D-1

APPENDIX D – REFERENCES

American Concrete Institute (ACI)

— — — — —, ACI 336.2R, “Suggested Analysis and Design Procedures for Combined Footings and Mats,” 1988 (reapproved 2002)

— — — — —, ACI 349-80, “Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary,” 2006.

— — — — —, ACI 349-89, “Code Requirements for Nuclear Safety Related Concrete Structures and Commentary,” 1989.

— — — — —, ACI 349-97, “Code Requirements for Nuclear Safety Related Concrete Structures and Commentary,” 1997.

— — — — —, ACI 349.1R-07, “Reinforced Concrete Design for Thermal Effects on Nuclear Power Plant Structures,” 2007.

— — — — —, ACI 350.1–10 “Specification for Tightness Testing of Environmental Engineering Concrete Containment Structures & Commentary,” 2010.

— — — — —, ACI 350-06, “Code Requirements for Environmental Engineering Concrete Structures and Commentary,” 2006.

American National Standards Institute (ANSI)

— — — — —, ANSI N13.1–1999, “Sampling And Monitoring Releases Of Airborne Radioactive Substances From The Stacks And Ducts Of Nuclear Facilities,” 1999.

— — — — —, ANSI N14.6–1993, “Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4,500 kg) or More,” 1993.

— — — — —, ANSI N15.8–2009, “Methods of Nuclear Material Control—Material Control Systems—Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants,” February 18, 2009.

— — — — —, ANSI N18.7-1976, “Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.”

— — — — —, ANSI N31.1, “Power Piping.”

— — — — —, ANSI N42.18-2004, "Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents." 2004. (This standard is a re-designation of ANSI N13.10-1974.)

— — — — —, ANSI N45.2-1971, "Quality Assurance Program Requirements for Nuclear Power Plants," October 20, 1971. (ANSI N45.2 series of standards are listed in RG 1.28, Revision 3.)

D-2

— — — — —, 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,” January 1, 1974. (The current standard is dated September 1, 1986.)

— — — — —, ANSI N101.2–1972, "Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities," 1972. (Withdrawn in 1988.)

American National Standards Institute/American Institute of Steel Construction (ANSI/AISC)

— — — — —, ANSI/AISC 2.8–1992, “Determining Design Basis Flooding at Power Reactor Sites,” Historical Technical Reference, July 1982.

— — — — —, ANSI/AISC N690–1984, “Specification for the Design, Fabrication, and Erection of Steel Safety-Related Structures for Nuclear Facilities,” 1984.

— — — — —, ANSI/AISC N690–1994, “Specification for the Design, Fabrication, and Erection of Steel Safety-Related Structures for Nuclear Facilities,” 1994.

American National Standards Institute/American Nuclear Society (ANSI/ANS)

— — — — —, ANSI/ANS-2.8–1992, “Determining Design Basis Flooding at Power Reactor Sites,” Historical Technical Reference, July 1982.

— — — — —, ANSI/ANS-3.1–1993, “Selection, Qualification, and Training of Personnel for Nuclear Power Plants,” 1993. (Reaffirmed in 1999, and Withdrawn in 2009.)

— — — — —, ANSI/ANS-3.2–1976, “Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants," 1976.

— — — — —, ANSI/ANS-5.1–1979, “Decay Heat Power in Light Water Reactors,” August

29, 1979

— — — — —, ANSI/ANS-57.1-1992, “Design Requirements for Light Water Reactor Fuel Handling Systems.” 1992. (Reaffirmed in 1999 and 2005)

— — — — —, ANSI/ANS-57.2-1983, “Design Requirements for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Plants,” 1983. (Withdrawn in 1993.)

— — — — —, ANSI/ANS-57.3-1983, “Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants,” 1983. (Withdrawn in 1993.)

— — — — —, ANSI/ANS-59.52–1998; “Lubricating Oil Systems for Safety-Related Emergency Diesel Generators,” 1998. (Reaffirmed in 2007.)

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American National Standards Institute/American Nuclear Society–Health Physics Society Standards Committee (ANSI/ANS-HPSSC)

— — — — —, ANSI/ANS-HPSSC-6.8.1–1981, “Location and design criteria for area radiation monitoring systems for light water nuclear reactors.” 1981, (Withdrawn in 1991.)

American National Standards Institute/Health Physics Society (ANSI/HPS)

— — — — —, ANSI/HPS N13.1–1999, “Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities,” 1999.

American National Standards Institute/American Society of Mechanical Engineers (ANSI/ASME)

— — — — —, ANSI/ASME AG-1–1997, “Code on Nuclear Air and Gas Treatment,” 1997.

— — — — —, ANSI/ASME AG-1–2009, “Code on Nuclear Air and Gas Treatment,” 2009.

— — — — —, ANSI/ASME N509-2002, “Nuclear Power Plant Air Cleaning Units and Components,” 2002.

— — — — —, ANSI/ASME NQA-1–1983, "Quality Assurance Program Requirements for Nuclear Power Plants,” 1983.

— — — — —, ANSI/ASME NQA-1–1994, “Quality Assurance Requirements for Nuclear Facility Applications,” 1994.

— — — — —, ASME Boiler Pressure Vessel Code, Section III, “Rules for Construction of Nuclear Facility Components,” Subsection NCA, “General Requirements for Division 1 and Division 2.”

NCA-1140: "Use of Code Editions, Addenda and Cases”

NCA-3550, “Requirements for Design Output Documents”

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

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

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

IWA-1500, “Accessibility”

1WA-2000, “Examination and Inspection”

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IWA-2300, “Qualifications of Nondestructive Examination Personnel”

IWA-2400, “Inspection Program”

IWA-4000, “Repair/Replacement Activities”

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

IWB-2000, “Examination and Inspection”

IWB-2400, “Inspection Program”

IWB-2500, “Examination and Pressure Test Requirements”

IWB-3000, “Acceptance Standards”

IWB-3400, “Standards”

IWB-3410-1, “Application of Standards”

IWB-4000, “Repair/Replacement Activities”

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWC, “Requirements for Class 2 Components of Light Water Cooled Plants.”

IWC-2000, “Examination and Inspection”

IWC-2500, “Examination and Pressure Test Requirements”

— — — — —, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWD, “Requirements for Class 3 Components of Light Water Cooled Plants.”

IWD-2000, “Examination and Inspection”

IWD-2500, “Examination and Pressure Test Requirements”

— — — — —, 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.”

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.”

IWL-2500, “Examination Requirements”

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Other ASME Documents

— — — — —, ASME AG-1–1991, “Code on Nuclear Air and Gas Treatment,” 1991.

— — — — —, ASME N510–1989, “Testing of Nuclear Air-Treatment Systems,” 1989.

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

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

— — — — —, ASME OM Code-1987, “Code for Operation and Maintenance of Nuclear Power Plants.”

— — — — —, ASME OM Code-2004, “Code for Operation and Maintenance of Nuclear Power Plants.”

— — — — —, ASME OMa Code-1988, Addenda to ASME OM Code -1987 “Operation and Maintenance of Nuclear Power Plants.”

— — — — —,ASME OM Code Case OMN-1 (Revision 1), “Alternative Rules for the Preservice and Inservice Testing of Certain Electric Motor Operated Valve Assemblies in Light Water Reactor Power Plants.”

— — — — —, ASME OM Code Case OMN-11, “Risk-Informed Testing of Motor-Operated Valves.”

— — — — —, ASME OM Code Case OMN-12, “Alternative Requirements for Inservice Testing Using Risk Insights for Pneumatically- and Hydraulically-Operated Valve Assemblies in Light-Water Reactor Power Plants.”

— — — — —, ASME OM Code Case OMN-13, “Requirements for Extending Snubber Inservice Visual Examination Interval at LWR Power Plants.”

— — — — —,ASME OM Code, Appendix I, “Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants.”

— — — — —, ASME QME-1 -2007, “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants,” November 28, 2007.

American National Standards Institute/ Institute of Electrical and Electronic Engineers (ANSI/IEEE) Standards (Std)

— — — — —, ANSI C37.06–1987, “AC High-Voltage Circuit Breakers Rated on a Symmetrical Current Basis – Preferred Ratings and related Required Capabilities,” 1987.

— — — — —, ANSI C84.1–2006, “American National Standard For Electric Power Systems and Equipment - Voltage Ratings (60 Hertz),” 2006.

D-6

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

American Nuclear Society/International Organization for Standardization/International Electrotechnical Commission (ANS/ISO/IEC)

— — — — —, ANS/ISO/IEC 17025, “General Requirements for the Competence of Testing and Calibration Laboratories," 2005.

American Society of Civil Engineers (ASCE)

— — — — —, “Structural Analysis and Design of Nuclear Plant Structures,” Editing Board and Task Groups of the Committee on Nuclear Structures and Materials of the Structural Division, 1980.

— — — — —, ASCE 4–98, “Seismic Analysis of Safety-Related Nuclear Structures and Commentary,” 1998.

— — — — —, ASCE 7–05, “Minimum Design Loads for Buildings and Other Structures,” 2005.

— — — — —, ASCE 7–88, "Minimum Design Loads for Buildings and Other Structures," January 1988.

American Society of Civil Engineers/Structural Engineering Institute (ASCE/SEI)

— — — — —, ASCE/SEI 7–02, “Minimum Design Loads for Buildings and Other Structures,” 2002.

— — — — —, 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,” 2005.

American Society of Heating, Refrigerating and Air-Conditioning Engineers, (ASHRAE):

— — — — —, “ASHRAE Handbook – Fundamentals,” 2001.

American Society for Testing and Materials (ASTM)

— — — — —, ASTM A36-08, "Standard Specification for Carbon Structural Steel," 2008.

— — — — —, ASTM A500-10, “Standard Specification for Cold-Formed Welded and Seamless Carbon Steel Structural Tubing in Rounds and Shapes,” 2010.

D-7

— — — — —, ASTM A606-09a,” Standard Specification for Steel, Sheet and Strip, High-Strength, Low-Alloy, Hot-Rolled and Cold-Rolled, with Improved Atmospheric Corrosion Resistance,” 2009.

— — — — —, ASTM A633-00a, "Standard Specification for Normalized High-Strength Low-Alloy Structural Steel Plates," 2000.

— — — — —, ASTM A992-11, “Standard Specification for Structural Steel Shapes,” 2011.

— — — — —, ASTM C267-01(2006), "Standard Test Methods for Chemical Resistance of Mortars, Grouts, and Monolithic Surfacings and Polymer Concretes," 2006.

— — — — —, ASTM D854–06, “Standard Test Methods for Specific Gravity of Soil Solids by Water Pycnometer,” January 2006.

— — — — —, ASTM D975–09, “Standard Specification for Diesel Fuel Oils,” March 2009.

— — — — —, ASTM D975–10, “Standard Specification for Diesel Fuel Oils,” March 2010.

— — — — —, ASTM D1056-07, “Standard Specification for Flexible Cellular Materials—Sponge or Expanded Rubber,” 2007.

— — — — —, ASTM D1552–08, “Standard Test Method for Sulfur in Petroleum Products (High-Temperature Method),” December 2008.

— — — — —, ASTM D1557–02, “Standard Test Methods for Laboratory Compaction Characteristics of Soil Using Modified Effort (56,000 ft-lbf/ft3 [2,700 kN-m/m3]),” November 2002.

— — — — —, ASTM D1586–99, “Standard Test Method for Penetration Test and Split-Barrel Sampling of Soils,” January 1999.

— — — — —, ASTM D1587–00, “Standard Practice for Thin-Walled Tube Sampling of Soils for Geotechnical Purposes,” August 2000.

— — — — —, ASTM D1883–05, “Standard Test Method for CBR (California Bearing Ratio) of Laboratory-Compacted Soils,” November 2005.

— — — — —, ASTM D1894-11e1, "Standard Test Method for Static and Kinetic Coefficients of Friction of Plastic Film and Sheeting," 2011.

— — — — —, ASTM D2113–08, “Standard Practice for Rock Core Drilling and Sampling of Rock for Site Investigation,” January 2008.

— — — — —, ASTM D2166–06, “Standard Test Method for Unconfined Compressive Strength of Cohesive Soil,” July 2006.

— — — — —, ASTM D2216–05, “Standard Test Methods for Laboratory Determination of Water (Moisture) Content of Soil and Rock by Mass,” March 2005.

— — — — —, ASTM D2276–06, “Standard Test Method for Particulate Contaminant in Aviation Fuel by Line Sampling,” December 2006.

D-8

— — — — —, ASTM D2435–04, “Standard Test Methods for One-Dimensional Consolidation Properties of Soils Using Incremental Loading,” November 2004.

— — — — —, ASTM D2622–08, “Standard Test Method for Sulfur in Petroleum Products by Wavelength Dispersive X-ray Fluorescence Spectrometry,” March 2008.

— — — — —, ASTM D2622–10, “Standard Test Method for Sulfur in Petroleum Products by Wavelength Dispersive X-ray Fluorescence Spectrometry,” February 2010.

