B-1

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-2

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-3

— — — — —, 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-4

— — — — —, 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-5

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-6

— — — — —, 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-7

— — — — —, 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-8

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-9

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-10

— — — — —, 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-11

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NG, “Core Support Structures,” 2001 Edition, 2003 Addenda.

NG-1122, “Internal Structures”

NG-2000, “Material”

NG-2500, “Examination and Repair of Core Support Structure Material”

NG-3000, “Design”

NG-3120, “Special Considerations”

NG-4000, “Fabrication and Installation”

NG-5000, “Examination”

NG-5300, “Acceptance Standards”

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Appendix D, “Nonmandatory Preheat Procedures,” 2001 Edition, 2003 Addenda.

D-1000, “Nonmandatory Preheat Procedures”

D-1210, “Preheat Temperatures”

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Appendix F, “Rules for Evaluation of Service Loadings with Level D Service Limits,” 2001 Edition, 2003 Addenda.

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Appendix N, “Dynamic Analysis Methods,” 2001 Edition, 2003 Addenda.

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Appendix O, “Rules for Design of Safety Valve Installations,” 2001 Edition, 2003 Addenda.

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” 2004 Edition.

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Division 2, “Code for Concrete Containments,” 2004 Edition.

— — — — —, Section III, “Rules for Construction of Nuclear Facility Components,” Division 2, “Code for Concrete Containments,” Subsection CC, “Concrete Containments (Prestressed or Reinforced),” 2004 Edition.

CC-1140, “Boundaries of Jurisdiction”

CC-2000, “Material”

CC-3000, “Design”

B-12

CC-3320, “Shells”

CC-3421.9, “Bearing”

CC-3440, “Concrete Temperatures”

CC-3535(b), “Concrete Crack Control”

CC-3600, “Liner Design Analysis Procedures”

CC-3700 , “Liner Design”

CC-3720, “Liner”

Table CC-3730-1, “Liner Anchor Allowables”

CC-4330, “Splicing of Reinforcing Bars”

CC-5521, “Welding Categories”

CC-6000, “Structural Integrity Test of Concrete Containments”

CC-6370, “Strain Measurements”

— — — — —, Section V, “Nondestructive Examination,” 2001 Edition, 2003 Addenda.

— — — — —, Section V, “Nondestructive Examination,” Article 10, “Leak Testing,”

2001 Edition, 2003 Addenda.

— — — — —, Section VIII, “Rules for Construction of Pressure Vessels,” 2001 Edition, 2003 Addenda.

— — — — —, Section VIII, “Rules for Construction of Pressure Vessels,” Division 1, 2001 Edition, 2003 Addenda.

— — — — —, Section IX, “Welding and Brazing Qualifications,” 2001 Edition, 2003 Addenda.

— — — — —, Section X, “Fiber-Reinforced Plastic Pressure Vessels,” 2001 Edition, 2003 Addenda.

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” 1998 Edition, 2000 Addenda.

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” 2001 Edition, 2003 Addenda.

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWA, “General Requirements,” 2001 Edition, 2003 Addenda.

IWA-2210, “Visual Examination”

B-13

IWA-2300, “Qualifications of Nondestructive Examination Personnel”

IWA-2400, “Inspection Program”

IWA-6000, “Records and Reports”

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWB, “Requirements for Class 1 Components of Light-Water Cooled Plants,” 2001 Edition, 2003 Addenda.

IWB-2400, “Inspection Schedule”

Table IWB-2500-1, “Vessel Shell Circumferential Weld Joints”

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWE, “Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants,” 2001 Edition, 2003 Addenda.

IWE-1220, “Components Exempted from Examination”

IWE-2500, “Examination and Pressure Test Requirements”

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWL, “Requirements for Class CC Concrete Components of Light-Water Cooled Plants,” 2001 Edition, 2003 Addenda.

IWL-2500, “Examination Requirements”

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Appendix I, “Ultrasonic Examinations,” 2001 Edition, 2003 Addenda.

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Appendix G, “Fracture Toughness Criteria for Protection Against Failure,” 2001 Edition, 2003 Addenda.

Other ASME Documents

— — — — —, ASME AG-1-2003, “Code on Nuclear Air and Gas Treatment.”

— — — — —, ASME B30.2-2005, “Overhead and Gantry Cranes (Top Running Bridge, Single or Multiple Girder, Top Running Trolley Hoist).”

— — — — —, ASME B30.9-2006, “Slings.”

— — — — —, ASME B30.10-2009, “Hooks.”

— — — — —, ASME B30.11-2010, “Monorails and Underhung Cranes.”

— — — — —, ASME B30.16-2007, “Overhead Hoists (Underhung).”

B-14

— — — — —, ASME B31.1-2004, “Power Piping.”

— — — — —, ASME B31.3-2002, “Process Piping.”

— — — — —, ASME N509-2002, “Nuclear Plants Air-Cleaning Units and Components.”

— — — — —, ASME Code NOG-1-2004, “Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder).”

— — — — —, ASME NQA-1-1983, “Quality Assurance Program Requirements for Nuclear Facilities,” including NQA-1a-1983 Addenda.

— — — — —, ASME NQA-1-1989, “Quality Assurance Program Requirements for Nuclear Facilities,” including NQA-1a-1989 Addenda, NQA-1b-1991, and Addenda NQA-1c-1992 Addenda.

— — — — —, ASME NQA-1-1994, “Quality Assurance Program Requirements for Nuclear Facilities.”

— — — — —, ASME NQA-2-1983, “Quality Assurance Requirements for Nuclear Facility Applications.”

— — — — —, ASME OM Code-2001 including Addenda through 2003, “Code for Operation and Maintenance of Nuclear Power Plants.”

— — — — —, ASME OM-S/G-2003, “Standards and Guides for Operation and Maintenance of Nuclear Power Plants.”

— — — — —, ASME QME-1-2007, “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.”

— — — — —, ASME-RA-Sb-2005, “Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications.”

American Society of Testing and Materials (ASTM)

— — — — —, ASTM A240, “Standard Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels and for General Applications,” 2008.

— — — — —, ASTM A262,”Standard Practices for Detecting Susceptibility to Intergranular Attack in Austenitic Stainless Steels,” 2010.

— — — — —, ASTM A325, “Standard Specification for Structural Bolts, Steel, Heat Treated, 120/105 ksi Minimum Tensile Strength,” 2010.

— — — — —, ASTM A490, “Standard Specification for Structural Bolts, Alloy Steel, Heat Treated, 150 ksi Minimum Tensile Strength,” 2010.

B-15

— — — — —, ASTM A516, “Standard Specification for Pressure Vessel Plates, Carbon Steel, for Moderate- and Lower-Temperature Service,” 2010.

— — — — —, ASTM A564, “Standard Specification for Hot-Rolled and Cold-Finished Age-Hardening Stainless Steel Bars and Shapes,” 2010.

— — — — —, ASTM A572, “Standard Specification for High-Strength Low-Alloy Columbium-Vanadium Structural Steel,” 2007.

— — — — —, ASTM A668, “Standard Specification for Steel Forgings, Carbon and Alloy, for General Industrial Use,” 2009.

— — — — —, ASTM A709, “Standard Specification for Carbon and High-Strength Low-Alloy Structural Steel Shapes, Plates, and Bars and Quenched-and-Tempered Alloy Structural Steel Plates,” 2010.

— — — — —, ASTM A709/A709M-9A, “Standard Specification for Structural Steel for Bridges,” 2009.

— — — — —, ASTM A800, “Standard Practice for Steel Casting, Austenitic Alloy, Estimating Ferrite Content Thereof,” 2006.

— — — — —, ASTM A887, “Standard Specification for Borated Stainless Steel Plate, Sheet, and Strip for Nuclear Application,” 2009.

— — — — —, ASTM D975, “Standard Specification for Diesel Fuel Oils,” 2010.

— — — — —, ASTM D3842, “Guide for Selection of Test Methods for Coatings for Use in Light-Water Nuclear Power Plants,” 1991.

— — — — —, ASTM D3911, “Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) Conditions,” 2008.

— — — — —, ASTM D5144, “Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants,” 2000.

— — — — —, ASTM E84, “Standard Test Method for Surface Burning Characteristics of Building Materials,” 2010.

— — — — —, ASTM E119, “Standard Test Methods for Fire Tests of Building Construction and Materials,” 2010.

— — — — —, ASTM E185, “Standard Recommended Practices for Surveillance Tests for Nuclear Reactor Vessels,” 1973.

— — — — —, ASTM E185, “Standard Practice for Conducting Surveillance Tests for Light- Water Cooled Nuclear Power Reactor Vessels,” 1982.

— — — — —, ASTM E741, “Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution,” 2000.

B-16

Bechtel Power Corporation

Bechtel Topical Reports (BC-TOP)

— — — — —, BC-TOP-1, Revision 1, “Containment Building Liner Plate Design Report,” December 1972.

— — — — —, BC-TOP-3-A, Revision 3, “Tornado and Extreme Wind Design Criteria for Nuclear Power Plants,” August 1974.

— — — — —, BC-TOP-4, Revision 3, “Seismic Analyses of Structures and Equipment for Nuclear Power Plants,” September 1974.

— — — — —, BC-TOP-4-A, Revision 3, “Seismic Analyses of Structures and Equipment for Nuclear Power Plants,” November 30, 1974.

— — — — —, BC-TOP-9A, Revision 2, “Design of Structures for Missile Impact,” September 1974.

Electric Power Research Institute (EPRI)

— — — — —, “Advanced Light Water Reactor Utility Requirements Document, Revision 4,” April 1992.

— — — — —, “Advanced Light Water Reactor Utility Requirements Document, Revision 6,” 1997.

— — — — —, “Advanced Light Water Reactor Utility Requirements Document, Volume III, ALWR Passive Plant,” EPRI: Palo Alto, CA: March 1999.

— — — — —, EPRI 1012137, “BWRVIP-41, Revision 1: BWR Vessel and Internals Project: BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines,” August 2005.

— — — — —, BWRVIP-66, “BWR Vessel and Internals Project, Review of Test Data for Irradiated Stainless steel Components,” March 1999.

— — — — —, BWRVIP-130, “BWR Water Chemistry Guidelines,” 2004.

— — — — —, NP-4947-SR, “BWR Hydrogen Water Chemistry Guidelines,” Revised 1987.

— — — — —, NP-5283-SR-A, “Guidelines for Permanent BWR Hydrogen Water Chemistry Installations,” 1985.

— — — — —, NP-5283-SR-A, “Guidelines for Permanent BWR Hydrogen Water Chemistry Installations,” Revised September 1987.

B-17

— — — — —, NP-5380, “Visual Weld Acceptance Criteria,”1987.

— — — — —, NP-6500, “The Effects of Soil-Structure Interaction on Laterally Excited Liquid-Storage Tanks,” September 1989.

— — — — —, NP-6559, “Voice Communication Systems Compatible with Respiratory Protection,” November 1989.

— — — — —, NSAC-60, “A Probabilistic Risk Assessment of Oconee, Unit 3,” June 1984.

— — — — —, NSAC-202L-R2, “Recommendations for an Effective Flow-Accelerated Corrosion Program,” April 8, 1999.

— — — — —, TR-107330, “Generic Requirements Specification for Qualifying a Commercially Available PLC (Programmable Logic Controller) for Safety-Related Applications in Nuclear Power Plants,” approved by the NRC on July 30, 1998.

— — — — —, TR-102323-R1, “Guidelines for Electromagnetic Interference Testing in Power Plants,” approved by the NRC on April 17, 1996.

— — — — —, TR-106439, “Guideline on Evaluation and Acceptance of Commercial - Grade Digital Equipment for Nuclear Safety Applications,” approved by the NRC in April 1997.

GE-Hitachi Nuclear Energy (GEH)

Letters from GEH to NRC

— — — — —, MFN 098-96, Letter from R. Reda, GEH, to R.C. Jones, NRC, “Implementation of Improved GE Steady State Nuclear Methods, PANACEA,” July 2, 1996. (ADAMS Accession Nos. ML070400507, ML083660032.)

— — — — —, MFN 03-086, “Revised Supplementary Information Regarding Amendment 11 to GE Licensing Topical Report NEDE-24011-P-A,” January 16, 1986.

— — — — —, MFN 04-059, Letter from Robert E. Gamble, GE Nuclear Energy, to Document Control Desk, NRC, “Update of ESBWR TRACG Qualification for NEDC-32725P and NEDC-33080P Using the 9-Apr-2004 Program Library Version of TRACG04,” June 2, 2004. (ADAMS Accession Nos. ML041610032, ML041610035, ML041610037.)

— — — — —, MFN 05-096, Letter from D.H. Hinds, GE Energy, to Document Control Desk, NRC, “Summary of September 9, 2005 NRC/GE Conference Call on TRACG LOCA SER Confirmatory Items,” September 20, 2005. (ADAMS Accession No. ML052910378.)

B-18

— — — — —, MFN 05-105, Letter from David H. Hinds, GEH, to Document Control Desk, NRC, “TRACG LOCA SER Confirmatory Items (TAC # MC8168),” October 6, 2005. (ADAMS Accession Nos. ML053140221, ML053140223.)

— — — — —, MFN 05-109, Letter from David H. Hinds, GEH, to Document Control Desk, NRC, “GE Response to Results of NRC Acceptance Review for ESBWR Design Certification Application—Item 2,” October 2005. (ADAMS Accession Nos. ML053000054, ML053000056.)

— — — — —, MFN 05-133, Letter from G. Stramback, GE Energy, to Document Control Desk, NRC, “Response to DSS-CD TRACG LTR RAIs,” November 11, 2005. (ADAMS Accession Nos. ML091740512, ML091740510.)

— — — — —, MFN 06-053, Letter from Hinds, David H., GE, to Document Control Desk, NRC, Subject: “Reply to Notice of Nonconformance NRC Inspection Report 05200010/2005-201, dated January 11, 2006,” February 9, 2006. (ADAMS Accession No. ML060440566.)

— — — — —, MFN 06-053, Supplement 1, Letter from David H. Hinds, GENE, to Document Control Desk, NRC, “NRC Inspection 05200010/2005-201 Unresolved Items,” October 27, 2006. (ADAMS Accession No. ML063170069.)

— — — — —, MFN 06-224, Revision 1, Letter from David H. Hinds, to Document Control Desk, NRC, “Reply to Notice of Nonconformance NRC Inspection Report 05200010/2006-201, dated June 14, 2006- Revision 1,” July 21, 2006. (ADAMS Accession No. ML062070133.)

— — — — —, MFN 06-244, Letter from Hinds, David H. GE, to Document Control Desk, NRC, “Reply to Notice of Nonconformance NRC Inspection Report 05200010/2006-201, dated June 14, 2006—Revision 1,” July 21, 2006. (ADAMS Accession No. ML062070133.)

— — — — —, MFN 06-278, Letter from Letter from D.H. Hinds, GE Energy, to NRC, Document Control Desk, “Revised Seismic Models for the ESBWR Reactor/Fuel Building Complex (RB/FB),” August 22, 2006. (ADAMS Accession No. ML062480460.)

— — — — —, MFN 06-435, Letter from Brown, R. E, GEH, to Document Control Room, NRC, “Commitment to Update GE’s Void Faction Data,” November 3, 2006. (ADAMS Accession No. ML063110299.)

— — — — —, MFN 07-334, Letter from James C. Kinsey, GEH, to Document Control Desk, NRC, “Submittal of ESBWR DCD Chapter 18, Human Factors Engineering—RAI to DCD Roadmap Document,” June 27, 2007. (ADAMS Accession No. ML071920160.)

— — — — —, MFN 07-521, Supplement 1, Letter from Kinsey J.C., GEH, to Document Control Desk, NRC, Transmittal of LTR NEDO-33337, “ESBWR Initial Core Transient Analyses,” October 26, 2007. (ADAMS Accession No. ML073050308.)

— — — — —, MFN 07-612, “Submittal of Licensing Topical Report NEDE-33243P, Revision 2, ‘ESBWR Marathon Control Rod Nuclear Design,’” July 3, 2008. (ADAMS Accession No. ML081980190.)

B-19

— — — — —, MFN 08-218, Letter from Kingston, R.E., GEH, to Document Control Room, NRC, “Request for Withdrawal of GNF Topical Report COBRAG Subchannel Code - Model Descript Report, NEDE-32199P, Revision 1,” March 6, 2008. (ADAMS Accession No. ML080670147.)

— — — — —, MFN 09-210, Letter from R.E. Kingston, GE Hitachi Nuclear Energy, to NRC, Document Control Desk, “Submittal of NEDC-33239P, Revision 4 and NEDO-33239, Revision 4 ‘GE14 for ESBWR Nuclear Design Report,’” March 31, 2009. (ADAMS Accession No. ML090970170.)

— — — — —, MFN 09-139, Letter from Richard E. Kingston, GEH, to, Document Control Desk, NRC, “ESBWR Design Certification Application –– Non-RAI Related Changes for DCD Chapter 16 (Technical Specifications) and Chapter 16B (Bases),” February 24, 2009. (ADAMS Accession No. ML090550395.)

— — — — —, MFN 09-141, Letter from Richard E. Kingston, GEH, to Document Control Desk, NRC, “Request for Exemption from 10 CFR 52.47(a)(8) and 10 CFR 50.34(f)(2)(iv),” March 10, 2009. (ADAMS Accession No. ML090690565.)

— — — — —, MFN 09-194, Letter from Hinds, D.H., GEH, to Document Control Desk, NRC, “Submittal of NEDC-33413P, Revision 2, and NEDO-33413, Revision 2, ‘Full Scale Critical Power Testing of GE14E and Validation of GEXL 14,’” March 2009. (ADAMS Accession No. ML090890021.)

— — — — —, MFN 09-604, Letter from GEH to NRC, “Response to Follow-up Actions from Summary Report of the July 20 to 24, 2009, Regulatory Audit of Design Specifications of Risk Significant ESBWR Components – Additional Information Provided for RAIs 3.2-6, 3.2-63 and 3.9-177,” September 21, 2009. (ADAMS Accession No. ML092650083.)

— — — — —, MFN 09-621, Letter from Richard E. Kingston, GEH, to Document Control Desk, NRC, “Response to NRC Report of August 25, 2009, and September 9, 2009, Regulatory Audit of Reactor Pressure Economic Simplified Boiling Water Reactor,” October 8, 2009. (ADAMS Accession Nos. ML092860174, ML092860175.)

— — — — —, MFN 09-621, Supplement 1, Letter from Richard E. Kingston, GEH, to Document Control Desk, NRC, “Supplemental Response, to NRC Report of August 25, 2009, and September 9, 2009, Regulatory Audit of Reactor Pressure Economic Simplified Boiling Water Reactor,” January 26, 2010. (ADAMS Accession No. ML100280660.)

— — — — —, MFN 09-621, Supplement 2, Letter from Richard E. Kingston, GEH, to Document Control Desk, NRC, “Supplemental Response Number 2, to NRC Report of August 25, 2009, and September 9, 2009, Regulatory Audit of Reactor Pressure Economic Simplified Boiling Water Reactor,” October 8, 2009. (ADAMS Accession No. ML101450336, ML101450337.)

B-20

— — — — —, MFN 09-718, Letter from Richard E. Kingston, GEH, to Document Control Desk, NRC, “Response to Staff Review Questions from Follow-up Actions from Summary Report of the July 20 to 24, 2009, Regulatory Audit of Design Specifications of Risk Significant ESBWR Components – GEH’s Review of Applicability of RG 1.100 R3 to the ESBWR General Valve Specification,” November 12, 2009. (ADAMS Accession No. ML093170020.)

— — — — —, MFN 10-081, Letter from Richard E. Kingston, GEH, to Document Control Desk, NRC, “Request for Addition of ASME Boiler and Pressure Vessel Code Case N-782 to ESBWR DCD,” March 12, 2010. (ADAMS Accession No. ML100710759.)

— — — — —, MFN 10-189, Letter from Richard Kingston, GEH to Document Control Desk, NRC, “Response to Audit Open Items from the Summary of the June 3 and 15, 2010 NRC Regulatory Audits of the ESBWR Spent Fuel Pool Required Water Inventory,” July 8, 2010. (ADAMS Accession No. ML101900082.)

— — — — —, MFN 10-189, Revision 1, Letter from Richard Kingston, GEH to Document Control Desk, NRC, “Revised Response to Audit Open Items from the Summary of the June 3 and 15, 2010 NRC Regulatory Audits of the ESBWR Spent Fuel Pool Required Water Inventory,” September 20, 2010. (ADAMS Accession No. ML102650087.)

— — — — —, MFN 10-189, Revision 2, Letter from Richard Kingston, GEH to Document Control Desk, NRC, “Revised Response (Revision 2) to Audit Open Items from the Summary of the June 3 and 15, 2010 NRC Regulatory Audits of the ESBWR Spent Fuel Pool Required Water Inventory,” October 4, 2010. (ADAMS Accession No. ML102790159.)

— — — — —, MFN 161-92, Letter from P. W. Marriott, GE Nuclear Energy, to Document Control Desk, NRC, “Application for Design Certification of the Simplified Boiling Water Reactor (SBWR),” August 27, 1992.

GE Licensing Topical Reports

— — — — —, NEDC-31336P-A, “General Electric Instrument Setpoint Methodology,” September 1996. (ADAMS Accession No. ML072950103.)

— — — — —, NEDC-31681, “BWR Owner’s Group Improved Technical Specification,” March 1989. (ADAMS Accession No. 8903220001.)

— — — — —, NEDC-31858P, Revision 2, “BWROG Report for Increasing MSIV Leakage Rate Limits and Elimination of Leakage Control Systems,” October 4, 1993. (ADAMS Accession No. 9310140034.)

— — — — —, NEDC-32084P-A, Revision 2, “TASC-03A, A Computer Program for Transient Analysis of a Single Channel,” July 2002. (ADAMS Accession Nos. ML003770790, ML003770794.)

B-21

— — — — —, NEDC-32288P, Revision 1, “Scaling of the SBWR Related Tests,” October 1995. (ADAMS Accession No. 9510170414.)

— — — — —, NEDC-32301P, “MIT and UCB Separate Effects Tests for PCCS Tube Geometry, “Single Tube Condensation Test Program,” March 1994. (ADAMS Accession No. 9403100218.)

— — — — —, NEDC-32505P-A, Revision 1, “R-factor Calculation Method for GE11, GE12, and GE13 Fuel,” July 1999. (ADAMS Accession Nos. ML060520634, ML060520637.)

— — — — —, NEDC-32606P, “SBWR Testing Summary Report,” August 2002. (ADAMS Accession Nos. ML022560102, ML022560530.)

— — — — —, NEDC-32725P, Revision 1, “TRACG Qualification for SBWR,” August 2002. (ADAMS Accession Nos. ML022560081, ML022560558, ML022560559, ML022560076.)

— — — — —, NEDC-32851P, Revision 2, “GEXL14 Correlation for GE14 Fuel,” September 2001. (ADAMS Accession Nos. ML012760516, ML012760513.)

— — — — —, NEDC-32851P-A, Revision 5, “GEXL14 Correlation for GE14 Fuel,” September 2008. (ADAMS Accession Nos. ML082530507, ML082530516, ML072620192, ML072620196.)

— — — — —, NEDC-32975P-A, Revision 0, “Regulatory Relaxation for BWR Loose Parts Monitoring Systems,” February 2001. (ADAMS Accession Nos. ML010510292, ML010510264.)

— — — — —, NEDC–32983P-A, Revision 2, “GE Methodology to Reactor Pressure Vessel Fast Neutron Flux Evaluations,” January 2006. (ADAMS Accession Nos. ML072480112, ML072480125.)

— — — — —, NEDC-33075P, Revision 5, “General Electric Boiling Water Reactor Detect and Suppress Solution—Confirmation Density,” November 2005. (ADAMS Accession Nos. ML053420450, ML053420461.)

— — — — —, NEDC-33075P-A, Revision 6, “General Electric Boiling Water Reactor Detect and Suppress Solution—Confirmation Density,” January 2008. (ADAMS Accession Nos. ML080310384, ML080310402.)

— — — — —, NEDC-33079P, Revision 1, “ESBWR Test and Analysis Program Description,” April 2005. (ADAMS Accession Nos. ML051390223, ML051390233.)

— — — — —, NEDC-33080P, Revision 0, “TRACG Qualification for ESBWR,” August 2002. (ADAMS Accession Nos. ML030090358, ML022610543.)

— — — — —, NEDC-33081P, Revision 1, “ESBWR Test Report,” May 2005. (ADAMS Accession Nos. ML051880441, ML051880444.)

B-22

— — — — —, NEDC-33082P, Revision 1, “ESBWR Scaling Report,” January 2006. (ADAMS Accession Nos. ML060250593, ML060250600, ML060250603.)

— — — — —, NEDC-33082P, Revision 2, “ESBWR Scaling Report,” April 2008. (ADAMS Accession No. ML081260450.)

— — — — —, NEDC-33083P, “TRACG Application for ESBWR,” November 2002. (ADAMS Accession No. ML0232640436.)

— — — — —, NEDC-33083P-A, “TRACG Application for ESBWR,” March 2005. (ADAMS Accession Nos. ML051390257, ML051390265.)

— — — — —, NEDC-33083P-A, Revision 1, “TRACG Application for ESBWR,” October 2010. (ADAMS Accession Nos. ML102800567, ML103050500.)

— — — — —, NEDC-33173P, “Applicability of GE Methods to Expanded Operating Domains,” February 2006. (ADAMS Accession Nos. ML060450677, ML060450690.)

— — — — —, NEDC-33173P, Supplement 1, “Void Fraction Error Based on 10x10 Fuel Pressure Drop Data,” August 2007. (ADAMS Accession Nos. ML072480198, ML072480223.)

— — — — —, NEDC-33197P, “Gamma Thermometer System for LPRM Calibration and Power Shape Monitoring,” September 2005. (ADAMS Accession Nos. ML052700447, ML052700451.)1

— — — — —, NEDC-33237P, “GE14 for ESBWR – Critical Power Correlation, Uncertainty, and OLMCPR Development,” March 2006. (ADAMS Accession Nos. ML060750685, ML060750695.)

— — — — —, NEDC-33237P, Revision 2, “GE for ESBWR – Critical Power Correlation, Uncertainty, and OLMCPR Development,” July 2008. (ADAMS Accession No. ML072841049, ML072841059.)

