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It covers concrete structures both inside and outside the containment system. The code may be referenced and applied by agreement between the Owner and the Regulatory Authority. 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Zalesiak Chairman  \nHans G. Ashar Ranjit Bandyopadhyay Ronald A. Cook Branko Galunic  \nHerman L. Graves III  \nGunnar A. Harstead Christopher Heinz Charles J. Hookham Ronald J. Janowiak  \nJagadish R. Joshi  \nRichard E. Klingner Dragos A. Nuta Richard S. Orr Barendra K. Talukdar Donald T. Ward  \nAlbert Y. C. Wong  \nThis standard covers the proper design and construction of concrete structures which form part of a nuclear power plant and which have nuclear safety related functions, but does not cover concrete reactor vessels and concrete containment structures (as defined by ACI-ASME Committee 359) .  \nThe structures covered by the Code include concrete structures inside and outside the containment system.  \nThis Code may be referenced and applied subject to agreement between the Owner and the Regulatory Authority.  \nThe format of this Code is based on the “Building Code Requirement for Structural Concrete (ACI 318-95)” and incorporates recent revisions of that standard, except for Chapter 12, which is based on ACI 318-99.  \nKeywords: admixtures; aggregates; anchorage (structural); beam-column frame; beams (supports); building codes; cements; cold weather construction; columns (supports); combined stress; composite construction (concrete and steel); composite construction (concrete to concrete); compressive strength; concrete construction; concretes; concrete slabs; construction joints; continuity (structural); cover;  \ncracking (fracturing); creep properties; curing; deep beams; deflection; drawings (drafting); earthquake resistant structures; edge beams; embedded service ducts; flexural strength; floors; folded plates; footings; formwork (construction); frames; hot weather construction; inspection; joists; loads (forces); load tests (structural); mixing; mix proportioning; modules of elasticity; moments; nuclear power plants; nuclear reactor containments; nuclear reactors; nuclear reactor safety; pipe columns; pipes (tubes); placing; precast concrete; prestressed concrete; prestressing steels; quality control; reinforced concrete; reinforcing steels; roofs; safety; serviceability; shear strength; shearwalls; shells (structural forms); spans; specifications; splicing; strength; strength analysis; structural analysis; structural design; T-beams; temperature; torsion; walls; water; welded wire fabric.  \nACI 349-01 supersedes ACI 349-97 and became effective February 1, 2001. Copyright © 2001, American Concrete Institute.  \nAll rights reserved including rights of reproduction and use in any form or by any means, including the making of copies by any photo process, or by electronic or mechanical device, printed, written, or oral, or recording for sound or visual reproduction or for use in any knowledge or retrieval system or device, unless permission in writing is obtained from the copyright proprietors.  \n349-2 ACI STANDARD  \nCONTENTS  \nPART 1—GENERAL  \nChapter 1—General Requirements . . . . . . . p. 349-5  \n1.1—Scope  \n1.2—Drawings, specifications, and calculations  \n1.3—Inspection and record keeping  \n1.4—Approval of special systems of design or construction  \n1.5—Quality assurance program  \nChapter 2—Definitions ................. p. 349-6  \nPART 2—STANDARDS FOR TESTS AND  \nMATERIALS  \nChapter 3—Materials................... p. 349-9  \n3.0—Notation  \n3. 1—Tests of materials  \n3.2—Cements  \n3.3—Aggregates  \n3.4—Water  \n3.5—Steel reinforcement  \n3.6—Admixtures  \n3.7—Storage and identification of materials  \n3. 8—Standards cited in this Code  \nPART 3—CONSTRUCTION REQUIREMENTS  \nChapter 4—Durability Requirements. . . . . p. 349-13  \n4.0—Notation  \n4. 1—Water-cementitious materials ratio  \n4.2—Freezing and thawing exposures  \n4.3—Sulfate exposures  \n4.4—Corrosion protection of reinforcement  \nChapter 5—Concrete Quality, Mixing,  \nand Placing . . . . . . . . . . . . . . . . . . . . . . . . p. 349-14  \n5.","cbCaitmaNFPE5SHF","https://ap.wps.com/l/cbCaitmaNFPE5SHF","pdf",3153225,134,"English","# PART 1—GENERAL\n## Chapter 1—General Requirements\n## Chapter 2—Definitions\n# PART 2—STANDARDS FOR TESTS AND MATERIALS\n## Chapter 3—Materials\n# PART 3—CONSTRUCTION REQUIREMENTS\n## Chapter 4—Durability Requirements\n## Chapter 5—Concrete Quality, Mixing, and Placing\n## Chapter 6—Formwork, Embedded Pipes, and Construction Joints\n## Chapter 7—Details of Reinforcement\n# PART 4—GENERAL REQUIREMENTS\n## Chapter 8—Analysis and Design: General Considerations\n## Chapter 9—Strength and Serviceability Requirements\n## Chapter 10—Flexure and Axial Loads","[{\"question\":\"What structures does ACI 349-01 cover in a nuclear power plant?\",\"answer\":\"It covers concrete structures forming part of a nuclear power plant that have nuclear safety-related functions, including concrete structures inside and outside the containment system.\"},{\"question\":\"What does ACI 349-01 exclude?\",\"answer\":\"It does not cover concrete reactor vessels and concrete containment structures as defined by ACI-ASME Committee 359.\"},{\"question\":\"Under what conditions can this code be referenced and applied?\",\"answer\":\"It may be referenced and applied subject to agreement between the Owner and the Regulatory Authority.\"}]","ACI 349-01-Code Requirements for Nuclear Safety Related Concrete Structures - Code | PDF",338]