— — — — —, ASTM D2850–03a, “Standard Test Method for Unconsolidated-Undrained Triaxial Compression Test on Cohesive Soils,” November 2003.

— — — — —, ASTM D3080–04, “Standard Test Method for Direct Shear Test of Soils Under Consolidated Drained Conditions,” November 2004.

— — — — —, ASTM D3803–89, “Standard Test Method for Nuclear-Grade Activated Carbon,” December 1989.

— — — — —, ASTM D4044–96, “Standard Test Method for (Field Procedure) for Instantaneous Change in Head (Slug) Tests for Determining Hydraulic Properties of Aquifers,” 1996.

— — — — —, ASTM D4057–06, “Standard Practice for Manual Sampling of Petroleum and Petroleum Products,” October 2006

— — — — —, ASTM D4176–04, “Standard Test Method for Free Water and Particulate Contamination in Distillate Fuels (Visual Inspection Procedures),” 2009.

— — — — —, ASTM D4176–04e1, “Standard Test Method for Free Water and Particulate Contamination in Distillate Fuels (Visual Inspection Procedures),” 2004. [Superseded by ASTM D4176-04(2009)]

— — — — —, ASTM D4220–95, “Standard Practices for Preserving and Transporting Soil Samples,” January 2000.

— — — — —, ASTM D4318–05, “Standard Test Methods for Liquid Limit, Plastic Limit, and Plasticity Index of Soils,” March 2005.

— — — — —, ASTM D4633–05, “Standard Test Method for Energy Measurement for Dynamic Penetrometers,” November 2005.

— — — — —, ASTM D4767–04, “Standard Test Method for Consolidated Undrained Triaxial Compression Test for Cohesive Soils,” November 2004.

— — — — —, ASTM D4972–01, “Standard Test Method for pH of Soils,” January 2001.

— — — — —, ASTM D5092–04e1, “Standard Practice for Design and Installation of Ground Water Monitoring Wells,” January 2004.

— — — — —, ASTM D5385-93(2006), “Standard Test Method for Hydrostatic Pressure Resistance of Waterproofing Membranes” 2006.

D-9

— — — — —, ASTM D5778–95, “Standard Test Method for Performing Electronic Friction Cone and Piezocone Penetration Testing of Soils,” September 1995.

— — — — —, ASTM D6913–04, “Standard Test Methods for Particle-Size Distribution (Gradation) of Soils Using Sieve Analysis,” August 2004.

— — — — —, ASTM E185–10, “Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels,” March 2010.

— — — — —, ASTM E814–00, “Standard Test Method for Fire Tests of Through-Penetration Fire Stops,” August 2000.

— — — — —, ASTM G57–95A, “Standard Test Method for Field Measurement of Soil Resistivity Using the Wenner Four-Electrode Method,” January 1995.

— — — — —, ASTM G114-07, "Standard Practices for Evaluating the Age Resistance of Polymeric Materials Used in Oxygen Service," 2007.

American Welding Society (AWS)

— — — — —, AWS D1.1-2006, “Structural Welding Code – Steel,” 2006.

Bechtel National Inc. (Bechtel, or BNI)

— — — — —, Bechtel “User's Manual for P-SHAKE, Version 1.0,” December 2006.

Bechtel Topical Report (BC-TOP)

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

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

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

Boiling-Water Reactor Owner’s Group (BWROG)

Topical Report (TR)

— — — — —, BWROG-TR-SIR-05-044-A, “Pressure-Temperature Limits Report Methodology for Boiling Water Reactors,” April 2007. (ADAMS Accession No. ML072340283.)

D-10

— — — — —, BWROG Project Task Report DRF 0000-0155-1541, “RCIC Pump and Turbine Durability Evaluation-Pinch Point Study,” Revision 0, January 2013.

Electric Power Research Institute (EPRI)

Reports

— — — — —, EPRI NP–4726, “Seismic Parameter Estimation Methods, in Seismic Hazard Methodology for the Central and Eastern United States,” 1986.

— — — — —, EPRI NP–4726-A, “Seismic Parameter Estimation Methods, in Seismic Hazard Methodology for Nuclear Facilities in the Eastern United States,” 1988.

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

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

— — — — —, EPRI NP–6316, "Guide for Threaded Fasteners," July 1989.

— — — — —, EPRI NP–6395-D, “Probabilistic Seismic Hazard Evaluation at Nuclear Plant Sites in the Central and Eastern United States: Resolution of the Charleston Earthquake Issue," April 1989.

— — — — —, EPRI NP–6695, "Guidelines for Nuclear Plant Response to an Earthquake," December 1989.

— — — — —, EPRI 1986-1989, “Seismic Hazard Methodology for the Central and Eastern United States” (NP-4726), Vol. 1-3 & 5-10, 1986-1989.

— — — — —, EPRI 2004- (EPRI TR-1009684), “CEUS Ground Motion Project Final Report,” December 2004.

— — — — —, EPRI 2005- (EPRI TR-1012045), “Program on Technology Innovation: Assessment of a Performance-Based Approach for Determining Seismic Ground Motions for New Plant Sites,” Final Report, Volume 2: Seismic Hazard Results at 28 Sites, August 2005.

— — — — —, EPRI 2006 – (EPRI TR-1014381), “Program on Technology Innovation: Truncation of the Lognormal Distribution and Value of the Standard Deviation for Ground Motion Models in the Central and Eastern United States,” August 2006.

Technical Reports (TR)

— — — — —, EPRI TR-1003113, “An Analysis of Loss of Decay Heat Removal Trends and Initiating Event Frequencies (1989 - 2000): Outage Risk Assessment and Management (ORAM) Technology,” November 2001.

D-11

— — — — —, EPRI TR-102261-V1, “The Earthquakes of Stable Continental Regions,” Volume 1: “Assessment of Large earthquake Potential,” December 1994.

— — — — —, EPRI TR-102293, “Guidelines for Determining Design Basis Ground Motions,” Volume 5,”Quantification of Seismic Source Effects,” November 1993.

— — — — —, EPRI TR-102293, “Guidelines for Determining Design Basis Ground Motions,” Volumes 1-5; Appendix 7.A, “Modeling of Dynamic Soil Properties,” 1993.

— — — — —, EPRI TR-1018794, “BWR Vessel and Internals Project–Steam Dryer Inspection and Flow Evaluation Guidelines,” BWRVIP-139-A, July 27, 2009. (ML101270122), [staff approval of BWRVIP-139-A is in ML111662165])

— — — — —, EPRI TR-102587, “Seismic Evaluation Guidance,” November 2012. (ADAMS Accession No. ML12333A170.)

Others

— — — — —, EPRI Nuclear Safety Analysis Center (NSAC) -202L, Revision 3, “Recommendations for an Effective Flow-Accelerated Corrosion Program,” 2006.

— — — — —, EPRI-SOG NP–4726, Revision 1, “Seismic Hazard Methodology for the Central and Eastern United States,” Volume 1, Part 2: “Methodology,” 1998.

— — — — —, EPRI “EPRI (2004, 2006) Ground-Motion Model Review Project: Final Products 3002000717,” Chapter 7, “Updated EPRI (2004, 2006) GMM,” June 2013, (ADAMS Accession No. ML13155A553).

Exelon Generation Company (Exelon)

— — — — —, Exelon, 2006– Exelon Generation Company (EGC), “Early Site Permit ESP Application for the EGC ESP Site,” Revision 4, Docket No. 52-007 (Proprietary), April 4, 2006.

Federal Energy Regulatory Commission (FERC)

— — — — —, FERC 2009, “Engineering Guidelines for the Evaluation of Hydropower Projects, Determination of the Probable Maximum Flood,” Chapter VIII, 2001; available at http://www.ferc.gov/industries/hydropower/safety/guidelines/eng-guide.asp; accessed on November 30.

Federal Emergency Management Agency (FEMA)

— — — — —, Letter from Vanessa E. Quinn, FEMA, to Kevin Williams, NRC, “Federal Emergency Management Agency’s (FEMA) Interim Finding Report (IFR) for Reasonable

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Assurance (RA) of the Offsite Emergency Response Plans for South Texas Project (STP) Nuclear Power Plant Units 3 and 4 Combined License (COL) Application,” January 27, 2010. (ADAMS Accession No ML100350989, ML100350985, ML100350987.)

— — — — —, “Numerical Models Meeting the Minimum Requirement of National Flood Insurance Program,” available at http://www.fema.gov/plan/prevent/fhm/en_coast.shtm , accessed on December 20, 2010.

Federal Register (FR)

— — — — —, 51 FR 28044, “Safety Goals for the Operations of Nuclear Power Plants; Policy Statement,” August 4, 1986, and is Republished in 51 FR 30028, August 21, 1986. (available at: www.nrc.gov/reading-rm/doc-collections/commission/policy/

General Electric Company (GE)

— — — — —,”ABWR Certified Design Material /ITAAC Review Guidance,” April 13, 1994 (Referenced in the response to RAI 03.02.02.02-6, [ADAMS Accession No. 092430131]).

Topical Reports (NEDE and NEDO)

— — — — —, NEDO–24011–A–14–US, “General Electric Standard Application for Reactor Fuel,” July 2000. (ADAMS Accession No. ML003734853.)

— — — — —, 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, "General Electric Standard Application on Fuel," September 1988.

— — — — —, NEDO-20533, “The General Electric Mark III Pressure Suppression Containment System Analytical Model,” June 1974.

— — — — —, NEDO–20533-1, "The General Electric Mark III Pressure Suppression Containment System Analytical Model Supplement 1," September 1975.

— — — — —, NEDO–21778-A, “Transient Pressure Rises Affecting Fracture Toughness Requirements for Boiling Water Reactors,” December 1978.

— — — — —, NEDE–24326-1-P, "General Electric Environmental Qualification Program,” January 1983.

— — — — —, NEDO-32686-A, “Utility Resolution Guidance for ECCS Suction Strainer Blockage,” October 1998. (ADAMS Accession No. ML092530449.)

— — — — —, NEDO–33297, “Advance Boiling Water Reactor (ABWR) Procedures Development Plan,” January 2007.

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— — — — —, NEDO–33315P, “Advanced Boiling Water Reactor (ABWR) Reactor Pressure Vessel (RPV) Material Surveillance Program," April 2007.

— — — — —, NEDO–33372, "Advanced Boiling Water Reactor (ABWR) Containment Analysis," September 2007.

General Electric Nuclear Engineering (GENE)

— — — — —, GENE–637-019-0893, Revision 0, “Analysis Guidelines for Backfill Modification of RPV Water Level Instrumentation,” July 1993.

Holtec International (HI) Technical Report

— — — — —, HI-2012627, “QA Documentation Package for ANSYS, Version 11.0 and higher,” Revision 10.

— — — — —, HI-2043215, “Sourcebook for Metamic Performance Assessment,” Revision 3.

— — — — —, HI-2114848, “QA Validation of DYNAMO Codes for Whole Pool Multi Rack Analysis.”

— — — — —, HI-2135462, “Licensing Report for South Texas Project Units 3 and 4 ABWR Spent Fuel Racks”, Revision 2, July 14, 2014. (ADAMS Accession No. ML14199A606 –Non-proprietary)

— — — — —, HI-961519, “LS-DYNA QA Validation,” Revision 7.

Illuminating Engineering Society of North America (IESNA)

— — — — —, IESNA, “Lighting Handbook,” 9th Edition, 2000.

Institute of Electrical and Electronics Engineers (IEEE) Standards (Std)

— — — — —, IEEE Std 7-4.3.2–1993, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” 1993.

— — — — —, IEEE Std 7-4.3.2–2002, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” 2002.

— — — — —, IEEE Std 81–1983, "IEEE Guide for Measuring Earth Resistivity, Ground Impedance, and Earth Surface Potentials of a Ground System,” 1983.

— — — — —, IEEE Std 141–1986, “IEEE Recommended Practice for Electric Power Distribution for Industrial Plants,” 1986.

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— — — — —, IEEE Std 242–1986, "IEEE Recommended Practice for Protection and Coordination of Industrial and Commercial Power Systems,” 1986.

— — — — —, IEEE Std 279–1971, "IEEE Criteria for Nuclear Power Plant Protection Systems," 1971.

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

— — — — —, IEEE Std 323–1974, "Qualifying Class 1E Equipment for Nuclear Power Generating Stations," 1974.

— — — — —, IEEE Std 336–1985, “IEEE Standard Installation, Inspection, and Testing Requirements for Power, Instrumentation, and Control Equipment at Nuclear Facilities,” 1985.

— — — — —, 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,” 2006.

— — — — —, IEEE Std 344–1987, “IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," 1987.

— — — — —, IEEE Std 379–1992, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems.”

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

— — — — —, IEEE Std 384–1992, "IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits," 1992.

— — — — —, 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,” 2002.

— — — — —, IEEE Std 484–2002, “IEEE Recommended Practice for Installation Design and Implementation of Vented Lead-Acid Batteries for Stationary Applications,” 2002.

