not suffer lo ss offunction during or after seismic loadin gs due to the DBEQ. This information will be comp l eted during fina l design of the RPF and provided in the Operating License Application. This certification of compliance with the specified seismic requirements , including compliance with the requirements of IEEE 344, is maintained as part of the permanent plant record i n accordance with the NWMIQAPP. 3.5.2.6 Qualification Methods Environmental qualification of safety-re l ated mechanical , instrumentation , and electrical systems and components is demonstrated by te s ts , analysis , or reliance on operating experience.

Qualification method testing will be accomplished either by tests on the particular equipment or by type tests performed on similar equipment under environmental conditions at least as severe as the specified conditions.

The equipment will be qualified for norma l and accident environments.

Qualification data will be maintained as part of the permanent plant record in accordance with the NWMI QAPP. 3.5.2.7 Radioisotope Production Facility Specific System Design Basis F u nctions and Values The design basis functions and values for each system identified in Table 3-1 a r e discussed in the following subsections.

Additional details for each system described below will be update d during the development of the Operating License App li cation. 3.5.2.7.1 Target Fabrication System An overview and detailed description of the target fabrication system are provided in Chapter 4.0, Sections 4.1.3.1 and 4.4, respectively. Design Basis Functions

• * * *

• Store fresh LEU, LEU target material , and new LEU targets Produce LEU target material from fresh and recycled LEU material Assemble , load , and fabricate LEU targets Reduce or eliminate the buildup of static e l ectricity Minimize uranium losses through target fabrication Safety-related functions: 3-56 NWM I ...... * * ' NOKTifWUT MEDfCAl ISOTOP£S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Maintain subcriticality conditions within target fabrication system Prevent flammable gas composition within target fabrication system Limit personnel exposure to hazardous chemicals and offgases Design Basis Values *

• 30-year design life with the exception of common replaceable part s (e.g., pumps) Maintain primary fission product boundary during and after normal operations , shutdown conditions , and DBEs 3.5.2.7.2 Target Receipt and Disassembly System An overview and detailed description of the target receipt and disassembly syste m are provided in Chapter 4.0 , Section 4.1.3.2, and Sections 4.3.2/4.3.3, respecti ve ly. Design Basis Functions

• * * *

• Handle irradiated target s hipping cask, including all opening, closing , and lifting operations Retrieve irradiated targets from a shipping cask Disassemble targets and retrieving irradiated target material from targets Reduce or eliminate the buildup of static electricity Safety-related functions:

Provide radiological shielding during receipt and disassembly activities Maintain subcriticality conditions within target receipt and di sasse mbly sys tem Prevent radiological materials from being released during target receipt and disassembly operations to limit the exposure of workers, the public, and environment to radioactive materi al Maintain positive control of radiological materi a l s (LEU target material and radiological waste) Protect personnel and equipment from indu s trial hazards associated with system equipment (e.g., moving part s) Design Basis Values

• 30-year de sign life *

• Maintain primary fission product boundary during and after normal operations , s hutdown conditions, and DBEs Crane de signe d for anticipated load (e.g., hot cell cover block) of approximately 68 metric ton s (MT) (75 ton) 3.5.2.7.3 Replace Target Dissolution (DS) An overview and detailed description of the target dissolution system are provided in Chapter 4.0, Sections 4.1.3.3 and 4.3.4, respectively.

Design Basis Functions

• * *

• Fill the dis so l ve r basket with the LEU target material Dissolve the LEU target material within di ss olver ba sket Treat the offgas from the target dissolution sys tem Handle and package solid waste created by normal operational activities 3-57

• Safety-related functions:

NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Provide radiological shielding during target dissolution activities Control and prevent flammable gas from reaching lower flammability limit conditions Maintain subcriticality conditions through inherently safe design of target dis so lution equipment Maintain positive control of radiological materials (LEU target material and radiological waste) Design Basis Values

• 30-yeardesign life with the exception of common replaceable part s (e.g., pump s) *

• Maintain primary fission product boundary during and after normal operations, shutdown conditions , and DBEs Prevent radiological mat eria l s from being relea se d during t a rget dissolution operations to limit the exposure of workers , the public, and environment to radioactive material per 10 C F R 20 3.5.2.7.4 Molybdenum Recovery and Purification (MR) An overview and detailed description of the Mo recovery and purification syste m are prov i ded in Chapter 4.0, Sections 4.1.3.4 and 4.3.5 , respectively. Design Basis Functions

• Recovery of Mo product from a nitric acid solution created from dissolved irradi ate d uranium targets

• Purification of the recovered Mo product to reach specified purity requirements , followed by shipment of the Mo product Safety-related function s: Maintain subcriticality conditions through inherently safe design o f components that could handle high-uranium content fluid Prevent radiological materials from being r e lea sed by containing fluids in appropriate tubin g, valves , an d other components Control and prevent flammable gas from reaching lower flamm a bility limit conditions Maintain positive control of radiological materials (99 Mo product , intermediate streams, and radiological waste) Provide appropriate containers and handling syste ms to protect personnel from industrial hazards s uch as chemical exposure (e.g., nitric acid, caustic , etc.) Design Basis Values * *

• Maint a in primary fission product boundary during and after normal operations , shutdown conditions, an d DBEs 30-year design life with the exception of common replaceable part s (e.g., pump s) Replace consumables after each batch 3.5.2.7.5 Uranium Recovery and Recycle (UR) An overview and detailed description of the uranium recovery and recycle sys tem are provided in Chapter 4.0 , Sections 4.1.3.5 and 4.3.6, respecti ve ly. 3-58

. .-.;;**NWMI ..... ........ *. *!'. NORTHWEST MEDICAL ISOTOHS NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of St r uctures, Systems and Co m ponents Design Basis Functions

• Receive and decay impure LEU solution

• Recover and purify impure LEU solution

• Decay and recycle LEU solution

• Transfer process waste

• Safety-related functions:

Provide radiological shielding during uranium recovery and recycle system activities Prevent radiological release during uranium recovery and recycle system activities Maintain subcriticality conditions through inherently safe design of the uranium recovery and recycle equipment Control and preventing flammable gas from reaching lower flammability limit conditions Maintain positive control of radiological material s Protect personnel and equipment from industrial hazards associated with the sys tem equipment , such as moving parts , high temperatures , and electric shock Design Basis Values *

• 30-year design life with the exception of common replaceable part s (e.g., pumps) Maintain primary fission product boundary during and after normal operations, shutdown conditions, and DBEs 3.5.2.7.6 Waste Handling An overview and detailed description of the waste handling sys tem are provided in Chapter 4.0 , Section 4.1.3.6 and Chapter 9.0 , Section 9.7.2 , respectively. Design Basis Functions

• * * *

• *

• Receive liquid waste that is divided into high-dose source terms and low-dose source terms to lag storage Transfer remotely loaded drums with high-activity solid waste via a so lid waste drum transit system to a waste encapsulation cell Encapsulate solid waste drums Load drum s with solidification agent and low-dose liquid waste Load high-integrity containers with solidification agent and high-do se liquid waste Handle and load a waste shipping cask with radiological waste drums/containers Safety-related functions: Maintain subcriticality conditions through mass limits Prevent spread of contamination to manned areas of the facility that could result in personnel exposure to radioactive materials or toxic chemicals Provide shielding, distance, or other means to minimize personnel exposure to penetrating radiation Design Basis Values *

• Maintain primary fission product boundary during and after normal operations, shutdown conditions , and DBEs 30-year design life with the exception of common replaceable parts (e.g., pumps) 3-59 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 3.5.2.7.7 Criticality Accident Alarm System Chapter 6.0, Section 6.3.3.1, and Chapter 7.0, Section 7.3.7, provide descriptions of the criticality accident alarm system. Design Basis Functions

• Provide analysis for criticality accident alarm system coverage in all areas where SNM is handled, processed, or stored * *

• Provide for continuous monitoring , indication, and recording of neutron or gamma radiation levels in areas where personnel may be present and wherever an accidental criticality event could result from operational processes.

Provide both local and remote annunciation of a criticality excursion Remain operational during DBEs Design Basis Values

• 30-year design life

• Capable of detecting a criticality accident that produces an absorbed dose in soft tissue of 20 absorbed radiation dose (rad) of combined neutron or gamma radiat i on at an unshielded distance of 2 m from reacting material within one minute 3.5.2.7.8 Continuous Air Monitoring System Chapter 7.0, Section 7.6, and Chapter 11.0 , Section 11.1.4 , provide detailed descriptions o f the RPF continuous air monitoring system. Design Basis Functions

• * * *

• Provide real-time local and remote annunciation of airborne contamination in excess of preset limits Provide real-time local and remote annunciation of radiological dose o f excess of preset limits Provide environmental monitoring of nuclear radioactive stack releases Provide the capability to collect continuous samples Remain operational during DBEs Design Basis Values * *

• Activate when airborne radioactivity levels exceed predetermined limits Activate when radiological dose levels exceed predetermined limits Adjust volume of air sampled to ensure adequate sensitivity with minimum sampling time 3.5.2.7.9 Standby Electrical Power Chapter 8.0, Section 8.2 provides a detailed description of the RPF standby electrical power (SEP) system. Design Basis Functions SEP includes two types of components:

uninterruptible power supplies (UPS) and a standby diesel generator:

• UPS -Provides power when normal power supplies are absent Standby diesel generator

-Provides power when normal power supplies are absent to allow continued RPF processing 3-60 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Design Basis Values * *

• 30-year design life Maintain power availability for a minimum of 120 min post-accident (UPS) Maintain power availability for 12 hr (diesel generator) 3.5.2.7.10 Normal Electrical Power Chapter 8.0, Section 8.1 provides a detailed description of the RPF normal electrical power (NEP) system. Design Basis Functions

• Provide facility power during normal operations Design Basis Values

• 30-year design life 3.5.2.7.11 Process Vessel Ventilation System Chapter 9.0, Section 9.1 provides a detailed description of the process vessel ventilation system. Design Basis Functions

• Provide primary system functions to protect on-site and off-site personnel from radiological and other industrial related hazards *

• Collect air in-leakage sweep from each of the numerous vessels and other components in main RPF processes and maintain hydrogen concentration process tanks and piping below lower flammability limit Minimize reliance on administrative or complex active engineering controls to provide a confinement system as simple and fail-safe as reasonably possible Design Basis Values * *

• Maintain primary fission product boundary during and after normal operations , shutdown conditions , and DBEs 30-year design life Contain and store noble gases generated in the RPF to meet 10 CFR 20 requirements 3.5.2.7.12 Facility Ventilation System Chapter 9.0, Section 9.1 provides a detailed description of the facility ventilation system. Design Basis Functions

• Provide confinement of hazardous chemical fumes and airborne radiological materials and conditioning of RPF environment for facility personnel and equipment

• * *

• Prevent release and dispersal of airborne radioactive materials (e.g., maintain pressure gradients to ensure proper flow of air from least potentially contaminated areas to most potentially contaminated areas) to protect health and minimize danger to life or property Maintain dose uptake through ingestion to levels as low as reasonably achievable (ALARA) Provide makeup air and condition the RPF environment for process and electrical equipment Process exhaust flow from the process vessel ventilation system 3-61

• NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Provide confinement of airborne radioactive materials by providing for t he rapid , automatic closure of isolation dampers within confinement zones for various accident conditions Provide conditioned air to ensure suitable environmental conditions for personnel and equipment inRPF Design Basis Values * * * *

• Maintain primary fission product boundary during and after normal operations , shu t down conditions , and DBEs Provide an integrated leak rate for confinement boundaries that meets the requirements of accident analyses that complies with 10 CFR 10.61 30-year design life Maintain occupied space at 24 degrees Celsius (0 C) (75 degrees Fahrenheit

[°F]) (summer) and 22°C (72°F) (winter), with active ventilation to support workers and equipment Maintain air qua li ty that complies with 10 CFR 20 dose limits for normal operations and shutdown 3.5.2.7.13 Fire Protection System Chapter 9.0, Section 9.3 provides a detailed de s cription of the RPF fire protection system. Design Basis Functions

• * * *

• Provide detection and suppression of fires Generate alarm signals indicating presence and location of fire Execute commands appropriate for the particular location of the fire (e.g., provide varying levels of notification of a fire event and transmitting notification to RPF central alarm station and RPF contro l room) Provide fire detection in RPF and initiate fire-rated damper closures Remain functional during DBEs Design Basis Values * *

• 30-year design life Provide a constant flow of water to an area experiencing a fire for a minimum of 120 min based on the size of the area per International Fire Code (IFC , 2012) Provide sprinkler systems , when necessary , per National Fire Protection Association (NFPA) 13 , Standard for th e Installation of Sprinkl e r System s 3.5.2.7.14 Plant and Instrument Air System Chapter 9.0, Section 9.7.1 provides a detailed description of the RPF pla n t and instrument air system. Design Basis Functions

• Provide small , advective flows of plant air for several RPF activities (e.g., tool operation, pump power , purge gas in tanks , valve actuation , and bubbler tank level measurement)

Provide plant air receiver buffer capacity to make up difference between peak demand and compressor capacity 3-62

• NWMl-2013-021 , Rev. 3 Chapter 3.0 -Des ig n of Structures , Systems and Components Provide plant air to in strument air subsystem for bubbl ers a nd valve actuat i on Provide instrument air receiver buff er capac it y to make up diff erence between peak demand and co mpr essor capac i ty Design Basis Values *

• 30-yeard esign life with the exception of co mmon replaceable parts (e.g., pumps) Provide in s trument air dried in regenerable desiccant beds to a dew point of no greater than -40°C (-40°F) and filtered to a maximum 40 micro n (µ) particle size 3.5.2.7.15 Emergency Purge Gas System C h apter 6.0 , Section 6.2.1.7.5 provides a detailed description of the emergency purge gas syste m. Design Basis Functions

• Pro vide> 12 hr of nitrogen to the emergency purge gas system E mer gency purge gas system to provide nitrogen to the required process tanks Remain functional during DBEs Design Basis Values

• 30-year de s ign li fe with the exception of co mmon replaceable parts Maintain hydrogen gas (H 2) co nc e ntrati ons l ess than 25% of the low er flammability limit 3.5.2.7.16 Gas Supply System Chapter 9.0, Section 9.7.1 provides a detailed description of the gas s uppl y s ystem. Design Basis Functions Provide helium , hydro gen , a nd oxygen in stan d ard gas bottl es

• Provide nitrogen from a tube truck to the chem ic a l supp l y room where manifold piping will be used to distribute the gas

• Pro vi de adequate flow to e n sure that the acc umul ation of combustible gases i s below hazardous concentrations and reduces radiological hazards du e to accumulation of gaseo u s fission produ ct s Design Basis Values

• 30-year de s ign life w ith the exception of common replaceable part s (e.g., pump s)

• Provide standard gas bottle s, with capacity of approximately 8 , 495 L (300 cub i c feet [ft 3]) 3.5.2.7.17 Process Chilled Water System Chapter 9.0 , Section 9.7.1 provides a detailed description of the RPF c hill ed water system. Design Basis Functions

• Provide process chilled water loop for three secondary loop s h eat excha n gers One l arge geo metry seco ndary loop in hot ce ll One criticality-safe geometry secondary loop in hot cell One criticality-safe geometry secondary loop in target fabrication area Provide monitoring of chilled water loop s fo r lo ss of primary containment 3-63

• NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components Provide cover gas to prevent flammable conditions in secondary loops Design Basis Values

• 30-yeardesign life with the exception of common replaceable parts (e.g., pumps) *

• Chi ll ed water to various process equipment at no greater than 10°C (50°F) during normal operations Maintain the hydrogen concentrat ion in the coo l ant system at l ess than 25 percent of the lower flammability limit of 5 percent H 2 3.5.2.7.18 Facility Chilled Water System Chapter 9.0, Section 9.7.1.2.2 provides a detailed description of the RPF facility chilled water system. Design Basis Functions

• Provide cooling media to heating , ventilation , and air conditioning (HV AC) system Supp ly HV AC system with coo lin g water that is circulated through the chilled water coils in airhandling units De sign Ba sis Values *

• Provide cooling water at a temperature of 9°C ( 48°F) to the HV AC air-h andling unit cooling coils 30-yeardesign li fe with the exception of common replaceable parts (e.g., pumps) 3.5.2.7.19 Facility Heated Water System Chapter 9.0 , Section 9.7.1.2.2 provides a detailed description ofthe RPF heated water system. De sign Ba s is Functions

• Provide heated media to HV AC system Sup pl y the HV AC system with heated water that is circulated through the heated water coils in the air-handling units De sign Basis Values

• Provide heated water at a temperature of 82°C (180°F) to HV AC air-hand lin g unit heating coils and reheat coi l

• 30-year design life with the exception of commo n replaceable parts (e.g., pumps) 3.5.2.7.20 Process Steam System -Boiler C h apter 9.0 , Section 9.7.1 provides a detailed description of the RPF process steam system for the boil er. De sign Basis Functions

• Generate low-an d medium-pressure steam using a natural gas-fir ed package boile r *

• Provide a closed loop steam system for the hot ce ll secondary loop s that meets criticality control req uir ements Provide monitoring of steam condensate for l oss of primary containment Limit sludge or dissolved solids content with automatic and makeup water stream s in the boiler 3-64 NWM I ...... ' *

• NOmfWEST MEDICAL lSOTOH.S NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components De sign Basis Values *

• 30-yeardesign life with the exception of common replaceable parts (e.g., pumps) Provide saturated steam at 1.7 kg/square centimeters (cm 2) (25 lb/square inch [in.2]) and 4.2 kg/cm 2 (60 lb/in.2) gauge to various process equipment 3.5.2.7.21 Process Steam System -Hot Cell Secondary Loops Chapter 9.0, Section 9.7.1 provides a detailed description of the RPF process steam system for the hot cell secondary loop s. De sign Basis Functions

• *

• Provide a closed loop steam syste m for the hot cell secondary l oops Ge nerat e low-pressure steam using a vertica l she ll-and-tube h eat exchanger Provide monitoring of steam condensate for lo ss of primary containment Design Basis Values

• 30-yeardesign life with the exception of common replaceable parts (e.g., pumps) 3.5.2.7.22 Demineralized Water System Chapter 9.0, Section 9.7.1 provides a detailed description of the RPF demineralized water system. Design Basis Functions

• Provide demineralized water to RPF except for administration and truck bay areas *

• Remove minera l ions from municipal water through an ion exc h ange (IX) process and acc umul ate in a storage tank Provide regenerable IX media u sing a strong acid and a strong base Feed acids and bases from local chemical drums by toe pumps D esig n Basis Values *

• 30-year design li fe with the exception of common replaceable parts (e.g., pumps) Provide the water at 4.2 k g/cm 2 (60 lb/in.2) gauge 3.5.2.7.23 Supply Air System Chapter 9.0, Section 9.1.2 provides a detailed description of the supp l y air s ystem. The design basis functions a nd values are identified in Section 3.5.2. 7.12. 3.5.2.7.24 Chemical Supply System Chapter 9.0 , Section 9. 7.4 provides a detailed description of the chemical supply system. Design Basis Functions

• *

• Provide storage capability for nitric acid, sodium h ydroxide, reductant , and nitrogen oxide absorber solutions, hydrogen peroxide, and fresh uranium IX resin Segregate incompatible chemica l s (e.g., ac id s from bases) Provide transfer capability for chemical so lution s mixed to required concentrations and u sed in target fabrication, target dissolution , Mo recovery and purification , and waste management systems 3-65 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components De sign Basis Values

• 30-year design life with the exception of common replaceable parts (e.g., pumps) 3.5.2. 7 .25 Biological Shielding System Chapter 4.0, Section 4.2 , provides a detailed description of the RPF biological shie ldin g. Design Basis Functions

• Provide biological shielding from radiation sources in the hot cells for workers in occ upied areas of the RPF

• Limit physical access to hot ce ll s

• Remain functional through DBEs without l oss of structura l integrity De sign Basis Values

• 30-year design life

• Provide dose rates consistent wit h ALA.RA goa l s for normally occupied areas 3.5.2.7.26 Facility Process Control System Chapter 7.0 , Section 7.2.3 provides a description of the FPC system. De sign Basis Functions

• * * * * *

• Perform as overa ll production process contro ll er Monitor and co ntrol process instrumented functions within the RPF (e.g., process fluid transfer s, controlled inter-equipment pump transfers of process fluid s) Provide monitoring of safety-related components while BMS (a s ub se t of the FPC sys tem) monitors ventilation system and mechanical utility systems Ensure ESF systems operate independently from FPC system or BMS Use h ard-wired analog contro l s/interlock s for each ESF safety function to protect workers, public , an d en v ironment Integrate into and monitor ESF parameter s and a l arm functions by FPC system or BMS Initiate act uation of isolation dampers for hot cell a rea or ana lytic al area on receipt of s ignal s from fire protection system Design Basis Values

• 30-year design life with the exception of commo n replaceable parts (e.g., controllers) 3-66

• i*:h NWMI ...*.. '

• NOWTHWEST MEDICAL lSOTOP'ES

3.6 REFERENCES

NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components 10 CFR 20, "Standards for Protec tion Against Radiation , Code of Federal Regulations , Office of the Federal Register , as amended. 10 CFR 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material,

Code of Federal Regulations, Office of the Federal Register , as amended. 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities,

Code of Federal Regulation s , Office of the Federal Register , as amended. 10 CFR 50.2, "Defin itions ," Cod e of Federal Regulations, Office of the Federal Register , as amended. 10 CFR 50.31, "Combining Applications,

Cod e of Federal R egu lation s, Office of the Federal Register , as amended. 10 CFR 50.32, "E limination of Repetition

, Cod e of Federal Regulations, Office of the Federal Register , as amended. 10 CFR 70, "Domestic Licensing of Special Nuclear Material , Code of Federal R egu lati ons, Office of the Federal Register, as amended. 10 CFR 70.61, "Performance Requirements,

Code of Federal Regulations , Office of the Federal Register , as a mended. 10 CFR 70.64, "Requirements for New Facilities or New Processes at Existing Facilities,'

