APPENDIX B. REFERENCES American Concrete Institute (ACI) — — — — —, ACI 318, "Building Code Requirements for Structural Concrete,” 1989. — — — — —, ACI 318, "Building Code Requirements for Structural Concrete,” 1992. — — — — —, ACI 318, "Building Code Requirements for Structural Concrete," 1995. — — — — —, ACI 318, "Building Code Requirements for Structural Concrete," 1999. — — — — —, ACI 349, “Code Requirements for Nuclear Safety-Related Concrete Structures,” 1997. — — — — —, ACI 349-80, “Code Requirements for Nuclear Safety Related Concrete Structures,” 1980. — — — — —, ACI 349-97, "Code Requirements for Nuclear Safety Related Concrete Structures," February 1998. — — — — —, ACI 349-01, “Code Requirements for Nuclear Safety Related Concrete Structures,” 2001. American Institute of Steel Construction (AISC) — — — — —, AISC 325-01, “Manual of Steel Construction: Load and Resistance Factor Design,” 3rd Edition, 2001. — — — — —, AISC 360-05-2005, “Specification for Structural Steel Building.” — — — — —, AISC M016-89, “Manual of Steel Construction Allowable Stress Design” 9th Edition, 1989. — — — — —, AISC N690, “Specification for the Design, Fabrication, and Erection of Steel in Safety-Related Structures for Nuclear Facilities,” 1994. American Iron and Steel Institute (AISI) — — — — —, AISI SG02-1, “Specification for the Design of Cold Formed Steel Structural Members,” 2001. — — — — —, AISI SG05-1e, “Supplement 2004 to the North American Specification for the Design of Cold-Formed Steel Structural Members, 2001 Edition,” 2004. B-1 American Nuclear Society (ANS) — — — — —, ANS 5.1-1979, “Decay Heat Power in Light Water Reactors.” — — — — —, ANS 52.1-1988, “Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants.” — — — — —, ANS 58.14-1993, “Safety and Pressure Integrity Classification Criteria for Light Water Reactors.” American National Standards Institute (ANSI) — — — — —, ANSI A58.1-1982, “Minimum Design Loads for Buildings and Other Structures.” — — — — —, ANSI C37.50-1989, “1989 Switchgear – Low-Voltage AC Power Circuit Breakers Used in Enclosures – Test Procedures.” — — — — —, ANSI N14.6-1993, “Special Lifting Devices for Shipping Containers Weighing 10000 Pounds (4500 kg) or More.” — — — — —, ANSI N42.18-2004, “Specification and Performance of On-Site Instrumentation for Continuous Monitoring Radioactivity in Effluents.” — — — — —, ANSI N45.2-1977, “Quality Assurance Program Requirements for Nuclear Facilities.” — — — — —, ANSI N45.2.1, “Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants,” 1973. — — — — —, ANSI N45.2.1, "Cleaning of Fluid Systems and Associated Components for Nuclear Power Plants,” 1980. — — — — —, ANSI N45.2.2-1978, “Packaging, Shipping, Receiving, Storage & Handling.” — — — — —, ANSI N45.2.5-1974, "Supplementary Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants." — — — — —, ANSI N101.4-1972, “Quality Assurance for Protective Coatings Applied to Nuclear Facilities." American National Standards Institute / American Institute of Steel Construction (ANSI / AISC) — — — — —, ANSI/AISC 360-05, “Specification for Structural Steel Building,” March 9, 2005. B-2 — — — — —, ANSI/AISC N690-1984, “Nuclear Facilities-Steel Safety-Related Structures for Design, Fabrication and Erection.” — — — — —, ANSI/AISC N690-1994, “Specification for the Design, Fabrication, and Erection of Steel in Safety-Related Structures for Nuclear Facilities.” — — — — —, ANSI/AISC N690-1994 s2, “Supplement No. 2 to the Specification for the Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities.” — — — — —, ANSI/AISC N690-2006, “Specification for Safety-Related Steel Structures for Nuclear Facilities.” American National Standards Institute / American Nuclear Society (ANSI / ANS) — — — — —, ANSI/ANS 3.2-1994, “Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.” — — — — —, ANSI/ANS 