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

— — — — —, IEEE Std 498–1985, “IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment Used in Nuclear Facilities,” 1985.

— — — — —, IEEE Std 519–1981, “IEEE guide for harmonic control and reactive compensation of static power converters,” 1981.

D-15

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

— — — — —, IEEE Std 603–1980, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Systems,” 1980.

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

— — — — —, IEEE Std 603–2009, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations” 2009.

— — — — —, IEEE Std 665–1995, "IEEE Guide for Generation Station Grounding" 1995.

— — — — —, IEEE Std 666–2007, “IEEE Design Guide for Electric Power Service Systems for Generating Stations,” 2007.

— — — — —, IEEE Std 741–2007, “IEEE Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations,” 2007.

— — — — —, IEEE Std 946–2004, “IEEE Recommended Practice for the Design of DC Auxiliary Systems for Generating Systems,” 2004.

— — — — —, IEEE Std 1050–2004, “IEEE Guide for Instrumentation and Control Equipment Grounding in Generating Stations” 2004.

— — — — —, IEEE Std C37.013–1997, “IEEE Standard for AC High Voltage Generator Circuit Breakers Rated on a Symmetrical Current Basis” 1997.

— — — — —, IEEE Std C57.19.100–1995, “IEEE Guide for Application of Power Apparatus Bushings,” 1995.

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

Instrument Society of America (ISA)

— — — — —, ISA-S67.4–1994, Part I, “Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants,” September 1994.

— — — — —, ISA-S67.4–1994, Part II, “Methodology for the Determination of Setpoints for Nuclear Safety-Related Instrumentation,” September 1994.

International Code Council (ICC)

— — — — —, “2006 International Building Code."

D-16

International Council of Building (ICB)

— — — — —, "1991 Uniform Building Code."

International Electrotechnical Commission (IEC) International Standard

— — — — —, IEC 61000-4-2, “Electromagnetic Compatibility (EMC) – Part 4-2: Testing and Measurement Techniques – Electrostatic Discharge Immunity Test,” December 9, 2008.

— — — — —, IEC Publication 801-2, Part 1, “Electromagnetic Compatability for Industrial Process Measurement and Control Equipment,” 1991.

— — — — —, IEC Publication 801-2, Part 2, “Electrostatic Discharge Requirements,” 1991.

Japan Society of Mechanical Engineers (JSME)

— — — — —, JSME Code for Nuclear Power Generation Facilities.

MACTEC Engineering and Consulting, Inc. (MACTEC)

— — — — —, MACTEC 2007, “Results of Subsurface Investigation and Laboratory Testing, South Texas Project Units 3 and 4,” Compact Disk Report, April.

Military Standards (MIL Std)

— — — — —, MIL Std 461E, “Requirements for the Control of Electromagnetic Interference Characteristics of Subsystems and Equipment,” 1999.

— — — — —, MIL Std 462E, "Measurement of Electromagnetic Interference Characteristics," 1999.

— — — — —, MIL Std 1478, “Military Standard, Task Performance Analysis,” 1999.

National Climatic Data Center (NCDC)

— — — — —, “Bay City Wtr Wks, Bay City, TX,” 2008a; http://www4.ncdc.noaa.gov/cgi-win/wwcgi.dll?wwDI~StnSrch~StnID~20024300; (April 17, 2008).

— — — — —, “Matagorda 2, Matagorda, TX,” 2008b; http://www4.ncdc.noaa.gov/cgi-win/wwcgi.dll?wwDI~StnSrch~StnID~20024268; (April 17, 2008).

D-17

— — — — —, “Palacios Municipal Airport, Palacios, TX,” 2008c; http://www4.ncdc.noaa.gov/cgi-win/wwcgi.dll?wwDI~StnSrch~StnID~20024269; (April 17, 2008).

National Fire Protection Association (NFPA)

— — — — —, NFPA 10, “Standard for Portable Fire Extinguishers,“ 2013.

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

— — — — —, NFPA 15, “Standard for Water Spray Fixed Systems for Fire Protection,” 2007.

— — — — —, NFPA 24, “Standard for the Installation of Private Fire Service Mains and Their Appurtenances.” 2013

— — — — —, NFPA 72, “National Fire Alarm Code,” 2013.”

— — — — —, NFPA 92A, “Standard for Smoke-Control Systems Utilizing Barriers and Pressure Differences,” 2009.

— — — — —, NFPA 214, “Standard for Water-Cooling Towers,” 2011.

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

— — — — —, NFPA 801, “Standard for Fire Protection for Facilities Handling Radioactive Materials,” 2014.

National Oceanic and Atmospheric Administration (NOAA)

— — — — —, “NOS Station #A772440, Freeport – Vertical Historical Tide Data,” available at http://tidesandcurrents.noaa.gov/sltrends/sltrends.shtml, accessed on August 19, 2008. ten Brink, U.S., et al., “Evaluation of Tsunami Sources with the Potential to Impact the U.S. Atlantic and Gulf Coasts ―An Updated Report to the Nuclear Regulatory Commission,” U.S. Geological Survey Administrative Report, 2008.

— — — — —, “Mean Sea Level Trend 8772440 Freeport, Texas”; http://tidesandcurrents.noaa.gov/sltrends/sltrends_station.shtml?stnid=8772440%20Freeport,%20TX; (April 3, 2009).

— — — — —, “Meteorological Criteria for Standard Project Hurricane and Probable Maximum Hurricane Windfields, Gulf and East Coasts of the United States,” NOAA Technical Report NWS 23, U.S. Department of Commerce, Washington, DC, September 1979.

— — — — —, “2006 Local Climatological Data, Annual Summary with Comparative Data, Victoria, Texas (KVCT),” National Climatic Data Center (NCDC), National Environmental Satellite Data and Information Service (NESDIS), 2007.

D-18

Nuclear Energy Institute (NEI)

— — — — —, NEI 00-01, Revision 2, “Guidance for Post-Fire Safe Shutdown Analysis,” May 2009. (ADAMS Accession No. ML091770265.)

— — — — —, NEI 03–12, Revision 6, “Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, [and Independent Spent Fuel Installation Security Program].” April 2009. (ADAMS Accession No. ML090920528.)

— — — — —, NEI 04–04, "Cyber Security Program for Power Reactors," February 2005. (Not publically available.)

— — — — —, NEI 04–07, “Pressurized Water Reactor Sump Performance Evaluation Methods,” December 2004. (ADAMS Accession No. ML050550138.)

— — — — —, NEI 06–06, Revision 5, "Fitness for Duty Program Guidance for New Nuclear Power Plant Construction Sites," August 2009. (ADAMS Accession No. ML092430016.)

— — — — —, NEI 06–13, “Template for an Industry Training Program Description,” October 2006. (ADAMS Accession No. ML063390459.)

— — — — —, NEI 06–13A, “Technical Report on Template for an Industry Training Program Description,” October 2007. (ADAMS Accession No. ML072920293.)

— — — — —, NEI 06–13A, Revision 2, “Template for an Industry Training Program Description,” March 2009. (ADAMS Accession No. ML090910554.)

— — — — —, NEI 06–14, Revision 7, “Quality Assurance Program Description,” July 2009. (ADAMS Accession No. ML092660025.)

— — — — —,NEI 06-14A, Revision 7, “Quality Assurance Program Description,” August 2010. (ADAMS Accession No. ML102370305.)

— — — — —, NEI 07–02, “Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52,” February 2007. (ADAMS Accession No. ML070610363.)

— — — — —, NEI 07–02, Revision 3, “Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52.” September 21, 2007. (ADAMS Accession No. ML072700564.)

— — — — —, NEI 07–02A, “Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52,” March 2008. (ADAMS Accession No. ML080910149.)

— — — — —, NEI 07–03, Revision 3, “Generic FSAR Template Guidance for Radiation Protection Description,” October 2007. (ADAMS Accession No. ML072780410.)

— — — — —, NEI 07–03A, “Generic FSAR Template Guidance for Radiation Protection Program Description,” May 2009. (ADAMS Accession No. ML091490684.)

D-19

— — — — —, NEI 07–08, Revision 3, “Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA),” November 2008. (ADAMS Accession No. ML083380351.)

— — — — —, NEI 07–08A, “Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA),” October 2009. (ADAMS Accession No. ML093220178.)

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

— — — — —, NEI 07–10A, Revision 0, “Generic FSAR Template Guidance for Process Control Program (PCP),” March 2009. (ADAMS Accession No. ML091460627.)

— — — — —, NEI 08–01, Revision 4, “Industry Guidelines for ITAAC Closure Progress under 10 CFR 52,” July 16, 2010. (ADAMS Accession No. ML102010076.)

— — — — —, NEI 08–08, Revision 3, “Generic FSAR Template Guidance for Life Cycle Minimization of Contamination,” September 2009. (ADAMS Accession Nos. ML092890146, ML092740379.)

— — — — —, NEI 08-08A, “Generic FSAR Template Guidance for Life Cycle Minimization of Contamination,” October 2009. (ADAMS Accession No. ML093220530.)

— — — — —, NEI 12-01, Revision 0, “Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities,” May 4, 2012. (ADAMS Accession No. ML12125A412.)

— — — — —, NEI 12-02, Revision 1, “Industry Guidance for Compliance with NRC Order EA-12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation,” August 24, 2012. (ADAMS Accession No. ML122400399.)

— — — — —, NEI 12-06, Revision 0, “Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,” August 21, 2012. (ADAMS Accession No. ML12242A378.)

— — — — —, NEI 99–01, Revision 5, “Methodology for Development of Emergency Action Levels,” February 2008. (ADAMS Accession No. ML080450149.)

Nuclear Information and Records Management Association (NIRMA)

— — — — —, TG 11-1998, "Authentication of Records and Media," 1998.

— — — — —, TG 15-1998, "Management of Electronic Records," 1998.

— — — — —, TG 16-1998, "Software Configuration Management and Quality Assurance," 1998.

— — — — —, TG 21-1998, "Electronic Records Protection and Restoration," 1998.

D-20

Nuclear Management and Resources Council, Inc. (NUMARC)

— — — — —, NUMARC 87–00, Revision 1,”Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors,” August 1991.

— — — — —, NUMARC 93–01, Revision 2, “Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” April 1996.

South Texas Project (STP)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 0, September 20, 2007. (ADAMS Accession Number ML072850066.).

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 1, January 31, 2008. (ADAMS Accession Number ML080700399.).

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 2, September 28, 2008. (ADAMS Accession Number ML082830938.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 3, September 16, 2009. (ADAMS Accession Number ML092930393.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 4, October 5, 2010. (ADAMS Accession Number ML102861292.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 5, January 26, 2011. (ADAMS Accession Number ML110340451.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 6, August 30, 2011. (ADAMS Accession Number ML11252A505.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 7, February 1, 2012. (ADAMS Accession Number ML110340451.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 8, September 17, 2012. (ADAMS Accession Number ML12291A415.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 9, April 17, 2013. (ADAMS Accession Number ML13115A094.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 10, October 29, 2013. (ADAMS Accession Number ML13310A599.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 11, October 21, 2014. (ADAMS Accession Number ML13310A599.)

— — — — —, South Texas Project, Units 3 and 4, Combined License Application, Revision 12, April 21, 2015. (ADAMS Accession Number ML15120A324.)

D-21

STP Policy, Technical, and Procedure Reports

— — — — —, U7-AD01-0004, “Units 3 & 4 Procedure Use and Adherence Policy,” April 2009. (ADAMS Accession No. ML090930716.)

— — — — —, U7-C-STP-NRC-090080, "South Texas Project (STP) Units 3 & 4 Pressure-Temperature Limits Report (PTLR) and Fluence Calculation Methodology," July 23, 2009. (ADAMS Accession No. ML092080079.)

— — — — —, U7-P-AD02-0002, “Units 3 & 4 Procedure Development, Review and Approval,” April 2009. (ADAMS Accession No. ML090930716.)

— — — — —, U7-P-RM02-0001, “Units 3 & 4 Records Management and Document Control,” April 2009. (ADAMS Accession No. ML090930716.)

— — — — —, U7-RHR-M-RPT-DESN-0001, Rev. B, Proprietary, “The Evaluation Report for Net Positive Suction Head of Pump in Emergency core Cooling System, “February 10, 2010. (ADAMS Accession No. ML100541570.)

— — — — —, U7-RHR-M-RPT-DESN-0002, Rev. C, Proprietary, “The Supplementary Documentation for the Head Loss Evaluation Report of Japanese ABWR ECCS Suction Strainer,” February 10, 2010. (ADAMS Accession No. ML100541572.)

— — — — —, U7-RHR-M-RPT-DESN-0003, Rev. A, Proprietary, “The Evaluation Example of the Head Loss of the ECCS Suction Strainer and Pipe in the ECCS Pump Run-out Flow Condition,” May 27, 2009. (ADAMS Accession No. ML093090336.)

— — — — —, U7-RPV-S-RPT-STRS-5000, Revision 0, “South Texas Project Units 3 and 4 Pressure-Temperature Limits Report (PTLR) for 60 Effective Full-Power Years (EFPY),” July 23, 2009. (ADAMS Accession No. ML092080079.)