— — — — —, NEDC-33237P, Revision 4, “GE for ESBWR – Critical Power Correlation, Uncertainty, and OLMCPR Development,” July 2008. (ADAMS Accession No. ML081990252, ML081990208.)

— — — — —, NEDC-33238P, Revision 0, “GE14 Pressure Drop Characteristics,” December 2005. (ADAMS Accession Nos. ML060050328, ML060050330.)

— — — — —, NEDC-33239P, Revision 0, “GE14 for ESBWR Nuclear Design Report,” February 2006. (ADAMS Accession Nos. ML060540343, ML060540345.)

— — — — —, NEDC-33239P, Revision 2, “GE14 for ESBWR Nuclear Design Report,” April 2007. (ADAMS Accession Nos. ML072841049, ML072841058.)

1 Throughout this report, the designation of NEDC-33197P is used interchangeably with the designation of NEDE-33197P. The ADAMS accession numbers provided correspond to NEDE-33197P, as designated by GEH. The non-proprietary version is designated as NEDO-33197 and is publicly available in ADAMS at the accession number provided in the reference list.

B-23

— — — — —, NEDC-33239P, Revision 4, “GE14 for ESBWR Nuclear Design Report,” March 2009. (ADAMS Accession Nos. ML090970170, ML090970169.)

— — — — —, NEDC-33239P-A, Revision 5, “GE14 for ESBWR Nuclear Design Report,” October 2010. (ADAMS Accession Nos. ML102800396, ML102800408, ML102800425.)

— — — — —, NEDC-33240P, Revision 1, “GE14E Fuel Assembly Mechanical Design Report,” February 2009. (ADAMS Accession Nos. ML090700714, ML090700717.)

— — — — —, NEDC-33242P, Revision 2, “GEl4 for ESBWR Fuel Rod Thermal-Mechanical Design Report,” June 2009. (ADAMS Accession Nos. ML091630221, ML091630215.)

— — — — —, NEDC-33326P, Revision 1, “GE 14E for ESBWR Initial Core Nuclear Design Report,” March 2009. (ADAMS Accession Nos. ML090970807, ML090970808, ML090970809.)

— — — — —, NEDC-33373P, Revision 1, “Dynamic, Load-Drop and Thermal-Hydraulic Analysis for ESBWR Fuel Racks,” November 2008. (ADAMS Accession Nos. ML083460457, ML083460456, ML083460458.)

— — — — —, NEDC-33374P, “Safety Analysis Report for Fuel Storage Racks Criticality Analysis for ESBWR Plants,” November 2007. (ADAMS Accession Nos. ML073180180, ML073180187.)

— — — — —, NEDC-33374P, Revision 3, “Safety Analysis Report for Fuel Storage Racks Criticality Analysis for ESBWR Plants,” December 2009. (ADAMS Accession Nos. ML093421411, ML093421412.)

— — — — —, NEDC-33374P-A, Revision 4, “Safety Analysis Report for Fuel Storage Racks Criticality Analysis for ESBWR Plants,” September 2010. (ADAMS Accession Nos. ML102860677, ML102860688.)

— — — — —, NEDC-33408P, Revision 0, “ESBWR Steam Dryer – Plant Based Load Evaluation Methodology,” February 2008. (ADAMS Accession Nos. ML080630413, ML080630234.)

— — — — —, NEDC-33408P, Revision 1, “ESBWR Steam Dryer – Plant Based Load Evaluation Methodology,” July 2009. (ADAMS Accession Nos. ML092190422, ML092190392.)

— — — — —, NEDC-33408P, Supplement 1, Revision 0, “ESBWR Steam Dryer – Plant Based Load Evaluation Methodology,” October 2008. (ADAMS Accession Nos. ML083050333, ML083050341, ML083050342.)

— — — — —, NEDC-33408P, Supplement 1, Revision 1, “ESBWR Steam Dryer – Plant Based Load Evaluation Methodology,” August 2009. (ADAMS Accession Nos. ML092460354, ML092460352, ML092460353, ML092460350.)

B-24

— — — — —, NEDC-33413P, Revision 0, “Full Scale Critical Power Testing of GE14E and Validation of GEXL14,” March 2008. (ADAMS Accession Nos. ML080990671, ML080990618.)

— — — — —, NEDC-33413P, Revision 2, “Full Scale Critical Power Testing of GE14E and Validation of GEXL14,” March 2009. (ADAMS Accession Nos. ML090890021, ML090890022.)

— — — — —, NEDC-33456P, “Full-Scale Pressure Drop Testing for a Simulated GE14E Fuel Bundle,” March 2009. (ADAMS Accession Nos. ML090920888, ML090920868.)

— — — — —, NEDE-11146, “Pressure Integrity Design Basis for New Gas Systems,” July 1971. (ADAMS Accession No. ML092260729.)

— — — — —, NEDE-24011-P-A, “GESTAR II—Implementing Improved GE Steady-State Methods (TAC No. MA6481),” November 1999. (ADAMS Accession No. ML993230184.)

— — — — —, NEDE-24011-P-A-16, Revision 16, Global Nuclear Fuel, “GESTAR II General Electric Standard Application for Reactor Fuel,” October 2007. (ADAMS Accession Nos. ML091340075, ML091340077, ML091340081.)

— — — — —, NEDE-24011-P-AUS-16, Revision 16, Global Nuclear Fuel, “GESTAR II General Electric Standard Application for Reactor Fuel, Supplement for United States,” October 2007. (ADAMS Accession Nos. ML091340075, ML091340080, ML091340082.)

— — — — —, NEDE-24154-P-A, Volume 3, “Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors,” August 1986. (ADAMS Accession No. ML102290145.)2

— — — — —, NEDE-24326-1-P, “General Electric Environmental Qualification Program,” January 1983. (ADAMS Accession Nos. 8302280264, ML053140250.)

— — — — —, NEDE-30130P-A, “Steady State Nuclear Methods,” April 1985. (ADAMS Accession No. ML070400570.)

— — — — —, NEDE-32176P, Revision 2, “TRACG Model Description,” December 1999. (ADAMS Accession Nos. ML993630096, ML993630283.)

— — — — —, NEDE-32176P, Revision 3, “TRACG Model Description,” April 2006. (ADAMS Accession Nos. ML061160236, ML061160238.)

— — — — —, NEDE-32176P, Revision 4, “TRACG Model Description,” January 2008. (ADAMS Accession Nos. ML080370259, ML080370276.)

— — — — —, NEDE-32177P, Revision 2, “TRACG Qualification,” January 2000. (ADAMS Accession Nos. ML003682751, ML003683162.)

2 The August 1988 date in the text is based on the response to RAI 6.2-64. The actual date of the report, August 1986, is listed here.

B-25

— — — — —, NEDE-32177P, Revision 3, “TRACG Qualification,” August 2007. (ADAMS Accession Nos. ML072480007, ML072480083, ML072480089.)

— — — — —, NEDE-32906P, Revision 2, “TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analysis,” February 28, 2006. (ADAMS Accession Nos. ML060530560, ML060530571, ML060530566.)

— — — — —, NEDE-32906P, Supplement 3, “Migration to TRACG04/PANAC11 from TRACG02/PANAC10 for TRACG AOO and ATWS Overpressure Transients,” May 2006. (ADAMS Accession Nos. ML061500184, ML061500185, ML061500186.)

— — — — —, NEDE-33083P, Supplement 1, “TRACG Application for ESBWR Stability,” December 2004. (ADAMS Accession Nos. ML0500601602, ML050060161.)

— — — — —, NEDE-33083P, Supplement 2, “TRACG Application for ESBWR Anticipated Transient Without Scram Analyses,” January 2006. (ADAMS Accession Nos.ML060190536, ML060190538, ML060190592.)

— — — — —, NEDE-33083P, Supplement 2, Revision 2, “TRACG Application for ESBWR Anticipated Transient Without Scram Analyses,” September 2009. (ADAMS Accession Nos. ML092750616, ML092750617, ML092750618.)

— — — — —, NEDE-33083P, Supplement 3, “TRACG Application for ESBWR Transient Analysis,” December 2007. (ADAMS Accession Nos. ML080020104, ML080020179, ML080020184.)

— — — — —, NEDE-33083P-A, Supplement 1, Revision1, “TRACG Application for ESBWR Stability,” January 2008. (ADAMS Accession Nos. ML080310454, ML080310464, ML080310470, ML080310476.)

— — — — —, NEDE-33083P-A, Supplement 1, Revision 2, “TRACG Application for ESBWR Stability,” September 2010. (ADAMS Accession Nos. ML102770546, ML102770552, ML102770550.)

— — — — —, NEDE-33083P-A, Supplement 2, Revision 2, “TRACG Application for ESBWR Anticipated Transient Without Scram Analyses,” October 2010. (ADAMS Accession Nos. ML103000359, ML103000355.)

— — — — —, NEDE-33083P-A, Supplement 3, Revision 1, “TRACG Application for ESBWR Transient Analysis,” September 2010. (ADAMS Accession Nos. ML102770610, ML102770608.)

— — — — —, NEDE-33197P, Revision 2, “Gamma Thermometer System for LPRM Calibration and Power Shape Monitoring,” August 2008. (ADAMS Accession Nos. ML082460979, ML102810320, ML102810341.)

— — — — —, NEDE-33197P-A, Revision 3 “Gamma Thermometer System for LPRM Calibration and Power Shape Monitoring,“ October 2010. (ADAMS Accession Nos. ML102810295, ML102810341.)

B-26

— — — — —, NEDE-33217P, Revision 3, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan (MMIS-HFE Plan),” July 2007. (ADAMS Accession Nos. ML072120422, ML072120424, ML072130096, ML072130099, ML072130100.)

— — — — —, NEDE-33217P, Revision 4, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan (MMIS-HFE Plan),” May 2008. (ADAMS Accession Nos. ML081970496, ML081970495.)

— — — — —, NEDE-33217P, Revision 6, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan (MMIS-HFE Plan),” February 2010. (ADAMS Accession Nos. ML100480522, ML100480285.)

— — — — —, NEDE-33220P, Revision 4, “ESBWR Human Factors Engineering Allocation of Function Implementation Plan,” February 2010. (ADAMS Accession Nos. ML100480208, ML100480209, ML100480202.)

— — — — —, NEDE-33221P, Revision 4, “ESBWR Human Factors Engineering Task Analysis Implementation Plan,” February 2010. (ADAMS Accession Nos. ML100480217, ML100480213.)

— — — — —, NEDE-33226P, Revision 2, “ESBWR I&C Software Management Plan,” July 2007. (ADAMS Accession Nos. ML072120422, ML072120425, ML072130102, ML072130104.)

— — — — —, NEDE-33226P, Revision 4, “ESBWR Software Management Program Manual,” May 2009. (ADAMS Accession Nos. ML091530168, ML091530167.)

— — — — —, NEDE-33226P, Revision 5, “ESBWR Software Management Program Manual,” February 2010. (ADAMS Accession Nos. ML100550851, ML100550844.)

— — — — —, NEDE-33243P, Revision 2, “ESBWR Control Rod Nuclear Design,” July 2008. (ADAMS Accession Nos. ML081980189, ML081980190, ML081980192.)

— — — — —, NEDE-33244P, Revision 1, “ESBWR Marathon Control Rod Mechanical Design Report,” November 2007. (ADAMS Accession Nos. ML073240185, ML073240227.)

— — — — —, NEDE-33245P, Revision 4, “ESBWR Software Quality Assurance Program Manual,” July 2009. (ADAMS Accession Nos. ML092160859, ML092160862.)

— — — — —, NEDE-33245P, Revision 5, “ESBWR Software Quality Assurance Program Manual,” February 2010. (ADAMS Accession Nos. ML100550851, ML100550847.)

— — — — —, NEDE-33259P, Revision 0, “ESBWR Reactor Internals Flow Induced Vibration Program – Part 1,” January 2006. (ADAMS Accession Nos. ML060180317, ML060180318.)

— — — — —, NEDE-33259P, Revision 1, “Reactor Internals Flow Induced Vibration Program,” December 2007. (ADAMS Accession Nos. ML073460623, ML073460650.)

B-27

— — — — —, NEDE-33259P, Revision 2, “Reactor Internals Flow Induced Vibration Program,” June 2009. (ADAMS Accession Nos. ML091660433, ML091660434, ML091660432.)

— — — — —, NEDE-33261P, Revision 0, “ESBWR Containment Load Definition,” May 2006. (ADAMS Accession Nos. ML061430332, ML061430337.)

— — — — —, NEDE-33261P, Revision 1, “ESBWR Containment Load Definition,” October 2007. (ADAMS Accession Nos. ML073180193, ML073180200, ML073180205.)

— — — — —, NEDE-33261P, Revision 2, “ESBWR Containment Load Definition,” June 2008. (ADAMS Accession Nos. ML082600719, ML082600720, ML082600721.)

— — — — —, NEDE-33268P, Revision 4, “ESBWR Human Factors Engineering Human-System Interface Design Implementation Plan,” May 2009. (ADAMS Accession Nos. ML091480378, ML091480381.)

— — — — —, NEDE-33268P, Revision 5, “ESBWR Human Factors Engineering Human-System Interface Design Implementation Plan,” February 2010. (ADAMS Accession Nos. ML100480178, ML100480179, ML100480180.)

— — — — —, NEDE-33271P, “NP-2010 COL Demonstration Project: Project Design Manual (PDM.),” January 2009. (ADAMS Accession Nos. ML090300133, ML090300134.)

— — — — —, NEDE-33276P, Revision 2, “ESBWR HFE Verification and Validation Implementation Plan,” May 2008. (ADAMS Accession Nos. ML081820297, ML081820346.)

— — — — —, NEDE-33276P, Revision 3, “ESBWR HFE Verification and Validation Implementation Plan,” July 2009. (ADAMS Accession Nos. ML091980184, ML091980183.)

— — — — —, NEDE-33276P, Revision 4, “ESBWR HFE Verification and Validation Implementation Plan,” February 2010. (ADAMS Accession Nos. ML100480176, ML100480183.)

— — — — —, NEDE-33279P, “ESBWR Containment Fission Product Removal Evaluation Model,” October 2006. (ADAMS Accession Nos. ML063060039, ML063060043.)

— — — — —, NEDE-33279P, Revision 2, “ESBWR Containment Fission Product Removal Evaluation Model,” July 2008. (ADAMS Accession Nos. ML081960497, ML081960491.)

— — — — —, NEDE-33295P, Revision 0, “ESBWR Cyber Security Program Plan,” October 2007. (ADAMS Accession Nos. ML073120433, ML073120499.)

— — — — —, NEDE-33295P, Revision 1, "ESBWR Cyber Security Program Plan," July 2009. (ADAMS Accession Nos. ML092220329, ML092250329, ML092220330.)

B-28

— — — — —, NEDE-33295P, Revision 2, "ESBWR Cyber Security Program Plan," September 2010. (ADAMS Accession Nos. ML102880100, ML102880104.)

— — — — —, NEDE-33304P, Revision 0, “GEH ABWR/ESBWR Setpoint Methodology,” October 2007. (ADAMS Accession Nos. ML073060147, ML073060148, ML073060154.)

— — — — —, NEDE-33304P, Revision 1, “GEH ABWR/ESBWR Setpoint Methodology,” November 2008. (ADAMS Accession Nos. ML083330297, ML083330298.)

— — — — —, NEDE–33304P, Revision 2, “GEH ESBWR Setpoint Methodology,” December 2009. (ADAMS Accession Nos. ML093500102, ML093500100.)

— — — — —, NEDE–33304P, Revision 3, “GEH ESBWR Setpoint Methodology,” February 2010. (ADAMS Accession Nos. ML100500498, ML100500499, ML100500500.)

— — — — —, NEDE-33304P, Revision 4, "GEH ESBWR Setpoint Methodology," May 2010. (ADAMS Accession Nos. ML101450250, ML101450251, ML101450253.)

— — — — —, NEDE-33312P, Revision 0, “ESBWR Steam Dryer Acoustic Load Definition,” November 2007. (ADAMS Accession Nos. ML073240102, ML073240128.)

— — — — —, NEDE-33312P, Revision 1, “ESBWR Steam Dryer Acoustic Load Definition,” July 2009. (ADAMS Accession Nos. ML092170657, ML092170607.)

— — — — —, NEDE-33313P, Revision 0, “ESBWR Steam Dryer Structural Evaluation,” November 2007. (ADAMS Accession Nos. ML073240156, ML073240214.)

— — — — —, NEDE-33313P, Revision 1, “ESBWR Steam Dryer Structural Evaluation,” July 2009. (ADAMS Accession No. ML092170644, ML092170583.)

— — — — —, NEDE-33313P-A, Revision 2, “ESBWR Steam Dryer Structural Evaluation,” October 2010. (ADAMS Accession Nos. ML102910269, ML102910306.)

— — — — —, NEDE-33386, Revision 1, “ESBWR Plant Flood Zone Definition Drawings and Other PRA Support Information,” May 2009. (ADAMS Accession Nos. ML092080075, ML092080090.)

— — — — —, NEDE-33440P, Revision 0, “ESBWR Safety Analysis—Additional Information,” March 2009. (ADAMS Accession Nos. ML090960676, ML090960677, ML090960678, ML090960679.)

— — — — —, NEDE-33440P, Revision 1, “ESBWR Safety Analysis—Additional Information,” June 2009. (ADAMS Accession Nos. ML091830294, ML091830295, ML091830297, ML091830298.)

— — — — —, NEDE-33440P, Revision 2, “ESBWR Safety Analysis – Additional Information,” March 2010. (ADAMS Accession Nos. ML100920310, ML100920317, ML100920318.)

B-29

— — — — —, NEDE-33516P, Revision 0, “ESBWR Qualification Plan Requirements for a 72-Hour Duty Cycle Battery,” July 2009. (ADAMS Accession Nos. ML092100227, ML092100217.)

— — — — —, NEDE-33516P, Revision 2, “ESBWR Qualification Plan Requirements for a 72-Hour Duty Cycle Battery,” December 2009. (ADAMS Accession Nos. ML093491006, ML093491007.)

— — — — —, NEDE-33536P, Revision 0, “Control Building and Reactor Building Environmental Temperature Analysis for ESBWR,” December 2009. (ADAMS Accession Nos. ML093570229, ML093570230, ML093570231.)

— — — — —, NEDE-33536P, Revision 1, “Control Building and Reactor Building Environmental Temperature Analysis for ESBWR,” October 2010. (ADAMS Accession Nos. ML102780327, ML102780330.)

— — — — —, NEDE-33564P, “Leakage Detection Instrumentation Confirmatory Test for the ESBWR Wetwell-Drywell Vacuum Breakers,” March 2010. (ADAMS Accession Nos. ML100890163, ML100890162.)

— — — — —, NEDE-33572P, Revision 0, “ESBWR PCCS Condenser Structural Evaluation,” March 2010. (ADAMS Accession Nos. ML100840087, ML100840092.)

— — — — —, NEDE-33572P, Revision 1, “ESBWR ICS and PCCS Condenser Combustible Gas Mitigation and Structural Evaluation,” May 2010. (ADAMS Accession Nos. ML101450381, ML101450382, ML101450389.)

— — — — —, NEDE-33572P, Revision 2, “ESBWR ICS and PCCS Condenser Combustible Gas Mitigation and Structural Evaluation,” August 2010. (ADAMS Accession Nos. ML102670082, ML102670083, ML102670086.)

— — — — —, NEDE-33572P, Revision 3, “ESBWR ICS and PCCS Condenser Combustible Gas Mitigation and Structural Evaluation,” September 2010. (ADAMS Accession Nos. ML102740580, ML102740566.)

— — — — —, NEDO-10871, “Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms,” March 1973. (ADAMS Accession No. ML110480056.)

— — — — —, NEDO-10958-A, “General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application,” January 1977. (ADAMS Accession No. ML102290144.)

— — — — —, NEDO-11209-04a, Revision 8, “GE Nuclear Energy Quality Assurance Program Description,” March 31, 1989.

— — — — —, NEDO-21159, “Airborne Releases from BWRs for Environmental Impact Evaluations,” March 1976. (ADAMS Accession Nos. ML110480064, ML110480067.)

B-30

— — — — —, NEDO-24011-A-16, Revision 16, “General Electric Standard Application Reactor Fuel (GESTAR II),” October 2007. (ADAMS Accession Nos. ML091340075, ML091340077.)

— — — — —, NEDO-24011-A-US-16, Revision 16, “General Electric Standard Application for Reactor Fuel (GESTAR II) (Supplement for United States),” October 2007. (ADAMS Accession Nos. ML091340075, ML091340080.)

— — — — —, NEDO-24154-A, Volume 1, “Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors,” August 31, 1986. (ADAMS Accession No. ML062690107.)

— — — — —, NEDO-24154-A, Volume 2, “Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors,” August 31, 1986. (ADAMS Accession No. ML062640349.)

— — — — —, NEDO-24222, “Assessment of BWR Mitigation of Anticipated Transients Without Scram,” December 1979. (ADAMS Accession No. ML093451460.)

— — — — —, NEDO-31960, “Long-Term Stability Solutions Licensing Methodology,” May 31, 1991. (ADAMS Accession No. ML072260045.)

— — — — —, NEDO-32047-A, “Mitigation of BWR Core Thermal-Hydraulic Instabilities in ATWS,” June 1995. (ADAMS Accession No. ML091760804.)

— — — — —, NEDO-32164, “Mitigation of BWR Core Thermal-Hydraulic Instabilities in ATWS,” December 1992. (ADAMS Accession No. ML102350204.)

— — — — —, NEDO-32291-A, “System Analyses for the Elimination of Selected Response Time Testing Requirements,” October 1995. (ADAMS Accession Nos. 9401180017, 9501200097.)

— — — — —, NEDO-32291-A, Supplement 1, “System Analyses for the Elimination of Selected Response Time Testing Requirements,” October 1999. (ADAMS Accession Nos. 9712180018, 9906160142.)

— — — — —, NEDO-32983-A, Revision 0, “General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluations,” December 2001. (ADAMS Accession No. ML020090698.)

— — — — —, NEDO-32983-A, Revision 2, “General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluations,” January 2006. (ADAMS Accession Nos. ML072480112, ML072480121.)

— — — — —, NEDO-32991-A, Revision 0, “Regulatory Relaxation for BWR Post-Accident Sampling Stations (PASS),” August 10, 2001. (ADAMS Accession Nos. ML012260107, ML012260048.)

— — — — —, NEDO-33083, Supplement 2, Revision 2, “TRACG Application for ESBWR Anticipated Transients Without Scram,” September 2009. (ADAMS Accession No. ML092750624.)

B-31

— — — — —, NEDO-33173, “Applicability of GE Methods to Expanded Operating Domains,” February 2006. (ADAMS Accession No. ML060720281.)

— — — — —, NEDO-33175, Revision 1, E&A No. 1, “Classification of ESBWR Abnormal Events and Determination of Their Safety Analysis Acceptance Criteria,” February 2005. (ADAMS Accession No. ML050630387.)

— — — — —, NEDO-33181, Revision 1, “NP-2010 COL Demonstration Project Quality Assurance Plan,” October 2005. (ADAMS Accession No. ML053430022.)

— — — — —, NEDO-33181, Revision 2, “NP-2010 COL Demonstration Project Quality Assurance Plan,” July 2006. (ADAMS Accession Nos. ML063450233, ML063450235.)

— — — — —, NEDO-33181, Revision 5, “NP-2010 COL Demonstration Project Quality Assurance Plan,” February 2008. (ADAMS Accession No. ML081210569.)

— — — — —, NEDO-33181, Revision 6, “NP-2010 COL Demonstration Project Quality Assurance Program,” August 2009. (ADAMS Accession No. ML100110150.)

— — — — —, NEDO-33197, Revision 2, “Gamma Thermometer System for LPRM Calibration and Power Shape Monitoring,” August 2008. (ADAMS Accession No. ML082460979.)

— — — — —, NEDO-33201, Revision 1, “ESBWR Certification Probabilistic Risk Assessment,” September 2006. (ADAMS Accession No. ML063310371.)

— — — — —, NEDO-33201, Revision 2, "ESBWR Design Certification Probabilistic Risk Assessment," September 2007. (ADAMS Accession No. ML081210271.)

— — — — —, NEDO-33201, Revision 3, “ESBWR Certification Probabilistic Risk Assessment,” May 2008. (ADAMS Accession No. ML081920299.)

— — — — —, NEDO-33201, Revision 4, “ESBWR Certification Probabilistic Risk Assessment,” June 2009. (ADAMS Accession No. ML092030211.)

— — — — —, NEDO-33201, Revision 5, “ESBWR Certification Probabilistic Risk Assessment,” February 2010. (ADAMS Accession No. ML100740286.)

— — — — —, NEDO-33201, Revision 6, “ESBWR Certification Probabilistic Risk Assessment,” October 2010. (ADAMS Accession No. ML102880536.)

— — — — —, NEDO-33217, Revision 3, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan (MMIS-HFE Plan),” July 2007. (ADAMS Accession Nos. ML072120422, ML072120424.)

— — — — —, NEDO-33217, Revision 4, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan (MMIS-HFE Plan),” May 2008. (ADAMS Accession No. ML081970496.)

B-32

— — — — —, NEDO-33217, Revision 6, “ESBWR Man-Machine Interface System and Human Factors Engineering Implementation Plan (MMIS-HFE Plan),” February 2010. (ADAMS Accession No. ML100480522.)

— — — — —, NEDO-33219, Revision 0, “ESBWR System Functional Requirements Analysis Implementation Plan,” January 2006. (ADAMS Accession No. ML060340055.)

— — — — —, NEDO-33219, Revision 1, “ESBWR System Functional Requirements Analysis Implementation Plan,” January 2007. (ADAMS Accession No. ML070440051.)

— — — — —, NEDO-33219, Revision 2, “ESBWR Human Factors Engineering Functional Requirements Analysis Implementation Plan,” May 2008. (ADAMS Accession No. ML081620099.)

— — — — —, NEDO-33219, Revision 3, “ESBWR Human Factors Engineering Functional Requirements Analysis Implementation Plan,” April 2009. (ADAMS Accession No. ML090930507.)