3.2-1999, “Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.” — — — — —, ANSI/ANS 3.5-1998, “Nuclear Power Plant Simulators for Use in Operator Training and Examination.” — — — — —, ANSI/ANS 5.1-1994, “Decay Heat Power in Light Water Reactors.” — — — — —, ANSI/ANS 6.4-2006, “Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants.” — — — — —, ANSI/ANS 6.4.2-2006, “Specification Radiation Shielding Materials.” — — — — —, ANSI/ANS 18.1-1999, “Radioactive Source Term for Normal Operation of Light-Water Reactors.” — — — — —, ANSI/ANS 55.4-1993, “Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants.” — — — — —, ANSI/ANS 55.6-1993, "Liquid Radioactive Waste Processing System for Light Water Reactor Plants." — — — — —, ANSI/ANS 56.2-1976, “Containment Isolation Provisions for Fluid Systems.” — — — — —, ANSI/ANS 56.4-1988, “Pressure and Temperature Transient Analysis for Light Reactor Containments.” — — — — —, ANSI/ANS 56.8-2002, “Containment System Leakage Testing Requirements.” B-3 — — — — —, ANSI/ANS 56.10-1987, “Subcompartment Pressure and Temperature Transient Analysis in LWRs.” — — — — —, ANSI/ANS 57.1-1980, “Design Requirements for Light Water Reactor Fuel Handling Systems.” — — — — —, ANSI/ANS 57.1-1992, “Design Requirements for Light Water Reactor Fuel Handling Systems.” — — — — —, ANSI/ANS 57.2-1983, “Design Requirements for Light Water Reactor Spent Fuel Storage Facilities in Nuclear Power Plants.” — — — — —, ANSI/ANS 57.3-1981, “Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants.” — — — — —, ANSI/ANS 57.3-1983, “Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants.” — — — — —, ANSI/ANS 58.2-1988, “Design Basis for Protection of Light Water Nuclear Power Plants Against the Effects of Postulated Pipe Rupture.” — — — — —, ANSI/ANS 58.8-1994, “Time Response Design Criteria for Safety-Related Operator Actions.” — — — — —, ANSI/ANS 58.9-2002, “Single Failure Criteria for LWR Safety-Related Fluid Systems.” — — — — —, ANSI/ANS-HPSSC-6.8.1-1981, “Location and Design Criteria for Area Radiation Monitoring Systems for Light-Water Nuclear Reactors.” American National Standards Institute/Hydraulic Institute (ANSI / HI) — — — — —, ANSI/HI 2.6 (M108), “American National Standard for Vertical Pump Tests,” January 1, 2000. American National Standards Institute / Health Physics Society (ANSI / HPS) — — — — —, ANSI/HPS N13.1-1999, “Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities.” American National Standards Institute/Instrument Society of America (ANSI / ISA) — — — — —, ANSI/ISA 7.0.01-1996, “Quality Standard for Instrument Air.” — — — — —, ANSI/ISA S7.3-R1981, “Quality Standard for Instrument Air.” B-4 American Society of Heating, Refrigerating, and Air-Conditioning Engineers (ASHRAE) — — — — —, “2005 ASHRAE Handbook - Fundamentals - I-P Units,” 2005. — — — — —, ASHRAE 62.1-2007, “Ventilation for Acceptable Indoor Air Quality.” — — — — —, ASHRAE 15-2004, “Safety Standard for Refrigeration Systems.” American Society of Civil Engineers (ASCE) — — — — —, ASCE 4-98, "Seismic Analysis of Safety-Related Nuclear Structures and Commentary,” 1999. — — — — —, ASCE 7-05, “Minimum Design Loads for Buildings and Other Structures,” 2010. — — — — —, ASCE 3269, “Wind Forces on Structures,” Transactions of the ASCE, 1961. American Society of Civil Engineers /Structural Engineering Institute (ASCE / SEI) — — — — —, ASCE/SEI 7-02, “Minimum Design Loads for Buildings and Other Structures,” April 2007. — — — — —, ASCE/SEI 7-05, “Minimum Design Loads for Buildings and Other Structures,” 2005. — — — — —, ASCE/SEI 43-05, “Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities,” January 2005. American Society of Mechanical Engineers (ASME) ASME Code Cases — — — — —, N-71-17, “Additional Materials for Subsection NF, Class 1, 2, 3, and MC Component