Other

— — — — —, “South Texas Project Development of the Evacuation Time Estimates” Final Report, April 2008.

— — — — —, “South Texas Project, Units 3 and 4 - Submittal of Technical Report,” May 10, 2010. (ADAMS Accession No. ML101320258.)

— — — — —, “South Texas Project Nuclear Operating – Company’s Response to NRC Inspection Report No. 05200012-09-201 and 0520013-09-201 and Notice of Violation,” April 15, 2009. (ADAMS Accession No. ML090990607.)

D-22

Texas Codes and Regulations

— — — — —, Texas Utilities Code, Chapter 39, Section 39.206, "Nuclear Generating Unit Decommissioning Cost Plan.”

— — — — —, Public Utility Commission of Texas, Electric Substantive Rule, Chapter 25, Subchapter L, Section 25.304, “Nuclear Decommissioning Funding and Requirements for Power Generation Companies,” January 9, 2014, available at: https://www.puc.texas.gov/agency/rulesnlaws/subrules/electric/25.304/25.304ei.aspx

Toshiba Corporation

— — — — —, RS-5126579, Revision 1, "STP 3 and 4 Reactor Internals Flow Induced Vibration Assessment Program.”

— — — — —, RS-5126954, Revision 1, "Prototype ABWR Reactor Internals Flow Induced Vibration Test Report."

— — — — —, UTLR-0003, Revision 0, "Reactor Vessel Materials Surveillance Program," April 2009. (ADAMS Accession No. ML090960297.)

— — — — —, UTLR-0004-P, Revision 1, "Application of Turbine Water Lubricated (TWL) Pump to South Texas Project Unit 3 & 4 RCIC Turbine-Pump." March 2010. (ADAMS Accession No. ML101320258.)

— — — — —, UTLR-0005, “ABWR Pool Swell Calculation Methodology Using GOTHIC,” September 2009.

— — — — —, UTLR-RS-5126528, Revision 1, “STP 3 & 4 Reactor Pressure Vessel Surveillance Program," July 2008. .

U.S. Army Corps of Engineers

Engineering Manuals (EM)

— — — — —, EM 1110-2-1100, “Coastal Engineering Manual,” June 2006.

— — — — —, EM 1110-2-1100, “Coastal Engineering Manual,” August 2008.

— — — — —, EM 1110-2-1100, “Coastal Engineering Manual – Part II,” August 2008.

— — — — —, EM 1110-2-1601 “Hydraulic Design of Flood Control Channels,” 1994.

— — — — —, EM 1110-2-1612, “Engineering and Design – Ice Engineering,” October 2002.

— — — — —, EM 1110-2-1417, “Flood-Runoff Analysis,” August 1994.

— — — — —, EP 1165-2-314, “Flood Proofing Regulations,” 1992.

D-23

Others

— — — — —, “Hydrologic Modeling System, HEC-HMS, User’s Manual, Version 3.1.0,” U.S. Army Corps of Engineers, Hydrologic Engineering Center, Washington, DC, November 2006.

— — — — —, “HEC-RAS, River Analysis System, User’s Manual, Version 3.1.3,” Hydrologic Engineering Center, 2005, available at http://www.hec.usace.army.mil/software/hec-ras/hecras-download.html.

— — — — —, “HEC-RAS, River Analysis System, User’s Manual,” Version 3.1.3, Hydrologic Engineering Center, 2005, U.S. Geological Survey, “Water Resources of Illinois: n-Values Project,” available at: http://il.water.usgs.gov/proj/nvalues/equations.shtml?equation=05-strickler, accessed on March 15, 2011, last updated February 28, 2009.

— — — — —, “Ice Jam Database,” Ice Jam Information Clearinghouse, Cold Regions Research and Engineering Laboratory, 2008; http://www.crrel.usace.army.mil/icejams/; April 17, 2008.

— — — — —, “River Analysis System, HEC-RAS, Version 3.1.3,” U.S. Army Corps of Engineers Hydrologic Engineering Center, Washington, DC, May 2005.

— — — — —, Shore Protection Manual, U.S. Army Coastal Engineering Research Center, Third Edition, 1977.

— — — — —, “User's Guide to RMA2 WES, Version 4.5,” Coastal and Hydraulics Laboratory, Waterways Experiment Station, Engineer Research and Development Center, Vicksburg, Mississippi, 2005.

— — — — —, “User's Guide to SED2D WES, Version 4.5,” Coastal and Hydraulics Laboratory, Waterways Experiment Station, Engineer Research and Development Center, Vicksburg, Mississippi, 2003.

— — — — —, “Shore Protection Manual,” Vol. I and Vol. 2, June 2002. (Reprinted from the 1973 edition), U.S. Army Coastal Engineering Research Center.

— — — — —, “The Estimation of Very-Low Probability Hurricane Storm Surges for Design and Licensing of Nuclear Power Plants in Coastal Areas”, Coastal and Hydraulics Laboratory, Engineer Research and Development Center, Vicksburg, MS, 2011

U.S. Department of Army, Technical Manual (TM)

— — — — —, TM 5-855-1, “Fundamentals of Protective Design for Conventional Weapons,” November 1986.

U. S. Department of Commerce, National Oceanic and Atmospheric Administration-National Geophysical Data Center, (NOAA-NGDC)

D-24

— — — — —, NOAA-NGDC, “Land and Marine Gravity CD-ROMS,” Dater, D., Metzger, D., and Hittelman, A., 1999.

U.S. Department of Energy, (DOE)

Technical Standard (STD)

— — — — —, DOE-STD-3014-96, “Accident Analysis for Aircraft Crash into Hazardous Facilities,” October 1996. (Updated in 2006; DOE-STD-3014-2006; available at: http://energy.gov/ehss/downloads/doe-std-3014-2006.)

U.S. Department of the Interior, Bureau of Reclamation

— — — — —, “Mansfield Dam Comprehensive Facility Review, Highland Lakes Dams, Lower Colorado River Authority,” Technical Service Center, Denver, CO, March 2003; http://www.usbr.gov/dataweb/dams/tx01087.html;

— — — — —, “Probable Maximum Flood, Marshall Ford Dam, Lower Colorado River Project, Texas,” November 1985.

— — — — —, “SEED Analysis Report - Marshall Ford Dam,” ATC Engineering Consultants Inc., prepared for the United States Department of the Interior, Bureau of Reclamation, Colorado River Project, July 1989.

U.S. Department of Transportation, Federal Highway Administration (FHWA)

— — — — —, FHWA-HRT-04-043 “A Laboratory and Field Study of Composite Piles for Bridge Substructures,” 2006.

U.S. Environmental Protection Agency (EPA)

— — — — —, “Drinking Water Standards,” available at http://www.epa.gov/lawsregs/rulesregs/sdwa/index.cfm.

— — — — —, 335.5, Revision 1, Report No. EPA/600/R-93/100, EPA 300.0, “Method for the Determination of Inorganic Substances in Environmental Samples,” August 1993.

— — — — —, Report No. EPA/ 816-F-10-079, “Secondary Drinking Water Regulations: Guidance for Nuisance Chemicals,” available at http://water.epa.gov/drink/contaminants/secondarystandards.cfm%20, (accessed on June 8, 2009).

D-25

U.S. Government Accounting Office (GAO)

— — — — —, GAO-06-322T, “Hurricane Protection: Statutory and Regulatory Framework for Levee Maintenance and Emergency Response for the Lake Pontchartrain Project,” 2006.

U.S. Global Change Research Program (USGCRP)

— — — — —, “Global Climate Change Impacts in the United States,” T.R. Karl, J.M. Melillo, and T.C. Peterson (eds.), Cambridge University Press, New York, 2009. (ADAMS Accession No. ML100580077.)

U. S. Geological Survey (USGS)

— — — — —, USGS 2002a, “Magnetic Anomaly Map of North America,” Open-File Report 02-414 accompanying booklet, Bankey, V., Cuevas, A., Daniels, D., Finn, C.A., Hernandez, I., Hill, P., Kucks, R., Miles, W., Pilkington, M., Roberts, C., Roest, W., Rystrom, V., Shearer, S., Snyder, S., Sweeney, R., and Velez, J., 2002.

— — — — —, USGS 2002b “Digital Data Grids for the Magnetic Anomaly Map of North America,” USGS Open-File Report 02-414, Bankey, V., Cuevas, A., Daniels, D., Finn, C.A., Hernandez, I., Hill, P., Kucks, R., Miles, W., Pilkington, M., Roberts, C., Roest, W., Rystrom, V., Shearer, S., Snyder, S., Sweeney, R., Velez, J., Phillips, J.D., and Ravat, D., 2002.

U. S. Natural Resources Conservation Service (NRCS)

— — — — —, “Urban Hydrology for Small Watersheds,” Technical Release 55, U.S. Department of Agriculture, Natural Resources Conservation Service, Second Edition revised June 1986, update of Appendix A, January 1999. (This is now called WIN TR-15 and is available at: http://go.usa.gov/koz.)

U.S. Nuclear Regulatory Commission (NRC)

Branch Technical Positions (BTP)

— — — — —, BTP 7-10, Revision 5, “Guidance on Application of Regulatory Guide 1.97,” March 2007. (ADAMS Accession No. ML070550082.)

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

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

D-26

— — — — —, BTP 7-19, Revision 5, “Guidance for Evaluation of Diversity and Defense-in-Depth in Digital Computer-Based Instrumentation and Control Systems,” March 2007. (ADAMS Accession No. ML070550075.)

— — — — —, BTP 7-21, Revision 5, “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 11-5, 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 ICSB-14, Revision 2, “Spurious with Drawings of Single Control Rods in Pressurized Water Reactors,” July 1981. (ADAMS Accession No. ML052350480.)

— — — — —, BTP SPLB 9.5-1, “Guidelines for Fire Protection for Nuclear Power Plants (formerly BTP CMEB 9.5-1),” July 1981. (ADAMS Accession No. ML052350030.) (This BTP is now included in NUREG–0800 Section 9.5.1.)

Bulletins (BL)

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

— — — — —, IE 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 2012-01, “Design Vulnerability in Electric Power System,” July 27, 2012 (ADAMS Accession No. ML12074A115)

U.S. Code of Federal Regulations (CFR)

— — — — —, Title 10, Energy, Part 19, “Notices, Instructions and Reports to Workers: Inspection and Investigations.”

— — — — —, Title 10, Energy, 19.12, “Instruction to workers.”

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

— — — — —, Title 10, Energy, 20.1301, “Dose limits for individual members of the public.”

D-27

— — — — —, 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, 20.2206, “Reports of individual monitoring.”

— — — — —, 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 21, “Reporting of Defects and Noncompliance.”

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

— — — — —, Title 10, Energy, 26.3, “Scope.”

— — — — —, Title 10, Energy, 26.4, “FFD program applicability to categories of individuals.”

— — — — —, Title 10, Energy, 26.205, “Work hours.”

— — — — —, Title 10, Energy, Part 30, “Rules of General Applicability to Domestic Licensing of Byproduct Material.”

— — — — —, Title 10, Energy, 30.32, “Application for specific licenses.”

— — — — —, Title 10, Energy, 30.33, “General requirements for issuance of specific licenses.”

— — — — —, Title 10 CFR 30.35, “Financial assurance and recordkeeping for decommissioning.”

— — — — —, Title 10, Energy, 30.53, “Tests."

— — — — —, Title 10, Energy, 30.72, “Schedule C—Quantities of radioactive materials requiring consideration of the need for an emergency plan for responding to release.”

— — — — —, Title 10, Energy, Part 31, “General Domestic Licenses for Byproduct Material.”

— — — — —, Title 10, Energy, Part 32, “Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material.”

— — — — —, Title 10, Energy, Part 33, “Specific Domestic Licenses of Broad Scope for Byproduct Material.”

— — — — —, Title 10, Energy, Part 34, “Licenses for Industrial Radiography and Radiation Safety Requirements for Industrial Radiographic Operations.”

— — — — —, Title 10, Energy, Part 37, “Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material.”

— — — — —, Title 10, Energy, Part 40, “Domestic Licensing of Source Material.”

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— — — — —, Title 10, Energy, 40.31, “Application for specific licenses.”

— — — — —, Title 10, Energy, 40.32, “Elimination of repetition.”

— — — — —, 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 applications; technical information.”

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

— — — — —, Title 10, Energy, 50.38, “Ineligibility of certain applicants.”

— — — — —, Title 10, Energy, 50.40, “Common standards.”

— — — — —, Title 10, Energy, 50.44, “Combustible gas control for nuclear power reactors.”

— — — — —, 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.”

— — — — —, 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, 50.68, “Criticality accident requirements.”

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— — — — —, Title 10, Energy, 50.71, “Maintenance of records, making of reports.”

— — — — —, Title 10, Energy, 50.120, “Training and qualification of nuclear power plant personnel."