— — — — —, NEDO-33219, Revision 4, “ESBWR Human Factors Engineering Functional Requirements Analysis Implementation Plan,” February 2010. (ADAMS Accession No. ML100350104.)

— — — — —, NEDO-33220, Revision 0, “ESBWR Allocation of Function Implementation Plan,” January 2006. (ADAMS Accession No. ML060340058.)

— — — — —, NEDO-33220, Revision 1, “ESBWR Human Factors Engineering Allocation of Function,” March 2007. (ADAMS Accession No. ML071020070.)

— — — — —, NEDO-33220, Revision 2, “ESBWR Human Factors Engineering Allocation of Function Implementation Plan,” May 2008. (ADAMS Accession No. ML081640208.)

— — — — —, NEDO-33220, Revision 3, “ESBWR Human Factors Engineering Allocation of Function Implementation Plan,” May 2009. (ADAMS Accession Nos. ML091410704, ML091410705.)

— — — — —, NEDO-33220, Revision 4, “ESBWR Human Factors Engineering Allocation of Function Implementation Plan,” February 2010. (ADAMS Accession Nos. ML100480208, ML100480209.)

— — — — —, NEDO-33221, Revision 1, “ESBWR Human Factors Engineering Task Analysis Implementation Plan,” March 2007. (ADAMS Accession No. ML070811022.)

— — — — —, NEDO-33221, Revision 4, “ESBWR Human Factors Engineering Task Analysis Implementation Plan,” February 2010. (ADAMS Accession No. ML100480217.)

— — — — —, NEDO-33237, Revision 2, “GE14 for ESBWR - Critical Power Correlation, Uncertainty, and OLMCPR Development,” April 2007. (ADAMS Accession Nos. ML072841052, ML072841056.)

B-33

— — — — —, NEDO-33239, Revision 4, “GE14 for ESBWR Nuclear Design Report,” March 2009. (ADAMS Accession No. ML090970170.)

— — — — —, NEDO-33242, “GE14 for ESBWR Fuel Rod Thermal Mechanical Design Report,” January 2006. (ADAMS Accession No. ML060370028.)

— — — — —, NEDO-33242, Revision 1, “GE14 for ESBWR Fuel Rod Thermal--Mechanical Design Report,” February 2007. (ADAMS Accession Nos. ML070870595, ML070870596.)

— — — — —, NEDO-33242, Revision 2, “GE14 for ESBWR Fuel Rod Thermal--Mechanical Design Report,” June 2009. (ADAMS Accession No. ML091630221.)

— — — — —, NEDO-33243, Revision 2, “ESBWR Control Rod Nuclear Design,” July 2008. (ADAMS Accession Nos. ML081980189, ML081980190.)

— — — — —, NEDO-33244, Revision 1, “ESBWR Marathon Control Rod Mechanical Design Report,” November 2007. (ADAMS Accession No. ML073240185.)

— — — — —, NEDO-33245, Revision 4, “ESBWR Software Quality Assurance Program Manual,” July 2009. (ADAMS Accession No. ML092160859.)

— — — — —, NEDO-33245, Revision 5, “ESBWR Software Quality Assurance Program Manual,” February 2010. (ADAMS Accession No. ML100550851.)

— — — — —, NEDO-33251, Revision 0, “ESBWR I&C Defense-in-Depth and Diversity Report,” July 2006. (ADAMS Accession No. ML062160171.)

— — — — —, NEDO-33251, Revision 1, “ESBWR I&C Defense-in-Depth and Diversity Report,” August 2007. (ADAMS Accession No. ML073480040.)

— — — — —, NEDO-33251, Revision 2, “ESBWR I&C Defense-in-Depth and Diversity Report,” June 2009. (ADAMS Accession No. ML091610601.)

— — — — —, NEDO-33251, Revision 3, “ESBWR I&C Defense-in-Depth and Diversity Report,” October 2010. (ADAMS Accession No. ML102860763.)

— — — — —, NEDO-33259P, Revision 0, “ESBWR Reactor Internals Flow Induced Vibration Program – Part 1,” January 2006. (ADAMS Accession No. ML060180317.)

— — — — —, NEDO-33259P, Revision 1, “Reactor Internals Flow Induced Vibration Program,” December 2007. (ADAMS Accession No. ML073460623.)

— — — — —, NEDO-33259P, Revision 2, “Reactor Internals Flow Induced Vibration Program,” June 2009. (ADAMS Accession Nos. ML091660433, ML091660434.)

— — — — —, NEDO-33261, Revision 0, “ESBWR Containment Load Definition,” May 2006. (ADAMS Accession No. ML061430332.)

— — — — —, NEDO-33261, Revision 1, “ESBWR Containment Load Definition,” October 2007. (ADAMS Accession Nos. ML073180193, ML073180200.)

B-34

— — — — —, NEDO-33261 Revision 2, “ESBWR Containment Load Definition,” June 2008. (ADAMS Accession No. ML082600719, ML082600720.)

— — — — —, NEDO-33262, Revision 3, “ESBWR Human Factors Engineering Operating Experience Review Implementation Plan,” January 2010. (ADAMS Accession No. ML100340030.)

— — — — —, NEDO-33266, Revision 1, “ESBWR Human Factors Engineering Staffing and Qualifications Implementation Plan,” January 2007. (ADAMS Accession No. ML070440053.)

— — — — —, NEDO-33266, Revision 3, “ESBWR Human Factors Engineering Staffing and Qualifications Implementation Plan,” January 2010. (ADAMS Accession No. ML100350167.)

— — — — —, NEDO-33267, Revision 3, “ESBWR Human Factors Engineering Human Reliability Analysis Implementation Plan,” May 2008. (ADAMS Accession No. ML081620281.)

— — — — —, NEDO-33267, Revision 4, “ESBWR Human Factors Engineering Human Reliability Analysis Implementation Plan,” January 2010. (ADAMS Accession No. ML100330609.)

— — — — —, NEDO-33268, Revision 0, “ESBWR Human-System Interface Design Implementation Plan,” March 2006. (ADAMS Accession No. ML060950481.)

— — — — —, NEDO-33268, Revision 2, “ESBWR Human-System Interface Design Implementation Plan,” March 2007. (ADAMS Accession No. ML071020070.)

— — — — —, NEDO-33268, Revision 3, “ESBWR Human Factors Engineering Human-System Interface Design Implementation Plan,” May 2008. (ADAMS Accession No. ML081640490.)

— — — — —, NEDO-33268, Revision 4, “ESBWR Human Factors Engineering Human-System Interface Design Implementation Plan,” May 2009. (ADAMS Accession No. ML091480378.)

— — — — —, NEDO-33268, Revision 5, “ESBWR Human-System Interface Design Implementation Plan,” February 2010. (ADAMS Accession Nos. ML100480178, ML100480179.)

— — — — —, NEDO-33274, Revision 2, “ESBWR Human Factors Engineering Procedures Development Implementation Plan,” March 2007. (ADAMS Accession Nos. ML070810993, ML070811048.)

— — — — —, NEDO-33274, Revision 5, “ESBWR Human Factors Engineering Procedures Development Implementation Plan,” February 2010. (ADAMS Accession No. ML100480550.)

B-35

— — — — —, NEDO-33275, Revision 4, “ESBWR Human Factors Engineering Training Development Implementation Plan,” January 2010. (ADAMS Accession No. ML100330718.)

— — — — —, NEDO-33276, Revision 0, “ESBWR HFE Verification and Validation Implementation Plan,” May 2006. (ADAMS Accession No. ML061670143.)

— — — — —, NEDO-33276, Revision 1, “ESBWR HFE Verification and Validation Implementation Plan,” March 2007. (ADAMS Accession No. ML071020070.)

— — — — —, NEDO-33276, Revision 2, “ESBWR HFE Verification and Validation Implementation Plan,” May 2008. (ADAMS Accession No. ML081820297.)

— — — — —, NEDO-33276, Revision 3, “ESBWR HFE Verification and Validation Implementation Plan,” July 2009. (ADAMS Accession No. ML091980184.)

— — — — —, NEDO-33276, Revision 4, “ESBWR HFE Verification and Validation Implementation Plan,” February 2010. (ADAMS Accession No. ML100480176.)

— — — — —, NEDO-33277, Revision 4, “ESBWR Human Factors Engineering Human Performance Monitoring Implementation Plan,” January 2010. (ADAMS Accession No. ML100270770.)

— — — — —, NEDO-33278, Revision 2, “ESBWR Human Factors Engineering Design Implementation Plan,” January 2007. (ADAMS Accession No. ML070440054.)

— — — — —, NEDO-33278, Revision 3, “ESBWR Human Factors Engineering Design Implementation Plan,” May 2008. (ADAMS Accession No. ML081620089.)

— — — — —, NEDO-33278, Revision 4, “ESBWR Human Factors Engineering Design Implementation Plan,” January 2010. (ADAMS Accession No. ML100270468.)

— — — — —, NEDO-33289, Revision 2, “ESBWR Reliability Assurance Program,” September 2008. (ADAMS Accession No. ML100110150.)

— — — — —, NEDO-33295, Revision 0, “ESBWR Cyber Security Program Plan,” October 2007. (ADAMS Accession No. ML073120433.)

— — — — —, NEDO-33295, Revision 1, “ESBWR Cyber Security Program Plan,” July 2009. (ADAMS Accession Nos. ML092220329, ML092250329.)

— — — — —, NEDO-33295, Revision 2, "ESBWR Cyber Security Program Plan," September 2010. (ADAMS Accession Nos. ML102880100.)

— — — — —, NEDO-33304, “ESBWR Setpoint Methodology,” October 2007. (ADAMS Accession Nos. ML073060147, ML073060148.)

— — — — —, NEDO-33304, Revision 1, “GEH ABWR/ESBWR Setpoint Methodology,” November2008. (ADAMS Accession No. ML083330297.)

— — — — —, NEDO-33304, Revision 4, "GEH ESBWR Setpoint Methodology," May 2010. (ADAMS Accession Nos. ML101450250, ML101450251.)

B-36

— — — — —, NEDO-33306, Revision 4, “ESBWR Severe Accident Mitigation Design Alternatives,” October 2010. (ADAMS Accession No. ML102990433.)

— — — — —, NEDO-33312, Revision 0, “ESBWR Steam Dryer Acoustic Load Definition,” November 2007. (ADAMS Accession Nos. ML073240102.)

— — — — —, NEDO-33312, Revision 1, “ESBWR Steam Dryer Acoustic Load Definition,” July 2009. (ADAMS Accession No. ML092170657.)

— — — — —, NEDO-33313, Revision 0, “ESBWR Steam Dryer Structural Evaluation,” November 2007. (ADAMS Accession No. ML073240156.)

— — — — —, NEDO-33326, Revision 1, “GE14E for ESBWR Initial Core Design Nuclear Report,” March 2009. (ADAMS Accession Nos. ML090970807, ML090970808.)

— — — — —, NEDO-33337, Revision 0, “ESBWR Initial Core Transient Analysis,” October 2007. (ADAMS Accession No. ML073050308.)

— — — — —, NEDO-33337, Revision 1, “ESBWR Initial Core Transient Analyses,” April 2009. (ADAMS Accession No. ML091130560.)

— — — — —, NEDO-33338, Revision 0, “ESBWR Feedwater Temperature Operating Domain Transient and Accident Analysis,” October 2007. (ADAMS Accession No. ML073050481.)

— — — — —, NEDO-33338, Revision 1, “ESBWR Feedwater Temperature Operating Domain Transient and Accident Analysis,” May 2009. (ADAMS Accession No. ML091380173.)

— — — — —, NEDO-33373, Revision 4, “Dynamic, Load-Drop, and Thermal-Hydraulic Analyses for ESBWR Fuel Racks,” March 2010. (ADAMS Accession No. ML100820399.)

— — — — —, NEDO-33386, Revision 1, “ESBWR Plant Flood Zone Definition Drawings and Other PRA Support Information,” May 2009. (ADAMS Accession Nos. ML092080075.)

— — — — —, NEDO-33392, Revision 0, “The MAC Experiments Fine Tuning of the BIMAC Design,” March 2008. (ADAMS Accession No. ML080980360.)

— — — — —, NEDO-33408, Revision 1, “ESBWR Steam Dryer – Plant Based Load Evaluation Methodology,” July 2009. (ADAMS Accession Nos. ML092190393, ML092190394.)

— — — — —, NEDO-33408, Supplement 1, Revision 1, “ESBWR Steam Dryer – Plant Based Load Evaluation Methodology,” August 2009. (ADAMS Accession No. ML092460350.)

— — — — —, NEDO-33411, Revision 0, “Risk Significance of Structures, Systems, and Components for the Design Phase of the ESBWR,” March 2008. (ADAMS Accession No. ML080880316.)

B-37

— — — — —, NEDO-33411, Revision 1, “Risk Significance of Structures, Systems and Components for the Design Phase of the ESBWR,” July 2009. (ADAMS Accession No. ML091890429.)

— — — — —, NEDO-33411, Revision 2, “Risk Significance of Structures, Systems and Components for the Design Phase of the ESBWR,” February 2010. (ADAMS Accession No. ML100610417.)

— — — — —, NEDO-33413, Revision 0, “Full Scale Critical Power Testing of GE14E and Validation of GEXL14,” March 2008. (ADAMS Accession No. ML080990671.)

— — — — —, NEDO-33413, Revision 2, “Full Scale Critical Power Testing of GE14E and Validation of GEXL14,” March 2009. (ADAMS Accession No. ML090890021.)

— — — — —, NEDO-33440, Revision 2, “ESBWR Safety Analysis – Additional Information,” March 2010. (ADAMS Accession No. ML100920310.)

— — — — —, NEDO-33456, “Full-Scale Pressure Drop Testing for a Simulated GE14E Fuel Bundle,” March 2009. (ADAMS Accession Nos. ML090920866, ML090920867.)

— — — — —, NEDO-33572, Revision 0, “ESBWR PCCS Condenser Structural Evaluation,” March 23, 2010. (ADAMS Accession Nos. ML100840089, ML100840090.)

— — — — —, NEDO-33572, Revision 3, “ESBWR ICS and PCCS Condenser Combustible Gas Mitigation and Structural Evaluation,” September 2010. (ADAMS Accession No. ML102740580.)

Other GEH Documents

— — — — —, ABWR DCD, Revision 3, Chapter 19, August 30, 1996. (ADAMS Accession No. ML101050210.)

— — — — —, Research Report, VTT-R-04413-06, “Estimation and Modeling of Effective Fission Product Decontamination Factor for ESBWR Containment—Part 1,” issued October 2006, (VTT Report No. 1). (ADAMS Accession No. ML080580217.)

— — — — —, Research Report, VTT-R-04413-06, “Estimation and Modeling of Effective Fission Product Decontamination Factor for ESBWR Containment—Part 2,” issued December 2006, (VTT Report No. 2). (ADAMS Accession No. ML080580218.)

— — — — —, Research Report, VTT-R-06771-07, Revision 2 “Estimation and Modeling of Effective Fission Product Decontamination Factor for ESBWR Containment—Part 3,” issued March 2008. (ADAMS Accession No. ML081000073.)

— — — — —, UM-0136, Revision 0, “TRACG04A, [TRACG04]P User’s Manual,” December 2005. (ADAMS Accession Nos. ML071150375, ML071150376.)

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GEH Reports

— — — — —, 0000-0102-6265-R0, “CFD Modeling of Blast Wave Propagation During an ESBWR Feedwater Line Break,” March 2010. (ADAMS Accession Nos. ML100920310, ML100920317, ML100920318.)

— — — — —, SER-ESB-038, Revision 3, “Modified RBFB Truncated FE Model Analysis Data,” October 26, 2006. (ADAMS Accession No. ML063190190.)

— — — — —, SER-ESB-038, Revision 4, “Modified RBFB Truncated FE Model Analysis Data,” November 30, 2006. (ADAMS Accession No. ML063490150.)

— — — — —, SER-ESB-038, Revision 5, “Modified RBFB Truncated FE Model Analysis Data,” April 2, 2007. (ADAMS Accession No. ML071060185.)

— — — — —, DRF 0000-0093-4723-RI, Revision 1, “ESBWR Design Comparison to BWROG EPG/SAG Revision 2 for Minimum Inventory Development,” July 8, 2009. (ADAMS Accession Nos. ML091960614, ML091960615, ML091960616.)

Global Nuclear Fuel (GNF)

— — — — —, Letter from Margaret E. Harding to Mel B. Fields, “GESTAR II, Amendment 28, Revision 1, “Misloaded Fuel Bundle Event Licensing Basis Change to Comply with Standard Review Plan 15.4.7,” August 23, 2004. (ADAMS Accession Nos. ML110530123, ML110530141.)

— — — — —, Letter from A.A. Lingenfelter, GNF, to NRC Document Control Desk, “Transmittal of Updated Attachments Supporting GESTAR II Amendment 28 and Associated GESTAR II Sections (TAC NO. MC3559),” June 2, 2006. (ADAMS Accession No. ML061580106.)

Institute for Electrical and Electronics Engineers (IEEE)

— — — — —, IEEE Std 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations.”

— — — — —, IEEE Std 242-2001, “IEEE Recommended Practice for Protection and Coordination of Industrial and Commercial Power Systems.”

— — — — —, IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 308-2001, “IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 317-1983, “IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations.”

B-39

— — — — —, IEEE Std 323-1974, “IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 323-2003, “IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 338-1987, “IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems.”

— — — — —, IEEE Std 338-2006, “IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems.”

— — — — —, IEEE Std 344-1975, "IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations."

— — — — —, IEEE Std 344-1987, “IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 344-2004, “IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 379-2000, “IEEE Standard Application of the Single-Failure Criterion of Nuclear Power Generating Station Safety Systems.”

— — — — —, IEEE Std 384-1992, “IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits.”

— — — — —, IEEE Std 384-2008, “Standard Criteria for Independence of Class 1E Equipment and Circuits.”

— — — — —, IEEE Std 387-1995, “IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 450-2002, “IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications.”

— — — — —, IEEE Std 485-1997, “IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications.”

— — — — —, IEEE Std 497-2002, “IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generation Stations.”

— — — — —, IEEE Std 535-1986, “IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 535-2006, “IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.”

B-40

— — — — —, IEEE Std 603-1998, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 665-1995, “IEEE Guide for Generating Station Grounding.”

— — — — —, IEEE Std 666-1991, “IEEE Design Guide for Electric Power Service Systems for Generating Stations.”

— — — — —, IEEE Std 692-1997, “IEEE Standard Criteria for Security Systems for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 741-1997, “IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations.”

— — — — —, IEEE Std 765-2002, “IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS).”

— — — — —, IEEE Std 828-1990, “IEEE Standard for Software Configuration Management Plans.”

— — — — —, IEEE Std 829-1983, “IEEE Standard for Software Test Documentation.”

— — — — —, IEEE Std 830-1993, “IEEE Recommended Practice for Software Requirements Specifications.”

— — — — —, IEEE Std 835-1994, “IEEE Standard Power Cable Ampacity Tables.”

— — — — —, IEEE Std 946-1992, “IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations.”

— — — — —, IEEE Std 1008-1987, “IEEE Standard for Software Unit Testing.”

— — — — —, IEEE Std 1012-2004, “IEEE Standard for Software Verification and Validation.”

— — — — —, IEEE Std 1028-2008, “IEEE Standard for Software Reviews and Audits.”

— — — — —, IEEE Std 1042-1987, “IEEE Guide to Software Configuration Management.”

— — — — —, IEEE Std 1050-1996, “IEEE Guide for Instrumentation and Control Equipment Grounding in Generating Stations.”

— — — — —, IEEE Std 1058-1998, “Standard for Software Project Management Plans.”

— — — — —, IEEE Std 1074-1996, “IEEE Standard for Developing Software Life Cycle Processes.”

— — — — —, IEEE Std 1188-1996, “IEEE Recommended Practice for Maintenance, Testing, and Replacement of Valve-Regulated Lead-Acid (VRLA) Batteries for Stationary Applications.”

B-41

— — — — —, IEEE Std 1188-2005, “IEEE Recommended Practice for Maintenance, Testing, and Replacement of Valve-Regulated Lead-Acid (VRLA) Batteries for Stationary Applications.”

— — — — —, IEEE Std 1202-2006, “Standard for Flame-Propagation Testing of Wire and Cable.”

— — — — —, IEEE Std 1219-1998, “Standard for Software Maintenance.”

— — — — —, IEEE Std 1228-1994, “Standard for Software Safety Plans.”

— — — — —, IEEE/EIA Std 12207-1996, “Standard for Information Technology - Software Life Cycle Processes.”

— — — — —, IEEE Std C37.06-2000, “AC High-Voltage Circuit Breakers Rated on a Symmetrical Current Basis—Preferred Ratings and Related Required Capabilities.”

— — — — —, IEEE Std C57.12.00-2006, “Standard General Requirements for Liquid-Immersed Distribution, Power, and Regulating Transformers.”

— — — — —, IEEE Std C62.23-1995, “IEEE Application Guide for Surge Protection of Electric Generating Plants.”

Instrumentation, Systems, and Automation Society (ISA)

— — — — —, ISA-S67.02.01-1999, “Nuclear Safety-Related Instrument-Sensing Line Piping and Tubing Standard for Use in Nuclear Power Plants.”

— — — — —, ISA-S67.04-Part I-1994, “Setpoints for Nuclear Safety-Related Instrumentation.”

— — — — —, ISA-S67.04-2006, “Setpoints for Nuclear Safety-Related Instrumentation.”

— — — — —, ISA-RP67.04-Part II-1994, “Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation.”

— — — — —, ISA-RP67.04.02-2000, “Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation.”

National Fire Protection Association (NFPA)

— — — — —, NFPA 10, “Standard for Portable Fire Extinguishers,” 2010.

— — — — —, NFPA 13, “Standard for Installation of Sprinkler Systems,” 2010.

— — — — —, NFPA 14, “Standard for the Installation of Standpipes and Hose Systems,” 2010.

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— — — — —, NFPA 24, “Standard for the Installation of Private Fire Service Mains and Their Appurtenances,” 2010.

— — — — —, NFPA 72, “National Fire Alarm Code,” 2010.

— — — — —, NFPA 90A, “Standard for Installation of Air-Conditioning and Ventilating Systems,” 2009.

— — — — —, NFPA 251, “Standard Method of Tests of Fire Resistance of Building Construction and Materials,” 2006.

— — — — —, NFPA 255, “Standard Method of Test of Surface Burning Characteristics of Building Materials,” 2006.

— — — — —, NFPA 804, “Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants,” 2006.

National Oceanic and Atmospheric Administration (NOAA)/NWS

Hydrometeorological Reports (HMRs)

— — — — —, NOAA/NWS HMR No. 49, “Probable Maximum Precipitation Estimates, Colorado River and Great Basin Drainages,” 1984.

— — — — —, NOAA/NWS HMR No. 51, “Probable Maximum Precipitation Estimates, United States East of the 105th Meridian,” 1978.

— — — — —, NOAA/NWS HMR No. 52, “Application of Probable Maximum Precipitation Estimates—United States East of the 105th Meridian,” 1982.

— — — — —, NOAA/NWS HMR No. 53, “Seasonal Variation of 10-Square-Mile Probable Maximum Precipitation Estimates, United States East of the 105th Meridian,” 1980.

— — — — —, NOAA/NWS HMR No. 55A, “Probable Maximum Precipitation Estimates - United States Between the Continental Divide and the 103rd Meridian,” 1988.

Nuclear Energy Institute (NEI)

— — — — —, NEI 00-01, “Guidance for Post-Fire Safe Shutdown Circuit Analysis,” May 2003. (ADAMS Accession No. ML031640322.)

— — — — —, NEI 00-01, Revision 1, “Guidance for Post-Fire Safe Shutdown Analysis,” January 2005. (ADAMS Accession No. ML050310295.)

— — — — —, NEI 00-04, Revision 0, “10 CFR 50.69 SSC Categorization Guideline,” July 2005. (ADAMS Accession No. ML052910035.)

B-43

— — — — —, NEI 07-09, “Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description,” September 2007. (ADAMS Accession No. ML072600366.)

— — — — —, NEI 07-09A, Revision 0, “Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description,” March 2009. (ADAMS Accession No. ML091050234.)

— — — — —, NEI 07-10A, Revision 0, “Generic FSAR Template Guidance for Process Control Program,” March 2009. (ADAMS Accession No. ML091460236.)

— — — — —, NEI 07-13, Revision 7, “Methodology for Performing Aircraft Impact Assessments for New Plant Designs,” May 2009. (ADAMS Accession No. ML091490723.)

— — — — —, NUMARC 93-01, Revision 2, “Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” April 1996. (ADAMS Accession No. ML101020415.)

Technical Specification Task Force

— — — — —, TSTF-360, Revision 1, “DC Electrical Rewrite,” November 11, 2000. (ADAMS Accession Nos. ML003767758, ML003778381.)

— — — — —, TSTF-369-A, “Removal of Monthly Operating Report and Occupational Radiation Exposure Report,” January 5, 2004. (ADAMS Accession Nos. ML040050211, ML041690439.)

— — — — —, TSTF-372-A, “Addition of LCO 3.0.8, Inoperability of Snubbers,” April 4, 2005. (ADAMS Accession Nos. ML041200567, ML051160013 )

— — — — —, TSTF-400-A, “Clarify SR on Bypass of diesel generator (DG) Automatic Trips,” November 30, 2004. (ADAMS Accession No. ML083380672.)

— — — — —, TSTF-423-A, “Technical Specifications End States, NEDC-32988-A,” August 12, 2003. (ADAMS Accession Nos. ML032270250, ML060760206.)

— — — — —, TSTF-439-A, “Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO,” June 20, 2005. (ADAMS Accession Nos. ML051860296, ML060120272.)

— — — — —, TSTF-447-A, “Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors,” July 18, 2003. (ADAMS Accession Nos. ML032020007, ML032600597.)

— — — — —, TSTF-448-A, Revision 3, “Control Room Habitability,” August 8, 2006. (ADAMS Accession Nos. ML062210095, ML063630467, ML070330657, ML063460558.)

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— — — — —, TSTF-479-A, "Changes to reflect Revisions of 10 CFR 50.55a," December 2, 2004. (ADAMS Accession Nos. ML052990317, ML053460302.)