Supports Fabricated by Welding, Section III, Division 1,” December 8, 2000. — — — — —, N-71-18, “Additional Materials for Subsection NF, Class 1, 2, 3, and MC Component Supports Fabricated by Welding, Section III, Division 1,” May 9, 2003. — — — — —, N-122-2, “Procedure for Evaluation of the Design of Rectangular Cross Section Attachments on Class 1 Piping, Section III, Division 1,” February 3, 2003. B-5 — — — — —, N-249-14 “Additional Material for Subsection NF, Classes 1, 2, 3 and MC Component Supports Fabricated Without Welding, Section III, Division 1,” February 20, 2004. — — — — —, N-284-1, “Metal Containment Shell Buckling Design Methods, Class MC, Section III, Division 1,” October 2, 2000. — — — — —, N-307-3, “Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1, When the Examinations are Conducted from the End of the Bolt or Stud or from the Center-Drilled Hole, Section XI, Division 1,” March 28, 2001. — — — — —, N-318-5, “Procedure for Evaluation of the Design of Rectangular Cross Section Attachments on Class 2 or 3 Piping, Section III, Division 1,” February 3, 2003. — — — — —, N-319-3, “Alternate Procedure for Evaluation of Stress in Butt Weld Elbows in Class 1 Piping, Section III, Division 1,” February 3, 2003. — — — — —, N-391-2, “Procedure for Evaluation of the Design of Hollow Circular Cross Section Welded Attachments on Class 1 Piping, Section III, Division 1,” May 4, 2004. — — — — —, N-392-3, “Procedure for Evaluation of the Design of Hollow Circular Cross Section Welded Attachments on Classes 2 and 3 Piping, Section III, Division 1,” May 4, 2004. — — — — —, N-411-1, “Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping, Section III, Division 1,” May 5, 2000. — — — — —, N-411-1, “Alternative Damping Values for Response Spectra Analysis of Class 1, 2, and 3 Piping, Section III, Division 1; Annulled,” May 5, 2000. — — — — —, N-457, “Qualification Specimen Notch Location for Ultrasonic Examination of Bolts and Studs Section XI, Division 1,” April 19, 2002. — — — — —, N-491-2, “Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plants, Section XI, Division 1,” February 14, 2003. — — — — —, N-580-1, “Use of Alloy 600 with Columbium Added, Section III, Division 1,” May 20, 1998. — — — — —, N-613-1, “Ultrasonic Examination of Penetration Nozzles in Vessels, Examination Category BD, Item Nos. B3.10 and B3.90, Reactor Nozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c), Section XI, Division 1,” August 20, 2002. — — — — —, N-634, “Alternatives to the Provisions of CC-2511 for Structural Attachments to Class CC Containment Liners Section III, Division 2,” June 14, 2002. B-6 — — — — —, N-763, “N-763 ASTM A 709-06, Grade HPS 70W (HPS 485W) Plate Material without Postweld Heat Treatment as Containment Liner Material or Structural Attachments to the Containment Liner, Subsection CC Section III, Division 2 SUPP 2,” March 19, 2010. ASME Boiler and Pressure Code — — — — —, Section II, “Materials,” 2001 Edition, 2003 Addenda, Part A, “Ferrous Materials Specifications.” — — — — —, Section II, “Materials,” 2001 Edition, 2003 Addenda, Part B, “Nonferrous Material Specifications.” — — — — —, Section II, “Materials,” 2001 Edition, 2003 Addenda, Part D, “Properties- (Customary).” — — — — —, Section II, “Materials,” 2004 Edition. — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” 1989 Edition with no Addenda. — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” 1992 Edition, 1993 Addenda. — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” 2001 Edition, 2003 Addenda. — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection N, “Division 1,” 2001 Edition, 2003 Addenda. — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NB, “Class 1 Components,” 2001 Edition, 2003 Addenda. NB-1100(a), “Scope” NB-2000, “Material” NB-2160, “Deterioration of