— — — — —, Title 10, Energy, 50.150, “Aircraft impact assessment.”

— — — — —, 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 H, “Reactor Vessel Material Surveillance Program 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 is 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, 51.50, “Environmental report—construction permit, early site permit, or combined license stage.”

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

— — — — —, Title 10, Energy, 52.7, “Specific exemptions.”

— — — — —, Title 10, Energy, 52.8, “Combining licenses; elimination of repetition.”

— — — — —, Title 10, Energy, 52.17, “Contents of applications; general information.”

— — — — —, Title 10, Energy, 52.47, “Contents of applications; technical information.”

— — — — —, Title 10, Energy, 52.59, “Criteria for renewal.”

— — — — —, Title 10, Energy, 52.63, “Finality of standard design certifications.”

— — — — —, Title 10, Energy, 52.73, “Relationship to other subparts.”

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— — — — —, Title 10, Energy, 52.77, “Contents of applications; general information.”

— — — — —, Title 10, Energy, 52.78, “Contents of applications; training and qualification of nuclear power plant personnel.”

— — — — —, 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, 52.80, “Transfer of licenses.”

— — — — —, Title 10, Energy, 52.81, “Standards for review of applications.”

— — — — —, Title 10, Energy, 52.83, “Finality of referenced NRC approvals; partial initial decision on site suitability.”

— — — — —, Title 10, Energy, 52.85, “Administrative review of applications; hearings.”

— — — — —, Title 10, Energy, 52.87, “Referral to the Advisory Committee on Reactor Safeguards (ACRS).”

— — — — —, Title 10, Energy, 52.97, “Issuance of combined licenses.”

— — — — —, Title 10, Energy, 52.98, “Finality of combined licenses; information requests.”

— — — — —, Title 10, Energy, 52.99, “Inspection during construction."

— — — — —, Title 10, Energy, Part 52, Appendix A, “Design Certification Rule for the U.S. Advanced Boiling Water Reactor.”

— — — — —, Title 10, Energy, Part 52, Appendix D, “Design Certification Rule for the AP1000 Design.”

— — — — —, Title 10, Energy, Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants.”

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

— — — — —, Title 10, Energy, 55.13, “General exemptions.”

— — — — —, Title 10, Energy, 55.31, “How to apply.”

— — — — —, Title 10, Energy, 55.41, “Written examination: Operators.”

— — — — —, Title 10, Energy, 55.43, “Written examination: Senior operators.”

— — — — —, Title 10, Energy, 55.45, “Operating tests.”

— — — — —, Title 10, Energy, 55.46, “Simulation facilities.”

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— — — — —, Title 10, Energy, 55.59, “Requalification.”

— — — — —, Title 10, Energy, 61.56, “Waste characteristics.”

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

— — — — —, Title 10, Energy, 70.22, “Contents of applications.”

— — — — —, Title 10, Energy, 70.23, “Requirements for the approval of applications.”

— — — — —, Title 10, Energy, 70.24, “Criticality accident requirements.”

— — — — —, Title 10, Energy, 70.31, “Issuance of licenses.”

— — — — —, Title 10, Energy, 70.52, “Reports of accidental criticality.”

— — — — —, 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, “Purpose and scope.”

— — — — —, Title 10, Energy, 73.2, “Definitions.”

— — — — —, Title 10, Energy, 73.21, “Protection of Safeguards Information: Performance requirements.”

— — — — —, 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.”

— — — — —, Title 10, Energy, 73.58, “Safety/security interface requirements for nuclear power plants.”

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

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— — — — —, Title 10, Energy, Part 73, Appendix B “General Criteria for Security Personnel.”

— — — — —, Title 10, Energy, Part 73, Appendix C, “Nuclear Power Plant Safeguards Contingency Plans.”

— — — — —, Title 10, Energy, Part 73, Appendix G, “Reportable Safeguards Events.”

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

— — — — —, Title 10, Energy, 74.7, “Specific exemptions.”

— — — — —, Title 10, Energy, 74.11, “Reports of loss or theft or attempted theft or unauthorized production of special nuclear material.”

— — — — —, Title 10, Energy, 74.15, “Nuclear material transaction reports.”

— — — — —, Title 10, Energy, 74.17, “Special nuclear material physical inventory summary report.”

— — — — —, Title 10, Energy, 74.19, “Recordkeeping.”

— — — — —, Title 10, Energy, 74.31, “Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance.”

— — — — —, Title 10, Energy, 74.41, “Nuclear material control and accounting for special nuclear material of moderate strategic significance.”

— — — — —, Title 10, Energy, 74.51, “Nuclear material control and accounting for strategic special nuclear material.”

— — — — —, Title 10, Energy, Part 75, “Safeguards on Nuclear material —Implementation of US/IAEA Agreement.”

— — — — —, Title 10, Energy, 75.34, “Inventory change reports.”

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

— — — — —, Title 10, Energy, 100.1, “Purpose.”

— — — — —, Title 10, Energy, 100.2, “Scope.”

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

— — — — —, Title 10, Energy, 100.11, “Determination of exclusion area, low population zone, and population center distance.”

— — — — —, Title 10, Energy, 100.20, “Factors to be considered when evaluating sites.”

— — — — —, Title 10, Energy, 100.21, “Non-seismic site criteria.”

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— — — — —, Title 10, Energy, 100.23, “Geologic and seismic siting criteria.”

— — — — —, Title 10, Energy, Part 100, Appendix A, “Seismic and Geologic Siting Criteria for Nuclear Power Plants.”

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

— — — — —, Title 10, Energy, 140.13, “Amount of financial protection required of certain holders of construction permits and combined licenses under 10 CFR Part 52.”

— — — — —, Title 10, Energy, 140.21, “Licensee guarantees of payment of deferred premiums.”

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

— — — — —, Title 44, Emergency Management and Assistance, Part 350, “Review and Approval of State and Local Radiological Emergency Plans and Preparedness.”

— — — — —, Title 44, Emergency Management and Assistance, Part 353, “Fee for Services in Support, Review and Approval of State and Local Government or Licensee Radiological Emergency Plans and Preparedness.”

— — — — —, Title 44, Emergency Management and Assistance, Part 353, Appendix A, “Memorandum of Understanding (MOU) Between Federal Emergency Management Agency and Nuclear Regulatory Commission Relating to Radiological Emergency Planning and Preparedness,” dated September 14, 1993,

Commission Papers (SECY)

— — — — —, SECY-79-299, “Generic Issue of Financial Qualifications: Licensing of Production and Utilization Facilities,” April 27, 1979, (ADAMS Accession No. ML12236A723.)

— — — — —, SECY-91-078, “Chapter 11 Of The Electric Power Research Institute's (EPRI's) Requirements Document And Additional Evolutionary Light Water Reactor (LWR) Certification Issues, “ March 25, 1991. (ADAMS Accession No. ML072150592.)

— — — — —, SECY-92-327, “Reviews of Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the General Electric (GE) Advanced Boiling Water Reactor (ABWR)," September 22, 1992. (ADAMS Accession No. ML003707916.)

— — — — —, SECY-93-067, “Final Policy Statement on TS Improvements for Nuclear Power Reactors,” July 22, 1993. (Federal Register Vol. 58 – 58FR 39132-39139.)

— — — — —, SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs," April 2, 1993. (ADAMS Accession No. M003708021.)

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— — — — —, SECY-95-0132, “Policy and Technical Issues Associated With the Regulatory Treatment of Non-Safety Systems (RTNSS) in Passive Plant Designs,” May 22, 1995. (ADAMS Accession No. ML003708005.)

— — — — —, SECY-00-0074, “Regulatory Guide for Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants,” May 28, 2000. (ADAMS Accession No. ML003710125.).)

— — — — —, 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 No. ML052770225.)

— — — — —, SECY-05-0197, “Review of Operational Programs in a Combined License Application and Generic Emergency Planning Inspections, Tests, Analyses, and Acceptance Criteria,” Approval date 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 31, 2006.

— — — — —, SECY-11-0093, “Near Term Report and Recommendations for Agency Actions Following the Events in Japan,” July 12, 2011. (ADAMS Accession No. ML11186A950.)

— — — — —, SECY-11-0124, “Recommended Actions to Be Taken Without Delay From NTTF Report,” September 9, 2011. (ADAMS Accession No. ML11245A144.)

— — — — —, SECY-11-0137, “Prioritization of Recommended Actions to Be Taken in Response to Fukushima Lessons Learned,” October 3, 2011. (ADAMS Accession No. ML11272A203.)

— — — — —, SECY-12-0025, “Proposed Orders and Requests for Information in Response to Lessons Learned from Japan’s March 11, 2011, Great Tohoku Earthquake and Tsunami,” February 17, 2012. (ADAMS Accession No. ML12039A103.)

— — — — —, SECY-013-0124, “Policy Options for Merchant (Non-Electric Utility) Plant Financial Qualifications,” dated November 22, 2013.

Commission Orders (EA)

— — — — —, EA-12-049, “Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,” March 12, 2012. (ADAMS Accession No. ML12054A735.)

— — — — —, EA-12-051, “Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation,” March 12, 2012. (ADAMS Accession No. ML12054A679.)

Federal Register Notices

— — — — —, 52 FR 3788, “Proposed Policy Statement on TS improvements for Nuclear Power Reactors,” February 6, 1987.

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— — — — —, 72 FR 74252-74255, “Clean Air Act Reclassification of the Houston/Galveston/Brazoria Ozone Nonattainment Area; Texas; Proposed Rule,” December 31, 2007. Available at: http://www.gpoaccess.gov/fr/index.html.

— — — — —, 72 FR 79923 -79928, Notice of Availability of Model Safety Evaluation, Model No Significant Hazards Determination, and Model Application for Licensees That Wish To Adopt TSTF–511, Revision 0, ‘‘Eliminate Working Hour Restrictions From TS 5.2.2 To Support Compliance With 10 CFR Part 26,’’ December 30, 2008. (ADAMS Accession No. ML083180519.)

— — — — —, 78 FR 16921 -17022, “Physical Protection and Byproduct Material; Rule,” Vol. 78, No. 53, March 19, 2013. Available at: http://www.gpo.gov/fdsys/pkg/FR-2013-03-19/pdf/2013-05895.pdf.

General Design Criteria (GDC)

— — — — —, 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 13, “Instrumentation and control.”

— — — — —, GDC 14, “Reactor coolant pressure boundary.”

— — — — —, GDC 15, “Reactor coolant system design.”

— — — — —, GDC 16, “Containment design.”

— — — — —, GDC 17, “Electric power systems.”

— — — — —, GDC 18, “Inspection and testing of 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 mode.”

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— — — — —, GDC 24, “Separation of protection and control system.”

— — — — —, GDC 26, “Reactivity control system redundancy and capability.”

— — — — —, GDC 27, “Combined reactivity control systems capability.”

— — — — —, 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 32, “Inspection 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 39, “Inspection of containment heat removal system.”

— — — — —, GDC 40, “Testing of containment heat removal system.”

— — — — —, GDC 41, “Containment atmosphere cleanup.”

— — — — —, GDC 42, “Inspection of containment atmosphere cleanup systems.”

— — — — —, GDC 43, “Testing of containment atmosphere cleanup systems.”

— — — — —, GDC 44, “Cooling water.”

— — — — —, GDC 45, “Inspection of cooling water system.”

— — — — —, GDC 46, “Testing of cooling water system.”

— — — — —, GDC 50, “Containment design basis.”

— — — — —, GDC 51, “fracture prevention of containment pressure boundary.”

— — — — —, GDC 52, “Capability for containment leakage rate testing.”

— — — — —, GDC 53, “Provisions for containment testing and inspection.”

— — — — —, GDC 54, “Piping systems penetrating containment.”

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— — — — —, GDC 55, “Reactor coolant pressure boundary penetration ontainment.”

— — — — —, GDC 56, “Primary containment isolation.”

— — — — —, GDC 57, “Closed system isolation valves.”

— — — — —, GDC 60, “Control of releases of radioactive materials 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 Letters (GL)

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

— — — — —, GL 1988–018, "Proposed Final NRC Generic Letter 88-18, Supplement 1,” “Guidance on Managing Quality Assurance Records in Electronic Media,” September 13, 1999.

— — — — —, GL 1989–002, “Actions to Improve the Detection of Counterfeit and Fraudulently Marked Products,” March 21,1989.

— — — — —, GL 1989–008, “Erosion/Corrosion-Induced Pipe Wall Thinning,” May 2, 1989. (ADAMS Accession No. ML031200731.)

— — — — —, GL 1989–013, “Service Water System Problems Affecting Safety-Related Equipment,” July 18, 1989. (ADAMS Accession No. ML031150348.)

— — — — —, GL 1991–005, “Licensee Commercial-Grade Procurement and Dedication Programs,” April 9, 1991. (ADAMS Accession No. ML031140508.)

— — — — —, GL 1992–001, “Reactor Vessel Structural Integrity, 10 CVF 50.54(f),” February 28, 1992. (ADAMS Accession No. ML031200626.)