— — — — —, TSTF-482-A, “Correct LCO 3.0.6 Bases,” February 15, 2005. (ADAMS Accession Nos. ML050530165, ML053460302.)

— — — — —, TSTF-484-A, Revision 0, “Use of TS 3.10.1 for Scram Testing Activities,” May 5, 2005. (ADAMS Accession Nos. ML052930102, ML062760109.)

— — — — —, TSTF-485-A, Revision 0, “Correct Example 1.4-1,” May 31, 2005. (ADAMS Accession Nos. ML051570066, ML053460302.)

— — — — —, TSTF-493-A, Revision 4, “Clarify Application of Setpoint Methodology for Limited Safety System Setting (LSSS) Functions,” January 5, 2010. (ADAMS Accession No. ML100060064.)

— — — — —, TSTF-497-A, “Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less,” July 1, 2006. (ADAMS Accession Nos. ML061930221, ML062780321.)

— — — — —, TSTF-500, Revision 1, “DC Electrical Rewrite—Update to TSTF-360,” November 5, 2008. (ADAMS Accession No. ML083110123.)

— — — — —, TSTF-500, Revision 2, “DC Electrical Rewrite—Update to TSTF-360,” September 22, 2009. (ADAMS Accession No. ML092670242.)

— — — — —, TSTF-511-A, “Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26,” September 17, 2008. (ADAMS Accession Nos. ML082610292, ML063390370.)

— — — — —, TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0, “Technical Specifications End States, NEDC-32988-A,” September 19, 2005. (ADAMS Accession No. ML052700156.)

U.S. Atomic Energy Commission (AEC)

— — — — —, AEC Technical Information Document (TID)-14844, “Calculation of Distance Factors for Power and Test Reactor Sites,” issued 1962. (ADAMS Accession No. ML083380438.)

U.S. Department of Defense / U.S. Department of State (DOD / DOS)

— — — — —, United States Army Corps of Engineers, Omaha, NE, “DOD and DOS Barrier Anti-Ram Vehicle Barrier Certification,” Last modified January 22, 2009. <https://pdc.usace.army.mil/library/BarrierCertification/>.

B-45

U.S. Department of Energy (DOE)

— — — — —, DOETIC-11268, “Manual for the Prediction of Blast and Fragment Loading for Structures,” July 1992.

— — — — —, R.A. Williamson and R.R. Alvy, “Impact Effect of Fragments Striking Structural Elements,” Holmes and Narver, Inc., revised November 1973.

U.S. Department of State (DOS)

— — — — —, SD-STD-02.01, Revision A, “Certification Standard, Test Method for Vehicle Crash Testing of Perimeter Barriers and Gates,” March 2003.

U. S. Nuclear Regulatory Commission (NRC)

Advisory Committee on Reactor Safeguards

— — — — —, ACRSR-2097, “Safety Evaluation of the Industry Guidelines Related to Pressurized Water Reactor Sump Performance,” October 18, 2004. (ADAMS Accession No. ML042920334.)

— — — — —, ACRSR-2110, “Safety Evaluation of the Industry Guidelines Related to Pressurized Water Reactor Sump Performance,” December 10, 2004. (ADAMS Accession No. ML043450346.)

Audit Summary Reports

— — — — —, December 21, 1994, Audit Summary Report from NRC, “Summary of the Visit on October 16, 1994, at the Societa Informazioni Esperienze Termoidrauliche (SIET) Performance Analysis and Testing of Heat Removal System (Panthers) Test Facility for the SBWR Design.”

— — — — —, July 19, 2006, Audit Summary Report from Lawrence Rossbach, NRC, “Summary of May 26, 2006, Meeting with General Electric, Regarding Audit of ESBWR Piping Design and Analysis.” (ADAMS Accession No. ML061980062.)

— — — — —, August 8, 2006, Audit Summary Report from Lawrence Rossbach, NRC, “Summary of June 8, 2006, Meeting with General Electric, Regarding Audit of ESBWR Seismic Design and Analysis.” (ADAMS Accession Nos. ML062060414, ML062060531.)

— — — — —, September 26, 2006, Audit Summary Report from Lawrence Rossbach, NRC, “Summary of July 14, 2006, Meeting with General Electric, Regarding Audit of ESBWR Structural Design and Analysis.” (ADAMS Accession Nos. ML062490288, ML062490291, ML062490294.)

B-46

— — — — —, January 4, 2007, Audit Summary Report from Shawn Williams, NRC, “Summary of Exit Meeting Held on December 15, 2006, to Discuss Staffs Audit of TRACG Loss-Of-Coolant Accident Analyses.” (ADAMS Accession No. ML063540379.)

— — — — —, January 16, 2007, Audit Summary Report from Amy Cubbage, NRC, “Summary of November 17, 2006, Category 1 Meeting with General Electric, to Discuss ESBWR Instrumentation and Control Design and Audit Results.” (ADAMS Accession No. ML063600378.)

— — — — —, February 21, 2007, Audit Summary Report from Martha C. Barillas, NRC, “Summary of Meeting Held on October 16-19, 2006, to Discuss the ESBWR Fuel, Codes and Topical Reports as They Relate to the ESBWR Design Control Document Chapter 4, and a Nuclear Physics Codes Audit Performed.” (ADAMS Accession No. ML070370613.)

— — — — —, March 23, 2007, Audit Summary Report from Thomas A. Kevern, NRC, “Summary of February 7, 2007, Public Meeting with General Electric Company Regarding ESBWR Containment Capacity Audit.” (ADAMS Accession No. ML070740431.)

— — — — —, May 3, 2007, Audit Summary Report from Chandu Patel, NRC, “Summary of January 12, 2007, Meeting with General Electric Regarding Audit of ESBWR Piping Design and Analysis.” (ADAMS Accession Nos. ML070930014, ML070930009, ML070930012.)

— — — — —, May 18, 2007, Audit Summary Report from Chandu Patel, NRC, “Summary of December 14, 2006, Meeting with General Electric, Regarding Audit of ESBWR Structural Design and Analysis.” (ADAMS Accession No. ML070430420.)

— — — — —, June 12, 2007, Audit Summary Report from Shawn Williams, NRC, “[May 14-15, 2007] Audit of General Electric’s (GEs) Economic Simplified Boiling Water Reactor (ESBWR) fission product removal in the ESBWR containment and confirmatory dose rate calculation.” (ADAMS Accession No. ML071580274.)

— — — — —, July 19, 2007, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of Audit for Nuclear Design Codes October /November 2006.” (ADAMS Accession No. ML071700037.)

— — — — —, July 19, 2007, Audit Summary Report from Lawrence Rossbach, NRC, “Summary of May 26, 2006, Meeting with General Electric, Regarding Audit of ESBWR Piping Design and Analysis.” (ADAMS Accession Nos. ML061980062, 061980073, ML061980070.)

— — — — —, September 13, 2007, Audit Summary Report from Thomas A. Kevern, NRC, “Summary of ESBWR Probabilistic Risk Assessment Audit Conducted July 18 and 19, 2007.” (ADAMS Accession No. ML072430760.)

— — — — —, September 21, 2007, Audit Summary Report from Shawn Williams, NRC, “ESBWR Design Certification Supplemental [October /November 2006] Audit Summary Documenting the Specific Codes that were Reviewed by Staff.” (ADAMS Accession No. ML072560485.)

B-47

— — — — —, January 14, 2008, Audit Summary Report from Rocky D. Foster, NRC, “Summary of ESBWR Probabilistic Risk Assessment Audit Conducted on October 25 and 26, 2007.” (ADAMS Accession No. ML073231167.)

— — — — —, February 27, 2008, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of Audit for ESBWR Gamma Thermometer January/February, 2008.” (ADAMS Accession No. ML080430614.)

— — — — —, April 18, 2008, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of Audit for Review of GEH Radiological Accident Analyses Using Radionuclide Transport and Removal and Dose Estimation (RADTRAD) Code and Chapter 15.4 Request for Additional Information (RAI) February 21-22, 2008.” (ADAMS Accession No. ML080910052.)

— — — — —, July 29, 2008, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of Audit Phase 2 and 3 for ESBWR Gamma Thermometer June 2008.” (ADAMS Accession No. ML081970423, ML081970430.)

— — — — —, November 5, 2008, Audit Summary Report from Bruce M. Bavol, NRC, “Final Audit Summary Including Phase 4 for ESBWR Gamma Thermometer July 2008.” (ADAMS Accession No. ML082940529, ML082940542.)

— — — — —, November 5, 2008, Audit Summary Report from Chandu P. Patel, NRC, “Summary of Audit for Resolution of Outstanding Request for Additional Information (RAI) in Section 3.8, June 23-27, 2008.” (ADAMS Accession No. ML082950077.)

— — — — —, December 22, 2008, Audit Summary Report from Bruce M. Bavol, NRC, and Chris N. Van Wert, NRC, “Audit Report and Summary ([July 30 – August 2] 2007 & [August 6-7] 2008) for Global Nuclear Fuels Control Blade and Fuel Assembly Design.” (ADAMS Accession No. ML083230072.)

— — — — —, April 29, 2009, Audit Summary Report from Bruce M. Bavol, NRC, “ESBWR Computer Code Review Technical Summary [December 15-19, 2008] Including a Followup Review Summary [January 13, 2009] for the TRACG04 Safety Analysis Code.” (ADAMS Accession Nos. ML090630819, ML090630826.)

— — — — —, July 27, 2009, Audit Summary Report from Dennis J. Galvin, NRC, “Summary of the [May 6-8, 2009] Audit of The Probabilistic Risk Assessment Supporting Chapter 19 of The ESBWR Design Certification Application.” (Adams Accession No. ML092020346.)

— — — — —, September 1, 2009, Audit Summary Report from Zahira Cruz Perez, NRC, “Summary of the July 20 to 24, 2009, Regulator Audit of Design Specification of Risk Significant ESBWR Components at General Electric Hitachi (GEH) Office in Wilmington, NC.” (ADAMS Accession No. ML092390403.)

— — — — —, September 15, 2009, Audit Summary Report from Zahira Cruz Perez, NRC, “Report of the August 25, 2009, and September 9, 2009, Regulatory Audit of Reactor Pressure Vessel Internals of the Economic Simplified Boiling Water Reactor at General Electric Hitachi (GEH) Office in Wilmington, NC.” (ADAMS Accession Nos. ML092540004, ML092570429.)

B-48

— — — — —, March 29, 2010, Audit Summary Report from Zahira Cruz, NRC, “Summary of Follow-Up Audit on Documentation of ESBWR Section 3.9.1 Computer Codes PISYS 08 & ANSI714 Related to RAI 3.9-254 and RAI 3.9-255.” (ADAMS Accession Nos. ML100890013, ML100890007, ML100890011.)

— — — — —, May 16, 2010, Audit Summary Report from Ilka T. Berrios, NRC, “Summary of [April 22, 2010] Audit for Review of GEH Methodology for Determining the Bounding Analyses and Parameters for the ESBWR Design with Respect to Atmospheric Dispersion of Radioactive Effluents and Closure of RAI 12.2-28.” (ADAMS Accession No. ML101260210.)

— — — — —, May 20, 2010, Audit Summary Report from Dennis Galvin, NRC, “Summary of the March 19-20, 2009 Regulatory Audit of ESBWR Chapter 9 RTNSS/Cold Shutdown Systems at General Electric Hitachi (GEH) Office in Washington, D.C.” (ADAMS Accession No. ML101250439.)

— — — — —, June 23, 2010, Audit Summary Report from Dennis Galvin, NRC, “Summary of the February 11 to 12, 2009, and September 29-30, 2009, Regulatory Audits of Supporting Information for Fuel Storage Racks Topical Reports at General Electric Hitachi Office in Washington, D.C.” (ADAMS Accession No. ML101450301.)

— — — — —, June 23, 2010, Audit Summary Report from Dennis Galvin, NRC, “Summary of the June 3 and 15, 2010 Regulatory Audits of the Economic Simplified Boiling Water Reactor Spent Fuel Pool Required Water Inventory at Nuclear Energy Institute Office in Rockville, Maryland.” (ADAMS Accession No. ML101680660.)

— — — — —, July 15, 2010, Audit Summary Report from Dennis Galvin, NRC, “Summary of the January 16-18, 2007, and July 25-27, 2007, Regulatory Audits of the ESBWR Human Factors Engineering Program at General Electric Hitachi (GEH) Office in Wilmington, NC.” (ADAMS Accession No. ML101960241.)

— — — — —, July 19, 2010, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of Audit for Nuclear Design Codes October/November 2006.” (ADAMS Accession No. ML071700037.)

— — — — —, September 29, 2010, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of [September 22, 2010] Audit for Review of License Topical Report NEDE-33572P, Revision 2, Appendix C and Supporting Analyses.” (ADAMS Accession No. ML102670186.)

— — — — —, October 14, 2010, Audit Summary Report from David Misenhimer, “Summary of the May 16 and 17, 2007, Regulator Audits of the Economic Simplified Boiling Water Reactor Design Certification Document Section 3.8 at GEH Offices in Wilmington, North Carolina.” (ADAMS Accession No. ML102530172.)

— — — — —, December 16, 2010, Audit Summary Report from David Misenhimer, NRC, “Final Audit Summary for Economic Simplified Boiling Water Reactor Probabilistic Risk Assessment Models Used to Support Economic Simplified Boiling Water Reactor Design Certification May [6-8,] 2009.” (ADAMS Accession No. ML103420463.)

B-49

— — — — —, February 23, 2011, Audit Summary Report from Bruce Bavol, NRC, “Summary of November 2, 2006, Meeting with General Electric Regarding Audit of ESBWR Seismic Design and Analysis.” (ADAMS Accession No. ML070930064.)

— — — — —, February 23, 2011, Audit Summary Report from Bruce M. Bavol, NRC, “Summary of October 26, 2009, Audit of ANS17 Computer Code for Fatigue Analysis of Economic Simplified Boiling Water Reactor Safety-Related Class 1 Piping.” (ADAMS Accession No. ML110540316.)

Bulletins

— — — — —, BL 74-04, “Malfunction of Target Rock Safety Relief Valves,” May 17, 1974. (ADAMS Accession No. ML031250081.)

— — — — —, BL 79-02, “Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts,” March 18, 1979.

— — — — —, BL 79-02, Revision 1, “Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts,” June 21, 1979. (ADAMS Accession No. ML031210363.)

— — — — —, BL 79-02, Revision 2, "Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts," November 8, 1979. (ADAMS Accession No. ML0312110461.)

— — — — —, BL 80-01, “Operability of ADS Valve Pneumatic Supply,” January 11, 1980. (ADAMS Accession No. ML031210505.)

— — — — —, BL 80-06, “Engineered Safety Feature (ESF) Reset Controls,” March 13, 1980. (ADAMS Accession No. ML031210518.)

— — — — —, BL 80-08, “Examination of Containment Liner Penetration Welds,” April 7, 1980. (ADAMS Accession No. ML031210525.)

— — — — —, BL 80-10, “Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radioactivity to Environment,” May 6, 1980. (ADAMS Accession No. ML031210532.)

— — — — —, BL 80-15, “Possible Loss of Emergency Notification System (ENS) with Loss of Offsite Power,” June 18, 1980. (ADAMS Accession No. ML031210543.)

— — — — —, BL 80-25, “Operating Problems with Target Rock Safety-Relief Valves at BWRs,” December 19, 1980. (ADAMS Accession No. ML031210646.)

— — — — —, BL 81-01, “Surveillance of Mechanical Snubbers,” January 27, 1981. (ADAMS Accession No. ML031210687.)

— — — — —, BL 81-03, “Flow Blockage of Cooling Water to Safety System Components by Corbicula SP (Asiatic Clam) and Mytilus SP (Mussel),” April 10, 1981. (ADAMS Accession No. ML031210703.)

B-50

— — — — —, BL 82-04, “Deficiencies in Primary Containment Electrical Penetration Assemblies,” December 3, 1982. (ADAMS Accession No. ML031210731.)

— — — — —, BL 84-03, “Refueling Cavity Water Seal,” August 24, 1984. (ADAMS Accession No. ML082700127.)

— — — — —, BL 85-03, “Motor Operated Valve Common Mode Failures During Plant Transient Due to Improper Switch Settings,” November 15, 1985. (ADAMS Accession No. ML031210854.)

— — — — —, BL 86-01, “Minimum Flow Logic Problems that Could Disable RHR Pumps,” May 23, 1986. (ADAMS Accession No. ML082970418.)

— — — — —, BL 87-01, “Thinning of Pipe Walls in Nuclear Power Plants,” July 9, 1987. (ADAMS Accession No. ML031210862.)

— — — — —, BL 88-08, “Thermal Stresses in Piping Connected to Reactor Cooling Systems,” June 28, 1988. (ADAMS Accession No. ML031220144.)

— — — — —, BL 88-10, “Nonconforming Molded-Case Circuit Breakers,” November 1988. (ADAMS Accession No. ML031220261.)

— — — — —, BL 93-02, “Debris Plugging of Emergency Core Cooling Suction Strainers,” May 11, 1993.

— — — — —, BL 93-02, Supplement 1, “Debris Plugging of Emergency Core Cooling Suction Strainers,” February 18, 1994. (ADAMS Accession No. ML031190684.)

— — — — —, BL 93-03, "Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs," May 28, 1993.

— — — — —, BL 95-02, “Unexpected Clogging of a Residual Heat Removal (RHR) Pump Strainer While Operating in Suppression Pool Cooling Mode,” October 17, 1995.

— — — — —, BL 96-02, “Movement of Heavy Loads over Spent Fuel, over Fuel in the Reactor Core, or over Safety-Related Equipment,” April 11, 1996. (ADAMS Accession No. ML082590698.)

— — — — —, BL 96-03, “Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors,” May 6, 1996. (ADAMS Accession No. ML022070323.)

— — — — —, BL 2005-02, “Emergency Preparedness and Response Actions for Security-Based Events,” July 18, 2005. (ADAMS Accession No. ML051740058.)

Branch Technical Positions

— — — — —, BTP 3-1, Revision 2, “Classification of Main Steam Components Other than the Reactor Coolant Pressure Boundary for BWR Plants,” March 2007. (ADAMS Accession No. ML070800127.)

B-51

— — — — —, BTP 3-3, Revision 3, "Protection against Postulated Piping Failures in Fluid Systems Outside Containment," March 2007. (ADAMS Accession No. ML070800027.)

— — — — —, BTP 3-4, Revision 2, “Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment,” March 2007. (ADAMS Accession No. ML070800008.)

— — — — —, BTP 7-1, “Guidance on Isolation of Low-Pressure Systems from the High-Pressure Reactor Coolant System,” March 2007. (ADAMS Accession No. ML070460345.)

— — — — —, BTP 7-2, “Guidance on Requirements of Motor-Operated Valves in the Emergency Core Cooling System Accumulator Lines,” March 2007. (ADAMS Accession No. ML070550090.)

— — — — —, BTP 7-3, “Guidance on Protection System Trip Point Changes for Operation with Reactor Coolant Pumps Out of Service,” March 2007. (ADAMS Accession No. ML070550091.)

— — — — —, BTP 7-4, “Guidance on Design Criteria for Auxiliary Feedwater Systems,” March 2007. (ADAMS Accession No. ML070880400.)

— — — — —, BTP 7-5, “Guidance on Spurious Withdrawals of Single Control Rods in Pressurized Water Reactors,” March 2007. (ADAMS Accession No. ML070550094.)

— — — — —, BTP 7-6, “Guidance on Design of Instrumentation and Controls Provided to Accomplish Changeover from Injection to Recirculation Mode,” March 2007. (ADAMS Accession No. ML070550095.)

— — — — —, BTP 7-8, “Guidance for Application of Regulatory Guide 1.22,” March 2007. (ADAMS Accession No. ML070550096.)

— — — — —, BTP 7-9, “Guidance on Requirements for Reactor Protection System Anticipatory Trips,” March 2007. (ADAMS Accession No. ML070550084.)

— — — — —, BTP 7-10, “Guidance on Application of Regulatory Guide 1.97,” March 2007. (ADAMS Accession No. ML070550082.)

— — — — —, BTP 7-11, “Guidance on Application and Qualification of Isolation Devices,” March 2007. (ADAMS Accession No. ML070550080.)

— — — — —, BTP 7-12, “Guidance on Establishing and Maintaining Instrument Setpoints,” March 2007. (ADAMS Accession No. ML070550078.)

— — — — —, BTP 7-13, “Guidance on Cross-Calibration of Protection System Resistance Temperature Detectors,” March 2007. (ADAMS Accession No. ML070550077.)

B-52

— — — — —, BTP 7-14, “Guidance on Software Reviews for Digital Computer-Based Instrumentation and Controls Systems,” March 2007. (ADAMS Accession No. ML070670183.)

— — — — —, BTP 7-16, “Guidance on Level of Detail Required for Design Certification Applications Under 10 CFR Part 52,” March 2007. (ADAMS Accession No. ML070450253.)

— — — — —, BTP 7-17, “Guidance on Self-Test and Surveillance Test Provisions,” March 2007. (ADAMS Accession No. ML070550075.)

— — — — —, BTP 7-18, “Guidance on the Use of Programmable Logic Controllers in Digital Computer-Based Instrumentation and Control Systems,” March 2007. (ADAMS Accession No. ML070550073.)

— — — — —, BTP 7-19, “Guidance for Evaluation of Diversity and Defense-in-Depth in Digital Computer-Based Instrumentation and Control Systems,” March 2007. (ADAMS Accession No. ML070550072.)

— — — — —, BTP 7-21, “Guidance on Digital Computer Real-Time Performance,” March 2007. (ADAMS Accession No. ML070550070.)

— — — — —, BTP 8-3, “Stability of Offsite Power Systems,” March 2007. (ADAMS Accession No. ML070710446.)

— — — — —, BTP 8-6, “Adequacy of Station Electric Distribution System Voltages,” March 2007. (ADAMS Accession No. ML070710478.)

— — — — —, BTP 11-3, Revision 3, “Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Reactor Plants,” March 2007. (ADAMS Accession No. ML070730202.)

— — — — —, BTP 11-5, Revision 3, “Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure,” March 2007. (ADAMS Accession No. ML070730056.)

— — — — —, BTP 11-6, “Postulated Radioactive Releases Due to Liquid-Containing Tank Failures,” March 2007. (ADAMS Accession No. ML070720635.)

— — — — —, BTP ASB 9-2, “Residual Decay Energy for Light Water Reactors for Long-Term Cooling,” 1981.

— — — — —, BTP CSB 6-1, “pH for Emergency Coolant Water for Pressurized Water Reactors,” March 2007. (ADAMS Accession No. ML063190011.)

— — — — —, BTP CSB 6-4, “Containment Purging During Normal Plant Operation,” March 2007. (ADAMS Accession No. ML070740319.)

— — — — —, BTP EMEB 3-1, “Postulated Break and Leakage Locations in Fluid System Piping Outside Containment,” June 1996. (ADAMS Accession No. ML052070315.)

B-53

— — — — —, BTP ICSB 11, Revision 3, “Stability of Offsite Power Systems,” April 1996. (ADAMS Accession No. ML052070493.)

— — — — —, BTP MEB 3-1, Revision 1, “Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment,” July 1981. (ADAMS Accession No. ML052340555.)

— — — — —, BTP PSB-1, Revision 3, “Adequacy of Station Electric Distribution System Voltages,” April 1996. (ADAMS Accession No. ML052070493.)

— — — — —, BTP RSB 5-1, Revision 4, Draft, “Design Requirements of the Residual Heat Removal System,” April 1996.

— — — — —, BTP SPLB 3-1. “Protection Against Postulated Piping Failures in Fluid Systems Outside Containment,” October 1990. (ADAMS Accession No. ML052340548.)

— — — — —, BTP SPLB 9.5-1, “Guidelines for Fire Protection for Nuclear Power Plants,” 2003. (ADAMS Accession No. ML070660454.)

U.S. Code of Federal Regulations

— — — — —, Title 10, Energy, Part 2, “Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders.”

— — — — —, Title 10, Energy, Part 20, “Standards for Protection Against Radiation.”

— — — — —, Title 10, Energy, 20.1101, “Radiation Protection Programs.”

— — — — —, Title 10, Energy, 20.1201, “Occupational Dose Limits for Adults.”

— — — — —, Title 10, Energy, 20.1301, “Dose Limits for Individual Members of the Public.”

— — — — —, Title 10, Energy, 20.1302, “Compliance with Dose Limits for Individual Members of the Public.”

— — — — —, Title 10, Energy, 20.1406, “Minimization of Contamination.”

— — — — —, Title 10, Energy, 20.2006, “Transfer for Disposal and Manifests.”

— — — — —, Title 10, Energy, Part 20, Subpart D, “Radiation Dose Limits for Individual Members of the Public.”

— — — — —, Title 10, Energy, Part 20, Appendix B, “Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage.”

— — — — —, Title 10, Energy, Part 20, Appendix G, “Requirements for Transfers of Low-Level Radioactive Waste Intended for Disposal at Licensed Land Disposal Facilities and Manifests.”

B-54

— — — — —, Title 10, Energy, Part 21, “Reporting of Defects and Noncompliance.”

— — — — —, Title 10, Energy, Part 26, “Fitness for Duty Programs.”

— — — — —, Title 10, Energy, Part 26, Subpart I, “Managing Fatigue.”

— — — — —, Title 10, Energy, Part 50, “Domestic Licensing of Production and Utilization Facilities.”

— — — — —, Title 10, Energy, 50.2, “Definitions.”

— — — — —, Title 10, Energy, 50.12, “Specific Exemptions.”

— — — — —, Title 10, Energy, 50.33, “Contents of Applications; General Information.”

— — — — —, Title 10, Energy, 50.34, “Contents of Construction Permit and Operating License Applications; Technical Information.”

— — — — —, Title 10, Energy, 50.34a, “Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents—Nuclear Power Reactors.”

— — — — —, Title 10, Energy, 50.35, “Issuance of Construction Permit”

— — — — —, Title 10, Energy, 50.36, “Technical Specifications.”

— — — — —, Title 10, Energy, 50.36a, “Technical Specifications on Effluents from Nuclear Power Reactors.”

— — — — —, Title 10, Energy, 50.44, “Combustible Gas Control for Nuclear Power Plants.”

— — — — —, Title 10, Energy, 50.46, “Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors.”