Material in Service” NB-2200, “Material Test Coupons and Specimens for Ferritic Steel Material” NB-2300, “Fracture Toughness Requirements for Material” NB-2331, “Material for Vessels” NB-2332, “Material for Piping, Pumps, and Valves, Excluding Bolting Material” NB-2333, “Bolting Material” NB-2500, “Examination and Repair of Pressure Retaining Material” B-7 NB-3000, “Design” NB-3120, “Special Considerations NB-3122.3, “Secondary and Peak Stresses” NB-3220, “Stress Limits for Other Than Bolts” NB-3500, “Valve Design” NB-3600, “Piping Design” NB-3650, “Analysis of Piping Products” NB-3658, “Analysis of Flanged Joints” NB-4000, “Fabrication and Installation” NB-4620, “Postweld Heat Treatment” NB-7510, “Safety, Safety Relief, and Relief Valves” NB-7520, “Pilot Operated Pressure Relief Valves” NB-7540, “Safety Valves or Pilot Operated Pressure Relief Valves with Auxiliary Actuating Devices” — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NC, “Class 2 Components,” 2001 Edition, 2003 Addenda. NC-1100(a), “Scope” NC-2000, “Material” NC-2200, “Material Test Coupons and Specimens for Ferritic Steel Material” NC-2300, “Fracture Toughness Requirements for Material” NC-2500, “Examination and Repair of Pressure Retaining Material” NC-2550, “Examination and Repair of Seamless and Welded (Without Filler Metal) Tubular Products and Fittings” NC-2560, “Examination and Repair of Tubular Products and Fittings Welded with Filler Metal” NC-2570, “Examination and Repair of Statically and Centrifugally Cast Products” NC-3000, “Design” NC-3217, “Design Criteria” B-8 NC-3600, “Piping Design” NC-3611.2, “Stress Limits” NC-4000, “FABRICATION AND INSTALLATION” — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NCA, “General Requirements for Division 1 and Division 2,” 2001 Edition, 2003 Addenda. NCA-1140(a), “Use of Code Editions, Addenda, and Cases” NCA-2000, “Classification of Components and Supports” NCA-2130, “Classifications and Rules of This Section” NCA-3200, “Owner’s Responsibilities” NCA-3254.2, “Definition of Division 2 Boundaries” NCA-3260, “Review of Design Report” NCA-3550, “Requirements for Design Output Documents” NCA-3557, “Availability of Design Report” NCA-4000, “Quality Assurance” NCA-5000, “Authorized Inspection” NCA-9000, “Glossary” — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection ND, “Class 3 Components,” 2001 Edition, 2003 Addenda. ND-1100(a), “Scope” ND-2000, “Material” ND-2200, “Material Test Coupons and Specimens for Ferritic Steel Material” ND-2300, “Fracture Toughness Requirements for Material” ND-2500, “Examination and Repair of Pressure Retaining Material” ND-3000, “Design” ND-3600, “Piping Design” ND-4000, “Fabrication and Installation” B-9 — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NE, “Class MC Components,” 2001 Edition, 2003 Addenda. NE-1120, “Rules for Class MC Containment Vessels” NE-2121, “Permitted Material Specifications” NE-2128(a), “Bolting Material” NE-3100, “General Design” NE-3122.1, “Primary Stresses” NE-3130, “General Design Rules” NE-3200, “Design by Analysis” NE-3220, “Stress Intensity and Buckling Stress Values for Other than Bolts” NE-3221.5(d), “Vessels Not Requiring Analysis for Cyclic Service” NE-3222, “Buckling Stress Values” NE-3228.3, “Simplified Elastic–Plastic Analysis” NE-3300, “Design by Formula” NE-3326, “Spherically Dished Covers with Bolting Flanges” NE-5352, “Acceptance Standards” — — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NF, “Supports,” 2001 Edition, 2003 Addenda. NF-2000, “Material” NF-3124, “Rolling and Sliding Supports” NF-3128, “Snubbers and Dampers” NF-3143, “Linear-Type Supports — Analysis Procedure” NF-3280, “Design by Load Rating” NF-3324.6, “Design Requirements for Bolted Joints” NF-3411.3, “Loads” NF-3412.4, “Snubbers” Table NF-3611-1, “Suggested Piping Support Spacing” B-10