— — — — —, GL 1992–004, ““Resolution of the Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(f),” August 19, 1992. (ADAMS Accession No. ML031130402.)

— — — — —, 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.)

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— — — — —, GL 1996–003, “NRC Generic Letter 96-03: Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits,” January 31, 1996.

— — — — —, GL 2004–002, “Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors,” September 13, 2004. (ADAMS Accession No. ML042360586.)

— — — — —, GL 2006-002, “Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power,” March 30, 2006. (ADAMS Accession No. ML060940432.)

— — — — —, 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.)

General Safety Issues (GSI)

— — — — —, GSI-191, “Potential Impact of Debris Blockage On Emergency Recirculation During Design Basis Accidents At Pressurized-Water Reactors,” (this GSI is discussed in GL 2004-002.)

Inspection Manual (IM)

— — — — —, IM 2503, “Construction Inspection Program: Inspections of Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC),” October 3, 2007. (ADAMS Accession No. ML072681114.)

Information Notice (IN)

— — — — —, IN 1986-83, “Underground Pathways into Protected Areas, Vital Areas, Material Access Areas, and Controlled Access Areas,” September 19, 1986.

— — — — —, IN 2005-15, “Three-Unit Trip and Loss of Offsite Power at Palo Verde Nuclear Generating Station.” June 1, 2005.

— — — — —, IN 2006-17, “Recent Operating Experience of Service Water Systems Due to External Conditions,” July 31, 2006.

— — — — —, IN 2009-02, "Biodiesel in Fuel Oil Could Adversely Impact Diesel Engine Performance," February 23, 2009.

— — — — —, IN 93-27,”Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization,” April 8, 1993.

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Inspection Procedure (IP)

— — — — —, IP 73758, “Part 52, Functional Design and Qualification, and Preservice and Inservice Testing Programs for Pumps, Valves and Dynamic Restraints,”

Inspection Reports/Notices of Violation

— — — — —, IR 05200012-09-201 & 05200013-09-201, “South Texas Project Nuclear Operating Company; on 01/13-15/2009; STP Units 3 and 4, Quality Assurance Implementation Inspection and Notice of Violation,” March 2, 2009. (ADAMS Accession No. ML090560120.)

Interim Findings Report (IFR)

— — — — —, Letter from Vanessa E. Quinn, FEMA, to Kevin Williams, NRC, “Federal Emergency Management Agency's (FEMA) Interim Finding Report (IFR) for Reasonable Assurance (RA) of the Offsite Emergency Response Plans for South Texas Project (STP) Nuclear Power Plant Units 3 and 4 Combined License (COL) Application,” January 27, 2010. (ADAMS Accession No. ML100350989, ML100350985, ML100350987). [See also FEMA]

Interim Staff Guidance (ISG)

Design Certification/Combined License (DC/COL)

— — — — —, DC/COL-ISG-03, “Interim Staff Guidance, Probabilistic Risk Assessment Information to Support Design Certification and Combined License Applications,” dated June 11, 2008. (ADAMS Accession No. ML081430087.)

— — — — —, DC/COL-ISG-016, “Compliance with 10 CFR 50.54(hh)(2) and 10 CFR 52.80(d) - Loss of Large Areas of the Plant due to Explosions or Fires from a Beyond-Design Basis Event,” (not publically available)

— — — — —, DC/COL-ISG-017 “Ensuring Hazard-Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses,” March 24, 2010. (ADAMS Accession No. ML100570203.)

— — — — —, DC/COL-ISG-020 “Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment,” March 15, 2010. (ADAMS Accession No. ML100491233.)

Digital Instrumentation and Controls (DI&C)

— — — — —, DI&C-ISG-01, Revision 0, “Cyber Security,” December 31, 2007. (ADAMS Accession No. ML072980159.) Revised June 5, 2009. (ADAMS Accession No. ML091590268.)

— — — — —, DI&C-ISG-02, Revision 1, “Diversity and Defense-in-Depth (D3),” September 26, 2007. (ADAMS Accession No. ML072540118.)

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— — — — —, DI&C-ISG-03, Revision 0, “Risk-Informed Digital Instrumentation and Controls,” August 11, 2008. (ADAMS Accession No. ML080570048.)

— — — — —, DI&C-ISG-04, Revision 0, “Highly Integrated Control Rooms – Communications Issues (HICRc),” September 28, 2007. (ADAMS Accession No. ML072540138.) Revised March 6, 2009. (ADAMS Accession No. ML083310185.)

— — — — —, DI&C-ISG-05, Revision 0, “Highly Integrated Control Rooms – Human Factors,” September 28, 2007. (ADAMS Accession No. ML072540140.) Revised November 3, 2008. (ADAMS Accession No. ML082740440.)

Japan Lesson-Learned Project Directorate (JLD)

— — — — —, JLD-ISG-2012-01, Revision 0, “Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,” August 29, 2012. (ADAMS Accession No. ML12229A174)

— — — — —, JLD-ISG-2012-03, Revision 0, “Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation,” August 29, 2012. (ADAMS Accession No. ML12221A339),

Japan Lesson-Learned Project Directorate- Letter

— — — — —, Letter from David L. Skeen (NRC) (JLD) to Susan Perkins-Grew (NEI), “U.S. Nuclear Regulatory Commission Review of NEI 12-01 ‘Guidelines for Assessing Beyond Design basis Accident Response Staffing and Communication capabilities,’ Revision 0, Dated May 2012,” May 15, 2012. (ADAMS Accession No. ML12131A043.)

Office of New Reactors Regulation (NRO-REG)

— — — — —, NRO-REG-108, "Regulatory Audits," April 2, 2009. (ADAMS Accession No. ML081910260.)

— — — — —, Letter from David L. Skeen (NRC) (JLD) to Susan Perkins-Grew (NEI), “U.S. Nuclear Regulatory Commission Review of NEI 12-01 ‘Guidelines for Assessing Beyond Design basis Accident Response Staffing and Communication capabilities,’ Revision 0, Dated May 2012,” May 15, 2012. (ADAMS Accession No. ML12131A043.)

Office of Nuclear Reactor Regulation

— — — — —, Letter of Approval for Exemption, “Edwin I. Hatch Nuclear Power Station, Units 1 and 2, Re: Approval of Relief Request RR-27, Third -Year Interval Inservice Inspection Program (TAC Nos. MA6163 and MA6164),” March 20, 2000. (ADAMS Accession No. ML003693241.),

D-41

— — — — —, Letter of Approval of Change to Quality Assurance Program, “Palo Verde Nuclear Generating Station, Units 1, 2, and 3 – Approval of Change to Quality Assurance Program (Commercial-Grade Calibration Services) (TAC Nos. MA440, MC4403, and MA4404),” September 28, 2005. (ADAMS Accession No. ML052710224.)

— — — — —, Letter of Recognition of ACLASS Accreditation Services, “Reply to Your Letter Dated September 26, 2007, Seeking Agency Assistance in Accepting ACLASS Accreditation Services,” December 19, 2007. (ADAMS Accession No. ML073440472.)

— — — — —, Letter of Recognition of Laboratory Accreditation Bureau (L-A-B), “Reply to Your Letter Dated February 29, 2008, Seeking Assistance in Accepting Laboratory Accreditation Bureau,” April 22, 2008. (ADAMS Accession No. ML081140564.)

— — — — —, Letter of Recognition of International Accreditation Services, “Reply to Your Letter Dated March 3, 2008, Seeking Assistance in Accepting International Accreditation Services, INC,” May 14, 2008. (ADAMS Accession No. ML081330253.)

— — — — —, Safety Evaluation of the Proposed Change to the Quality Assurance Program, "Approval of Nuclear Management Company Quality Assurance Topical Report,” August 26, 2005. (ADAMS Accession No. ML052360625.)

NUREG and NUREG/CR Series Reports

— — — — —, NUREG–0016, Revision 1, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors,” January 1979.

— — — — —, NUREG–75/019, “Final Environmental Statement related to the proposed South Texas Project Units 1 and 2.” March 1975. (ADAMS Accession No. ML11174A118).

— — — — —, NUREG–75/067, “Technical Report -- Investigation and Evaluation of Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactor Plants," October 1975.

— — — — —, NUREG–0554, “NRC Collection of Abbreviations,” July 1998.

— — — — —, NUREG–0612, “Control of Heavy Loads at Nuclear Power Plants: Resolution of Generic Technical Activity A-36,” July 1980.

— — — — —, 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 (see also March 2002 Addenda).

— — — — —, NUREG–0696, “Functional Criteria for Emergency Response Facilities,” February 1981.

— — — — —, NUREG–0711, Revision 2, “Human Factors Engineering Program Review Model,” February 2004.

— — — — —, NUREG–0713, Volume 30, “Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2008: Forty-First Annual Report,” January 2010.

D-42

— — — — —, NUREG–0737, “Clarification of TMI Action Plan Requirements,” November 1980.

— — — — —, NUREG–0737, Supplement 1, “Clarification of TMI Action Plan Requirements: Requirements for Emergency Response Capability,” January 1983.

— — — — —, NUREG–0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” June 1987.

— — — — —, NUREG–0800, Revision 3, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (LWR Edition),” March 2007.

— — — — —, NUREG–0917, "Nuclear Regulatory Commission Staff Computer Programs for Use with Meteorological Data," July 1982.

— — — — —, NUREG–0933, “Resolution of Generic Safety Issues (Formerly entitled "A Prioritization of Generic Safety Issues"),” August 2008. (ADAMS Accession No. ML082410719.)

— — — — —, NUREG–1021, Revision 9, “Operator Licensing Examination Standards for Power Reactors,” July 2004. (ADAMS Accession No. ML042320438.)

— — — — —, NUREG–1061, Volume 1, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee," August 1984.

— — — — —, NUREG–1061, Volume 2, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee," April 1985.

— — — — —, NUREG–1061, Volume 3, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee," November 1984. (ADAMS Accession No. ML093170485.)

— — — — —, NUREG–1061, Volume 4, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee," December 1984.

— — — — —, NUREG–1061, Volume 5, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee," April 1985.

— — — — —, NUREG–1171, “Final Environmental Statement related to the operation of South Texas Project, Units 1 and 2,” August 1986.

— — — — —, NUREG–1220, “Training Review Criteria and Procedures,” January 1993.

— — — — —, NUREG–1275, Volume 11, “Operating Experience Feedback Report –Turbine-Generator Overspeed Protection Systems,” April 1995. (ADAMS Accession No.ML063560418).

— — — — —, NUREG–1431, Revision 3, “Standard Technical Specifications — Westinghouse Plants: Specifications,” June 2004. (ADAMS Accession No. ML041830612.)

— — — — —, NUREG–1433, Revision 3, “Standard Technical Specifications General Electric Plants, BWR/4,” July 2004. (ADAMS Accession No. ML041910194.)

— — — — —, NUREG–1434, Revision 3, “Standard Technical Specifications — General Electric Plants (BWR/6),” June 2004. (ADAMS Accession Nos. ML041910204, ML041910220.)

D-43

— — — — —, NUREG–1482, “Guidelines for Inservice Testing at Nuclear Power Plants,” April 1995.

— — — — —, NUREG–1503, “Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design,” July 1994. (ADAMS Accession No. ML080670592.)

— — — — —, NUREG–1520, Revision 1, “Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility,” May 2010. (ADAMS Accession No. ML101390110.)

— — — — —, NUREG–1556, Volume 7, Program-Specific Guidance about Academic, Research and Development, and Other Licenses of Limited Scope Including Gas Chromatographs and X-Ray Fluorescence Analyzers,” December 1999. (ADAMS Accession No. ML010370258.)

— — — — —, NUREG–1577, Revision 1, “Standard Review Plan on Power Reactor License Financial Qualifications and Decommissioning Funding Assurance,” February 1999.

— — — — —, NUREG–1736, “Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against Radiation,” October 2001. (ADAMS Accession No. ML013330179.)

— — — — —, NUREG–1801, Revision 2, “Generic Aging Lesson Learned (GALL) Report,” December 2010.

— — — — —, NUREG–1805, “Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program,” December 2004. (ADAMS Accession No. ML043290075.)

— — — — —, NUREG–1864, “A Pilot Probabilistic Risk Assessment of a Dry Cask Storage System at a Nuclear Power Plant,” March 2007. (ADAMS Accession No. ML071340012.)

— — — — —, NUREG–1948, “Final Safety Evaluation Report Related to the Aircraft Impact Amendment to the U.S. Advanced Boiling Water Reactor (ABWR) Design Certification,” dated June 2011, (ADAMS Accession No. ML11182A163.)

— — — — —, NUREG–2115, “Central and Eastern United States Seismic Source Characterization for Nuclear Facilities,” January 2012

— — — — —, NUREG/CR-0660, “Enhancement of Onsite Emergency Diesel Generator Reliability,” January 1979.

— — — — —, NUREG/CR–1486, “Hydrometeorological Report No. 53: Seasonal Variation of 10-Square-Mile Probable Maximum Estimates, United States East of the 105th Meridian,” April 1980.