— — — — —, Title 10, Energy, 50.47, “Emergency Plans.”

— — — — —, Title 10, Energy, 50.48, “Fire Protection.”

— — — — —, Title 10, Energy, 50.49, “Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.”

— — — — —, Title 10, Energy, 50.54, “Conditions of Licenses.”

— — — — —, Title 10, Energy, 50.55, “Conditions of Construction Permits, Early Site Permits, Combined Licenses, and Manufacturing Licenses.”

— — — — —, Title 10, Energy, 50.55a, “Codes and Standards.”

— — — — —, Title 10, Energy, 50.59, “Changes, Tests and Experiments.”

B-55

— — — — —, Title 10, Energy, 50.62, “Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water-Cooled Nuclear Power Plants.”

— — — — —, Title 10, Energy, 50.63, “Loss of All Alternating Current Power.”

— — — — —, Title 10, Energy, 50.65, “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.”

— — — — —, Title 10, Energy, 50.67, “Accident Source Term.”

— — — — —, Title 10, Energy, 50.68, “Criticality Accident Requirements.”

— — — — —, Title 10, Energy, 50.120, “Training and Qualification of Nuclear Power Plant Personnel.”

— — — — —, Title 10, Energy, Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants.”

— — — — —, Title 10, Energy, Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.”

— — — — —, Title 10, Energy, Part 50, Appendix E, “Emergency Planning and Preparedness for Production and Utilization Facilities.”

— — — — —, Title 10, Energy, Part 50, Appendix G, “Fracture Toughness Requirements.”

— — — — —, Title 10, Energy, Part 50, Appendix I, “Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion ‘As Low As Reasonably Achievable’ for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.”

— — — — —, Title 10, Energy, Part 50, Appendix J, “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.”

— — — — —, Title 10, Energy, Part 50, Appendix K, “ECCS Evaluation Models.”

— — — — —, Title 10, Energy, Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.”

— — — — —, Title 10, Energy, Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.”

— — — — —, Title 10, Energy, 52.1, “Definitions.”

— — — — —, Title 10, Energy, 52.17, “Contents of Applications; Technical Information.”

— — — — —, Title 10, Energy, 52.47, “Contents of Applications; Technical Information.”

— — — — —, Title 10, Energy, 52.48, “Standards for Review of Applications.”

B-56

— — — — —, Title 10, Energy, 52.53, “Referral to the Advisory Committee on Reactor Safeguards (ACRS).”

— — — — —, Title 10, Energy, 52.79, “Contents of Applications; Technical Information in Final Safety Analysis Report.”

— — — — —, Title 10, Energy, 52.80, “Contents of Applications; Additional Technical Information.”

— — — — —, Title 10, Energy, 52.97, “Issuance of Combined Licenses.”

— — — — —, Title 10, Energy, 52.99, “Inspection during Construction.”

— — — — —, Title 10, Energy, 52.103, “Operation under a Combined License.”

— — — — —, Title 10, Energy, Part 52, Subpart E, “Standard Design Approvals.”

— — — — —, Title 10, Energy, Part 55, “Operators’ Licenses.”

— — — — —, Title 10, Energy, Part 61, “Licensing Requirements for Land Disposal of Radioactive Waste.”

— — — — —, Title 10, Energy, Part 70, “Domestic Licensing of Special Nuclear Materials.”

— — — — —, Title 10, Energy, 70.24, “Criticality Accident Requirements.”

— — — — —, Title 10, Energy, Part 71, “Packaging and Transportation of Radioactive Material.”

— — — — —, Title 10, Energy, Part 73, “Physical Protection of Plants and Materials.”

— — — — —, Title 10, Energy, 73.1, “Radiological Sabotage.”

— — — — —, Title 10, Energy, 73.45, “Performance Capabilities for Fixed Site Physical Protection Systems.”

— — — — —, Title 10, Energy, 73.46, “Fixed Site Physical Protection Systems, Subsystems, Components, and Procedures.”

— — — — —, Title 10, Energy, 73.54, “Protection of Digital Computer and Communication Systems and Networks.”

— — — — —, Title 10, Energy, 73.55, “Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors against Radiological Sabotage.”

— — — — —, Title 10, Energy, 73.56, “Personnel Access Authorization Requirements for Nuclear Power Plants.”

— — — — —, Title 10, Energy, 73.57, “Requirements for Criminal History Records Checks of Individuals Granted Unescorted Access to a Nuclear Power Facility or Access to Safeguards Information.”

B-57

— — — — —, Title 10, Energy, 73.70, “Records.”

— — — — —, Title 10, Energy, Part 74, “Material Control and Accounting of Special Nuclear Material.”

— — — — —, Title 10, Energy, Part 100, “Reactor Site Criteria.”

— — — — —, Title 10, Energy, 100.3, “Definitions.”

— — — — —, Title 10, Energy, 100.20, “Factors to be Considered when Evaluating Sites.”

— — — — —, Title 10, Energy, 100.21, “Non-seismic Site Criteria.”

— — — — —, Title 10, Energy, 100.23, “Geologic and Seismic Siting Criteria.”

— — — — —, Title 10, Energy, Part 140, “Financial Protection Requirements and Indemnity Agreements.”

— — — — —, Title 40, Protection of Environment, Part 190, “Environmental Radiation Protection Standards for Nuclear Power Operations.”

— — — — —, Title 49, Transportation, Part 171, “General Information, Regulations, and Definitions.”

— — — — —, Title 49, Transportation, Part 172, “Hazardous Materials Table, Special Provisions, Hazardous Materials Communications, Emergency Response Information, Training.”

— — — — —, Title 49, Transportation, Part 173, “Shippers - General Requirements for Shipments and Packagings.”

— — — — —, Title 49, Transportation, Part 174, “Carriage by Rail.”

— — — — —, Title 49, Transportation, Part 175, “Carriage by Aircraft.”

— — — — —, Title 49, Transportation, Part 176, “Carriage by Vessel.”

— — — — —, Title 49, Transportation, Part 177, “Carriage by Public Highway.”

— — — — —, Title 49, Transportation, Part 178, “Specifications for Packagings.”

— — — — —, Title 49, Transportation, Part 179, “Specifications for Tank Cars.”

— — — — —, Title 49, Transportation, Part 180, “Continuing Qualification and Maintenance of Packagings.”

B-58

Commission Papers

— — — — —, SECY-83-293, “Amendments to 10 CFR Part 50 Related to Anticipated Transients Without Scram Events,” July 19, 1983.

— — — — —, SECY-89-013, “Design Requirements Related to the Evolutionary Advanced Light Water Reactors,” January 19, 1989. (ADAMS Accession No. ML003707947.)

— — — — —, SECY-90-016, “Evolutionary Light-Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements,” January 12, 1990, (ADAMS Accession No. ML003707849), and the related SRM, dated June 26, 1990. (ADAMS Accession No. ML003707885.)

— — — — —, SECY-90-241, “Level of Detail Required for Design Certification Under Part 52,” July 11, 1990, (ADAMS Accession No. ML003707877), and the related SRM, dated August 22, 1990. (ADAMS Accession No. ML003707878.)

— — — — —, SECY-90-377, “Requirements for Design Certification under 10 CFR Part 52,” November 8, 1990, (ADAMS Accession No. ML003707889), and the related SRM, dated February 15, 1991. (ADAMS Accession No. ML003707892.)

— — — — —, SECY-90-406, “Quarterly Report on Emerging Technical Concerns,” December 17, 1990.

— — — — —, SECY-91-078, “Chapter 11 of the Electric Power Research Institute’s (EPRI’s) Requirements Document and Additional Evolutionary LWR Certification Issues,” April 1991. (ADAMS Accession Nos. ML010050043, ML072150592.)

— — — — —, SECY-91-153, “Draft Safety Evaluation Report on General Electric Company ABWR Design Covering Chapters 1, 2, 3, 4, 5, 6, and 17 of the Standard Safety Analysis Report,” May 24, 1991.

— — — — —, SECY-91-178, “Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for Design Certifications and Combined Licenses,” June 12, 1991. (ADAMS Accession No. ML003707907.)

— — — — —, SECY-91-210, “Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Requirements for Design Review and Issuance of a Final Design Approval (FDA),” July 16, 1991. (ADAMS Accession No. ML003707915.)

— — — — —, SECY-92-053, “Use of Design Acceptance Criteria during 10 CFR Part 52 Design Certification Reviews,” February 19, 1992. (ADAMS Accession No. ML003707942.)

— — — — —, SECY-92-214, “Development of Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for Design Certifications,” June 11, 1992. (ADAMS Accession No. ML003707966.)

— — — — —, SECY-93-067, “Final Policy Statement on TS Improvements for Nuclear Power Reactors,” July 22, 1993.

B-59

— — — — —, SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs,” April 2, 1993, (ADAMS Accession No. ML003708021), and the related SRM, dated July 21, 1993. (ADAMS Accession No. ML003708056.)

— — — — —, SECY-94-084, “Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems (RTNSS) in Passive Plant Designs,” March 28, 1994, (ADAMS Accession No. ML003708068), and the related SRM, dated June 30, 1994. (ADAMS Accession No. ML003708098.)

— — — — —, SECY-94-302, “Source Term-Related Technical and Licensing Issues Pertaining to Evolutionary and Passive Light-Water-Reactor Designs,” December 19, 1994. (ADAMS Accession No. ML003708141.)

— — — — —, SECY-95-132, “Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems (RTNSS) in Passive Plant Designs (SECY-94-084),” May 22, 1995, (ADAMS Accession No. ML003708005), and the related SRM dated June 28, 1995. (ADAMS Accession No. ML003708019.)

— — — — —, SECY-96-128, “Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design,” June 12, 1996, (ADAMS Accession No. ML003708224), and the related SRM, dated January 15, 1997. (ADAMS Accession No. ML003708192.)

— — — — —, SECY-96-128, “Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design,” June 12, 1996, (ADAMS Accession No. ML003708224), and the related SRM, dated June 23, 1997. (ADAMS Accession No. ML003708229.)

— — — — —, SECY-97-044, “Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design,” February 19, 1997, (ADAMS Accession No. ML003708316), and the related SRM, dated June 30, 1997. (ADAMS Accession No. ML003708232.)

— — — — —, SECY-97-168, “Issuance for Public Comment of Proposed Rulemaking Package for Shutdown and Fuel Storage Pool Operation,” July 1997, and the related SRM, dated December 11, 1997. (ADAMS Accession No. ML003752569.)

— — — — —, SECY-98-161, “The Westinghouse AP600 Standard Design as it Relates to the Fire Protection and the Spent Fuel Pool Cooling Systems,” July 1, 1998. (ADAMS Accession No. ML992880086.)

— — — — —, SECY-00-0198, “Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on Risk-Informed Changes to 10 CFR 50.44 (Combustible Gas Control),” September 14, 2000. (ADAMS Accession No. ML003747699.)

— — — — —, SECY-02-0067, “Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for Operational Programs (Programmatic ITAAC),” April 15, 2002, (ADAMS Accession No. ML020700641), and the related SRM, dated September 11, 2002. (ADAMS Accession No. ML022540755.)

B-60

— — — — —, SECY-04-0032, “Programmatic Information Needed for Approval of a Combined License without Inspections, Tests, Analyses and Acceptance Criteria,” February 26, 2004, (ADAMS Accession No. ML040230079), and the related SRM, dated May 14, 2004. (ADAMS Accession No. ML041350440.)

— — — — —, SECY-04-0200, “A Risk-Informed Approach to Defining the Design Basis Tornado for New Reactor Licensing,” November 22, 2004. (ADAMS Accession Nos. ML043280245, ML043270446.)

— — — — —, SECY-05-0197, “Review of Operational Programs in a Combined License Application and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria,” October 28, 2005, (ADAMS Accession Nos. ML052770225, ML052770257), and the related SRM, dated February 22, 2006. (ADAMS Accession No. ML060530316.)

— — — — —, SECY-06-0220, “Final Rule to Update 10 CFR Part 52, ‘Licenses, Certifications, and Approvals for Nuclear Power Plants’ (RIN AG24),” October 2006. (ADAMS Accession No. ML062610267.)

Federal Register Notices

— — — — —, Federal Register, Vol. 49, pp. 26036-26045, “Rules and Regulation,” issued June 26, 1984.

— — — — —, Federal Register, Vol. 54, p. 31268, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” issued July 27, 1989.

General Design Criteria (10 CFR Part 50, Appendix A)

— — — — —, GDC 1, “Quality Standards and Records.”

— — — — —, GDC 2, “Design Bases for Protection against Natural Phenomena.”

— — — — —, GDC 3, “Fire Protection.”

— — — — —, GDC 4, “Environmental and Dynamic Effects Design Bases.”

— — — — —, GDC 5, “Sharing of Structures, Systems, and Components.”

— — — — —, GDC 10, “Reactor Design.”

— — — — —, GDC 11, "Reactor Inherent Protection."

— — — — —, GDC 12, "Suppression of Reactor Power Oscillations."

— — — — —, GDC 13, "Instrumentation and Control."

— — — — —, GDC 14, “Reactor Coolant Pressure Boundary.”

B-61

— — — — —, GDC 15, “Reactor Coolant System Design.”

— — — — —, GDC 17, “Electric Power Systems.”

— — — — —, GDC 19, “Control Room.”

— — — — —, GDC 20, "Protection System Functions."

— — — — —, GDC 21, “Protection System Reliability and Testability.”

— — — — —, GDC 22, “Protection System Independence.”

— — — — —, GDC 23, “Protection System Failure Modes.”

— — — — —, GDC 24, “Separation of Protection and Control Systems.”

— — — — —, GDC 25, "Protection System Requirements for Reactivity Control Malfunctions."

— — — — —, GDC 26, “Reactivity Control System Redundancy and Capability.”

— — — — —, GDC 27, “Combined Reactivity Control Systems Capability.”

— — — — —, GDC 28, "Reactivity Limits."

— — — — —, GDC 29, “Protection Against Anticipated Operational Occurrences.”

— — — — —, GDC 30, “Quality of Reactor Coolant Pressure Boundary.”

— — — — —, GDC 31, “Fracture Prevention of Reactor Coolant Pressure Boundary.”

— — — — —, GDC 33, “Reactor Coolant Makeup.”

— — — — —, GDC 34, “Residual Heat Removal.”

— — — — —, GDC 35, "Emergency Core Cooling."

— — — — —, GDC 36, “Inspection of Emergency Core Cooling System.”

— — — — —, GDC 37, “Testing of Emergency Core Cooling System.”

— — — — —, GDC 38, “Containment Heat Removal.”

— — — — —, GDC 40, “Testing of Containment Heat Removal System.”

— — — — —, GDC 41, “Containment Atmosphere Cleanup.”

— — — — —, GDC 43, “Testing of Containment Atmosphere Cleanup Systems.”

— — — — —, GDC 44, “Cooling Water.”

— — — — —, GDC 45, “Inspection of Cooling Water System.”

B-62

— — — — —, GDC 46, “Testing of Cooling Water System.”

— — — — —, GDC 50, “Containment Design Basis.”

— — — — —, GDC 53, “Provisions for Containment Testing and Inspection.”

— — — — —, GDC 54, “Piping Systems Penetrating Containment.”

— — — — —, GDC 55, “Reactor Coolant Pressure Boundary Penetrating Containment.”

— — — — —, GDC 60, “Control of Releases of Radioactive Material to the Environment.”

— — — — —, GDC 61, “Fuel Storage and Handling and Radioactivity Control.”

— — — — —, GDC 62, “Prevention of Criticality in Fuel Storage and Handling.”

— — — — —, GDC 63, “Monitoring Fuel and Waste Storage.”

— — — — —, GDC 64, “Monitoring Radioactivity Releases.”

Generic Safety Issues and Task Action Plan Items (see NUREG–0933)

— — — — —, Issue 29, “Bolting Degradation of Failure in Nuclear Power Plants.”

— — — — —, Issue 43, “Contamination of Instrument Air Lines.”

— — — — —, Issue 45, “Inoperability of Instrumentation Due to Extreme Cold Weather.”

— — — — —, Issue 48, “LCO for Class 1E Vital Instrument Buses in Operating Reactors.”

— — — — —, Issue 49, “Interlocks and LCOs for Class 1E Tie-Breakers.”

— — — — —, Issue 51, “Proposed Requirements for Improving the Reliability of Open Cycle Service Water System.”

— — — — —, Issue 64, “Identification of Protection System Instrument Sensing Lines.”

— — — — —, Issue 67.3.3, “Steam Generator Staff Actions - Improved Accident Monitoring.”

— — — — —, Issue 78, “Monitoring of Fatigue Transient Limits for Reactor Coolant System.”

— — — — —, Issue 86, “Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping.”

— — — — —, Issue 107, “Main Transformer Failures.”

B-63

— — — — —, Issue 113, “Dynamic Qualification Testing of Large Bore Hydraulic Snubbers.”

— — — — —, Issue 119.2, “Piping Review Committee Recommendations - Piping Damping Values.”

— — — — —, Issue 119.4, ”Piping Review Committee Recommendations - BWR Piping Materials.”

— — — — —, Issue 120, “On-Line Testability of Protection Systems.”

— — — — —, Issue 128, “Electrical Power Reliability.”

— — — — —, Issue 142, “Leakage through Electrical Isolators in Instrumentation Circuits.”

— — — — —, Issue 143, “Availability of Chilled Water System and Room Cooling.”

— — — — —, Issue 146, "Support Flexibility of Equipment and Components."

— — — — —, Issue 153, “Loss of Essential Service Water in LWRs.”

— — — — —, Issue 156.6.1, “Systematic Evaluation Program - Pipe Break Effects on Systems and Components.”

— — — — —, Issue 157, “Containment Performance.”

— — — — —, Issue 191, “Assessment of Debris Accumulation on PWR Sump Performance.”

— — — — —, Item A-1, “Water Hammer.”

— — — — —, Item A-10, “BWR Feedwater Nozzle Cracking.”

— — — — —, Item A-13, “Snubber Operability Assurance.”

— — — — —, Item A-19, “Digital Computer Protection Systems.”

— — — — —, Item A-29, “Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage.”

— — — — —, Item A-30, “Adequacy of Safety-Related DC Power Supplies.”

— — — — —, Item A-34, “Instruments for Monitoring Radiation and Process Variables During Accidents.”

— — — — —, Item A-40, “Seismic Design Criteria.”

— — — — —, Item A-42, “Pipe Cracks in Boiling Water Reactors.”

— — — — —, Item A-44, “Station Blackout.”

B-64

— — — — —, Item A-47, “Safety Implications of Control Systems.”

— — — — —, Item B-6, “Loads, Load Combinations, Stress Limits.”

— — — — —, Item B-26, “Structural Integrity of Containment Penetrations.”

— — — — —, Item B-55, “Improved Reliability of Target Rock Safety Relief Valves.”

— — — — —, Item A-46, “Seismic Qualification of Equipment in Operating Plants.”

— — — — —, Task II.B.8, “Consideration of Degraded or Melted Cores in Safety Review - Rulemaking Proceeding on Degraded Core Accidents.”

Generic Letters

— — — — —, GL 1980-009, “Low Level Radioactive Waste Disposal,” January 29, 1980. (ADAMS Accession No. ML031350287.)

— — — — —, GL 1980-034, “Clarification of NRC Requirements for Emergency Response Facilities at Each Site,” April 1980.

— — — — —, GL 1981-003, “Implementation of NUREG–0313, Technical Report on Material Selection & Processing GL for BWR Coolant Press Boundary Piping,” February 1981.

— — — — —, GL 1981-004, “Emergency Procedures and Training for Station Blackout Events,” February 25, 1981. (ADAMS Accession No. ML031080489.)

— — — — —, GL 1981-010, “Post-TMI Requirements for the Emergency Operations Facility,” February 1981.

— — — — —, GL 1981-011, “BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG–0619),” February 1981.

— — — — —, GL 1981-038, “Storage of LLW at Power Reactor Sites,” November 10, 1981. (ADAMS Accession No. ML031110064.)

— — — — —, GL 1981-039, “NRC Volume Reduction Policy,” November 30, 1981. (ADAMS Accession No. ML031210460.)

— — — — —, GL 1982-009, "Environmental Qualification of Safety-Related Electrical Equipment," April 20, 1982. (ADAMS Accession No. ML031080281.)

— — — — —, GL 1982-021, “Technical Specifications for Fire Protection Audits,” October 6, 1982. (ADAMS Accession No. ML031080469.)

— — — — —, GL 1982-023, “Inconsistency Between Requirements of 10 CFR 73.40(D) and Standard Technical Specifications for Performing Audits of Safeguards Contingency Plans,” October 30, 1982. (ADAMS Accession No. ML031080482.)

B-65

— — — — —, GL 1982-026, Revision 1, "NUREG–0744, Pressure Vessel Material Fracture Toughness," November 1981. (ADAMS Accession No. ML031080494.)

— — — — —, GL 1982-033, “Supplement 1 to NUREG–0737—Requirements for Emergency Response Capability,” December 1982. (ADAMS Accession No. ML031080548.)

— — — — —, GL 1983-005, “Safety Evaluation of ’Emergency Procedure Guidelines,’ Revision 2, NEDO-24934, June 1982,” February 8, 1983. (ADAMS Accession No. ML031210022.)

— — — — —, GL 1984-015, “Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability,” July 2, 1984. (ADAMS Accession No. ML031180013.)

— — — — —, GL 1985-006, “Quality Assurance Guidance for ATWS Equipment that is Not Safety-Related,” April 16, 1985. (ADAMS Accession No. ML031140390.)

— — — — —, GL 1987-002, “Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46,” February 19, 1987. (ADAMS Accession No. ML031150371.)

— — — — —, GL 1987-002, Supplement 1, “Supplement No. 1 to Generic Letter (GL) 87-02 that Transmits Supplemental Safety Evaluation Report No. 2 (SSER No. 2) on SQUG Generic Implementation Procedure, Revision 2, as Corrected on February 14, 1992 (GIP-2)," May 22, 1992. (ADAMS Accession No. ML 031140292.)

— — — — —, GL 1987-009, “Sections 3.0 and 4/0 of the Standard Technical Specifications on the Applicability of Limiting Conditions for Operation and Surveillance Requirements,” June 4, 1987. (ADAMS Accession No. ML031140381.)

— — — — —, GL 1987-011, “Relaxation in Arbitrary Intermediate Pipe Rupture Requirements,” June 19, 1987. (ADAMS Accession No. ML031150493.)

— — — — —, GL 1988-001, “NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping,” January 1988. (ADAMS Accession No. ML031130463.)

— — — — —, GL 1988-001, Supplement 1, “NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping,” February 4, 1992. (ADAMS Accession No. ML031130421.)

— — — — —, GL 1988-014, “Instrument Air Supply System Problems Affecting Safety-Related Equipment,” August 8, 1988. (ADAMS Accession No. ML031130440.)

— — — — —, GL 1988-015, “Electric Power System—Inadequate Control over Design Processes,” September 12, 1988. (ADAMS Accession No. ML031130443.)

— — — — —, GL 1988-016, “Removal of Cycle-Specific Parameter Limits from Technical Specifications,” October 3, 1988. (ADAMS Accession No. ML031130447.)

B-66

— — — — —, GL 1988-020, “Individual Plant Examination for Severe Accident Vulnerabilities – 10 CFR 50.54(f),” November 23, 1988. (ADAMS Accession No. ML031150465.)

— — — — —, GL 1989-001, Supplement 1, “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors,” November 14, 1990. (ADAMS Accession Nos. ML031290465, ML031290469.)

— — — — —, GL 1989-006, “Task Action Plan Item I.D.2—Safety Parameter Display System—10 CFR 50.54(f),” April 12, 1989. (ADAMS Accession No. ML031200729.)

— — — — —, GL 1989-007, “Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs,” April 1989.

— — — — —, GL 1989-008, “Erosion/Corrosion-Induced Pipe Wall Thinning,” May 2, 1989. (ADAMS Accession No. ML031200731.)

— — — — —, GL 1989-010, “Safety-Related Motor-Operated Valve Testing and Surveillance,” June 28, 1989. (ADAMS Accession No. ML031150300.)

— — — — —, GL 1989-013, “Service Water System Problems Affecting Safety-Related Equipment,” July 18, 1989. (ADAMS Accession No. ML031150348.)

— — — — —, GL 1989-013, Supplement 1, “Service Water System Problems Affecting Safety-Related Equipment,” April 4, 1990. (ADAMS Accession No. ML031140185.)

— — — — —, GL 1989-014, “Line-Item Improvements in Technical Specifications—Removal of the 3.25 Limit on Extending Surveillance Intervals,” August 2, 1989. (ADAMS Accession No. ML031140189.)

— — — — —, GL 1989-016, “Installation of a Hardened Wetwell Vent,” September 1, 1989. (ADAMS Accession No. ML031140220.)

— — — — —, GL 1989-022, “Potential for Increased Roof and Plant Area Flood Runoff Depth at Licensed Nuclear Power Plants Due to Recent Change in Probable Maximum Precipitation Criteria Developed by the National Weather Service,” October 19, 1989. (ADAMS Accession No. ML031210438.)

— — — — —, GL 1991-003, “Reporting of Safeguards Events,” March 6, 1991. (ADAMS Accession No. ML031140131.)

— — — — —, GL 1991-004, “Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle,” April 2, 1991. (ADAMS Accession No. ML031140501.)

— — — — —, GL 1991-006, “Resolution of Generic Issue (GI) A-30—‘Adequacy of Safety-Related DC Power Supplies,’ Pursuant to 10 CFR 50.54(f),” April 29, 1991. (ADAMS Accession No. ML031200665.)

— — — — —, GL 1991-010, “Explosives Searches at Protected Area Portals,” July 8, 1991. (ADAMS Accession No. ML031140265.)

B-67

— — — — —, GL 1991-011, “Resolution of GI 48, ‘LCOs for Class 1E Vital Instrument buses,’ and GI 49, ‘Interlocks and LCOs for Class 1E Tie Breakers,’ Pursuant to 10 CFR 50.54 (f),” July 18, 1991. (ADAMS Accession No. ML031200668.)

— — — — —, GL 1991-017 "Bolting Degradation of Failure in Nuclear Power Plants," October 17, 1991. (ADAMS Accession No. ML031140534.)