' Code of Federal R e gulations, Office of the Federal Register, as amended. 10 CFR 71, "Energy: Packaging and Transportation of Radioactive Material ," Code of Federal R egu lation s, Office of the Federal Register , as amended. 10 CFR 73, "Physical Protection of Plants and Materials,

Code of Federal Regulations, Office of the Federal Regi ste r , as amended. 10 CFR 74, "Material Control and Accounting of Special Nuclear Material ," Code of Federal R eg ulati ons, Office of the Federal Register , as amended. 10 CFR 851, "Worker Safety and Health Program , Code of Federal R egu lation s, Office of the Federal Register , as a mended. 10 CSR 10-6.01, "Amb ient Air Quality Standards,

Missouri Code of State Regulations , as amended. 20 CSR 2030, "Missouri Board for Architects, Professional Engineers , Professional Land Surveyors, and Landscape Architects," Cod e of State Regulations, Jefferson City, Missouri , as amended. 21 CFR 210, "Current Good Manufacturing Practice in Manufacturing , Processing, Packaging, or Holding of Drugs," Code of Federal R egu lation s, Office of the Federal Register , as amended. 21 CFR 211, "Current Good Manufacturing Practice for Finished Pharmaceuticals," Code of Federal R egu lation s, Office of the Federal Register , as amended. 29 CFR 1910 , "Occupational Safety and Health Standards,

Code of Federal R egu lation s, Office of the Federal Regi ste r , as amended. 40 CFR 61, "National Emissions Standards for Hazardous Air Pollutants

, Code of Federal R egu lation s, Office of the Federal Regi ste r , as amended. 40 CFR 63, "NESHAP for Source Categories,

Code of Federal Regulations , Office of the Federal Register , as amended. 3-67 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components 40 CFR 141, "National Primary Drinking Water Regulations

," Code of Federal Regulations, Office of the Federal Register , as amended. ACGIH 2097 , Indu s trial Ventilation:

A Manual of R ec ommend e d Pra c ti ce for Design , 28th Edition , ,,-American Conference of Governmental Industrial Hygienists , Cincinnati , Ohio , 2013. ACI 318, Building Cod e Requir e ments for Stru c tural Concrete Comm e ntary , American Concrete Institute , Farmington Hills , Michigan , 2014. ACI 349 , Cod e R e quir e m e nt s for N ucl e ar Saf e ty-R e lat e d Con c r e t e Structur e s and Comm e ntary , American Concrete Institute , Farmington Hills , Michigan , 2013. Adams , A., 2016, " Re: University of Missouri at Columbia -Staff Assessment of Applicability of Fukushima Lessons Learned to University of Missouri -Columbia Research Reactor, (Letter to R. Butler , University of Missouri Research Reactor , December 8), U.S. Nuclear Regulatory Commission , Washington , D.C., 2016. AISC 360 , Sp ec ifi c ation for Stru c tural St e el Buildin gs, American Institute of Steel Construction , Chicago , Illinois , 2010. AMCA Publication 201, Fans and S y st e ms , Air Movement and Control Association International, Inc., Arlington Heights , Illinoi s, 2002 (R201 l). AMCA Publication 203 , Field P e rformanc e M e asur e m e nt of Fan S y st e m s, Air Movement and Control Association International , Inc., Arlington Heights , Illinois , 1990 (R2011 ). AMCA Publication 211 , Certifi e d Ratings Program -Produ c t Rating Manual for Fan Air Performanc e, Air Movement and Control Association International , Inc., Arlington Heights , Illinois, 2013. AMCA Publication 311 , Certifi e d Ratings Program -Produ c t Rating Manual for Fan Sound Performan ce, Air Movement and Control Association International , Inc., Arlington Heights , Illinois , 2006 (R2010). ANS 2.8, Determining Design Basis Flooding at Pow e r R e a c tor Sit e s , American Nuclear Society , La Grange Park , Illinois , 1992 (W2002). ANSI C84. l, Am e ri c an National Standard for El ec tric Pow er S ys t e ms and Equipm e nt -V o ltage Ratin gs (60 H e rt z), American National Standards Institute , Inc., Washington , D.C., 2011. ANSI NI 3.1, Sampling and Monitoring R e leas e s of Airborn e Radioa c tiv e Substan ce s from the Sta c ks and Ducts of Nucl e ar Faciliti e s , American Nuclear Society , La Grange Par k , Illinois , 2011. ANSI N42. l 7B , Am e rican National Standard P e rformance Sp ec ifi c ation s for Health Ph ys i c s Instrum e ntation -Occupational Airborn e Radioa c ti v i ty Monitoring In s trum e ntation , American National Standards Institute , Inc., Washington , D.C., 1989. ANSI N42. l 8, Sp ec ifi c ation and P e rforman c e of On-Sit e Instrum e ntation for Continuou s l y Monitoring Radioactivi ty in Effluent s, American National Standards Institute , Inc., Washington, D.C., 2004. ANSI N323D, Am e ri c an National Standard for In s tall e d Radiation Prot ec tion Instrum e ntation, American National Standards Institute , Inc., Washington , D.C., 2002. ANSVAHRI Standard 365, Performanc e Rating of Comm e r c ial and Industrial Unitary Air-Conditioning Conden s in g Units , Air-Conditioning, Heating , and Refrigeration Institute , Arlington, Virginia , 2009. ANSVAHRI Standard 390, Performance Rating of Singl e Pa c kag e V e rti c al Air-Condition e rs and H e at Pumps , Air-Conditioning, Heating, and Refrigeration Institute , Arlington, Virginia , 2003. 3-68 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components ANSI/ AHRI Standard 410 , Forced-Circu l ation Air-Cooling and Air-Heating Coils, Air-Conditioning, Heating , and Refrigeration In s titute , Arlington, Virginia , 2001. ANSl/AHRI Standard 430 , P erformance Ratin g of Ce ntral Station Air-Handling Units, Air-Co nditi oning, Heating , and Refrigeration Institute , Arlington, Virginia, 2009. ANSl/AHRI Standard 850, P erfor man ce Ratin g of Commercial and Indu s trial Air Filter Equipment, Conditioning, Heating , and R e frigeration Institute , Arlingto n , Virginia, 2013. ANSl/AIHA/ASSE Z9.5, Laborat ory Ventilation , American Society of Safety Engineers , Des Plaines , lllinoi s, 20 1 2. ANSl/AISC N690, Spec ifi c ation fo r Safety-Related Steel S tru ctures for Nuclear Facilities, American Institute of Stee l Construction, Chicago, Illinois , January 3 1 , 2012. ANSl/AMCA 204, Balance Qu ality and Vibration Levels for Fans, Air Movement and Contro l Association International , Inc., Arlington Hei g ht s, Illinoi s, 2005 (R20 1 2). ANSl/AMCA 210, Labo rato ry Methods for Testing Fans for R atings, Air Movement and Contro l Association International , Inc., and American Society of Heating , Refrigerating a nd Air Conditioning Engi ne ers, Inc., A rlin gton H e ight s, Ill inois, 1999. ANSI/ ANS-2.26, Catego ri za ti on of Nuclear Facility Structures , Systems , and Components for Seismic D es ign , American Nucle ar Society, La Grange Park , Illinoi s, 2004 (R2010). ANSl/ANS-2.27, Criteria for In vest i ga tion s of Nuclea r Facility Sites for Seism i c Ha zard Assess m e nt s, A meric an Nuc l ear Society , La Grange P ar k , Illinoi s, 2008. ANSl/ANS-2

.29, Probabi li stic Seismic Ha zard Ana l ys i s, American Nuclear Society, La Grange Park , Illinoi s, 2008. ANSl/ANS-6.4, Nuclear A nal ysis and D es i gn of Concrete Radiati on Shieldingfor Nuclear Pow e r Pl ants, American Nuc l ear Soci ety, La Grange Park , Illin ois, 2006. ANSl/ANS-6.4.2, Specification for Radiation Shie ldin g Materials, American Nucl ea r Society , La Grange Park , Illinoi s, 2006. ANSI/ ANS-8 .1 , Nuclear C riti ca l ity Safety in Op erations w ith Fissionab l e Mate rial s Out side R eactors, American Nuc l ea r Society , La Grange P ar k , Illin o i s, 1998 (R2007) (W20 14). ANSl/ANS-8.3 , Critica ll y Accident Alarm System, American Nuc l ear Society, L a Grange P a rk , Illin ois, 1997 (R2003 , R2012). ANSI/ ANS-8. 7, Nuclear Criticality Safety in t h e Storage of Fissile Mat e rials, American Nuc l ear Society , La Grange Park, Illinoi s, 199 8 (R2007). ANSI/ ANS-8.10, Criter ia for Nuclear Criticality Cont rol in Op erations with Shielding and Co nfin e m ent, Amer i can Nuclear Society , L a Grange P a rk, Illinoi s, 1983 (RI 988, Rl 999 , R2005). ANSI/ ANS-8.19 , Adm ini s trativ e Practices for Nuclea r Critica l ity Safety , American National Standards Institute/ American Nuclear Society, La Grange Park , Illinois , 1996 (R2014). ANS l/A NS-8.2 0 , Nuclear Criticality Safety Trainin g, American National Stan dard s In s titute/American Nuclear Society , La Grang e Park, Ill inois, 1991 (R2005). ANSl/ANS-8.21 , Use of Fixed Neutro n Absorbers in Nuclear Facilities Out side R eac t ors, American Nuclear Society, La Grange Park , Illinoi s, 1995 (R2011 ). 3-69

.... ;. NWMI ...... .. .. .... .. .. .. *

• MOUMWUT MEDtCA&. tsOTWH NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components ANSVANS-8.24, Validation of Neutron Transport Methods for Nuclear Criticality Safety Calcu l ations , American National Standards Institute/American Nuclear Society, La Grange Park, Illinois, 2007 (R2012). ANSVANS-10.4, V e rification and Va lid ation of Non-Safety-Related Sci e ntific and Engine e ring Comput e r Programs for the Nuclear Industry, American Nu clear Society , La Gra n ge Park, Illinois, 2008. ANSVANS-10.5, A cc ommodating Us e r Needs in Computer Program Development, American Nuclear Society, La Grange Park , Illinois, 2006 (R201 1 ). ANSVANS-15.17, Fire Protection Program Criteria for Res e arch R e a c tors , American Nuclear Society , La Grange Park , Illinoi s , 198 1 (R2000) (W2014). ANSVANS-40.37, Mobile Low-L e v e l Radioactiv e Waste Proce s sing Syst e ms, American Nuclear Society , La Grange Park, Illinois , 2009. ANSVANS-55.1 , Solid Radioacti ve Wast e Processing Syst e m for Light Water Cool e d R e a c tor Plants , American Nuclear Society , La Grange Park , Illinois , 1992 (R2000, R2009). ANSVANS-5 5.4 , Gas e ous Radioa c tiv e Waste Pro ce ssing Syst e ms for Light Water Reactor P l ants , American Nuclear Society , La Grange Park , Illinoi s , 1993 (R l 999 , R2007). ANS V ANS-55.6 , Liquid Radioa c ti ve Wast e Pro ce ssing S y st e m for Light Wat e r R e actor Plants, American Nuc l ear Society , La Grange Park , Illinois , 1993 (Rl 999 , R2007). ANSVANS-58.3, Ph y sica l Prot ec tion for Nucl e ar Saf e ty-R e lat e d Syst e m s and Compon e nts , American Nuclear Society , La Grange Park , Ill inois , 19 92 (Rl998, R2008). ANSVANS-58