— — — — —, NUREG/CR–2858, “PAVAN: An Atmospheric Dispersion Program for Evaluating Design Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations,” November 1982.

— — — — —, NUREG/CR–2919, “XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations,” September 1977.

D-44

— — — — —, NUREG/CR–3759, “Lightning Strike Density for the Contiguous United States from Thunderstorm Duration Records,” May 1984.

— — — — —, NUREG/CR–4461, Revision 2, “Tornado Climatology of the Contiguous United States,” February 2007. (ADAMS Accession No. ML070810400.)

— — — — —, NUREG/CR-5250, “Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains,” Volumes 1–8, January 1989, U.S. Nuclear Regulatory Commission, Washington, D.C., [Also reported as Bernreuter et al., (Bernreuter, D.L., Savy, J.B., Mensing, R.W., Chen, J.C., and Davis, B.C.), 1989]

— — — — —, NUREG/CR–6146 “Local Control Stations: Human Engineering Issues and Insights,” September 1994. (ADAMS Accession No. ML102520390.)

— — — — —, NUREG/CR–6190, Vol. 1, Protection against Malevalent use of Vehicles at Nuclear Power Plants, “December 2004. (ADAMS Accession No. ML072710046.)

— — — — —, NUREG/CR–6224, “Parametric Study of the Potential for BWR ECCS Strainer Blockage Due to LOCA Generated Debris,” October 1995.

— — — — —, NUREG/CR–6244, “Probabilistic Accident Consequence Uncertainty Analysis, Dispersion and Deposition Uncertainty Assessment,” January 1995. (ADAMS Accession Nos. ML010670124, ML010670167, ML010670239.)

— — — — —, NUREG/CR–6331, "Atmospheric Relative Concentrations in Building Wakes," May 1995.

— — — — —, NUREG/CR–6372, “Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts,” April 1997. (ADAMS Accession Nos: Vol 1-ML080090003, Vol 2-ML080090004.)

— — — — —, NUREG/CR–6728, “Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Hazard and Risk-Consistent Motions Spectra Guidelines,” October 2001. (Also referenced as McGuire et al. 2001.) (ADAMS Accession No. ML013100232.)

— — — — —, NUREG/CR–6769, “Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Development of Hazard- & Risk-Consistent Seismic Spectra for Two Sites,” April 2002. (ADAMS Accession Nos. ML021440275, ML021440282.)

— — — — —, NUREG/CR–6808, “Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance,” February 2003. (ADAMS Accession No. ML030920542.)

— — — — —, NUREG/CR–6890, Volume 1, “Reevaluation of Station Blackout Risk at Nuclear Power Plants Analysis of Loss of Offsite Power Events: 1986-2004,” December 2005. (ADAMS Accession No. ML060200477.)

— — — — —, NUREG/CR–6890, Volume 2, “Reevaluation of Station Blackout Risk at Nuclear Power Plants Analysis of Station Blackout Risk,” December 2005. (ADAMS Accession No. ML060200479.)

D-45

— — — — —, NUREG/CR–6890, Volume 3, “Reevaluation of Station Blackout Risk at Nuclear Power Plants Resolution of Comments,” December 2005. (ADAMS Accession No. ML060200510.)

— — — — —, NUREG/CR–7000, “Essential Elements of an Electric Cable Condition Monitoring Program,” January 2010. (ADAMS Accession No. ML100540050.)

Regulatory Guides (RGs)

— — — — —, RG 1.7, "Control of Combustible Gas Concentrations in Containment," March 1971.

— — — — —, RG 1.7, Revision 3, "Control of Combustible Gas Concentrations in Containment," March 2007. (ADAMS Accession No. ML.070290080.)

— — — — —, RG 1.8, “Qualification and Training of Personnel for Nuclear Power Plants,” March 1971.

— — — — —, RG 1.8, Revision 3, "Qualification and Training of Personnel for Nuclear Power Plants," May 2000. (ADAMS Accession No. ML003706932.)

— — — — —, RG 1.9, “Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants,” August 1971. (ADAMS Accession No. ML12305A251.)

— — — — —, RG 1.9, Revision 4, "Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants," March 2007. (ADAMS Accession No. ML070380553.)

— — — — —, RG 1.11, Revision 1, "Instrument Lines Penetrating Primary Reactor Containment,” March 2010. (ADAMS Accession No. ML100250396.)

— — — — —, RG 1.12, Revision 2, “Nuclear Power Plant Instrumentation for Earthquakes,” March 1997. (ADAMS Accession No. ML00373994.)

— — — — —, RG 1.13, Revision 2, “Spent Fuel Storage Facility Design Basis,” March 2007.

— — — — —, RG 1.16, “Reporting of Operating Information – Appendix A Technical Specifications (for Comment),” October, 1971.

— — — — —, RG 1.16, Revision 4, “Reporting of Operating Information - Appendix A, Technical Specifications,” August 1975. (Withdrawn, See 74 FR 40244, 08/11/2009.)

— — — — —, RG 1.20, “Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing,” December 1971.

— — — — —, RG 1.20, Revision 3, “Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing,” March 2007. (ADAMS Accession No. ML070260376.)

D-46

— — — — —, RG 1.21, Revision 2, “Measuring and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,” June 2009. (ADAMS Accession No. ML091170109.)

— — — — —, RG 1.22, "Periodic Testing of Protection System Actuation Functions (Safety Guide 22)," 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 Group 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, “Quality Assurance Program Criteria (Design and Construction),” June 1972.

— — — — —, 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 1.32, Revision 3, "Criteria for Power Systems for Nuclear Power Plants," March 2004. (ADAMS Accession No. ML040680488.)

— — — — —, RG 1.33, Revision 2, “Quality Assurance Program Requirements (Operation),” February 1978. (ADAMS Accession No. ML003739995.)

— — — — —, 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. ML070250057.)

— — — — —, RG 1.39, Revision 2, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants," September 1977.

D-47

— — — — —, 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, 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 for Welding of Low-Alloy Steel,” May 1973. (ADAMS Accession No. ML003740136.)

— — — — —, RG 1.52, Revision 2, “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.)

— — — — —, 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 0, "Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems," June 1973. (ADAMS Accession No. ML003740182.)

— — — — —, RG 1.54, “Service Level I, II, and III, Protective Coatings Applied to Nuclear Power Plants,” June 1973. (ADAMS Accession No. ML003740187.)

— — — — —, 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 1.55, "“Concrete Placement in Category I Structures”," (Withdrawn -- See 46 FR 37579, 07/21/1981)

— — — — —, RG 1.57, Revision 0, "Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components" June 1976. (ADAMS Accession No. ML003740195.)

— — — — —, RG 1.57, Revision 1, "Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components" March 2007

— — — — —, RG 1.60, Revision 1, "Design Response Spectra for Seismic Design of Nuclear Power Plants," December 1973. (ADAMS Accession No. ML003740207.)

— — — — —, RG 1.61, Revision 1, “Damping Values for Seismic Design of Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070260029.)

— — — — —, RG 1.63, Revision 3, "Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants," February 1987. (ADAMS Accession No. ML003740219.)

D-48

— — — — —, RG 1.65, Revision 1, “Materials and Inspections for Reactor Vessel Closure Studs,” April 2010. (ADAMS Accession No. ML092050716.)

— — — — —, RG 1.68, "Initial Test Programs for Water-Cooled Nuclear Power Plants,” November 1973.

— — — — —, RG 1.68, Revision 3, "Initial Test Programs for Water-Cooled Nuclear Power Plants,” March 2007. (ADAMS Accession No. ML070260039.)

— — — — —, RG 1.70, Revision 3, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)," November 1978. (ADAMS Accession No. ML011340122.)

— — — — —, RG 1.72, Revision 2, “Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin,” November 1978. (ADAMS Accession No. ML003740265.)

— — — — —, RG 1.75, Revision 3, “Physical Independence of Electric Systems,” February 2005. (ADAMS Accession No. ML043630448.)

— — — — —, 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,” June 1974. (ADAMS Accession No. ML003740298.)

— — — — —, RG 1.78, Revision 1, "Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release," December 2001. (ADAMS Accession No. ML013100014.)

— — — — —, 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 Materials Code Case Acceptability, ASME Section III,” August 2005. (ADAMS Accession No. ML052130562.)

— — — — —, RG 1.85, "Materials Code Case Acceptability -- ASME Section III, Division 1," (Withdrawn, See -- 69 FR 34202 06/18/2004).

— — — — —, RG 1.89, “Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants,” November 1974.

— — — — —, RG 1.91, “Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plants,” January 1975.

D-49

— — — — —, 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 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), (Withdrawn, See 75 FR 54921, 09/09/2010.)

— — — — —, RG 1.97, Revision 4, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants," June 2006. (ADAMS Accession No. ML061580448.)

— — — — —, RG 1.99, Revision 2, “Radiation Embrittlement of Reactor Vessel Materials,” May 1988. (ADAMS Accession No. ML031430205.)

— — — — —, RG 1.100, “Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants,” March 1976.

— — — — —, RG 1.100, Revision 2, “Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants,” June 1988. (ADAMS Accession No. ML003740293.)

— — — — —, RG 1.102, Revision 1, “Flood Protection for Nuclear Power Plants,” September 1976. (ADAMS Accession No. ML003740308.)

— — — — —, RG 1.105, Revision 3, "Setpoints for Safety-Related Instrumentation," December 1999. (ADAMS Accession No. ML993560062.)

— — — — —, RG 1.106, Revision 1, "Thermal Overload Protection for Electric Motors on Motor-Operated Valves," March 1977.

— — — — —, RG 1.108, "Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," August 1993. (Withdrawn – See 58 FR 41813, 08/5/1993)

— — — — —, RG 1.109, Revision 1, "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, “Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,” March 1976.

— — — — —, 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.)

D-50

— — — — —, 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 1.113, Revision 1, “Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,” April 1977.

— — — — —, RG 1.115, Revision 1, “Protection Against Low-Trajectory Turbine Missiles,” July 1977. (ADAMS Accession No. ML003739456.)

— — — — —, RG 1.117, Revision 3, "Tornado Design Classification, “ April 1978. (ADAMS Accession No. ML003739346.)

— — — — —, RG 1.118, Revision 2, "Periodic Testing of Electric Power and Protection Systems," June 1978. (ADAMS Accession No. ML12216A012.)

— — — — —, 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 1.128, Revision 2, "Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants," February 2007. (ADAMS Accession No. ML070080013.)

— — — — —, RG 1.132, Revision 2, "Site Investigations for Foundations of Nuclear Power Plants," October 2003. (ADAMS Accession Nos. ML032790474, ML032790495, ML032790499.)

— — — — —, RG 1.136, Revision 3, “Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments,” March 2007. (ADAMS Accession No. ML070310045.)

— — — — —, RG 1.138, Revision 2, "Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants," December 2003. (ADAMS Accession No. ML033510166.)

— — — — —, RG 1.140, Revision 2, “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. ML011710150.)

— — — — —, 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, 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, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments Revision 1, at Nuclear Power Plants," February 1983.

D-51

— — — — —, RG 1.147, Revision 15, “Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1,” October 2007. (ADAMS Accession No. ML072070419.)

— — — — —, 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 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations, Revision 1." February 2008. (Withdrawn, See 73 FR 7766, 02/11/2008.)

— — — — —, RG 1.151, “Instrument Sensing Lines,” July 1983. (ADAMS Accession No. ML003740003.)

— — — — —, RG 1.152, Revision 1, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” January 1996. (ADAMS Accession No. ML003740015.)

— — — — —, RG 1.152, Revision 2, “Criteria for Use of 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.)

— — — — —, RG 1.158, “Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants, “ February 1989. (ADAMS Accession No. ML003740047.)

— — — — —, RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” June 1993.

— — — — —, RG 1.160, Revision 2, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," March 1997. (ADAMS Accession No. ML003761662.)

— — — — —, RG 1.165, "Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion," April 2010. (Withdrawn, -- See 75 FR 22868, 04/30/2010.)

— — — — —, 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.)

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— — — — —, 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, “Development Software Life Cycle Process for Digital Computer Software Used in Safety Systems of Nuclear power Plants,” September 1997. (ADAMS Accession No. ML003740101.)

— — — — —, RG 1.174, Revision 2,“An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” May 2011. (ADAMS Accession No. ML100910006)

— — — — —, 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.)

— — — — —, RG 1.182, "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 1.192, “Operation and Maintenance Code Case Acceptability, ASME OM Code,” June 2003. (ADAMS Accession No. ML030730430.)

— — — — —, RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," June 2003. (ADAMS Accession No. ML031530505.)

— — — — —, RG 1.198, "Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites," November 2003. (ADAMS Accession No. ML033280143.)

— — — — —, RG 1.199, "Anchoring Components and Structural Supports in Concrete," October 2003. (ADAMS Accession No. ML033360660.)

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— — — — —, 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 1.204, "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 1.208, "A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion," March 2007. (ADAMS Accession No. ML070310619.)