— — — — —, GL 1993-005, “Line-Item Technical Specification Improvements to Reduce Surveillance Requirements for Testing During Power Operation,” September 27, 1993. (ADAMS Accession No. ML031070342.)

— — — — —, GL 1994-001, “Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators,” May 31, 1994. (ADAMS Accession No. ML031200434.)

— — — — —, GL 1994-002, “Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors,” July 11, 1994. (ADAMS Accession No. ML031070189.)

— — — — —, GL 1995-007, “Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves,” August 17, 1995. (ADAMS Accession No. ML031070145.)

— — — — —, GL 1996-003, “Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits,” January 31, 1996. (ADAMS Accession No. ML031110004.)

— — — — —, GL 1996-005, “Periodic Verification of Design-Basis Capability of Safety-Related Motor Operated Valves,” September 18, 1996. (ADAMS Accession No. ML031110010.)

— — — — —, GL 1996-006, “Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions,” September 30, 1996. (ADAMS Accession No. ML031110021.)

— — — — —, GL 1998-004, “Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System after a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment,” July 14, 1998. (ADAMS Accession No. ML031110081.)

— — — — —, GL 2003-001, “Control Room Habitability,” June 12, 2003. (ADAMS Accession No. ML031620248.)

— — — — —, GL 2007-001, “Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients,” February 7, 2007. (ADAMS Accession No. ML070360665.)

— — — — —, GL 2008-001, “Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,” January 11, 2008. (ADAMS Accession No. ML072910759.)

B-68

Information Notices

— — — — —, IN 1984-87, “Piping Thermal Deflection Induced by Stratified Flow,” December 3, 1984. (ADAMS Accession No. ML082840456.)

— — — — —, IN 1984-93, “Potential for Loss of Water from the Refueling Cavity,” December 17, 1984. (ADAMS Accession No. ML082560407.)

— — — — —, IN 1986-64, “Deficiencies in Upgrade Programs for Plant Emergency Operating Procedures,” August 14, 1986. (ADAMS Accession No. ML031250068.)

— — — — —, IN 1986-83, “Underground Pathways into Protected Areas, Vital Areas, Material Access Areas, and Controlled Access Areas,” September 19, 1986. (ADAMS Accession Nos. ML031250244, ML031250275.)

— — — — —, IN 1988-46, “Licensee Report of Defective Refurbished Circuit Breakers,” July 8, 1988. (ADAMS Accession No. ML031150194.)

— — — — —, IN 1991-38, “Thermal Stratification in Feedwater System Piping,” June 13, 1991. (ADAMS Accession No. ML031190533.)

— — — — —, IN 1994-01, “Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance,” January 7, 1994. (ADAMS Accession No. ML031070067.)

— — — — —, IN 1995-48, “Results of Shift Staffing Study,” October 10, 1995. (ADAMS Accession No. ML031060170.)

— — — — —, IN 1997-78, “Crediting of Operator Actions in Place of Automatic Actions and Modifications of Operator Actions, Including Response Times,” October 23, 1997. (ADAMS Accession No. ML013050065.)

— — — — —, IN 2005-24, “Nonconservatism in Leakage Detection Sensitivity,” August 3, 2005. (ADAMS Accession No. ML051780073.)

— — — — —, IN 2006-18, “Significant Loss of Safety-Related Electrical Power at Forsmark, Unit-1, in Sweden,” August 17, 2006. (ADAMS Accession No. ML062220339.)

Interim Staff Guidance

— — — — —, DI&C-ISG-04, Revision 1, “Highly-Integrated Control Rooms—Communications Issues (HICRc),” March 6, 2009. (ADAMS Accession No. ML083310185.)

— — — — —, DI&C-ISG-05, Revision 1, “Highly-Integrated Control Rooms—Human Factors Issues,” November 3, 2008. (ADAMS Accession No. ML082740440.)

B-69

— — — — —, DC/COL-ISG-07, “Interim Staff Guidance on Assessment of Normal and Extreme Winter Precipitation Loads on the Roofs of Seismic Category I Structures,” June 23, 2009. (ADAMS Accession No. ML091490565.)

— — — — —, DC/COL-ISG-8, “Necessary Content of Plant-Specific Technical Specifications When a Combined License is Issued,” December 9, 2008. (ADAMS Accession No. ML083310259.)

NUREG Series Reports

— — — — —, NUREG–0016, Revision 1, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR),” January 1979.

— — — — —, NUREG–0123, “Standard Technical Specifications General Electric Boiling Water Reactors,” August 1971.

— — — — —, NUREG–0123, Revision 2, “Standard Technical Specifications General Electric Boiling Water Reactors,” August 1979.

— — — — —, NUREG–0133, “Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,” October 1978.

— — — — —, NUREG–0313, Revision 2, “Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping,” January 31,1988. (ADAMS Accession No. ML031470422.)

— — — — —, NUREG–0460, “Anticipated Transients Without Scram for Light Water Reactors,” March 1980.

— — — — —, NUREG–0471, “Generic Task Problem Descriptions (Categories B, C, and D),” June 1978.

— — — — —, NUREG–0484, “Methodology for Combining Dynamic Responses,” September 1978.

— — — — —, NUREG–0484, Revision 1, “Methodology for Combining Dynamic Responses,” May 1980.

— — — — —, NUREG–0493, “A Defense-in-Depth & Diversity Assessment of the RESAR-414 Integrated Protection System,” February 1979.

— — — — —, NUREG–0554, “Single-Failure Proof Cranes for Nuclear Power Plants,” May 1979.

— — — — —, NUREG–0570, “Toxic Vapor Concentrations in Control Room Following Postulated Accidental Release,” June 1979. (ADAMS Accession No. ML063480551.)

B-70

— — — — —, NUREG–0588, “Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,” November 1980. (ADAMS Accession No. ML031480402.)

— — — — —, NUREG–0588, Revision 1, “Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,” July 1981. (ADAMS Accession No. ML031480402.)

— — — — —, NUREG–0609, “Asymmetric Blowdown Loads on PWR Primary Systems,” January 1981.

— — — — —, NUREG–0612, “Control of Heavy Loads at Nuclear Power Plants: Resolution of Generic Technical Activity A-36,” July 1980. (ADAMS Accession No. ML070250180.)

— — — — —, NUREG–0619, “BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,” November 1980. (ADAMS Accession No. ML031600712.)

— — — — —, NUREG–0619, Revision 1, “BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,” November 1980. (ADAMS Accession No. ML031600712.)

— — — — —, NUREG–0654, “Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,” November 1980. (ADAMS Accession No. ML 040420012.)

— — — — —, NUREG–0654/FEMA-REP-1, Revision 1, “Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,” November 1980. (ADAMS Accession No. ML040420012.)

— — — — —, NUREG–0696, “Functional Criteria for Emergency Response Facilities,” February 28, 1981. (ADAMS Accession No. ML051390358.)

— — — — —, NUREG–0700, “Human-System Interface Design Review Guidelines,” May 31, 2002. (ADAMS Accession Nos. ML021700373, ML021700337, ML021700342 and ML021700371.)

— — — — —, NUREG–0700, Revision 2, “Human-System Interface Design Review Guidelines,” May 2002. (ADAMS Accession No. ML 021700373.)

— — — — —, NUREG–0705, “Identification of New Unresolved Safety Issues Relating to Nuclear Power Plants—Special Report to Congress,” March 1981.

— — — — —, NUREG–0711, Revision 2, “Human Factors Engineering Program Review Model,” February 29, 2004. (ADAMS Accession No. ML040770540.)

— — — — —, NUREG–0737, “Clarification of TMI Action Plan Requirements,” November 1980. (ADAMS Accession No. ML051400209.)

— — — — —, NUREG–0737, Supplement 1, “Clarification of TMI Action Plan Requirements,” January 1983. (ADAMS Accession No. ML051390367.)

B-71

— — — — —, NUREG–0744, Revision 1, "Resolution of the Task A-11, Reactor Vessel Materials Toughness Safety Issue," October 1982.

— — — — —, NUREG–0763, “Guidelines for Confirmatory In-Plant Tests of Safety Relief Valve Discharges for BWR Plants,” May 1981.

— — — — —, NUREG–0782, “Draft Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Waste,” September 1981. (ADAMS Accession No. ML052590348.)

— — — — —, NUREG–0783, “Suppression Pool Temperature Limits for BWR Containment,” November 1981.

— — — — —, NUREG–0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (LWR Edition),” March 2007. (ADAMS Accession No. ML070660036.)

— — — — —, NUREG–0800, Section 4.2, Revision 2, “Fuel System Design,” July 1981. (ADAMS Accession No. ML052340660.)

— — — — —, NUREG–0800, Section 4.2, Revision 3, “Fuel System Design,” March 2007. (ADAMS Accession No. ML070740002.)

— — — — —, NUREG–0800, Section 14.2, Draft Revision 3, “Initial Plant Test Program,” April 1996. (ADAMS Accession No. ML052070650.)

— — — — —, NUREG–0800, Section 15.0.2, “Review of Analytical Computer Codes,” December 2000. (ADAMS Accession No. ML003773356.)

— — — — —, NUREG–0802, “Safety/Relief Valve Quencher Loads: Evaluation for BWR Mark II and III Containments,” October 1982.

— — — — —, NUREG–0803, “Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping,” August 1981. (ADAMS Accession No. ML072500084.)

— — — — —, NUREG–0808, “Mark II Containment Program Load Evaluation and Acceptance Criteria,” August 1981.

— — — — —, NUREG–0927, “Evaluation of Water Hammer Occurrences in Nuclear Power Plants,” March 1984.

— — — — —, NUREG–0933, “Resolution of Generic Safety Issues (Formerly Entitled ‘A Prioritization of Generic Safety Issues’),” August 2008. (ADAMS Accession No. ML082410719.)

— — — — —, NUREG–0978, “Mark III LOCA-Related Hydrodynamic Load Definition,” August 1984.

— — — — —, NUREG–1000, Volume 1, “Generic Implications of ATWS Events at the Salem Nuclear Power Plant,” April 1983.

B-72

— — — — —, NUREG–1061, “Report of the U.S. Nuclear Regulatory Commission Piping Review Committee: Evaluation of Other Loads and Load Combinations,” December 1984.

— — — — —, NUREG–1174, “Evaluation of Systems Interactions in Nuclear Power Plants: Technical Findings Related to Unresolved Safety Issue A-17,” May 1989.

— — — — —, NUREG–1229, “Regulatory Analysis for Resolution of USI A-17,” August 1989.

— — — — —, NUREG–1242, “NRC Review of EPRI Advanced LWR Utility Requirements Document,” August 1992.

— — — — —, NUREG–1275, Volume 2, “Operating Experience Feedback Reported - Air Systems Problems,” December 1987.

— — — — —, NUREG–1302, “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for BWRs,” April 1991.

— — — — —, NUREG–1342, “A Status Report Regarding Industry Implementation of Safety Parameter Display System,” April 1989.

— — — — —, NUREG–1344, “Erosion/Corrosion-Induced Pipe Wall Thinning in U.S. Nuclear Power Plants,” April 1989.

— — — — —, NUREG–1358, “Lessons Learned from the Special Inspection Program for Emergency Operating Procedures,” April 1989.

— — — — —, NUREG–1367, “Functional Capability of Piping Systems,” November 1992. (ADAMS Accession No. ML083510056.)

— — — — —, NUREG–1431, Revision 3, “Standard Technical Specifications—Westinghouse Plants,” June 2004. (ADAMS Accession No. ML041830612.)

— — — — —, NUREG–1433, Revision 3, “Standard Technical Specifications, General Electric Plants, BWR/4,” June 2004. (ADAMS Accession No. ML 041910194.)

— — — — —, NUREG–1434, Volume 1, Revision 3, “Standard Technical Specifications General Electric Plants, BWR/6,” June 2004. (ADAMS Accession No. ML041910204.)

— — — — —, NUREG–1449, “Shutdown and Low-Power Operations at Commercial Nuclear Power Plants in the United States,” September 30, 1993. (ADAMS Accession No. ML063470582.)

— — — — —, NUREG–1465, “Accident Source Terms for Light-Water Nuclear Power Plants,” February 1995. (ADAMS Accession No. ML041040063.)

— — — — —, NUREG–1482, Revision 1, “Guidelines for Inservice Testing at Nuclear Power Plants: Final Report,” January 2005. (ADAMS Accession No. ML050550290.)

B-73

— — — — —, NUREG–1503, “Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design,” July 1994. (ADAMS Accession No. ML080670592.)

— — — — —, NUREG–1512, “Final Safety Evaluation Report Related to Certification of the AP600 Standard Design,” September 1998. (ADAMS Accession No. ML. ML081160453.)

— — — — —, NUREG–1552, “Fire Barrier Penetration Seals in Nuclear Power Plants,” July 1996. (ADAMS Accession No. ML070600315.)

— — — — —, NUREG–1552, Supplement 1, “Fire Barrier Penetration Seals in Nuclear Power Plants,” January 1999. (ADAMS Accession No. ML070600313.)

— — — — —, NUREG–1560, “Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance,” October 1997.

— — — — —, NUREG–1736, “Consolidated Guidance: 10 CFR Part 20—Standards for Protection Against Radiation,” October 2001. (ADAMS Accession No. ML013330179.)

— — — — —, NUREG–1774, “A Survey of Crane Operating Experience at U.S. Nuclear Power Plants from 1968 through 2002,” July 2003. (ADAMS Accession No. ML032060160.)

— — — — —, NUREG–1793, “Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design,” September 2004. (ADAMS Accession No. ML043570339.)

— — — — —, NUREG–1801, Revision 1, “Generic Aging Lessons Learned (GALL) Report,” September 2005. (ADAMS Accession Nos. ML052770419, 052780376.)

— — — — —, NUREG–1835, “Safety Evaluation Report for an Early Site Permit (ESP) at the North Anna ESP Site,” September 2005. (ADAMS Accession No. ML052710305.)

— — — — —, NUREG–1837, “Regulatory Effectiveness Assessment of Generic Issue 43 and Generic Letter 88-14,” October 2005. (ADAMS Accession No. ML053040160.)

— — — — —, NUREG–1840, “Safety Evaluation Report for an Early Site Permit (ESP) at the Grand Gulf Site,” April 2006. (ADAMS Accession No. ML061070443.)

— — — — —, NUREG–1844, “Safety Evaluation Report for an Early Site Permit (ESP) at the Exelon Generation Company, LLC (EGC) ESP Site,” May 2006. (ADAMS Accession No. ML061210203.)

— — — — —, NUREG/BR–0058, Revision 4, “Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission,” August 2004. (ADAMS Accession No. ML042820192.)

— — — — —, NUREG/BR–0184, “Regulatory Analysis Technical Evaluation Handbook,” January 1997. (ADAMS Accession No. ML050190193.)

B-74

— — — — —, NUREG/CR–0098, “Development of Criteria for Seismic Review of Selected Nuclear Power Plants,” May 1978. (ADAMS Accession No. ML061882412.)

— — — — —, NUREG/CR–1161, “Recommended Revisions to NRC Seismic Design Criteria,” May 1980.

— — — — —, NUREG/CR–1677, “Piping Benchmark Problems Dynamic Analysis Uniform Support Motion Response Spectrum Method,” August 1980.

— — — — —, NUREG/CR–1677, Volume 2, “Piping Benchmark Problems - Dynamic Analysis Independent Support Motion Response Spectrum Method,” August 1985.

— — — — —, NUREG/CR–1980, “Dynamic Analysis of Piping, Using the Structural Overlap Method,” March 1981.

— — — — —, NUREG/CR–2239, “Technical Guidance for Siting Criteria Development,” December 1982.

— — — — —, NUREG/CR–2300, “A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants,” January 1983. (ADAMS Accession Nos. ML063560439, ML063560440, ML092870607.)

— — — — —, NUREG/CR–2919, “XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,” September 1982.

— — — — —, NUREG/CR–3331, “A Methodology for Allocation of Nuclear Power Plant Control Functions to Human and Automated Control.” August 1983.

— — — — —, NUREG/CR–3587, “Identification and Evaluation of Facilitation Techniques for Decommissioning Light Water Power Reactors,” June 30, 1986. (ADAMS Accession No. ML081360413.)

— — — — —, NUREG/CR–3862, “Development of Transient Initiating Event Frequencies for Use in Probabilistic Risk Assessments,” May 1985.

— — — — —, NUREG/CR–4013, “LADTAP II – Technical Reference and User Guide,” April 1986.

— — — — —, NUREG/CR–4250, “Vehicle Barriers: Emphasis on Natural Features,” July 1985.

— — — — —, NUREG/CR–4461, Revision 1, “Tornado Climatology of the Contiguous United States,” May 1986.

— — — — —, NUREG/CR–4461, Revision 2, “Tornado Climatology of the Contiguous United States,” January 1987.

— — — — —, NUREG/CR–4513, Revision 1, “Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems,” August 31, 1994. (ADAMS Accession No. ML052360554.)

B-75

— — — — —, NUREG/CR–4663, “GASPAR II – Technical Reference and User Guide,” March 1987.

— — — — —, NUREG/CR–4780, Volume 1, “Procedures for Treating Common Cause Failures in Safety and Reliability Studies,” January 1988.

— — — — —, NUREG/CR–4780, Volume 2, “Procedures for Treating Common Cause Failures in Safety and Reliability Studies,” January 1989.

— — — — —, NUREG/CR–5249, Revision 4, “Quantifying Reactor Safety Margins: Application of Code Scaling Applicability, and Uncertainty Evaluation Methodology to a Large-Break, Loss-of-Coolant Accident,” December 1989. (ADAMS Accession No. ML070310119.)

— — — — —, NUREG/CR–5347, “Recommendations for Resolution of Public Comments on USI A-40,” June 1989.

— — — — —, NUREG/CR–5385, “Initial Assessment of the Mechanisms and Significance of Low-Temperature Embrittlement of Cast Stainless Steels in LWR Systems,” August 1990.

— — — — —, NUREG/CR–5407, “Assessment of the Impact of Degraded Shear Wall Stiffnesses on Seismic Plant Risk and Seismic Design Loads,” February 1994.

— — — — —, NUREG/CR–5497, “Common Cause Failure Parameter Estimations,” October 1998.

— — — — —, NUREG/CR–5750, “Rates of Initiating Events at U.S Nuclear Power Plants 1987-1995,” February 1999.

— — — — —, NUREG/CR–5801, “Procedures for Analysis of Common Cause Failure in Safety Analysis,” April 1993.

— — — — —, NUREG/CR–5809, “A Hierarchical, Two-Tiered Scaling Analysis,” November 1991.

— — — — —, NUREG/CR–5950, “Iodine Evolution and pH Control,” December 31, 1992. (ADAMS Accession No. ML063460464.)

— — — — —, NUREG/CR–6049, “Piping Benchmark Problems for the General Electric Advanced Boiling Water Reactor,” August 1993.

— — — — —, NUREG/CR–6082, “Data Communications,” August 1993. (ADAMS Accession No. ML063530379.)

— — — — —, NUREG/CR–6101, "Software Reliability and Safety in Nuclear Reactor Protection Systems,” November 1993.

— — — — —, NUREG/CR–6119, Gauntt, R.O., et al, Version 1.8.5, Vol. 1, Revision 2, “MELCOR Computer Code Manuals: Primer and User’s Guide,” December 31, 2000. (ADAMS Accession Nos. ML010120456, ML010190162.)

B-76

— — — — —, NUREG/CR–6119, Gauntt, R.O., et al, Version 1.8.5, Vol. 2, Revision 2, “MELCOR Computer Code Manuals: Reference Manuals,” December 31, 2000. (ADAMS Accession Nos. ML010190117, ML010190222, ML010190463.)

— — — — —, NUREG/CR–6119, Gauntt, R.O., et al, Version 1.8.5, Vol. 3, “MELCOR Computer Code Manuals: Demonstration Problems May 2001,” September 30, 2001. (ADAMS Accession No. ML012670311.)

— — — — —, NUREG/CR–6303, “Method for Performing Diversity and Defense-in-Depth Analyses of Reactor Protection Systems,” December 1994. (ADAMS Accession No. ML071790509.)

— — — — —, NUREG/CR–6331, Revision 1, “Atmospheric Relative Concentrations in Building Wakes,” May 1997.

— — — — —, NUREG/CR–6400, “HFE Insights for Advanced Reactors Based upon Operating Experience,” January 1997.

— — — — —, NUREG/CR–6409, BNL-NUREG–52377 (Attachment B), “Piping Benchmark Problems for the General Electric Advanced Boiling Water Reactor,” August 1993.

— — — — —, NUREG/CR–6595, “An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events,” January 1999.

— — — — —, NUREG/CR–6645, “Reevaluation of Regulatory Guidance on Modal Combination Methods for Seismic Response Spectrum Analysis,” December 1999. (ADAMS Accession No. ML003724092.)

— — — — —, NUREG/CR–6696, ORNL/TM-2000/340, “LAPUR5.2 Verification and User’s Manual,” November 2000. (ADAMS Accession No. ML010520049.)

— — — — —, NUREG/CR–6728, “Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Hazard- and Risk-Consistent Ground Motion Spectra Guidelines,” October 2001. (ADAMS Accession No. ML013100232.)

— — — — —, NUREG/CR–6847, “Cyber Security Self-Assessment Method for U.S. Nuclear Power Plants,” October 2004. (ADAMS Accession No. ML043200191.)

— — — — —, NUREG/CR–6850 (EPRI 1011989), “Fire PRA Methodology for Nuclear Power Facilities,” September 2005. (ADAMS Accession Nos. ML052580075, ML052580118.)

— — — — —, NUREG/CR–6890, Volume 1, “Reevaluation of Station Blackout Risk at Nuclear Power Plants Analysis of Loss of Offsite Power Events: 1986–2004,” December 31, 2005. (ADAMS Accession No. ML060200477.)

— — — — —, NUREG/CR–6909, “Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials,” February 2007. (ADAMS Accession No. ML070660620.)

B-77

— — — — —, NUREG/CR–6928, “Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants,” February 28, 2007. (ADAMS Accession No. ML070650650.)

Policy Statements

— — — — —, NRC Policy Statement, 50 FR 32138, “Severe Reactor Accidents Regarding Future Designs and Existing Plants,” August 8, 1985. (ADAMS Accession No. ML003711521.)

— — — — —, NRC Policy Statement, 51 FR 28044, “Safety Goals for the Operations of Nuclear Power Plants,” August 4, 1986. (ADAMS Accession No. ML051580401.)

— — — — —, NRC Policy Statement, 52 FR 34884, “Nuclear Power Plant Standardization,” September 15, 1987. (ADAMS Accession No. ML003711530.)

— — — — —, NRC Policy Statement, 60 FR 42622, “The Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities,” August 16, 1995. (ADAMS Accession No. ML021980535.)

Regulatory Guides

— — — — —, RG 1.6, “Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6),” March 1971. (ADAMS Accession No. ML003739924.)

— — — — —, RG 1.7, Revision 3, “Control of Combustible Gas Concentrations in Containment,” March 2007. (ADAMS Accession No. ML070290080.)

— — — — —, RG 1.8, Revision 3, “Qualification and Training of Personnel for Nuclear Power Plants,” May 2000. (ADAMS Accession No. ML003706932.)

— — — — —, RG 1.9, Revision 3, “Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants,” July 1993. (ADAMS Accession No. ML003739929.)

— — — — —, RG 1.11, “Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11),” March 1971, (ADAMS Accession No. ML003739934), and related Supplement to Safety Guide 11, “Backfitting Considerations,” February 1972.

— — — — —, RG 1.12, Revision 2, "Nuclear Power Plant Instrumentation for Earthquakes," March 1997. (ADAMS Accession No. ML003739944.)

— — — — —, RG 1.13, “Spent Fuel Storage Facility Design Basis,” March 1971.

— — — — —, RG 1.13, Revision 2, "Spent Fuel Storage Facility Design Basis," March 2007. (ADAMS Accession No. ML070310035.)

B-78

— — — — —, RG 1.20, Revision 3, "Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing,” March 2007. (ADAMS Accession No. ML070260376.)

— — — — —, RG 1.21, Revision 1, “Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,” June 1974. (ADAMS Accession No. ML003739960.)

— — — — —, RG 1.22, “Periodic Testing of Protection System Actuation Functions,” February 1972. (ADAMS Accession No. ML083300530.)

— — — — —, RG 1.23, Revision 1, “Meteorological Monitoring Programs for Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070350028.)

— — — — —, RG 1.26, Revision 3, “Quality Groups Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants,” February 1976. (ADAMS Accession No. ML003739964.)

— — — — —, RG 1.26, Revision 4, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants," March 2007. (ADAMS Accession No. ML070290283.)

— — — — —, RG 1.27, Revision 2, "Ultimate Heat Sink for Nuclear Power Plants (for Comment)," January 1976. (ADAMS Accession No. ML003739969.)

— — — — —, RG 1.28, Revision 3, “Quality Assurance Program Requirements (Design and Construction),” August 1985. (ADAMS Accession No. ML003739981.)

— — — — —, RG 1.28, Revision 4, "Quality Assurance Program Criteria (Design and Construction)," June 2010. (ADAMS Accession No. ML100160003.)

— — — — —, RG 1.29, “Seismic Design Classification,” June 1972.

— — — — —, RG 1.29, Revision 3, “Seismic Design Classification,” September 1978. (ADAMS Accession No. ML003739983.)

— — — — —, RG 1.29, Revision 4, “Seismic Design Classification,” March 2007. (ADAMS Accession No. ML070310052.)

— — — — —, RG 1.31, Revision 3, “Control of Ferrite Content in Stainless Steel Weld Metal,” April 1978. (ADAMS Accession No. ML003739986.)

— — — — —, RG 1.32, Revision 2, “Criteria for Power Systems for Nuclear Power Plants,” February 1977. (ADAMS Accession No. ML003739990.)

— — — — —, RG 1.32, Revision 3, “Criteria for Power Systems for Nuclear Power Plants,” March 2004. (ADAMS Accession No. ML040680488.)

— — — — —, RG 1.33, “Quality Assurance Program Requirements (Operation),” November 1972.

B-79

— — — — —, RG 1.33, Revision 2, “Quality Assurance Program Requirements (Operation),” February 1978. (ADAMS Accession No. ML003739995.)

— — — — —, RG 1.33, Appendix A, “Quality Assurance Program Requirements (Operation),” February 1978. (ADAMS Accession No. ML003739995.)