.8 , Tim e R e spons e D e sign Crit e ria for Saf e ty-R e lat e d Op e rator Actions , American Nuclear Society , La Grange P ark , Illinois, 1994(R2001 , R2008). ANSVANS-59.3 , N ucl e ar Saf ety Crit e ria for Control Air S ys tem s , American Nuclear Society , La Grange Park , Illinois , 1992 (R2002) (W20 1 2). ANSVASHRAE 51-07 , Laboratory M e thods of T e sting Fans for Certifi ed A e rodynamic P e rforman ce Rating , American Society of Heating , Refrigerating , and Air-Conditio nin g Engineers, Atlanta , Georgia , 2007. ANS V ASHRAE 110 , M e thod of T es ting P e rforman ce of Laboratory Fum e Hoods , American Soc i ety of Heating, Refrigerating , and Air-Conditioning Engineers, At l anta , Georg i a , 1 995. ANSVASHRAE 111 , Measurem e nt , Te s ting , Adju s ting and Balancing of Building H e ating , Venti l ation, Air-Conditioning and R e frig e ration S y st e ms , American Society of Heating , Refrigerating , a nd Air-Co nd itioning Engineers , Atlanta , Georgia , 2008. ANSVASHRAE Standard 15, Saf e ty Standard for Refrig e ration Syst e ms , American Society of Heating , Refrigerating , and Air-Cond iti o nin g Engineers, At l anta , Georgia , 2013. ANSVASHRAE Standar d 52.2 , M e thod of Testing G e n e ral V e ntilation Air-Cleaning D e vic e s for R e mo v al Efficienc y by Particle Si ze , American Soc i ety of Heating , Refrigerating , and Air-Conditioning Engineers, At l a nt a , Georgia , 2007. ANSVASHRAE Standard 55 , Th e rma l Environm e ntal Conditions for Human Occupan cy, American Society of Hea ting , Re frigerating, and Air-Cond iti oning Engineers , Atlanta , Georgia, 2013. ANSVASHRAE Standar d 62.1 , V e nti l ation for A c c e ptab l e Indoor Air Quality , American Society of Heating , Refrigerating , and Air-Conditioning Engineers, At l anta , Georgia , 20 l 0. 3-70

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• HORTM'WHT M£0tCAl tsOTOP'fl NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components ANSVASHRAE

/IES 90.1, Energy Standard for Buildings Except Low-R ise Residential Buildings, American Society of Heating , Refrigerating , and Air-Conditioning Engineers, Atlanta, Georgia, 2010. ANSVHI 3.1-3.5 , Rotary Pumps, Hydraulic In sti tute , Parsippany , New Jersey , 2008. ANSVIEEE C2, 2012 National Electrical Safety Code (NESC), Institute of Electrical and Electronics Engineers, Piscataway , New Jersey , 2012. ANSVIEEE N320 , American National Standard Performance Specifications for R eactor Emergency Radiologi cal Monitoring Instrumentation, Institute of Electrical and Electronics Engineers, Piscataway , New Jersey , 1979. ANSVIES RP-1-12 , American National Standard Practice for Office Lighting , Illuminating Engineering Society, New York , New York, 2012. ANSVISA-5.06.01-2007, Functional Requir ements Docum entat ion for Control Software Applications, The International Society of Automation, Research Triang l e Park , North Carolina, 2007. ANSVISA-5.1

-2009 , Instrumentation Symbols and Id entification, The International Society of Automation, Research Triangle Park , North Carolina, 2009. ANSVISA-7.0.01-1996, Quality Standard for In stru m e nt Air, The International Society of Automation, Research Triangle Park , North Carolina, 1996. ANSVISA-12

.01.01-2 013 , D efinitions and Information P ertaini ng to Electrical Equipment in Hazardou s (Classified)

Locations, The International Society of Automation, Research Triangle Park, North Carolina , 2013. ANSVISA-67.04.01-2006, Setpoints for Nuclear Safety-Related Instrum entation, The International Society of Automation, Research Triangl e Park , North Carolina, 2006 (R2011 ). ANSVISA-75

.05.0 1-2000 , Control Valve T ermino lo gy, The International Society of Automation, Research Triangle Park , North Carolina, 2000 (R2005). ANSVISA-82.03-1988, Safety Standard for Electrical and Electronic T est, Measuring , Controlling, and R e lat ed Equipment , The International Society of Automation, Research Triangle Park, North Carolina, 1988. ANSVISA-TR99.00.0l-2007, Security Technologi es for Indu stria l Automation and Control Systems, The International Society of Automation, Re sea rch Triangle Park , North Carolina, 2007. ANSl/ITSDF B56. l, Safety Standard for Low Lift and High Lift Trucks , Indu st rial Truck Standards Developm ent Foundation, Washington , D.C., February 2013. ANSl/NEMA Z535. l, Safety Colors, American National Standards Institute , Inc., Washington , D.C., 2006 (R2011 ). ANSl/NEMA Z535.2 , Environmental and Facility Safety Signs, American National Standards Institute , Inc., Washington , D.C., 2011. ANSl/NEMA Z535.3, Criteria for Safety Symbols, American Nationa l Standards Institute , Inc., Washington , D.C., 2011. ANSl/NEMA Z535.4 , Produ ct Safety Signs and Labels, American National Standards Institute, Inc., Washington , D.C., 2011. 3-71 "NWMI ...*.. .. .. * * *

• NOllTHWUT MEDtCAL tsOTOPH NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components ANSI/NET A A TS-2013, Standard for Acceptance T est ing Specifications for Electrical Power Distribution Equipment and Systems, InterNational Electrical Testing Association, Portage, Michigan , 2013. ANSI/NETA ETT-2010, Standard for Certification of Electrical T esti ng Technicians, lnterNational Electrical Testing Association, Portage , Michigan, 2010. ANSI/NETA MTS-2011 , Maintenance T esting Specifications for Electrical Power Di stributio n Equipment and Systems, InterNational Electrical Te sti ng Association, Portage , Michigan, 2011. ANSVSMACNA 001-2008, Seismic R estra int Manual: Guidelines for Mechanical Systems, Sheet Metal and Air Conditioning Contractors' National Association, Chantilly, Virginia, 2008. ANSVTIA-568-C

.1 , Commercial Building T elecom muni cations Cabling Standard, Telecommunication s Industry Association, Arlington, Virginia, 2012. ANSVTIA-568-C.2, Balan ced Twisted-Pair Telecommunications Cabling and Components Standards, Telecommunication s Industry Association , Arlington, 2014. ANSVTIA-568-C.3, Optical Fiber Cabling and Components Standard, Telecommunication s Industry Association , Arlington, 2011. ANSVTIA-569, Commercial Building Standard for T e l ecommu ni cat ions Pathways and Spaces, Telecommunications Indu stry Association, Arlington, 2013. ANSVTIA-606, Administrat ion Standard for Commercial Telecommunications Infra structure, Telecommunications Industry Association, Arlington, 2012. ANSVTIA-607, Commercial Building Grounding (Earthing) and Bonding Requirements for T e l eco mmuni catio n s, T eleco mmunications Industry Association, Arlington, 2013. ANSVTIA-758-A , Customer-O wned Outsid e Plant T e l ecommu nication s Infr astructure Standa rd , Telecommunication s Indu stry Association, Arlington, 2004. ASCE 4, Seismic Ana l ys i s of Safety-Related Nuclear Structures and Commentary, American Society of Civil Engineers, Reston , Virginia, 2000. ASCE 7 , Minimum Design Loads for Buildin gs and Oth er Structures, American Society o f Civil Engineers, Re s ton , Virginia, 2005 (R2010/2013). ASCE 43 , S e ismi c Design Criteria for Stru c tur es, Systems, and Components in Nuclear Facilities, American Society of Civil Engineers, Reston , Virginia , 2005. ASCE Manual of Practice 37, Design and Construction of Sanitary and Storm Sewe r s, (Out-of-Print), American Society of Civil Engineers, Re s ton , Virginia , 1969. ASHRAE Stand ar d 70 , Method of Testing the Performance of Air Outl ets and A ir Inl ets, American Society of Heating, Refrigerating , and Air-Conditioning Engineers, Atlanta, Geor g ia , 2011. ASME, 2013 , Boil er and Pr essure Vessel Code, American Society of Mechanical Engineers, New York, New York , 2010/2013. ASME A I 7 .1 , Safety Code for Elevators and Escalators, American Society of Mechanical Engineers, New York , New York, 2 007. ASME AG-I , Code on Nuclear Air and Gas Treatment, American Society of Mechanical E ngineer s, New York , New York , 2012. ASME Bl6.5 , Pip e Flanges and Flanged Fitting s: NPW Yi through 24, American Society of Mechanical Engineers, New York , New York , 2003. 3-72 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components ASME B20. l, Safety Standard for Conveyors and R e lated Equipment, American Society of Mechanical Engineers , New York, New York , 2012. ASME B30.17, Ov e rhead and Gantry Cranes (Top Running Bridg e, Single Girder , Underhung Hoi st), American Society of Mechanical Engineers, New York, New York , 2006. ASME B30.20, Below-the-Hook Lifting Devices, American Society of Mechanical Engineers, New York, New York , 2013. ASME B31, Standards of Pres sure Piping, American Society of Mechanical Engineers , New York , New York, 2014. ASME B3 l.3, Process Piping, American Society of Mechanical Engineers , New York, New York, 2014. ASME B3 l.9, Building Services Piping, American Society of Mechanical Engineers , New York , New York, 2014. ASME B31.12 , H y drog e n Pipin g and Pipelines, American Society of Mechanical Engineers, New York , New York , 2014. ASME B40.100 , Pressure Gauges and Gauge Attachments , American Society of Mechanical Engineers, New York , New York , 2013. ASME B40.200 , Th er mometers , Direct R eading and R emote Reading , American Society of Mechanical Engineers , New York, New York , 2013. ASME HST-I, Performance Standard for Electric Chain Hoi sts, American Society of Mechanical Engineers , New York , New York, 2012. ASME N509, Nuclear Power Plant Air-Cleaning Units and Compon e nt s, American Society of Mechanical Engineers , New York, New York , 2002 (R2008). ASME N 510 , Testing of Nuclear Air-Treatment Systems, American Society of Mechanical Engineers, New York , New York, 2007. ASME NQA-1 , Quality Assuranc e Requirements for Nuclear Facility Appli c ations , American Society of Mechanical E ngineers , New York, New York , 2012. ASME QME-1, Qualification of Active M ec hani ca l Equipment Used in Nuclear Fa c iliti es, American Society of Mechanical Engineers , New York , New York, 2012. ASTM Cl055, Standard Guide for Heated System Surface Conditions that Produce Contact Burn Injuries , ASTM International , West Conshohocken, Pennsylvania , 2003 (2014). ASTM C 1217 , Standard Guide for D es ign of Equipm e nt for Processing Nuclear and Rad ioact iv e Materials , ASTM International , West Conshohocken , Pennsylvania , 2000. ASTM Cl533 , Standard Guide for General D esign Considerations for Hot Cell Equipment, ASTM International , West Conshohocken, Pennsylvania , 2008 (R2015). ASTM Cl554, Standard Guide for Materials Handling Equipm e nt for Hot Cells , ASTM International , West Conshohocken, Pennsylvania , 2011. ASTM Cl572, Standard Guide for Dry Lead Glass and Oil-Filled Lead Glass Radiation Shielding Window Components for R e mot e ly Op erated Facilities, ASTM International , West Conshohocken, Pennsylvania , 2010. ASTM C1615, Standard Guide for M e chanical Driv e Systems for R emote Operation in Hot Cell Facilities , ASTM International , West Conshohocken, Pennsylvania , 2010. 3-73

