Appendix B - References.

101 Pages·2011·0.25 MB·English

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