— — — — —, RG 1.34, “Control of Electroslag Weld Properties,” December 1972. (ADAMS Accession No. ML003739997.)

— — — — —, RG 1.36, “Nonmetallic Thermal Insulation for Austenitic Stainless Steel,” February 1973. (ADAMS Accession No. ML003740046.)

— — — — —, RG 1.37, “Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants,” March 1973. (ADAMS Accession No. ML003740051.)

— — — — —, RG 1.37, Revision 1, “Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070250571.)

— — — — —, RG 1.39, “Housekeeping Requirements for Water-Cooled Nuclear Power Plants,” September 1977. (ADAMS Accession No. ML003740067.)

— — — — —, RG 1.43, “Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components,” May 1973. (ADAMS Accession No. ML003740095.)

— — — — —, RG 1.44, “Control of the Use of Sensitized Stainless Steel,” May 1973. (ADAMS Accession No. ML003740109.)

— — — — —, RG 1.45, “Reactor Coolant Pressure Boundary Leakage Detection Systems,” May 1973. (ADAMS Accession No. ML003740113.)

— — — — —, RG 1.45, Revision 1, “Guidance on Monitoring and responding to Reactor Coolant System Leakage,” May 2008. (ADAMS Accession No. ML073200271.)

— — — — —, RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems,” May 1973. (ADAMS Accession No. ML003740127.)

— — — — —, RG 1.47, Revision 1, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems,” February 2010. (ADAMS Accession No. ML0923330064.)

— — — — —, RG 1.50, “Control of Preheat Temperature Employed for Welding of Low-Alloy Steel,” May 1973. (ADAMS Accession No. ML003740136.)

— — — — —, RG 1.52, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants,” March 1978. (ADAMS Accession No. ML003740139.)

B-80

— — — — —, RG 1.52, Revision 3, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants,” June 2001. (ADAMS Accession No. ML011710176.)

— — — — —, RG 1.53, Revision 2, “Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems,” November 2003. (ADAMS Accession No. ML033220006.)

— — — — —, RG 1.54, Revision 1, "Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants," July 2000. (ADAMS Accession No. ML003714475.)

— — — — —, RG 1.56, “Maintenance of Water Purity in Boiling Water Reactors (for Comment),” June 1973.

— — — — —, RG 1.56, Revision 1, “Maintenance of Water Purity in Boiling Water Reactors,” July 1978. (ADAMS Accession No. ML003740192.)

— — — — —, RG 1.57, Revision 1, "Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components," March 2007. (ADAMS Accession No. ML070310029.)

— — — — —, RG 1.59, Revision 1, “Design-Basis Floods for Nuclear Power Plants,” April 1976.

— — — — —, RG 1.59, Revision 2, "Design Basis Floods for Nuclear Power Plants," August 1977. (ADAMS Accession No. ML003740388.)

— — — — —, RG 1.60, Revision 1, “Design Response Spectra for Seismic Design of Nuclear Power Plants,” December 1973. (ADAMS Accession No. ML003740207.)

— — — — —, RG 1.61, “Damping Values for Seismic Design of Nuclear Power Plants,” October 1973. (ADAMS Accession No. ML003740213.)

— — — — —, RG 1.61, Revision 1, "Damping Values for Seismic Design of Nuclear Power Plants," March 2007. (ADAMS Accession No. ML070260029.)

— — — — —, RG 1.62, “Manual Initiation of Protective Actions,” October 1973. (ADAMS Accession No. ML003740216.)

— — — — —, RG 1.62, Revision 1, “Manual Initiation of Protective Actions,” June 2010. (ADAMS Accession No. ML092530559.)

— — — — —, RG 1.63, “Electric Penetration Assemblies in Containment Structures for Nuclear Plants,” September 1987. (ADAMS Accession No. ML003740219.)

— — — — —, RG 1.63, Revision 3, "Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants," February 1987. (ADAMS Accession No. ML003740219.)

B-81

— — — — —, RG 1.65, “Materials and Inspections for Reactor Vessel Closure Studs,” October 1973. (ADAMS Accession No. ML003740228.)

— — — — —, RG 1.65, Revision 1, "Materials and Inspections for Reactor Vessel Closure Studs," April 2010. (ADAMS Accession No. ML092050716.)

— — — — —, RG 1.68, Revision 2, “Initial Test Programs for Water-Cooled Nuclear Power Plants,” August 1978. (ADAMS Accession No. ML061880482.)

— — — — —, RG 1.68, Revision 3, “Initial Test Programs for Water-Cooled Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070260039.)

— — — — —, RG 1.68.1, Revision 1, “Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants,” January 1977. (ADAMS Accession No. ML003740230.)

— — — — —, RG 1.68.3, “Preoperational Testing of Instrument and Control Air Systems,” April 1982. (ADAMS Accession No. ML003740231.)

— — — — —, RG 1.69, “Concrete Radiation Shields for Nuclear Power Plants,” December 1973. (ADAMS Accession No. ML003740235.)

— — — — —, RG 1.69, Revision 1, "Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants," May 2009. (ADAMS Accession No. ML090820425.)

— — — — —, RG 1.70, Revision 3, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants,” November 1978. (ADAMS Accession No. ML011340116.)

— — — — —, RG 1.71, “Welder Qualification for Areas of Limited Accessibility,” December 1973. (ADAMS Accession No. ML003740244.)

— — — — —, RG 1.71, Revision 1, “Welder Qualification for Areas of Limited Accessibility,” March 2007. (ADAMS Accession No. ML070320476.)

— — — — —, RG 1.75, Revision 3, “Criteria for Independence of Electrical Safety Systems,” February 2005. (ADAMS Accession No. ML043630448.)

— — — — —, RG 1.76, Revision 0, “Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants,” April 1974. (ADAMS Accession No. ML003740273.)

— — — — —, RG 1.76, Revision 1, “Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070360253.)

— — — — —, RG 1.78, “Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release,” December 2001. (ADAMS Accession No. ML013100014.)

— — — — —, RG 1.79, Revision 1, “Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors,” September 1975. (ADAMS Accession No. ML003740351.)

B-82

— — — — —, RG 1.81, Revision 1, “Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants,” January 1975. (ADAMS Accession No. ML003740343.)

— — — — —, RG 1.82, Revision 3, “Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident,” November 2003. (ADAMS Accession No. ML031960432.)

— — — — —, RG 1.84, Revision 33, “Design, Fabrication and Material Code Case Acceptability,” August 2005. (ADAMS Accession No. ML052130562.)

— — — — —, RG 1.84, Revision 34, “Design, Fabrication, and Materials Code Case Acceptability, ASME Section III,” October 2007. (ADAMS Accession No. ML072070407.)

— — — — —, RG 1.89, Revision 1, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," June 1984. (ADAMS Accession No. ML003740271.)

— — — — —, RG 1.91, Revision 1, “Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants,” February 1978. (ADAMS Accession No. ML003740286.)

— — — — —, RG 1.92, Revision 1, “Combining Modal Responses and Spatial Components in Seismic Response Analysis,” February 1976. (ADAMS Accession No. ML003740290.)

— — — — —, RG 1.92, Revision 2, "Combining Modal Responses and Spatial Components in Seismic Response Analysis," July 2006. (ADAMS Accession No. ML053250475.)

— — — — —, RG 1.94, Revision 1, "Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants," April 1976. (ADAMS Accession No. ML003740305.)

— — — — —, RG 1.95, Revision 1, “Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release,” January 2002.

— — — — —, RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants,” December 1975.

— — — — —, RG 1.97, Revision 2, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident,” December 1980. (ADAMS Accession No. ML060750525.)

— — — — —, RG 1.97, Revision 3, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants,” May 1983. (ADAMS Accession No. ML003740282.)

— — — — —, RG 1.97, Revision 4, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants,” June 2006. (ADAMS Accession No. ML061580448.)

B-83

— — — — —, RG 1.99, Revision 2, “Radiation Embrittlement of Reactor Vessel Materials,” May 1988. (ADAMS Accession No. ML031430205.)

— — — — —, RG 1.99, Revision 2, “Radiation Embrittlement of Reactor Vessel Materials,” May 1988. (ADAMS Accession No. ML003740284.)

— — — — —, RG 1.100, Revision 3, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants," September 2009. (ADAMS Accession No. ML091320468.)

— — — — —, RG 1.101, Revision 4, “Emergency Planning and Preparedness for Nuclear Power Reactors,” July 2003. (ADAMS Accession ML030440627.)

— — — — —, RG 1.102, Revision 1, “Flood Protection for Nuclear Power Plants,” September 1976. (ADAMS Accession No. ML003740308.)

— — — — —, RG 1.105, “Setpoints for Safety-Related Instrumentation,” December 1999. (ADAMS Accession No. ML993560062.)

— — — — —, RG 1.108, Revision 1, “Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants,” August 1993.

— — — — —, RG 1.109, “Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,” October 1977. (ADAMS Accession No. ML003740384.)

— — — — —, RG 1.110, “Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors (for comment),” March 1976. (ADAMS Accession No. ML003740332.)

— — — — —, RG 1.111, Revision 1, “Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,” July 1977. (ADAMS Accession No. ML003740354.)

— — — — —, RG 1.112, Revision 1, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,” March 2007. (ADAMS Accession No. ML070320241.)

— — — — —, RG 1.114, “Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit,” October 2008. (ADAMS Accession No. ML082380236.)

— — — — —, RG 1.115, Revision 1, “Protection Against Low-Trajectory Turbine Missiles,” July 1977. (ADAMS Accession No. ML003739456.)

— — — — —, RG 1.116, Revision 0-R, “Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems,” May 1977. (ADAMS Accession No. ML003739465.)

— — — — —, RG 1.117, “Tornado Design Classification,” April 1978. (ADAMS Accession No. ML003739346.)

B-84

— — — — —, RG 1.117, Revision 1, "Tornado Design Classification," April 1978. (ADAMS Accession No. ML003739346.)

— — — — —, RG 1.122, Revision 1, "Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components," February 1978. (ADAMS Accession No. ML003739367.)

— — — — —, RG 1.118, Revision 3, “Periodic Testing of Electric Power and Protection Systems,” April 1995. (ADAMS Accession No. ML003739468.)

— — — — —, RG 1.123, “Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants,” July 1991.

— — — — —, RG 1.124, Revision 2, "Service Limits and Loading Combinations for Class 1 Linear-Type Supports," February 2007. (ADAMS Accession No. ML070160591.)

— — — — —, RG 1.127, Revision 1, "Inspection of Water-Control Structures Associated with Nuclear Power Plants," March 1978. (ADAMS Accession No. ML003739392.)

— — — — —, RG 1.128, “Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants,” October 1978. (ADAMS Accession No. ML037400990.)

— — — — —, RG 1.128, Revision 2, “Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants,” February 2007. (ADAMS Accession No. ML070080013.)

— — — — —, RG 1.129, “Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Nuclear Power Plants,” February 1978. (ADAMS Accession No. ML037401040.)

— — — — —, RG 1.130, “Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports,” March 2007. (ADAMS Accession No. ML070170053.)

— — — — —, RG 1.133, Revision 1, “Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors,” May 1981. (ADAMS Accession No. ML003740137.)

— — — — —, RG 1.136, Revision 3, “Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments,” March 2007. (ADAMS Accession No. ML070310045.)

— — — — —, RG 1.137, “Fuel Oil Systems for Standby Diesel Generators,” October 1979. (ADAMS Accession No. ML003740180.)

— — — — —, RG 1.139, “Guidance for Residual Heat Removal,” May 1978. (ADAMS Accession No. ML040750334.)

B-85

— — — — —, RG 1.140, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants,” June 2001. (ADAMS Accession No. MLML011710150.)

— — — — —, RG 1.141, “Containment Isolation Provisions for Fluid Systems,” April 1978. (ADAMS Accession No. ML003740194.)

— — — — —, RG 1.141, Revision 1, “Containment Isolation Provisions for Fluid Systems,” July 2010. (ADAMS Accession No. ML092850042.)

— — — — —, RG 1.142, Revision 2, "Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)," November 2001. (ADAMS Accession No. ML013100274.)

— — — — —, RG 1.143, “Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants,” October 1979. (ADAMS Accession No. ML003740200.)

— — — — —, RG 1.143, Revision 2, “Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants,” November 2001. (ADAMS Accession No. ML013100305.)

— — — — —, RG 1.145, Revision 1, “Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants,” November 1982. (ADAMS Accession No. ML003740205.)

— — — — —, RG 1.147, “Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1,” October 2007. (ADAMS Accession No. ML072070419.)

— — — — —, RG 1.149, “Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations,” October 2001. (ADAMS Accession No. ML012770164.)

— — — — —, RG 1.149, Revision 3, “Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations,” October 2001. (ADAMS Accession No. ML012770164.)

— — — — —, RG 1.151, “Instrument Sensing Lines,” July 1983. (ADAMS Accession No. ML003740003.)

— — — — —, RG 1.151, Revision 1, “Instrument Sensing Lines,” July 2010. (ADAMS Accession No. ML092330219.)

— — — — —, RG 1.152, Revision 2, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” January 2006. (ADAMS Accession No. ML053070150.)

— — — — —, RG 1.153, Revision 1, “Criteria for Safety Systems,” June 1996. (ADAMS Accession No. ML003740022.)

— — — — —, RG 1.155, “Station Blackout,” August 1988. (ADAMS Accession No. ML003716792.)

B-86

— — — — —, RG 1.160, Revision 2, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” March 1997. (ADAMS Accession No. ML003761662.)

— — — — —, RG 1.163, “Performance-Based Containment Leak-Test Program,” September 1995. (ADAMS Accession No. ML003740058.)

— — — — —, RG 1.166, "Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions," March 1997. (ADAMS Accession No. ML003740089.)

— — — — —, RG 1.167, "Restart of a Nuclear Power Plant Shut Down by a Seismic Event," March 1997. (ADAMS Accession No. ML003740093.)

— — — — —, RG 1.168, Revision 1, “Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” February 2004. (ADAMS Accession No. ML040410189.)

— — — — —, RG 1.169, “Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” September 1997. (ADAMS Accession No. ML003740102.)

— — — — —, RG 1.170, “Software Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” September 1997. (ADAMS Accession No. ML003740105.)

— — — — —, RG 1.171, “Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” September 1997. (ADAMS Accession No. ML003740108.)

— — — — —, RG 1.172, “Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” September 1997. (ADAMS Accession No. ML003740094.)

— — — — —, RG 1.173, “Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” September 1997. (ADAMS Accession No. ML003740101.)

— — — — —, RG 1.174, Revision 1, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” November 2002. (ADAMS Accession No. ML023240437.)

— — — — —, RG 1.177, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications,” August 1998. (ADAMS Accession No. ML003740176.)

— — — — —, RG 1.180, Revision 1, "Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems," October 2003. (ADAMS Accession No. ML032740277.)

B-87

— — — — —, RG 1.182, Revision 0, “Assessing and Managing Risk before Maintenance Activities at Nuclear Power Plants,” May 2000. (ADAMS Accession No. ML003740117.)

— — — — —, RG 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,” July 2000. (ADAMS Accession No. ML003716792.)

— — — — —, RG 1.189, Revision 1, “Fire Protection for Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070370183.)

— — — — —, RG 1.189, Revision 2, “Fire Protection for Nuclear Power Plants,” October 2009. (ADAMS Accession No. ML092580550.)

— — — — —, RG 1.190, “Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence,” March 2001. (ADAMS Accession No. ML010890301.)

— — — — —, RG 1.192, “Operation and Maintenance Code Case Acceptability, ASME OM Code,” June 2003. (ADAMS Accession No. ML030730430.)

— — — — —, RG 1.193, Revision 2, "ASME Code Cases Not Approved for Use," October 2007. (ADAMS Accession No. ML072470294.)

— — — — —, RG 1.194, “Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants,” June 2003. (ADAMS Accession No. ML031530505.)

— — — — —, RG 1.195, “Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors,” May 2003. (ADAMS Accession No. ML031490640.)

— — — — —, RG 1.197, “Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors,” May 2003. (ADAMS Accession No. ML031490664.)

— — — — —, RG 1.199, "Anchoring Components and Structural Supports in Concrete," November 2003. (ADAMS Accession No. ML033360660.)

— — — — —, RG 1.200, Revision 1, “An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,” January 2007. (ADAMS Accession No. ML070240001.)

— — — — —, RG 1.200, Revision 2, “An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,” March 2009. (ADAMS Accession No. ML090410014.)

— — — — —, RG 1.201, Revision 1, “Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance,” May 2006. (ADAMS Accession No. ML061090627.)

B-88

— — — — —, RG 1.204, “Guidelines for Lightning Protection of Nuclear Power Plants,” November 2005. (ADAMS Accession No. ML052290422.)

— — — — —, RG 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition),” June 2007. (ADAMS Accession No. ML070720184.)

— — — — —, RG 1.207, "Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors," March 2007. (ADAMS Accession No. ML070380586.)

— — — — —, RG 1.208, "A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion," March 2007. (ADAMS Accession No. ML070310619.)

— — — — —, RG 1.209, "Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants," March 2007. (ADAMS Accession No. ML070190294.)

— — — — —, RG 4.1, Revision 1, “Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants,” April 1975. (ADAMS Accession No. ML003739496.)

— — — — —, RG 4.7, Revision 2, “General Site Suitability Criteria for Nuclear Power Stations,” April 1998. (ADAMS Accession No. ML003739894.)

— — — — —, RG 4.8, “Environmental Technical Specifications for Nuclear Power Plants (for Comment),” December 1975.

— — — — —, RG 4.15, “Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination)—Effluent Streams and the Environment,” December 1977.

— — — — —, RG 4.15, Revision 2, “Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination)-Effluent Streams and the Environment,” July 2007. (ADAMS Accession No. ML071790506.)

— — — — —, RG 4.21, “Minimization of Contamination and Radioactive Waste Generation: Life-Cycle Planning,” June 2008. (ADAMS Accession No. ML080500187.)

— — — — —, RG 5.12, “General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials,” November 1973. (ADAMS Accession No. ML003740035.)

— — — — —, RG 5.44, Revision 3, “Perimeter Intrusion Alarm Systems,” October 1997. (ADAMS Accession No. ML003739217.)

— — — — —, RG 5.65, “Vital Area Access Controls, Protection of Physical Security Equipment, and Key and Lock Controls,” September 1986. (ADAMS Accession No. ML003739336.)

— — — — —, RG 5.7, Revision 1, “Entry/Exit Control for Protected Areas, Vital Areas, and Material Access Areas,” May 1980. (ADAMS Accession No. ML003739976.)

B-89

— — — — —, RG 8.2, “Guide for Administrative Practices in Radiation Monitoring,” February 1973. (ADAMS Accession No. ML003739444.)

— — — — —, RG 8.7, Revision 2, “Instructions for Record Keeping and Recording Occupational Radiation Exposure Data,” November 2005. (ADAMS Accession No. ML052970092.)

— — — — —, RG 8.8, “Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable,” July 1973.

— — — — —, RG 8.8, Revision 3, “Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable,” June 1978. (ADAMS Accession No. ML003739549.)

— — — — —, RG 8.9, Revision 1, “Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program,” July 1993. (ADAMS Accession No. ML003739554.)

— — — — —, RG 8.10, Revision 1-R, “Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as Is Reasonably Achievable,” May 1977. (ADAMS Accession No. ML003739563.)

— — — — —, RG 8.13, Revision 3, “Instruction Concerning Prenatal Radiation Exposure,” June 1999. (ADAMS Accession No. ML003739505.)

— — — — —, RG 8.15, Revision 1, “Acceptable Programs for Respiratory Protection,” October 1999. (ADAMS Accession No. ML003739528.)

— — — — —, RG 8.19, Revision 1, “Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants Design Stage Man-Rem Estimates,” June 1979. (ADAMS Accession No. ML003739550.)

— — — — —, RG 8.20, Revision 1, “Applications of Bioassay for I-125 and I-131,” September 1979. (ADAMS Accession No. ML003739555.)

— — — — —, RG 8.25, Revision 1, “Air Sampling in the Work Place,” June 1992. (ADAMS Accession No. ML003739616.)

— — — — —, RG 8.26, “Applications of Bioassay for Fission and Activation Products,” September 1980. (ADAMS Accession No. ML080140014.)

— — — — —, RG 8.27, “Radiation Protection Training for Personnel at Light-Water Cooled Nuclear Power Plants,” March 1981. (ADAMS Accession No. ML003739628.)

— — — — —, RG 8.28, “Audible-Alarm Dosimeters,” August 1981. (ADAMS Accession No. ML003739382.)

— — — — —, RG 8.29, Revision 1, “Instructions Concerning Risks from Occupational Radiation Exposure,” February 1996. (ADAMS Accession No. ML003739438.)

B-90

— — — — —, RG 8.34, “Monitoring Criteria and Methods to Calculate Occupational Radiation Doses,” July 1992. (ADAMS Accession No. ML090770221.)

— — — — —, RG 8.35, “Planned Special Exposures,” June 1992. (ADAMS Accession No. ML003739507.)

— — — — —, RG 8.36, “Radiation Dose to the Embryo/Fetus,” July 1992. (ADAMS Accession No. ML003739548.)

— — — — —, RG 8.38, Revision 1, “Control of Access to High and Very High Radiation Areas in Nuclear Power Plants,” May 2006. (ADAMS Accession No. ML061350096.)

Draft Regulatory Guides

— — — — —, DG–1120, “Transient and Accident Analysis Methods,” December 2000. (ADAMS Accession No. ML052560476.)

— — — — —, DG–1127, “Combining Modal Responses and Spatial Components in Seismic Response Analysis,” February 2005. (ADAMS Accession No. ML050230006.)

— — — — —, DG–1144, “Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors,” May 2006. (ADAMS Accession No. ML061280573.)

— — — — —, DG–1176 “Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts,” July 2009. (ADAMS Accession No. ML073170252.)

Regulatory Issue Summaries

— — — — —, RIS 2000-03, “Resolution of Generic Safety Issue 158: Performance of Safety-Related Power-Operated Valves Under Design Basis Conditions,” March 15, 2000. (ADAMS Accession No. ML003686003.)

— — — — —, RIS 2000-012, “Resolution of Generic Safety Issue B-55, ‘Improved Reliability of Target Rock Safety Relief Valves,’” August 2000. (ADAMS Accession No. ML003726865.)

— — — — —, RIS 2005-17, "Clarification of Requirements for Application of the ASME Code Symbol Stamp on Safety-Related Components," August 8, 2005. (ADAMS Accession No. ML051160005.)

— — — — —, RIS 2005-20, Revision 1, “Revision to NRC Inspection Manual Part 9900 Technical Guidance, ‘Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety,’” April 16, 2008. (ADAMS Accession No. ML073440103.)

— — — — —, RIS 2005-25, Supplement 1, “Clarification of NRC Guidelines for Control of Heavy Loads,” May 29, 2007. (ADAMS Accession No. ML071210434.)

B-91

— — — — —, RIS 2005-030, “Clarification of Post-Fire Safe-Shutdown Circuit Regulatory Requirements,” December 20, 2005. (ADAMS Accession No. ML053360069.)

— — — — —, RIS 2006-17, “NRC Staff Position on the Requirements of 10 CFR 50.36, ‘Technical Specifications,’ Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels,” August 24, 2006. (ADAMS Accession No. ML051810077.)

— — — — —, RIS 2008-32, “Interim Low Level Radioactive Waste Storage at Reactor Sites,” December 30, 2008. (ADAMS Accession No. ML082190768.)

Safety Evaluation Reports

— — — — —, Safety Evaluation Report for NEDC-31858P, Revision 2, "Safety Evaluation by the Office of Nuclear Reactor Regulation BWROG Generic Resolution for the BWR Main Steam Isolation Valve V Leakage," dated March 3, 1999. (ADAMS Accession No. ML010640286.)

— — — — —, Safety Evaluation Report for NEDC-32851P, Revision 2, “Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report NEDC-32851P, Revision 2, “GEXL14 Correlation for GE14 Fuel,” Global Nuclear Fuel Project No. 712 717,” dated August 3, 2007. (ADAMS Accession Nos. ML072080365, ML072080378.)

— — — — —, Safety Evaluation Report for NEDC-33083P, “Safety Evaluation by the Office of Nuclear Reactor Regulation NEDC-33083P, “TRACG Application for ESBWR,” GE Nuclear Energy Project 717 – ESBWR Preapplication Review,” dated October 28, 2004. (ADAMS Accession Nos. ML043000318, ML043000303, ML043000295.)

— — — — —, Addendum with open items to the Safety Evaluation Report for NEDC-33083P-A, “Addendum to the Safety Evaluation Report with Open Items for NEDC-33083P-A, ‘Application of the TRACG Computer Code to the ECCS and Containment LOCA Analysis for the ESBWR Design,’” dated April 2, 2008. (ADAMS Accession Nos. ML080640522, ML080040217, ML073190044.)

— — — — —, Safety Evaluation Report with open items for NEDC-33083P-A, Section 4, “Safety Evaluation Report with Open Items for the Application of the TRACG Computer Code to the Transient Analysis for the ESBWR Design,” dated April 2, 2008. (ADAMS Accession Nos. ML080640522, ML080040175, ML080700368.)

— — — — —, Addendum to the Safety Evaluation Report for NEDE-33083P-A, “Addendum to the Safety Evaluation Report for NEDC-33083P-A, ‘Application of the TRACG Computer Code to the ECCS and Containment LOCA Analysis for the ESBWR Design,’” dated September 20, 2010. (ADAMS Accession Nos. ML102500164, ML093450400.)

B-92

— — — — —, Safety Evaluation Report for NEDE-33083P, Supplement 1, “Safety Evaluation by the Office of Nuclear Reactor Regulation Application of the TRACG Computer Code to Stability Analysis for the ESBWR Design NEDE-33083P, Supplement 1,” dated August 29, 2007. (ADAMS Accession Nos. ML072270192, ML072270267, ML072270244.)

— — — — —, Addendum with open items to the Safety Evaluation Report for NEDE-33083P, Supplement 1, “Addendum with Open Items to the Safety Evaluation by the Office of New Reactors Application of the TRACG Computer Code to Stability Analysis for the ESBWR Design NEDE-33083P, Supplement 1,” dated April 2, 2008. (ADAMS Accession Nos. ML080640522, ML080040226.)