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• NQRTlfW(ST Mf.OK:Al ISOTOPH NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components ASTM Cl661, Standard Guide for Viewing Systems for R emote ly Operated Facilities, ASTM International, West Conshohocken, Pennsylvania , 2013. ASTM E493, Standard Practice for Leaks Using the Mass Spectrometer Leak Detector in t he In side-Out Testing Mode, ASTM International, West Conshohocken, Penn sy l va nia , 2011. ASTM F 14 71 , Standard Test Method for Air Cleaning Performance of High-Efficiency Particulate Filter Syst e m , ASTM International, West Conshohocken, Pennsyl vania , 2009. A WS B2.1/B2.1 M, Specification for Welding Procedure and Performance Qualification , American Welding Society, Miami, Florida, 2009. A WS Dl.l/ Dl.lM , Structural Welding Code -Steel, American W e lding Society, Miami , Florida, 2010. A WS Dl.3/Dl.3M , Struc tural Welding Code -Sheet Steel , American Welding Society, Miami, Florida , 2008. AWS Dl .6/DI .6M , Structural Welding Code -Stainless Steel, American Welding Society, Miami, Florida, 2007. A WS D9.1/ D9.1M, Sheet Metal Welding Code, American Welding Society, Miami , Florida, 2006. AWS QCl, Standard for AWS Certifi c ation of Welding Insp ectors, Am e ric a n Welding Society, Miami , Florida , 2007. City of Columbia, "City of Columbia Code of Ordinances," http s://www.gocolumbiamo.com/Council/

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/, accessed September 8, 2014. CPDG Division 22, " Plumbing ," Consu ltant Procedures and Design Guidelines, Univer sity of Mis souri, Managem ent Services, Facilities Planning and Development , Columbi a , Missouri, 2009. CPDG Division 23, "Hea ting , Ventilating, and Air-Conditioning (HV AC)," Consultant Procedures and Design Guidelines, University of Mi sso uri , Management Services, Fac i litie s Planning and Development , Columbia, Missouri, 2014. CPDG Section 2.4, " Planning , De sig n and Contract Document Development Guidelines for Master Construction Delivery Method," Consultant Procedures and D esign Guidelines , University of Missouri, Management Services, Facilities Planning and Development , Columbia , Missouri, as amended. CRR 70.060, "Consulting, Design , and Construction," Collected Rul es and Re gu lation s, University of Missouri , Co lumbia , Missouri, as amended. DC/COL-ISG-007 , Interim Staff Guidance on Assessme nt of Norma l and Extreme Winter Precipitation Loads on the Roofs of Seismic Category I Structures, Federal Regi s ter Volume 74 , I ss ue 125 , Nuclear Regulatory Commission, Office of New Reactors , Washington, D.C., July 1 , 2009. DHHS (NIOSH) 2003-136, Guidance for Filtration and Air-Cleaning Systems to Protect Building Environments from Airborne C h e mi cal, Biologi ca l , and Radiologi cal A ttacks, Department of Health and Human Services , Centers for Di sease Control and Pre ven tion , Nationa l Institute for Occupational Safety and Health, Cincinnati , Ohio, 2003. DOE-STD-1020-2002 , Natural Phenomena Ha zards Design and Evaluation C r it e ria for Department of Energy Facilities, U.S. Department of Energy, Washington , D.C., 2002 (R2012). FEMA, 2011, "National Flood Insurance Program , Flood Insurance Rate Map, Boone County, Missouri and Incorporated Areas ," Federal Emergency Management Agency , Washington , D.C., 2011. 3-74

.; .. ; NWMI *::**::* ...... ' * * ! NORTNWUT MEDICAL ISOTOrEJ NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Hydrometeorological Report No. 51, Probable Maximum Precipitation Estimates, United States East of the I 05th M e ridian, U.S. Department of Commerce , National Oceanic and Atmospheric Administration, Washington , D.C., 197 8. H ydrometeoro logic a l Report No. 52 , Application of Probable Maximum Pr ec ipitation Estimates , Unit e d States East of the 105 1 h M e ridian, U.S. Department of Commerce , National Oceanic and Atmospheric Administration , Washington , D.C., I 982. Hydrometeorological Report No. 53 , Seasonal Variation of JO-Squar e-Mile Probabl e Ma x imum Precipitation Estimates, U nited States East of th e 105 1 h M e ridian , U.S. Departm en t of Commerce , National Oceanic and Atmospheric Administration , Washington , D.C., 1980. IAEA-TECDOC-1250 , Seismic Design Considerations of Nuclear Fuel Cycle Facilities, International Atomic Energy Agency , Vienna, Austria , 2001. IAEA-TECDOC-134 7 , Consideration of External Eve nt s in th e D es i gn of N ucl e ar Fa c iliti es Oth e r Than Nuclear Pow e r Plants , With Emphasis on Earthquak es, International Atornjc Energy Agency , Vienna , 2003. IAEA-TECDOC-1430 , Radioi sotope Handling Facilities and Automation of Radioi sotope Production , Internation a l Atomic Energy Agency, Vienna , 2004. IBC , 2012 , "International Buildin g Code," International Code Council , Inc., Washington , D.C., 2012. ICC A 1 I 7 .1 , Acc essi bl e and Usab l e Buildings and Facilities Standard , International Code Co uncil , In c., Washington , D.C., 2009. ICC-ES AC156, "Acceptance Criteria for Seismic Certification by Shake-Table Te s tin g of Nonstructural Components

, International Code Council Eva luation Service , October 2010. IECC , 2012, 2012 Int e rnational En ergy Conservation Code, International Code Council , Inc., Washington , D.C., May 2011. IEEE 7-4.3.2 , Standard Criteria for Digital Compute rs in Saf ety Syst e m s of Nuclear Pow e r Generating Stations , Institute of Electrical and Electronics Engineers, Pi scataway, New J ersey, 2003. IEEE 141 , R ecommended Practi ce for E l ec tric Pow e r Distribution for Indu s trial Plants (Red B ook), In s titut e of Electr ical and Elect ronics Engineers , Pi scataway, New Jersey , 1993 (R1999). IEEE 142, R ecommended Practi ce for Grounding of Indu strial and Commercial Pow er Systems (Gr ee n Book), Institute of Electrical and Electronics Engineers , Piscat away, New Jer sey, 2007. IEEE 241 , R ecommended Pra ctice fo r E l ectr i c Po we r Systems in Commercia l Buildin gs (Gray Book), Institute of E l ectr ical and E l ectro njc s Engineers , Pisc ataway, New Jersey , 1990 (Rl 997). IEEE 242, R ecommende d Pra ctice for Protection and Coordination of In dustria l and Commerc ial Pow er Systems (Buff Book), In stitute of Electrical and E lectronics E ngine ers, Piscataw ay, New J e rs ey, 2 001. IEEE 279 , Criteria for Protection Systems for Nuclear P owe r G e n e rating Stations , In st itut e of Electrical and Electronics Engineers , Pi s cataway , New Jer sey, 1971. IEEE 308 , Standard Crite ria for C la ss IE Po wer Syste m s for Nuclea r Pow e r G e n e rating Stations , Institute of E lectrical and E l ec tronics Engineers, Piscataway , New Jersey, 2012. IEEE 315 , Graphic Symbo ls for Electr i c al and E l ec troni cs Dia gra m s, In sti tute of Electrical and E lectronics E ngineers , Pi scataway, N ew Jer sey, 19 75 (Rl 993). 3-75

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• NOWTHWEn MEDICAL ISOTOPES NWMl-201 3-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components IEEE 323, Standard for Qualifying Class JE Equipment for Nuclear Power Generating Stations, Institute of Electrical a nd Electronics E ngineer s, Piscataway, New Jer sey, 2003. IEEE 336, R ecommended Practice for In sta llati on, In spection, and Testing/or C l ass IE Power, Instrumentation, and Control Equipment at Nuclear Facilities, Institute of E l ectrical and E l ectro n ics Engi n eers, Piscataway, New Jersey, 2010. IEEE 338, Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems , Institute of Electrical a nd Electronics Engineer s, Piscataw ay, New Jer sey, 2012. IEEE 344, IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations, Institute of Electrica l and Electronics Engineers, Piscataw ay, New J ersey, 20 1 3. IEEE 379, Standard App li cation of the Single-Failure Criterion to Nuclear Power Generating Station Safety Syst e ms, Institute of E l ec trical and E lectronics Engineers, Pi scataway, New Jersey , 2014. IE EE 38 4 , Standard Criteria for Independence of C l ass J E Equipment and Circuits, Institute of Electrical and Electronics Engineers , Piscataway, New Jersey , 2008. IEEE 399 , Recomm ended Pra ctice for Power Systems Analysis (Brown B ook), Institute of Electrica l and E lectronic s Eng ineers , Piscataway, New Jersey , 1997. IEEE 446, Re commended Pra ctice for Emergency and Standby Power Systems for Indu str i al and Commercial App li cations (Orange Bo ok), Institute of Electrica l and E l ectronics Engi neers , Piscataway , New Jer sey, 1995 (R2000). IEEE 493, R ecommended Pra ctice for the D esign of R e liabl e Industrial and C o mm e r cial Power Systems (Go l d Book), Institute of Electrica l and E l ectronics Engineers, Pi scataway, New Jersey, 2007. IEEE 497, Standard Crite ria for Accident Monitoring In strumentat ion for Nuclear Power Generating Stations , Institute of Electrical and Electronics Engineers, Pi scataway, New Jersey , 20 10. IEEE 519 , Recomm ended Pra ctice and R equirements for Harmoni c Control in Electrical Power Systems , Institute of E lectrical and Electronics Engineers , Piscataway , New Jers e y, 2014. IEEE 535 , Standard for Qualification of C l ass J E Lead Storage Batt er i es for Nuclear Power Generating Stations, In sti tute of Electrical and Electronics Engineers, Piscataway , New Jer sey, 2013. IEEE 577, Standard Requirements for R e liabili ty Analysis in the Design and Op eration of Safety Systems for Nuclear Facilities, Institute of E l ectrical and Electronics E n gineers , Piscataway , New Jersey , 2012. IEEE 603 , Standard Criteria for Safety Systems for Nuclear Power Generating Stations, Institute of E l ectrical and Electronics Engi n eers, Pi sca taway , New Jer sey, 2009. IEEE 650, Standard for Qualification of Class 1 E Static Batt ery Chargers and Inv er t ers for Nuclear Power Generating Stations , institut e of Electrica l and E l ectronics Eng i neers, Piscataway , New Jersey , 2006. IEEE 739, Re commende d Pra ctice for Energy Management in Indu str ial and Commercial Facilities (Bronze B ook), Institute of Electrical and E l ectronics Engineers , Pi sca taway , New Jersey , 1 995 (R2000). IEEE 828, Standard for Configuration Manag eme nt in Systems and Software Engineering , Institute of Electrical and Electronics Engineers, Pi scataway, New Jersey , 2012. IEEE 829, Standard fo r Software and System Test Do cume ntation , Institute of E lectrical and E l ectronics Engineers, Pi sca taway , New Jersey , 2008. 3-76