— — — — —, RG 1.209, "Guideline for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear power Plants," March 2007.

— — — — —, RG 1.212, “Sizing of Large Lead-Acid Storage Batteries,” November 2008. (ADAMS Accession No. 082740047.)

— — — — —, RG 1.221, "Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants," October 2011. (ADAMS Accession No. ML110940300.)

— — — — —, RG 4.1, Revision 2, “Radiological Environmental Monitoring for Nuclear Power Plants,” June 2009. (ADAMS Accession No. ML091310141.)

— — — — —, RG 4.7, “General Site Suitability Criteria for Nuclear Power Stations,” September 1974.

— — — — —, 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,” (Withdrawn, See 74 FR 21017, 05/06/2009).

— — — — —, RG 4.15, Revision 2, “Quality Assurance for Radiological Monitoring Programs (Normal Operation)—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 5.7, “Entry/Exit Control for Protected Areas, Vital Areas, and Material Access Areas,” June 1973.

— — — — —, RG 5.7, Revision 1, “Entry/Exit Control for Protected Areas, Vital Areas, and Material Access Areas,” May 1980. (ADAMS Accession No. ML003739976.)

— — — — —, RG 5.12, “General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials,” November 1973.

— — — — —, RG 5.29, Revision 2, “Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants,” June 2013. (ADAMS Accession No. ML13051A421.)

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— — — — —, RG 5.44, “Perimeter Intrusion Alarm Systems,” January 1975.

— — — — —, RG 5.44, Revision 3, “Perimeter Intrusion Alarm Systems,” October 1997.

— — — — —, RG 5.62, “Reporting of Safeguards Events,” February 1981.

— — — — —, RG 5.62, Revision 1, “Reporting of Safeguards Events,” November 1987.

— — — — —, RG 5.65, “Vital Area Access Controls, Protection of Physical Security Equipment, and Key and Lock Controls,” September 1986. (ADAMS Accession No. ML003739336.)

— — — — —, RG 5.66, “Access Authorization Program for Nuclear Power Plants,” June 1991. (ADAMS Ac cession No. ML003739354.)

— — — — —, RG 5.66, “Access Authorization Programs For Nuclear Power Plants,” June 1991. (ADAMS Accession No. ML003739354.)

— — — — —, RG 5.68, “Protection Against Malevolent Use of Vehicles at Nuclear Power Plants,” August 1994.

— — — — —, RG 5.69, “Guidance for the Application of Radiological Sabotage Design Basis Threat in the Design, Development, and Implementation of a Physical Security Protection Program that Meets 10 CFR 73.55 Requirements,” June 2006. (Not publicly available)

— — — — —, RG 5.71, “Cyber Security Programs for Nuclear Facilities,” January 2010. (ADAMS Accession No. ML090340159.)

— — — — —, RG 5.74, “Managing the Safety/Security Interface,” March 2009. (ADAMS Accession No. ML091690036.)

— — — — —, RG 5.75, “Training and Qualification of Security Personnel at Nuclear Power Reactor Facilities,” June 2009. (ADAMS Accession No. ML091690037.)

— — — — —, RG 5.76, “Physical Protection Programs at Nuclear Power Reactors,” July 2009. (Not publicly available)

— — — — —, RG 5.77, “Insider Mitigation Program,” March 2009. (Not publicly available).

— — — — —, RG 8.2, “Guide for Administrative Practices in Radiation Monitoring,” February 1973. (ADAMS Accession No. ML003739444.)

— — — — —, RG 8.7, Revision 2, “Instructions for Recording and Reporting Occupational Radiation Exposure Data,” November 2005. (ADAMS Accession No. ML052970092.)

— — — — —, 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.)

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— — — — —, 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 8.27, “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, “Instruction Concerning Risks from Occupational Radiation Exposure,” February 1996. (ADAMS Accession No. ML003739438.)

— — — — —, 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. ML.003739548.)

— — — — —, 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.)

Regulatory Issue Summaries (RIS)

— — — — —, RIS 2000–03, "Resolution of Generic Safety Issue 158: Performance of Safety Related Power-Operated Valves Under Design Basis Conditions,” March 15, 2000.

— — — — —, RIS 2000–18, "Guidance on Managing Quality Assurance Records in Electronic Media,” October 23, 2000.

— — — — —, RIS 2005–04, "Guidance on the Protection of Unattended Openings that Intersect a Security Boundary or Area,” April 14, 2005.

Safety Evaluation /Safety Evaluation Reports

— — — — —, Safety Evaluation Report for Bulletin 96-03, “Boiling Water Reactor Owners Group Topical Report NEDO-32686-A, ’Utility Resolution Guidance for ECCS Suction Strainer Blockage,’” September 31, 1998. (ADAMS Accession No. ML092530449.)

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— — — — —, Safety Evaluation, "Final Safety Evaluation On Joint Owners' Group Program On Motor-Operated Valve Periodic Verification (TAC Nos. MC2346, MC2347, and MC2348)," September 25, 2006. (ADAMS Accession No. ML061280315).

— — — — —, Safety Evaluation “Final Safety Evaluation for the Boiling Water Reactor Owners’ Group (BWORG) Structural Integrity Associates Topical Report (TR) SIR-05-044, ‘Pressure Temperature Report Methodology For Boiling Water Reactors’ ,” (TAC No. MC9694), January 6, 2007. (ADAMS Accession No. ML070180483.)

— — — — —, Safety Evaluation Report for Topical Report WCAP-16406-P, Revision 1, “Evaluation of Downstream Sump Debris Effects in Support of GSI-191,” December 27, 2007. (ADAMS Accession No. ML073520295.)

— — — — —, Safety Evaluation for Topical Report, NEI 07-02, Revision 3, "Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52," January 24, 2008. (ADAMS Accession No. ML073650081.)

— — — — —, Safety Evaluation, "Final Supplement To Safety Evaluation For Joint Owners' Group Motor-Operated Valve Periodic Verification Program (TAC Nos. MD8920 and MD8921)," September 18, 2008. (ADAMS Accession No. ML082480638)

— — — — —, “NRC Staff Review of Nuclear Energy Institute 03–12, ’Template for Security Plan’, Training and Qualification, Safeguards Contingency Plan, [and Independent Spent Fuel Storage Installation Security Program], Revision 6," April 9, 2009. (ADAMS Accession No. ML090920528.)

— — — — —, Final Safety Evaluation for Technical Report NEI 06-14, Revision 7, "Quality Assurance Program Description," November 3, 2009. (ADAMS Accession No. ML092650695.)

— — — — —, Final Safety Evaluation for Technical Report NEI 06-14, Revision 9, “Quality Assurance Program Description,” July 13, 2010. (ADAMS Accession No. ML101800497.)

Staff Review Guidance

— — — — —, “NRC Staff Review Guidance Regarding Generic Letter 2004-2 Closure in the Area of Strainer Head Loss and Vortexing,” March 2008. (ADAMS Accession No. ML080230038.)

— — — — —, “NRC Staff Review Guidance Regarding Generic Letter 2004-02 Closure in the Area of Coatings Evaluation,” March 2008. (ADAMS Accession No. ML080230462.)

— — — — —, “NRC Staff Review Guidance Regarding Generic Letter 2004-02 Closure in the Area of Plant-Specific Chemical Effects Evaluations,” March 2008. (ADAMS Accession No. ML080380214.)

Technical Information Document (TID)

— — — — —, TID-7026, “Nuclear Reactors and Earthquakes,” Division of Reactor Development, U.S. Atomic Energy Commission, August 1963

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Other NRC Documents

NRC Memorandum from L. Kopp to T. Collins, “Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light Water Reactor Power Plants,” dated August 19, 1998. (ADAMS Accession No. ML11088A013.) (Not publicly available.)

Nuclear Regulatory Commission, 1986, “Safety Goals for the Operations of Nuclear Power Plants; Policy Statement,” (Republication in 51 FR 30028), Published August 21, 1986.

Westinghouse Electric Corporation

Westinghouse Commercial Atomic Power (WCAP) Reports:

— — — — —, WCAP-7391, “Pressurized Water and Steam Jet Effects on Concrete,” 1969.

— — — — —, WCAP-16078-NP-A, “Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96-Optima 2 Fuel,” November 30, 2004. (ADAMS Accession No. ML050390435.)

— — — — —, WCAP-16097-P-A, Revision 0, “Common Qualified Platform Topical Report,” May 2003. (ADAMS Accession No. ML031820484.)

— — — — —, WCAP-16406-P, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191," December 2007. (ADAMS Accession No. ML073520767.)

— — — — —, WCAP-16406-P, Revision 1, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191," May 3, 2006. (ADAMS Accession No. ML061580182.)

— — — — —, WCAP-16530-NP, Revision 0, “Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI-191,” February 28, 2006. (ADAMS Accession No. ML060890509.)

— — — — —, WCAP-16530-NP-A, “Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI-191,” March 31, 2008. (ADAMS Accession No. ML081150383.)

— — — — —, WCAP-17058-NP, Revision 0, “Implementation of ABWR Methodology Using GOTHIC for STP 3 and 4 Containment Design Analyses,” June 2009. (ADAMS Accession No. ML092740183.)

— — — — —, WCAP-17119-P, Revision 0, “Methodology for South Texas Project Units 3 and 4 - ABWR Technical Specification Setpoints,” October 2009. (ADAMS Accession Nos. ML093130113, ML093130332 [Non-proprietary version].)

— — — — —, WCAP-17119-P, Revision 1, “Methodology for South Texas Project Units 3 and 4 - ABWR Technical Specification Setpoints,” March 2010. (ADAMS Accession No. ML100900137.)

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— — — — —, WCAP-17119-P, Revision 2, “Methodology for South Texas Project Units 3 and 4 - ABWR Technical Specification Setpoints,” July 31, 2010. (ADAMS Accession No. ML102140490 [Public Version].) (Located in the response to RAI 07.01-16 dated July 29, 2010 [ML102140489].)

— — — — —, WCAP-17137-P, Revision 0, “Westinghouse Stability Methodology for the ABWR.” October 2010. (ADAMS Accession No. ML103080623.)

— — — — —, WCAP-17256-P, Revision 6, “STP Unit 3 ABWR Prototype Reactor Internals Flow-Induced Vibration Assessment Program,” dated April 2013. (ADAMS Accession No. ML13256A317.)

— — — — —, WCAP-17257-P, Revision 5, “STP Unit 4 Reactor Internals Flow-Induced Vibration Assessment Program,” dated April 2013. (ADAMS Accession No. ML13259A136.)

— — — — —, WCAP-17369-P, Revision 1, “ABWR Dryer Operating Experience for STP Units 3 and 4,” dated February 2011 (ML110490192).

— — — — —, WCAP-17370-P, Revision 7, “South Texas Project Unit 3 Comprehensive Vibration Assessment Program–Measurement, Test, and Inspection Plan,” dated April 2013. (ADAMS Accession No. ML13256A355.)

— — — — —, WCAP-17371-P, Revision 7, “South Texas Project Units 3 and 4 Reactor Internals Non-Dryer Component Flow-Induced Vibration Assessment,” dated May 2012 (ADAMS Accession No. ML13256A174.)

— — — — —, WCAP-17385-P, Revision 6, “STP Unit 3 Steam Dryer Flow-Induced Vibration Assessment,” dated April 2013. (ADAMS Accession No. ML13256A205 and ML13256A206.)

Westinghouse Electric Company (WEC) and other Reports:

— — — — —, CENPD-300-NP-A (Nonproprietary), "Reference Safety Report for Boiling Water Reactor Reload Fuel," July 1996. (ADAMS Accession No. ML110260388.)

— — — — —, WEC STP-2010-0040 NP, “Revision to STP 3/4 Analysis of Downstream Debris Effects on Fuel, Response to RAI 04.04-4” September 2010. (ADAMS Accession No. ML102870255.)

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Resio, D., “Modern Methods for Coastal Storm Surge Estimation,” presentation at NRC Hydrology Research Workshop in Rockville, MD, U.S. Army Corps of Engineers, Coastal and Hydraulics Laboratory, Engineering Research and Development Center, Vicksburg, MS, November 17–18, 2009. (ADAMS Accession No. ML102990221).

Reynolds, K.W, “2006 Radioactive Effluent Release Report,” South Texas Project Electric Generating Station, Bay City, Texas, 2007.

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Sanders, T.L., et al., "A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements," SAND 90-2406, Sandia National Laboratories, November 1992.

SC Solutions, “Confirmatory Seismic SSI Analysis of UHS and RSW Pump House for South Texas Project (STP) Units 3 and 4,” Prepared for the U.S. Nuclear Regulatory Commission by dated June 1, 2010.

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Schreiner, L.C., and J.T Riedel, “Probable Maximum Precipitation Estimates, United States East of the 105th Meridian,” Hydrometeorological Report No. 51, Hydrometeorological Branch, Office of Hydrology, National Oceanic and Atmospheric Administration National Weather Service, United States Department of Commerce, Washington, DC, 1978.

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