— — — — —, Addendum to the Safety Evaluation Report for NEDE-33083P, Supplement 1, “Addendum to the Safety Evaluation Report by the Office of New Reactors Application of the TRACG Computer Code to Thermal-Hydraulic Stability Analysis for the ESBWR Design NEDE-33083P, Supplement 1,” dated September 13, 2010. (ADAMS Accession No. ML102430396.)

— — — — —, Safety Evaluation Report with open items for NEDE-33083P, Supplement 2, “Safety Evaluation with Open Items by the Office of New Reactors, Application of the TRACG Computer Code to Anticipated Transients Without Scram for the ESBWR Design NEDE-33083P, Supplement 2,” dated April 2, 2008. (ADAMS Accession Nos. ML080640522, ML080790401, ML080790398.)

— — — — —, Safety Evaluation Report for NEDE-33083P, Supplement 2, “Safety Evaluation by the Office of New Reactors ‘TRACG Application for ESBWR Anticipated Transients Without Scram Analyses,’ NEDE-33083P, Supplement 2, Revision 2,” dated October 20, 2010. (ADAMS Accession Nos. ML102810123, ML101820347.)

— — — — —, Safety Evaluation Report for NEDE-33083P, Supplement 3, “Safety Evaluation for the TRACG Application for ESBWR Transient Analysis NEDE-33083P, Supplement 3, Revision 1,” dated September 14, 2010. (ADAMS Accession Nos. ML102430484, ML100270024.)

— — — — —, Safety Evaluation Report for NEDC-33173P, “Safety Evaluation Report by the Office of Nuclear Reactor Regulation Topical Report NEDC-33173P, ‘Applicability of GE Methods to Expanded Operating Domains,’” January 17, 2008. (ADAMS Accession Nos. ML073340214, ML073340175, ML073340189, ML073340186, ML070540389, ML070540477, ML070540484, ML073340722.)

— — — — —, Safety Evaluation Report for NEDC-33237P, Revision 4 and NEDC-33413P, Revision 2, “Safety Evaluation by the Office of New Reactors NEDC-33237P, Revision 4, ‘GE14 for ESBWR Critical Power Correlation, Uncertainty, and OLMCPR Development,’ and NEDC-33413P, Revision 2, ‘Full Scale Critical Power Testing of GEXL14,’ Licensing Topical Reports for Reference in the Economic Simplified Boiling-Water Reactor Design Certification Application,” September 8, 2010. (ADAMS Accession Nos. ML101740168, ML101740299.)

B-93

— — — — —, Safety Evaluation Report for NEDC-33239P, Revision 4 and NEDE 33197P, Revision 2, “Safety Evaluation for NEDC-33239P, ‘GE14 for ESBWR Nuclear Design Report,’ and NEDE-33197P, ‘Gamma Thermometer System for LPRM Calibration and Power Shape Monitoring,’ Licensing Topical Reports for Reference in the Economic Simplified Boiling-Water Reactor Design Certification Application,” September 14, 2010. (ADAMS Accession Nos. ML101650747, ML101670068.)

— — — — —, Safety Evaluation Report for NEDC-33240P, Revision 1 and NEDC 33242P, Revision 2, “Safety Evaluation by the Office of New Reactors NEDC-33240P, Revision 01, ‘GE14E Fuel Assembly Mechanical Design Report’ and NEDC-33242P, Revision 02, ‘GE14 for ESBWR Fuel Rod Thermal-Mechanical Design Report’ Global Nuclear Fuel,” September 7, 2010. (ADAMS Accession Nos. ML101740522, ML101750007.)

— — — — —, Safety Evaluation Report for NEDC-33326P, Revision 1, “Final Safety Evaluation Report (SER) Revision 1 for GE Hitachi Nuclear Energy Licensing Topical Report (LTR) NEDC-33326P Revision 1, ‘GE14E for the Economic Simplified Boiling Water Reactor Initial Core Nuclear Design Report,’” September 7, 2010. (ADAMS Accession Nos. ML101380505, ML101380560.)

— — — — —, Safety Evaluation Report for NEDC-33374P, Revision 3, “Safety Evaluation of GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33374P, ‘Safety Analysis Report for Fuel Storage Racks Criticality Analysis for ESBWR Plants,’” September 21, 2010. (Adams Accession Nos. Ml102430582, Ml101600141.)

— — — — —, Safety Evaluation Report for NEDE-33312P, NEDC-33408P, and NEDC-33408P Supplement 1, “Safety Evaluation Report GEH Licensing Topical Reports NEDE-33312P, NEDC-33408P, and NEDC-33408P Supplement 1,” August 2010. (ADAMS Accession Nos. ML ML102640350, ML102640388.)

— — — — —, Safety Evaluation Report for NEDE-31096P, “Safety Evaluation of accepted NEDE-31096-P, ‘Anticipated Transients Without Scram; Response to NRC ATWS Rule 10 CFR 50.62,’” October 21, 1988. (ADAMS Accession No. 8612050358.)

— — — — —, Safety Evaluation Report for NEDE-32906P, Supplement 3, “Final Safety Evaluation by the Office of Nuclear Reactor Regulation Licensing Topical Report NEDE-32906P, Supplement 3, ‘Migration to TRACG04/PANAC11 from TRACG02/PANAC10 for TRACG AOO and ATWS Overpressure Transients,’” July 10, 2009. (ADAMS Accession Nos. ML091890758, ML091751102, ML091400057.)

— — — — —, Safety Evaluation Report for NEDE-33243P, Revision 2, and NEDE-33244P, Revision 1, “Safety Evaluation by the Office of New Reactors NEDE-33244P, Revision1, ‘ESBWR Marathon Control Rod Mechanical Design Report, and NEDE-33243P, Revision 2, “ESBWR Control Rod Nuclear Design,’” September 7, 2010. (ADAMS Accession Nos. ML101750384, ML101750396.)

— — — — —, Safety Evaluation Report for NEDE-33259P, “Safety Evaluation Report for Reactor Internals Flow Induced Vibration Program NEDE-33259P,” September 28, 2010. (ADAMS Accession Nos. ML102640432, ML102640455.)

B-94

— — — — —, Safety Evaluation Report for NEDE-33313P, “Safety Evaluation Report General Electric-Hitachi Licensing Topical Report NEDE-33313P, ‘ESBWR Steam Dryer Structural Evaluation,’” September 28, 2010. (ADAMS Accession Nos. ML102640389, ML102640402.)

— — — — —, Safety Evaluation Report for NEDE-33516P, “Safety Evaluation General Electric-Hitachi Topical Report NEDE-33516P Qualification Plan Requirements for 72-Hour Duty Cycle Batteries for the Economic Simplified Boiling-Water Reactor Design,” September 20, 2010. (ADAMS Accession Nos. ML102500553, ML100680081.)

— — — — —, Safety Evaluation Report for NEDO-32991, “Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Topical Report NEDO-32991, ‘Regulatory Relaxation for BWR Post Accident Sampling Stations (PASS),’” June 12, 2001. (ADAMS Accession No. ML011630016.)

— — — — —, Safety Evaluation Report for NEDO-33373, Revision 5, “Safety Evaluation Report on General Electric Hitachi Nuclear Energy Topical Report NEDO-33373: ‘Dynamic, Load-Drop and Thermal-Hydraulic Analyses for ESBWR Fuel Racks,’” October 20, 2010. (ADAMS Accession Nos. ML102700454, ML101600135.)

— — — — —, Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Bulletin 96-03, Boiling Water Reactor Owners Group Topical Report NEDO-32686-A, “Utility Resolution Guidance for ECCS Suction Strainer Blockage,” August 20, 1998.

— — — — —, Safety Evaluation Report for NEI 07-09, Revision 4, “Final Safety Evaluation by the Office of New Reactors Technical Report NEI 07-09, ‘Generic FSAR Template Guidance for Offsite Dose Calculation Manual Program Description,’ (Revision 4, November 2008),” January 27, 2009. (ADAMS Accession No. ML083530745.)

— — — — —, Safety Evaluation Report NEI 07-10, Revision 3, “Safety Evaluation Final Safety Evaluation for the Nuclear Energy Institute’s Technical Report NEI 07-10, ‘Generic Final Safety Analysis Review Template Guidance for Process Control Program,’ Revision 3 (TAC NO. Q00159),” January 8, 2009. (ADAMS Accession No. ML082910077.)

— — — — —, Safety Evaluation Report for NEDE-24011-P-A, Amendment 26, “Safety Evaluation Report by the Office of Nuclear Reactor Regulation Amendment No. 26 to General Electric (GE) Topical Report NEDE-24011-P-A, ‘GESTAR II’ Item 2: Implementing Improved GE Steady-State Methods,” November 10, 1999. (ADAMS Accession Nos. ML993230184, ML993230190.)

— — — — —, Safety Evaluation Report for DPR-28, License Amendment 229, “Safety Evaluation Report by the Office of Nuclear Reactor Regulation Related to Amendment No. 229 to Facility Operating License No. DPR-28,” March 2, 2006. (ADAMS Accession Nos. ML060050024, ML060050051.)

B-95

NRC Letters and Memorandums

— — — — —, March 24, 1975, Memorandum from H.R. Denton, NRC, to R.R. Maccary, NRC, “Site Analysis Branch Position—Winter Precipitation Loads.” (ADAMS Accession No. ML050630277.)

— — — — —, May 12, 1979, Letter from M. Hartzman, NRC, to R. Brughey, GE, “Computer Code Verification.”

— — — — —, March 25, 1988, Letter from L.S. Rubinstein, NRC, to E.E. Kintner, “ALWR Design Basis Tornado.” (ADAMS Accession No. ML031270370.)

— — — — —, May 9, 1988, Letter from T.E. Murley, NRC, to R. F. Janecek , BWR Owners’ Group, “NRC Staff Review of Nuclear Steam Supply System Vendor Owner Groups’ Application of the Commission’s Interim Policy Statement Criteria to Standard Technical Specifications.” (ADAMS Accession No. 9405160267.)

— — — — —, August 29, 1994, Letter from G. Holahan, NRC, to R. Pinelli, Boiling Water Reactor Owners Group, “Transmittal of the Safety Evaluation of General Electric Co. Topical Reports; NEDO-30832 Entitled ‘Elimination of limit on BWR Suppression Pool Temperature for SRV Discharge with Quenchers’ and NEDO-31695 Entitled ‘BWR Suppression Pool Temperature Technical Specification Limits.’”

— — — — —, July 24, 1995, Memorandum to Docket File, from Dennis M. Crutchfield, NRC, “Consolidation of SECY-94-084 and SECY-95-132.” (ADAMS Accession No. ML003708048.)

— — — — —, November 7, 1995, Letter from A.E. Levin, NRC to J. Duncan, GE Nuclear Energy, “GIRAFFE/SIT Trip Report dated October 27, 1995.”

— — — — —, March 1996, Letter from Gallo, R.M., NRC, to C.P. Kipp, GEH, “NRC Inspection Report No. 99900003/95-01.”

— — — — —, March 3, 1999, Letter from Akstulewick, F., NRC, to Green, T.A., GE, “Safety Evaluation of GE Topical Report, NEDC-31858P, Revision 2, ’BWROG Report for Increasing MSIV Leakage Limits and Elimination of Leakage Control Systems,’ September 1993,” NEDC-31858P, Revision 2. (ADAMS Accession No. ML010640286.)

— — — — —, March 11, 1999, Letter from Akstulewicz, F., NRC, to G.A. Watford, GEH, “Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Methodology and Uncertainties for Safety Limit MCPR Evaluations; NEDC-32694P, Power Distribution Uncertainties for Safety Limit MCPR Evaluation; and Amendment 25 to NEDE-24011-P-A on Cycle-Specific Safety Limit MCPR.” (ADAMS Accession No. ML993140059.)

— — — — —, November 10, 1999, Letter from Richards, S.A., NRC, to G.A. Watford, GEH, “Amendment 26 to GE Licensing Topical Report NEDE-24011-P-A, ‘GESTAR II -Implementing Improved GE Steady-State Methods (TAC No. MA6481).’” (ADAMS Accession No. ML993230184.)

B-96

— — — — —, May 19, 2000, Letter from Grimes, Christopher I., NRC, to Douglas J. Walters, Nuclear Energy Institute, “License Renewal Issue No. 98-0030, ‘Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components.’” (ADAMS Accession No. ML003717179.)

— — — — —, January 25, 2001, Letter from Richards, S.A. NRC, to J.M. Kenny (BWROG), “BWROG—Topical Report NEDC-32975(P)-A, Regulatory Relaxation for BWR LPMS.” (ADAMS Accession No. ML010310355.)

— — — — —, August 19, 2004, Letter from W.D. Beckner, NRC, to L. Quintana, GENE, “Safety Evaluation Report Regarding the Application of GENE’s TRACG Code to ESBWR LOCA Analyses.” (ADAMS Accession No. ML041450323.)

— — — — —, October 28, 2004, Letter from W.D. Beckner, NRC, to L.M. Quintana, GENE, “Re-Issuance of Safety Evaluation Report Regarding the Application of General Electric Nuclear Energy’s TRACG Code to ESBWR Loss-of-Coolant (LOCA) Analyses.” (ADAMS Accession No. ML043000318.)

— — — —, November 9, 2004, Letter from Gramm, R. A., NRC, to Putnam, K, Chairman, BWR Owners Group, “Technical Specification Task Force Traveler 357 (TSTF-357), Revision 1, ‘Minimum Critical Power Ration Safety Limit.’” (ADAMS Accession No. ML043140475.)

— — — — —, September 7, 2005, Letter from Patrick L. Hiland, NRC, to Michael A. Schoppman, NEI, “Technical Specification for Addressing Issues Related to Setpoint Allowable Values.” (ADAMS Accession No. ML052500004.)

— — — — —, January 11, 2006, Letter from David B. Matthews, NRC, to David H. Hinds, GE, “NRC Inspection Report 05200010/2005-201 and Notice of Nonconformance.” (ADAMS Accession No. ML053560155.)

— — — — —, April 11, 2006, Letter from Boyce, T.H., NRC, to Technical Specifications Task Force, “Request for Public Meeting to Discuss Enclosed Document ‘Electrical Engineering Branch Concerns with Technical Specifications Task Force (TSTF)-360, Revision 1 DC Electrical Rewrite.’” (ADAMS Accession Nos. ML061020636, ML061100185.)

— — — — —, June 14, 2006, Letter from David B. Matthews, NRC, to David H. Hinds, GE, “NRC Inspection Report 05200010/2006-201 and Notice of Nonconformance.” (ADAMS Accession No. ML061590328.)

— — — — —, January 19, 2007, Letter from David B. Matthews, NRC, to David H. Hinds, GENE, “NRC Inspection Report for General Electric Nuclear Energy (GENE) General Economic and Simplified Boiling Water Reactor (ESBWR) Quality Assurance Implementation Follow-up Inspection.” (ADAMS Accession No. ML070100142.)

— — — — —, March 8, 2007, Letter from Nieh, Ho, NRC, to Lingenfelter, A., GE, “Final Safety Evaluation for Global Nuclear Fuel (GNF) Topical Report (TR) Amendment 28, ‘Misloaded Fuel Bundle Event Licensing Basis Change to Comply with Standard Review Plan 15.4.7,’ to General Electric Standard Application for Reload Fuel (GESTAR II) (TAC No. MC3559).” (ADAMS Accession No. ML070470055.)

B-97

— — — — —, March 25, 2009, Letter from John Nakoski, NRC, to Mark Harvey, GEH, “Nuclear Regulatory Commission Inspection Report 05200010/2008-201, Notice of Violation to General Electric Hitachi Nuclear Energy.” (ADAMS Accession No. ML090790473.)

Other NRC Documents

— — — — —, IE Circular 79-18, “Proper Installation of Target Rock Safety Relief Valves,” September 10, 1979. (ADAMS Accession No. ML080310517.)

— — — — —, Information Systems Laboratories, prepared for the NRC, “Nuclear Power Plant Security Assessment Format and Content Guide, Part 1 of 3,” September 2007. (ADAMS Accession No. ML073030054.)

— — — — —, Office of New Reactors Office Instruction NRO-REG-108, Revision 0, “Regulatory Audits,” April 2, 2009. (ADAMS Accession No. ML081910260.)

— — — — —, Temporary Instruction (TI) 2515/92, “Emergency Operating Procedures Team Inspections.”

Other Standards

Aluminum Association, Aluminum Design Manual, 2000 Edition.

American Welding Society, AWS D1.1/D1.1M-2010, “Structural Welding Code—Steel.”

Atlantic Oceanographic and Meteorological Laboratory (AOML), “Frequently Asked Questions, Subject: D4) What Does ‘Maximum Sustained Wind’ Mean? How Does it Relate to Gusts in Tropical Cyclones?” FAQ: Hurricanes, Typhoons, and Tropical Cyclones, April 2006. <http://www.aoml.noaa.gov/hrd/tcfaq/D4.html> (February 2007). (ADAMS Accession No. ML071650549.)

Crane Manufacturer’s Association of America, CMAA 70, “Specifications for Electric Overhead Traveling Cranes,” 2004.

Federal Emergency Management Agency, FEMA 361, “Design and Construction Guidance for Community Safe Rooms,” issued in 2000. <http://www.fema.gov/plan/prevent/saferoom/fema361.shtm>

Heat Exchanger Institute (HEI), “Standards for Steam Surface Condensers,” 6th Edition, 1970.

Illuminating Engineering Society of North America, IESNA, “Lighting Handbook,” 9th Edition, 2000.

International Code Council (ICC), “International Building Code,” January 1, 2003.

B-98

International Conference on Nuclear Engineering, ICONE 16-48410, “Steam Dryer Acoustic Load Prediction in the Main Steam Line Break Event,” May 15, 2008.

International Electrotechnical Commission, IEC 61000-4, “Electromagnetic Compatibility - Testing and Measurement Techniques.”

International Organization for Standardization, ISO 9001:2000, “Quality Management System (QMS)—Requirements.”

Institute of Nuclear Power Operations (INPO), ACAD 97-014, National Academy for Nuclear Training, “Guidelines for Instructor Training and Qualifications,” 1998.

Military Standard, Mil Std 461E, “Department of Defense Interface Standard - Requirement for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment,” August 1999.

National Climate Data Center (NCDC), “Solar and Meteorological Surface Observational Network (SAMSON) (years 1961-1990),” September 1993.

National Electrical Manufacturers Association (NEMA) Standards Publication 250-2003, Type 1, “Enclosures for Electrical Equipment (1000 Volts Maximum),” January 1, 2003.

National Electrical Manufacturers Association/Insulated Cable Engineers Association (NEMA/ICEA), ANSI/NEMA WC-51-2009/ICEA P-54-440, “Ampacities of Cable in Open-Top Cable Trays,” April 23, 2009.

National Electrical Manufacturers Association/Insulated Cable Engineers Association (NEMA/ICEA), ANSI/NEMA WC-70-2009/ICEA S-95-658, “Non-shielded 0-2 kV Cables,” July 15, 2009.

National Hurricane Center (NHC), “The Saffir-Simpson Hurricane Scale,” June 22, 2006. <http://www.nhc.noaa.gov/aboutsshs.shtml> (February 2007). (ADAMS Accession No. ML071650547.)

Nuclear Construction Issue Group, NCIG 01, “Visual Weld Acceptance Criteria for Structural Welding at Nuclear Plants,” September 1987.

Nuclear Management and Resources Council, NUMARC 93-01, “Nuclear Energy Institute Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” February 22, 2000.

Organization for Economic Cooperation and Development (OECD), Svanholm, K., “Gamma Thermometer and Neutron Detector Application,” Institute for Atomenergi, Halden Reactor Project Technical Report, January 1, 1967.

Sheet Metal and Air Conditioning Contractors’ National Association, SMACNA 1481, “HVAC Duct Construction Standards – Metal and Flexible,” 3rd Edition, 2005.

Structural Engineering Institute /American Society of Civil Engineers, SEI/ASCE 7-02, “Minimum Design Loads for Buildings and Other Structures,” 2002.

B-99

Tubular Exchanger Manufacturers Association, “Standards of Tubular Exchanger Manufacturers Association,” 8th Edition, 1999.

Welding Research Council, WRC Bulletin No. 353, “Position Paper on Nuclear Pipe Supports,” March 1990.

Other Documents

Anderson, T., O. Berg, and K. Romslo, “Ringhals-2 Core Monitoring Experience,” Nuclear Energy Agency, In-Core Instrumentation and Core Assessment. Proceedings of a Specialists’ Meeting, Mito-Shi, Japan, October 1996.

Begley, J.A. and W.A. Logsdon, “Correlation of Fracture toughness and Charpy properties for Rotor Steels,” Westinghouse Report, Scientific paper 71-1E7, MSLRF-P1, 1971.

Brookhaven National Laboratory, BNL 52361, “Seismic Design and Evaluation Guidelines for the Department of Energy High Level Waste Storage Tanks and Appurtenances,” October 1995.

di Marzo, M. “A Simplified Model of the BWR Depressurization Transient.” Nuclear Engineering and Design. Vol. 205, No. 2001, pp. 107–114. July 28, 2000.

Dubrovskii, I.S. “Hydrodynamics of Adiabatic Two-Phase Flow in Large Core Risers.” Teploenergetika. Vol. 21, No. 2, pp. 31–35. February 1, 1974.

Ferguson, P.M., Reinforced Concrete Fundamentals, Section 1.3. 3rd Edition, John Willey & Sons, 1973.

Galletly, G.D., “A Simple Design Equation for Preventing Buckling in Fabricated Torispherical Shells under Internal Pressure.” ASME Journal of Pressure Vessel Technology. Vol. 108, No. 4, pp. 521-526. November 1986.

Hirukawa, K., S. Sakurai, and T. Naka, “Nuclear Reactor Power Distribution Monitoring System and Method Including Nuclear Reactor Instrumentation System,” U.S. Patent No. 6477219 B2. November 5, 2002.

Ho, Chih-Ming and Nagy S. Nossier, “Dynamics of an Impinging Jet. Part 1. The Feedback Phenomenon.” Journal of Fluid Mechanics, Vol. 105, pp. 119-142. 1981.

Humphreys, S.L., L.A. Miller, D.K. Monroe, and T.J. Heames. RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation. Sandia National Laboratory, Albuquerque, NM, 2001.

Hwang, H.L. and E.O. Swain, “Comparison of the Performances of the Strut and Snubber Subject to Dynamic Load.” Proceedings of International Nuclear Power Plant Thermal Hydraulics and Operations Topical Meeting, in Taipei, Taiwan, Republic of China, October 22–24, 1984.

B-100

Lahey, R.T., and F.J. Moody. Thermal-Hydraulics of a Boiling Water Nuclear Reactor. 2nd Edition. American Nuclear Society, May 1993.

Lawrence Livermore National Laboratory, UCRL-CR-135687 S/C B 505188, James R. McDonald, “Rationale for Wind-Borne Missile Criteria for DOE Facilities,” California, USA, September 1999. (ADAMS Accession No. ML012760038.)

Martin, C.L. “Application of the Gamma Thermometer to BWR Core Monitoring.” Core Monitoring Methods, Designs, and Experience, Transactions of the American Nuclear Society. Vol. 75, pp. 333-334. December 31, 1996.

Moody, F.J. “Maximum Flow Rate of a Single Component, Two-Phase Mixture,” Journal of Heat Transfer, Trans. ASME, Series C. Vol. 87, No.1, p. 134. February 1965.

Nuclear Energy Agency/Committee on the Safety of Nuclear Installations (NEA/CSNI), NEA/CSNI/R(95)11, “Knowledge Base for Emergency Core Cooling System Recirculation Reliability,” February 1996.

Oak Ridge National Laboratory (ORNL) “Technical Evaluation Report for GE-Hitachi’s Setpoint Methodology NEDE-33304P,” October 30, 2009. (ADAMS Accession No. ML093020611.)

Raghavan, R., C.L. Martin, A.L. Wirth, T. Itoh, Y. Goto, and R. Arai, “Application of the Gamma Thermometer as BWR Fixed In-Core Calibration System,” Nuclear Energy Agency, In-Core Instrumentation and Core Assessment. Proceedings of a Specialists’ Meeting, Mito-Shi, Japan, October 1996.

Ransom, V., “Comments on GSI 191 Models for Debris Generation,” September 14, 2004. (ADAMS Accession No. ML050830341.)

Shield, R.T. and D.C. Drucker. “Design of Thin-Walled Torispherical and Toriconical Pressure-Vessel Heads.” ASME Journal of Applied Mechanics. June 1961.

Sandia National Laboratory, SAND 2007-5591, “Nuclear Power Plant Security Assessment Technical Manual,” Albuquerque, New Mexico, September 2007. (ADAMS Accession No. ML072620172.)

Sandusky, D.W., C.N. Spalaris, and U.E. Wolff. “Irradiation Temperature Dependence of Void Formation in Type 304 Stainless Steel.” Journal of Nuclear Materials. Vol. 42, pp. 133-141. 1972.

Shepherd, J.E., A. Teodorcyzk, R. Knystautas, J. H. Lee. “Shock Waves Produced by Reflected Detonations.” Progress in Astronautics and Aeronautics. Vol. 134, pp. 244-264. 1991.

Shepherd, J.E., “Structural Response of Piping to Internal Gas Detonation,” ASME Pressure Vessels and Piping Conference, VP2006-ICPVT11-93670, presented in Vancouver, BC, Canada. July 23-27, 2006.

Sieffert, J.G., and F. Cevaer. Handbook of Impedance Functions. Editions of Ouest-France, April 4, 1995.

B-101

Underwriters Laboratories, UL 752, "Standard for Bullet Resisting Equipment," Northbrook, IL, March 29, 2006.

U.S. General Services Administration (GSA), “Window Glazing Analysis Response and Design, Limited Edition (WINGARD LE 2.0) software.” <http://www.gsa.gov/portal/content/> (November 25, 2010).

Wallis, G., “The ANSI/ANS Standard 58.2-1988: Two Phase Jet Model,” September 15, 2004. (ADAMS Accession No. ML050830344.)

Yilmaz, T.P. and Paschal W.B. “An Analytical Approach to Transient Room Temperature Analysis.” Nuclear Technology. Vol. 114, No. 1, pp.135-140. April 1996.