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• NOmfWEST llEDtCAl lSOTDPU NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components IEEE 902, Guide for Maintenance , Operation , and Safety of Industrial and Commercial Power Systems (Ye llo w Book), Institute of E l ectrica l and Electronics Engineers , Piscataway, New Jersey , 1998. IEEE 946, Gen e rating Stations, Institute of Electrica l a nd Electron i cs Engineers, Piscataway, New Jersey , 2004. IEEE 1012, Standard Criteria for Software Verificat i on and Validation, In stitute of E l ectrical and E lectroni cs Engi neer s, Piscataway, New Jersey, 2012. IEEE 1015, Recomm e nded Practi ce Applying Low-Voltag e Circuit Br ea k e rs Used in Indu s trial and Commercial Power Syst ems (Blue Book), Institute of Electrica l and Electronics Engineers, Piscataway , New Jer sey, 2006 (C2007). IEEE 1023, Guide for the Application of Human Factors Engineering to Systems , Equipment, and Facilities of Nuclear Pow er Generating Stations, In stitute of E l ectrical and E l ectronics E ngin eers , Piscataway , New Jersey , 2004 (R20 10). IEEE 1028, Standard for Softwar e R ev i ews and Audits, Institute of E l ectrical and E l ectronics Eng in eers , Piscataway , New J ersey, 2008. IEEE 1046, Appli catio n Guide for Distributed Digital Control and Monitoring/or Pow er Plants , Institute of Electrical and E lectroni cs Engineers, Piscataway , New J ersey, 1991 (Rl 996). IEEE 1050, Guid e for Instrum e ntation and Control Equipment Grounding in Gen era ting Stations, Institute of Electrica l and Electronics Engineers, Piscataway , New Jersey , 2004. IEEE 1100, R eco mm e nd e d Practi ce for Powering and Grounding Electronic Equipm e nt (Emerald Book), Institute of Electr ical and Electron ics Engineers , Piscataway , New Jersey , 2005. IEEE 1289, Guid e for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Di sp lays for Nuclea r Power G e nerating Stations, Institute of Electrical and Electronics Engineers, Pi s cataway , New Jersey , 1998 (R2004). IEEE 1584, IEEE Guide for P e rforming Arc-Flash Ha z ard Calculations, Institute of Electrical and Electronics Engineers, Piscataway , New Jersey , 2002. IES RP-7 , American National Standard Practic e for Lighting Industrial Fa ci liti es, Illuminating E ngine ering Society, New York, New York , 1991 (W2001). IES-2011, The Lighting Handbook , J0 1 h Ed ition , Illuminating Engineeri n g Society, New York , N ew York, 2011. IFC , 2012, Int e rnational Fire Code, International Code Council, Inc., Washington , D.C., 2012. IMC , 2012 , Int e rnational Me c hani ca l Code, International Code Co uncil , Inc., Washington , D.C., 2012. IP C, 2012, 2012 lnt erna tional Plumbing Code, International Code Co uncil , Inc., Washington , D.C., April 2011. IS A-5.3-1983, Graphic S y mbols for Distributed Control/Shared Displa y Instrumentation , Logic, and Computer Systems, The International Society of Automation , Research Triangle Park , North Caro lin a, 1983. IS A-5 .4-199 I , In st rum e nt Loop Dia gr ams, The International Society of Automation , Research Triangl e Park, North Carolina, 1991. ISA-5.5-1985 , Graphi c Symbol s for Pro cess Di sp lays , The International Society of Automation , Research Triangle Park , North Carolina, I 985. 3-77 NWMl-201 3-021, Rev. 3 Chapter 3.0 -Des ign of Structures , Systems and Components ISA-18.1-1979, Annunciator Sequences and Specifications, The International Society of Automation, Research Triangle Park , North Carolina, 1979 (R2004). ISA-67.01.01-2002 , Transducer and T rans mi tter In s tallation for Nuclear Safe ty App li cations, The Internation a l Society of Automation, Re sea rch Triangle Park , North Caro lin a , 2002 (R2007). ISA-RP60.1-l 990, Co ntrol Center Facilities, The International Society of Automation, Re sea rch Triangle Park , North Caro lin a, 1990. ISA-RP67.04.02-20 I 0 , Methodologies for the D etermi nati on of Setpoints for Nuclear Saf ety-Relat e d Instrum entation , The International Society of A ut omation, Re searc h Triangle Park , North Carolina , 20 10. ISA-TR20.00.01-2007 , Specification Forms for Process Measurement and Control Instrum e nts Part 1: General Considerat ion s Update d with 27 n ew specificatio n forms in 2004-2006 and updated with 11 n ew specification forms in 2 00 7, The Int e rnational Society of Automation, Re sea rch Tri a n gle Park , North Ca rolina , 2007. ISA-TR84.00.04-20 1 l , Part 1 Guideline for the Impl ementation of ANSI/lSA-84.00.01-2004 (!EC 61511), The International Society of Automation, Re sea rch Triang l e P a rk , Nort h Carolina, 20 11. ISA-TR84.00

.0 9-2013 , Security Counte rm easures R e lat ed to Safety In strumented Systems (S IS), The Internation a l Society of Automat ion , R esea rch Triangle Park , North Caro lin a , 2013. IS A-TR91.00.02-2003, Criticality C la ssifica ti on Guid e lin e for In s trum e ntation, The Int ernat ional Society of Automation , Re sea rch Triangle Park , Nort h Carolina, 2003. MU , Faci litie s Management P o li cy and Pr ocedures Manual, http://www.umsystem.edu

/ums/rule s/fPm/, University of Mi ss ouri , Co lumbia , Mi sso uri , as amended. NECA 1 , Standard Practice of Good Workmanship in Electri c al Construction, Nat i ona l E l ectrica l Contractors Assoc iation , Beth es da , M ary l a nd , 2010. NECA 90, R ecommended Pra ctice for Co mmi ssio nin g Buildin g E l ectr i c al Sys t e m s (ANSI), National E l ectrical Con tractors Association , Bethe s da , Maryland , 2009. NECA 100 , Symbols for Electrical Co n struction Drawings (ANS!), National E l ectrical Contrac tor s Association , Bethesda , Maryland, 2013. NECA 101 , Standard for In sta ll ing St ee l Conduits (Rigid, !MC, EMT) (ANSI), National E lectrical Co ntra ctors Association, B et h esda, Maryland , 2013. NECA 111, Standard for In sta llin g No nm eta lli c Ra cew ays (RNC, ENT, LFNC) (ANS I), Nationa l E lectrical Co ntractor s Associa tion , B e th es da , Maryland, 2003. NECA 120 , Standard for In s tallin g Ar mor ed Cable (Type AC) and M e tal-Clad Cab l e (Type MC) (ANSI), National Electrica l Contractors Associ a tion , Bethesda , Maryland , 2013. NECA 202 , Standard for In sta llin g and Maintaining Indu strial H eat Tra cing Systems (ANS I), Nation a l E l ectrical Co ntractors Associa tion , Bethesda , Maryland , 2013. NE CA 230, Standard for Selecting , In sta llin g, and Maintaining E l ec tri c Motors and Motor Controll e rs (ANS I), Nationa l E l ectrical Co nt ractors Association, Bethe s da , Maryland , 2010. NECA 331, Standard for Buildin g and Serv i ce Entrance Grounding a nd B o nding , Nation a l Electrical Contractors Association , B e the s da , Maryland , 2009. NECA 400 , Standard for In s tall ing and Maintaining Switchboards (ANSI), Natio n al E l ectrica l Co ntra ctors Assoc iati on , Bethesda , Ma ry land , 2007. 3-78 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Des ign of Structu res, Systems and Compone nt s NECA 402, Standard for Installing and Maintaining Motor Control Centers (ANSI), Nationa l E l ectrical Contractors Association, Bethesda, Maryland , 2007. NECA 407, R ecommended Practice for In sta llin g and Maintaining Pane/boards (ANSI), National Electrical Contrac tor s Association, Bethe s da , Maryland , 2009. NECA 408, Standard for Installin g and Maintaining Buswa ys (ANS I), National Electrical Contractors Association, Bet h esda, Mary l and, 2009. NECA 409, Standard for Installin g and Maintaining Dry-Type Transformers (ANSI), National Electrical Contractors Association, Bethesda, Maryland , 2009. NECA 410, Standard for Installin g and Maintaining Liquid-Filled Transformers (ANS I), Nationa l Electrical Contractors Associatio n , Bethesda , Maryland , 2013. NECA 41 1 , Standard for Installin g and Maintaining U nint erruptib l e Power Supplies (UPS) (ANSI), National Electr ical Contractors Association , Bethesda , Mary l and , 2006. NECA 420, Standard for Fuse Applications (ANSI), National Electrica l Contractors Association, Bethesda , Mary l a nd , 2014. NECA 430, Standard for Installin g Medium-Voltage Metal-Clad Switchgear (ANS I), National E l ectrical Contractors Association , Bethesda, Maryland, 2006. NECNAA 104 , Standa rd for In sta lling A luminum Building Wire and Cable (ANS I), Nationa l Electrical Co nt ractors Association, B e thesda , M ary land, 2012. NEC N BICSI 568, Sta ndard for Installing Buildin g T e l ecommunications Cabling (ANSI), National E l ectrical Co ntractors Association, Beth es da , Maryland , 2006. NECNEGSA 404, Standard for Installing Generator Sets (ANSI), National Electrical Contrac tor s Association, Bethesda, Maryland, 2014. NECNFOA 301, Standard for Installing and Testing Fiber Optics, N at ion al Electrical Contrac tor s Association, B et hesda , Marylan d , 2009. NECNIESNA 500 , Recommended Practice for In stalli n g Ind oor Lighting Systems (ANS I), National Electrical Contrac tor s Associat i o n , Beth es d a, Maryland , 2006. NECNIESNA 501, Recommended Practice for Installing Exterior Lighting Systems (ANSI), Nat i onal E l ectrical Contractors Association, Beth es d a , Maryland , 2006. N ECNIESNA 502, Recommended Practice for Installing Ind ustria l Lighting Systems (ANS I), National E l ectrical Contrac tors Association, Beth es d a, Maryland , 2 006. NECNNCSCB 600 , Recommend e d Practice for In sta llin g and Maintaining Medium-Voltage Cable (ANS I), Nationa l E l ectrical Contractors Association, Bethe s d a , M ary land , 20 14. NECNNEMA 105 , Standard for Insta llin g Metal Cab l e Tray Systems (ANSI), Nation a l E l ec trical Co ntra ctors Association, Bethesda, Maryland , 2007. N ECNNE MA 605 , Insta llin g Underground Nonmeta lli c Uti li ty Duct (ANSI), Nationa l Electrica l Co ntractor s Association , B e th es da , Maryl a nd , 2005. NEMA MG-1 , Motors and G enerators, National E l ectr i ca l Manufacturer s Associat i on, Ro ssly n , Virginia , 2009. NFPA 1 , Fire Code , Nationa l Fire Prot e ction Association, Quincy, Massachusetts , 2015. 3-79

..... NWMI *::**::* ...... * * ! . NOmfWE.ST MEDICAL ISOTOfllS NWM l-2013-021 , Re v. 3 C h a pte r 3.0 -Desi gn of Struct ur es , Sys t ems a n d Compone nts NFPA 2, Hydrogen Techno l ogies Code, Nationa l Fire Protection Association, Q u incy, Massac h usetts, 201 1. NFPA 4, Standard for Integrated Fire Protection and Life Safety System Testing, National Fire Protection Association, Quincy, Massachusetts, 2015. NFPA 10, Standard for Portable Fire Extinguishers, Nat i onal Fire Protection Assoc i ation, Quincy, Massac h usetts , 2013. NFPA 13, Standard for the Installation of Sprinkler Systems, Nationa l Fire Protection Association, Q u incy, Massachusetts, 2013. NFPA 14, Standard for the Installation of Standpipe and Hose Systems, National Fire Protection Association, Quincy, Massach u setts, 2013. NFPA 20 , Standard for the Installation of Stationary Pumps for Fire Protection , National Fire Protection Association, Quincy, Massach u setts, 20 1 3. NFPA 22, Standard for Water Tanks for Private Fire Protection, National Fire Protection Association, Q u i n cy, Massachusetts, 2013. NFPA 24, Standard for the Installation of Private Fir e Service Mains and Thei r Appurtenances, National Fire Protection Association, Quincy, Massachusetts, 2013. NFPA 25, Standard for the Insp ec tion , Testing , and Maintenance of Water-Based Fire Protection Systems, Nationa l Fire Protection Associatio n , Quincy , Massachusetts, 2014. NFPA 30, F l ammable and Combustible Liquids Code , Nationa l Fire Protection Association , Q ui ncy , Massachusetts, 2015. NFPA 37 , Standard for the Installation and Use of Stationary Combustion Engines and Gas Turbines , Nationa l Fire Protection Associat i on, Quincy, Massachusetts , 2015. NFPA 45, Standard on Fire Protection for Laboratories Using Chemicals, Nat i ona l Fire Pro t ec t io n Assoc i ation , Quincy, Massach u setts, 2015. NFPA 55, Compress e d Gases and Cryogenic Fluids Code, National Fire Protectio n Association, Quincy, Massachusetts, 2013. NFPA 59A, Standard for the Production, Storage, and Handling of Liquefied Natural Gas , National Fire Protection Association, Quincy, Massachusetts, 2013. NFPA 68 , Standard on Explosion Protection by Dejlagration Venting, Nationa l Fire Protection Association , Qu in cy, Massac hu setts , 2013. NFPA 69, Standard on Explosion Pr e vention Systems, National Fire Protection Association, Qu i ncy , Massachusetts, 2014. NFPA 70, National Electrical Code (NEC), Nationa l Fire Protection Association, Quincy, Massachusetts, 2014. NFPA 70B, R ecommended Practice for Electrical Equipment Maintenance, Natio n a l Fire Protection Assoc i ation , Quincy , Massach u setts, 2013. NFPA 70E, Standard for Electrical Safety in the Workplace, Natio n a l Fire Protectio n Associat i on, Quincy , Massach u setts, 2015. NFPA 72, National Fire Alarm and Signaling Code, National Fire Protection Association, Q uin cy, Massachusetts , 2013. 3-80

.... ;. NWMI ...*.. .. .. .... .... .. NOATKWESTMCrnWISOTOP'lS NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components NFPA 75, Standard for the Fire Protection of Information Technology Equipment, National Fire Protection Association , Quincy, Massachusetts , 2013. NFPA 79 , Electrical Standard for Industrial Machinery , National Fire Protection Association, Quincy , Massachusetts, 2015. NFPA 80, Standard for Fire Doors and Other Op e ning Prot ectives, National Fire Protection Association , Quincy , Massachusetts , 2013. NFPA 80A, Recomm e nd e d Practice for Prote ctio n of Buildings from Exterior Fire Expo su r es, National Fire Protection Association , Quincy , Massachusetts , 2012. NFPA 86, Standard for Ovens and Furnaces, National Fire Protection Association , Quincy , Massachusetts , 2015. NFPA 86C, Standard for Indu strial Furnaces Using a Special Processing Atmosph e r e, National Fire Protection Association, Quincy , Massachusetts, 1999. NFPA 90A, Standard for the Installation of Air-Conditioning and Ventilating System, National Fire Protection Association, Quincy , Massachusetts , 2015. NFPA 90B , Standard for the Installation of Warm Air H ea ting and Air-Conditioning Systems , National Fire Protection Association, Quincy , Massachusetts, 2015. NFPA 91, Standard for Exhaust Systems for Air Conveying of Vapors, Gas es, Mists , and Noncombustible Particulat e Solids, National Fire Protection Association, Quincy , Massachusetts , 2015. NFPA 92, Standard for Smoke Contro l Systems , National Fire Protection Association, Quincy, Massachusetts , 2012. NFPA 92A , Standard for Smok e-Control Syst e ms Utilizing Barriers and Pr ess ur e Differ e n ces, National Fire Protection Association , Quincy , Massachusetts , 2009. NFPA 92B, Standard for Smok e Management Systems in Malls , Atria, and Large Spa ces, Nationa l Fire Protection Association, Quincy , Massachusetts, 2009. NFPA 101 , Life Saf ety Code, National Fire Protection Association , Quincy , Massachusetts , 2015. NFPA lOlB, Cod e for M e ans of Egress for Buildings and Stru ct ures, National Fire Protection Association, Quincy , Massachusetts , 2002 (W-Next Editio n). NFPA 105, Standard for th e Installation of Smok e Door A sse mblies and Oth e r Op e ning Prot ec tives , National Fire Protection Association , Quincy, Massachusetts , 2013. NFPA 110, Standard for Em erge nc y and Standb y Pow e r Systems, National Fire Protection Association, Quincy , Massachusetts, 20 13. NFPA 111 , Standard on Stored El ec trical En e r gy Emergency and Standb y Pow er S ys t e ms , National Fire Protection Association, Quincy , Massachusetts , 2013. NFPA 170, Standard for Fire Saf ety and Em e rg e n cy Symbols, National Fire Protection Association, Quincy , Massachusetts, 20 I 2. NFPA 204, Standard for Smok e and Heat V e nting , National Fire Protection Associatio n , Quincy, Massachus etts, 2012. NFPA 220, Standard on Types of Building Con s tru c tion, National Fire Protection Association, Quincy , Massachusetts , 2015. 3-81 NWMl-2013-021 , Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components NFPA 221, Standard for High Chall e nge Fire Walls, Fir e Walls , and Fir e Barrier Walls , National Fire Protection Association , Quincy, Massachusetts , 2015. NFPA 262 , Standard Method of T es t for F l am e Trav e l and Smok e of Wir e s and Cabl e s for Us e in Handling Spaces , National Fire Protection Association , Quincy , Massachusetts, 2015. NFPA 297 , Guid e on Principles and Practices for Communications Syst e ms, National Fire Protection Association , Quincy , Massachusetts , 1995. NFPA 329 , Recomm e nd e d Practi ce for Handling R e l e as e s of Flammabl e and Combustibl e Liquid s and Gases , National Fire Protection Associat ion , Quincy , Massachu s etts , 20 15. NFPA 400, Hazardous Material s Cod e , National Fire Protection Association, Quincy , Massachusetts , 2013. NFPA 496 , Standard for Purg e d and Pressuriz e d Enclosur e s for El ec tri c al Equipm e nt , Nationa l F ir e Protection A s sociation , Quincy, Massachusetts, 2013. NFPA 497, Recomm e nd e d Pra c ti ce for th e Clas s ifi c ation of Flammabl e Liquids , Gas e s, o r Vapors and of Hazardou s (Classified)

Locations for El ec tri c al Installations in Ch e mical Pro ces s Areas, National Fire Protection Association , Quincy, Massachusetts , 2012. NFPA 704 , Standard Syst e m for th e Id e ntification of th e Ha z ards of Mat e rials for Em e rg e n cy R e spons e, Nationa l Fire Protection Association , Quincy , Massachusetts , 2012. NFPA 730, Guid e for Pr e mis es S ec urity, National Fire Protection Association , Quincy , Massachusetts , 20 14. NFPA 731 , Standard for the In s tallation of El ec tronic Pr e mis e s S ec urity S ys t e ms , National Fire Protection Association, Quincy, Massachusetts , 2015. NFPA 780 , Standard for the In s tallation of Lightnin g Prot ec tion Sy s t e ms , Nationa l Fire Protection Association , Qu inc y, Massachusetts, 2014. NFP A 791, Recomm e nded Practi ce and Procedur e s for Unlab e l e d El e ctrical Equipm e nt Evaluation , National Fire Protection Association, Quincy, Massachusetts , 2014. NFPA 801, Standard for Fir e Prot ec tion for Fa c iliti e s Handlin g Radioa c tiv e Mat e rial s, Nationa l Fire Protection Association , Quincy , Massachusetts, 2014. NIOSH 2003-136 , Guidance for Filtration and Air-C l eaning Syst e ms to Protect Building Environment s from Airborn e Chemical , Biological , and Radiological Atta c ks , Nationa l Institute for Occupational Safety and Health, Cincinnati, Ohio , 2003. NOAA , 20 1 7 , "NOAA Atlas 14 Point Precipitation Frequency Estimates: Mo," https://hdsc.nws.noaa.gov/hdsc

/pfds/pfds _map_ cont.html

?bkmrk=mo , National Ocean i c and Atmospheric Ad mini stration, Si l ver Spring, Maryland , accessed 2017. NOAA Atlas 14 , Pr ec ipitation-Fr e quen cy Atla s of th e Unit e d States , Volume 8 , Version 2.0: Midwestern States , National Oceanic and Atmospheric Administration , Silver Spring, Maryland , 2013. NRC , 2012 , Final Int e rim Staff Guidanc e Augm e nting NUREG-15 3 7 , " Guidelin e s for Pr e paring and Reviewing Applications for th e Licensing of Non-Power R e a c tors ," Parts 1 and 2,for Lic e n s ing Radioisotop e Production Fa c ilities and Aqueous Homogeneous Rea c tors , Docket Number: NRC-2011-0135 , U.S. Nuclear Regulatory Commission , Washington , D.C., October 30, 2012. NUREG-0 700 , Human-S y st e m Int e rfa ce Design R e vi e w Guid e lin e s , Rev. 2 , U.S. Nuclear Reg ulatory Commission, Office of Nuclear Regulatory Research , Was hin gton , D.C., 2002. 3-82 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components NUREG-0800, Standard Review Plan for the R eview of Safety Analysis Reports for Nuclear Power Plants , LWR Ed ition , U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards , Washington , D.C., 1987. NUREG-1513, Int eg rat e d Saf ety Ana l ysis Guidan ce Do c um ent, U.S. Nuclear Regulatory Commission, Office of Nuc l ear Material Safety and Safegua rd s, Washington , D.C., May 2001. NUREG-1520 , Standard R eview Plan for th e R ev i ew of a Li ce ns e Application for a Fu e l Cycle Facility , Rev. 1 , U.S. Nuclear Regulatory Commission , Office of Nuclear Material Safety and Safeguard s, Washington , D.C., May 2010. NUREG-153 7, Guidelines for Pr ep aring and R ev i ew ing Applications for the Li ce nsing of Non-Power Reactors -Format and Content, Part 1 , U.S. Nuclear Regulatory Commission , Office of Nuclear Reactor Regulation , Washington , D.C., February 1996. NUREG/CR-4604/PNL-5849 , Statistical M e thod s for Nuclear Material Manag e m e nt , Pacific Northw est Laboratory , Richland , Washington , December, 19 88. NUREG/CR-6410 , Nu cl ea r Fu e l Cycle Facili ty Accident Analysis Handbook , U.S. Nuclear Regulatory Commission , Washington , D.C., 1998. NUREG/CR-6463 , R ev i ew Guid e lines on Softwar e Languag es for Use in Nucle ar Pow e r Plant Safety S ys t e m s -Final R e port , U.S. Nuclear Regulatory Commissio n , Office of Nuclear Regulatory Research , Washington , D.C., 1996. NUREG/CR-6698 , Guide for Validation of Nuclear Criticali ty Safety Calculational M e thodology, U.S. Nucl ear Regulatory Commission, Office of Nucl ear Material Safety and Safeguards, Washington , D.C., January 2001. NUREG/CR-7005 , Technica l Ba s i s for R eg ulatory Guidan ce on Design-Ba s i s Hurri c an e Wind Spe eds for Nuclear Po we r Plant s, U.S. Nuclear Regulatory Com m ission, Washington , D.C., 2011. NWMI-2013-043 , NWM I Radioi so tope Produ ction Fa ci li ty Structura l D es i gn Ba s is , Rev. B , Northwest Medical Isotopes , Corvalli s, Oregon , 2015. NWMI-20 l 5-LIST-003 , NWMJ Radioisotop e Produ ctio n Facility Mast e r Equipment Li st, Rev. A , Northwest Medical Isotopes, Corvallis , Oregon , 2015. NWMI-2015-SAFETY-O 11 , Evaluation of Natura l Ph e nom eno n and Man-Mad e Events on Safety Features and It e ms R e li ed on for Safety, Rev. A , Northwest Medical I sotopes, Corvallis, Oregon , 20 15. NWMI-2015-SDD-001 , RPF Fa c ili ty SDD , Re v. A, Northwe s t Medical Isotopes , Corvallis, Oregon , 2015. NWMI-DRD-2013-030 , NWM J Radioisotop e Produ c tion Fa ci lity D es ign R eq uir e m e nts D oc um e nt , Rev. B , Northwest Medical Isotopes , Corva lli s, Oregon , 2015. Open-File Report 2008-1 128 , Do c um e ntation for the 2008 Update of the United Stat es Natio n al Sei s mi c Ha z ard Map s, U.S. Geological Survey , Washington , D.C., 2008. Regulatory Guide 1.29 , S e ismi c D es ign Classifi ca tion , R ev. 3 , U.S. Nuclear Regulatory Commission, Washington , D.C., September 1978. Regulatory Guide 1.53 , Appli c ation of the Singl e-Failur e Criterion to Saf ety Systems, R ev. 2, U.S. Nuclear Regulatory Commission , Washington , D.C., November 2003 (R201 l). Regul atory Guide 1.60 , D es ign R es pon se Sp ec tra for S e ismi c D es ign of Nuclear Pow e r Plants , Rev. 2 , U.S. Nuclear Regulatory Commission, Wa s hington , D.C., Jul y 2014. 3-83

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• NORTHWEST MEDICAL ISOTOPES NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Str u ctures, Systems and Com p onents Regulatory Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants, Rev. 1 , U.S. Nuclear Regulatory Commission, Washington, D.C., March 2007 (R2015). Regulatory Guide 1.76, Design-Basis Tornado and Tornado Missiles for Nuclear Pow er Plants , Rev. 1, U.S. Nuclear Regulatory Commission, Washington, D.C., March 2007. Regulatory Guide 1.92, Combining Modal Respons es and Spatial Components i n Seismic Response Analysis, Rev. 2 , U.S. Nuclear Regulatory Commission, Washington , D.C., July 2006. Regulatory Guide 1.97, Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants , Rev. 4 , U.S. Nuclear Regulatory Commission, Washington , D.C., June 2006 (R2013). Regulatory Guide 1. I 00 , Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear P o wer Plant s, Rev. 3, U.S. Nuclear Regulatory Commission, Washington, D.C., September 2009. Regulatory Guide 1.102, Flood Protection for Nuclear Power Plants, Rev. 1 , U.S. Nuclear Regulatory Commission, Office of Standards Development, Washington , D.C., September 1976. Regulatory Guide 1.122, Developm en t of Floor D esign Respons e Spectra for Seismic D esig n of Supported Equipment or Components , U.S. Nuc l ear Regulatory Commission, Office of Standards Development, Washington , D.C., February 1978. Regulatory Guide 1.152 , Criteria for Use of Computers in Safety Systems of Nuclear Pow e r Plants , Rev. 3, U.S. Nuclear Regulatory Commission, Washington , D.C., July 2011. Regulatory Guide 1.166 , Pr e-Earthquake Planning and Imm ediate Nuclear Power Plant Operator Post Earthquake Actions, U.S. Nuclear Regulatory Commission , Washington , D.C., March 1997. Regulatory Guide 1. I 67, R estart of a Nuclear Power Plant Shut down by a Seismic Event, U.S. Nuclear Regulatory Commission, Washington, D.C., March 1997. Regulatory Guide 1.208, P e rformanc e Based Approach to D efi ne the Site-Specific Earthquake Ground Motion, U.S. Nuclear Regulatory Commission, Washington , D.C., Mar c h 2007. Regulatory Guide 3.3, Quality Assurance Program Requirem e nt s for Fu el R eprocessing Plants and for Plutonium Proc e ssing and Fuel Fabrication Plant s, Rev. I , U.S. Nuclear Regulatory Commission, Washington , D.C., March 1974 (R2013). Regulatory Guide 3.6, Content of T ec hni ca l Specification for Fuel R e pro cessi ng Plants , U.S. Nuclear Regulatory Commission, Washington , D.C., April 1973 (R2013). Regulatory Guide 3.10 , Liquid Waste Tr ea tm e nt System D es ign Guide for Plutonium Pro cess ing and Fuel Fabrication Plants, U.S. Nuclear Regulatory Commission, Washington , D.C., June 1973 (R2013). Regulatory Guide 3.18 , Confinement Barri ers and Systems for Fuel R e pro cessing Plant s, U.S. Nuclear Regulatory Commission , Washington , D.C., February 1974 (R2013). Regulatory Guide 3.20, Proc ess Offga s Systems for Fuel Repro cess ing Plant s, U.S. Nuclear Regulatory Commission, Washington , D.C., February 1974 (R2013). Regulatory Guide 3.71 , Nuclear Criticality Safety Standards for Fuels and Mat e rials Fac ili ti es, Rev. 2, U.S. Nuclear Regulatory Commission , Washington , D.C., December 2010. Regulatory Guide 5.7 , Entry/Exit Control for Prot ec ted Areas, Vital Areas, and Material Access Areas, Rev. 1 , U.S. Nuclear Regulatory Commission, Washington , D.C., May 1980 (R20 1 0). 3-84 NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures, Systems and Components Regulatory Guide 5.12, General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials, U.S. Nuclear Regulatory Commission, Washington, D.C., November 1973 (R2010). Regulatory Guide 5.27, Special Nuclear Material Doorway Monitors, U.S. Nuclear Regulatory Commission, Washington, D.C., June 1974. Regulatory Guide 5.44 , Perimeter Intrusion Alarm Systems, Rev. 3, U.S. Nuclear Regulatory Commission, Washington, D.C., October 1997 (R2010). Regulatory Guide 5.57, Shipping and Receiving Control of Strategic Special Nuclear Material, U.S. Nuclear Regulatory Commission, Washington, D.C., June 1980. 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SMACNA-2006, HVAC Systems Duct Design, Sheet Metal and Air Conditioning Contractors' National Association, Chanti ll y , Virginia, 2006. SNT-TC-lA, Recommended Practice No. SNT-TC-JA:

Personnel Qualification and Certification in Nondestructive Testing, American Society for Nondestructive Testing, Columbus , Ohio, 2011. Technical Paper No. 40, Rainfall Frequency Atlas of the United States for Durations from 30 Minutes to 24 Hours and Return Periods from 1 to JOO Years, Weather Bur eau, U.S. Department of Commerce, Washington, D.C. 1963. Terracon, 2011 a, Phase I Environmental Site Assessment Discovery Ridge Lots 2, 5, 6 , 7, 8, 9, 10, 11, 12 , 13 , 14 , 15, 16 , 17 , and 18 , Terracon Consultants, Inc., prepared for University of Missouri and Trabue, Hansen & Hinshaw , Inc., Terracon Project No. 09117701 , March 23, 2011. Terracon, 2011 b , Preliminary Geotechnical Engineering Report Discovery Ridge-Certified Site Program Lots 2 , 5, 6 , 7 , 8 , 9, 10 , 11 , 12, 13 , 14 , 15 , 16 , 1 7, and 18, Terracon Consultants , Inc., prepared for University of Missouri and Trabue, Hansen & Hinshaw, Inc., Terracon Project No. 09105094.1, February 11 , 2011. UL 181, Standard for Factory-Made Air Ducts and Connectors, Underwriters Laboratories, Washington, D.C., 2013. UL 499, Standard for Electric Heating Appliances, Underwriters Laboratories , Washington , D.C., 2014. UL 555, Standard for Fire Dampers, Underwriters Laboratories , Washington, D.C., 2006. 3-85

.... NWMI ...*.. ..* .. . ........ *. ' * ! . NORTHWEST MEDfCAl tsOTOPf.S NWMl-2013-021, Rev. 3 Chapter 3.0 -Design of Structures , Systems and Components UL 586, Standard for High Efficiency, Particulat e, Air Filt e r Units, Underwriters Laboratories, Washington, D.C., 2009. UL 900 , Standard for Air Filter Units, Underwriters Laboratories, Washington , D.C., 2004. UL 1995 , Heating and Cooling Equipment, Underwriters Laboratories, Washington , D.C., 2011. USGS, "2008 U.S. Geological Survey National Seismic Hazard Maps," U.S. Geological Survey , Roll a, Missouri, 2008. 3-86