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1、Code Requirements for Nuclear Safety Related Concrete Structures (AC1 349-97) and Commentary-AC1 349R-97 Reported by AC1 Committee 349 american concrete institute P.O. BOX 9094 FARMINGTON HILLS, MICHIGAN 48333 Obb2949 0538055 403 m First printing, February 1998 Code Requirements for Nuclear Safety-R
2、elated Concrete Structures (AC1 349-97) and Commentary-ACI349R-97 Most AC1 Standards and committee reports reports in the general areas of materials and are gathered together in the annually revised properties of concrete, construction practices AC1 Manual of Concrete Practice. The several and inspe
3、ction, pavements and slabs, struc- volumes are arranged to group related material tural design and analysis, structural specifica- together and may be purchased individually or tions, and special products and processes. in setS.The AC1 Manual of Concrete Practice is also available on CD-ROM. A compl
4、ete catalog of all AC1 publications is AC1 Committees prepare standards and available without charge. American Concrete Institute P.O. Box 9094 Farmington Hills, MI 48333-9094 AC1 Certification Programs Enhancement of AC1 Documents The final quality of a concrete structure depends on The technical c
5、ommittees responsible for AC1 committee qualified people to construct it. AC1 certification pro- reports and standards strive to avoid ambiguities, omis- grams identify craftsmen, technicians, and inspectors sions, and errors in these documents. In spite of these who have demonstrated their qualific
6、ations. The follow- efforts, the users of AC1 documents occasionally find ing programs are administered by AC1 to fulfill the grow- information or requirements that may be subject to more ing demand in the industry for certified workers: than one interpretation or may be incomplete or incor- Concret
7、e Flatwork Finisher Concrete Flatwork Technician Concrete Field Testing Technician-Grade I Concrete Strength Testing Technician Concrete Laboratory Testing Technician-Grade I Concrete Laboratory Testing Technician-Grade II Concrete Construction Inspector-ln-Training Concrete Construction Inspector C
8、oncrete Transportation Construction Inspector-ln- Training Concrete Transportation Construction Inspector This document may already contain reference to these AC1 certification programs, which can be incorporated into project specifications or quality control procedures. If not, suggested guide spec
9、ifications are available on request from the AC1 Certification Department. rect. To assist in the effort for accuracy and clarity, the Technical Activities Committee solicits the help of indi- viduals using AC1 reports and standards in identifying and eliminating problems that may be associated with
10、 their use. Users who have suggestions for the improvement of AC1 documents are requested to contact the AC1 Engi- neering Department in writing, with the following infor- mation: 1. Title and number of the document containing the problem and specific section in the document; 2. Concise description
11、of the problem; 3. If possible, suggested revisions for mitigating the problem. The Institutes Engineering Staff will review and take appropriate action on all comments and suggestions received. Members as well as nonmembers of the Insti- tute are encouraged to assist in enhancing the accuracy and u
12、sefulness of AC1 documents. -,-,- AC1 349R-97 Commentary on Code Requirements for Nuclear Safety Related Concrete Structures (AC1 349-97) Reported by AC1 Committee 349 Charles A. Zalesiak Chairman Hans G. Ashar Ranjit Bandyopadhyay Ronald A. Cook Jack M. Daly Fadi M. Diya Arobindo Dutt Branko Galuni
13、c Dwaine A. Gadfrey Herman L. Graves III Gunnar A. Harstead Christopher Heim Charles J. Hookham John C. Hughes Richard E. Klingner Sandra L. Lee Timothy J. Lynch Frederick L. Moreadith Dragos A. Nuta Richard S. O r r Robert B. Pan Julius V. Rotzt John P. Russ Robert W. Talmadge Chen P. Tan Richard E
14、. Toland Donald T. Ward Albert Y. c. Wong The content of this commentary is the responsibility of the committee which prepared it. Institute authority attaches only to standards adopted as provided in the Bylaws. This commentary discusses some of the considerations of AC1 Committee 349 in developing
15、 “Code Requirements for Nuclear safety related Concrete Structures (AC1 349-97).“ This information i s pmvided in the commentary because the Code is written as a legal document and cannot therefore present backgmund details or suggestions for carrying out its require- ments. AC1 349-97 is based on “
16、Building Code Requirements for Reinforced Con- cwte (AC1 318-89)(Revised 1992); except for Chapter 12, which is based on AC1 318-95 This commentary provides discussion of those require- ments i n AC1 349 that differ from those of AC 318. Keywords: admixtures; aggregates; anchorage (structural); beam
17、-column frame; beams (supports); building codes; cements; cold weather construc- AC1 Committee Reports, Guides, Standard Practices, and Commen- taries m intended for guidance in planning, designing, executing, and inspecting construction. This document is intended for the use of individuals who are
18、competent to evaluate the signifi- cance and limitations of its content and recommendations and who will accept responsibility for the application of the material it contains. The American Concrete Institute disclaims any and all responsibility for the stated principles. The Institute shall not be l
19、ia- ble for any loss or damage arising therefrom. Reference to this document shall not be made in contract docu- ments. If items found in this document are desired by the Archi- tect/Engineer to be a part of the contract documents, they shall be restated in mandatory language for incorporation by th
20、e Architecd Engineer. tion; columns (supports); combined stress; composite construction (con- crete and steel); composite construction (concrete to concrete); compressive strength; concrete construction; concretes; concrete slabs; construction joints; continuity (structural): cover; curing; deep bea
21、ms; deflection; earthquake resistant structures; edge beams; embedded service ducts; flexural strength; floors; folded plates; footings; formwork (con- struction); frames; hot weather construction; inspection; joists; loads (forces); load tests (structural); mixing; mix proportioning; modulus of ela
22、sticity; moments; nuclear power plants; nuclear rextor containment; pipe columns; pipes (tubes); placing; precast concrete; prestressed con- crete; prestressing steels: quality control; reinforced concrete; reinforcing steels; roofs; safety; serviceability; shear strength; shearwalls; shells (struc-
23、 tural forms); spans; specifications; splicing; stability standards; strength; stresses; structural analysis; structural design; T-beams; temperature; ten- sile strength; torsion; walls; water: welded wire fabric. CONTENTS Introduction, p. 349R-3 Chapter l-General Requirements, p. 349R-3 1.2-Drawing
24、s, specifications, and calculations 1.3-Inspection and record keeping l. 1 “scope AC1 349R-97 supersedes AC1 349R-W and became effective April 11.1997. Copyright O 1998, American Concrete Institute. All rights reserved including rights of reproduction and use in any form or by any means, including t
25、he making of copies by any photo process. or by electronic o r mechanical device, printed, written, or oral, or recording for sound o r visual reproduc- tion or for use in any knowledge or retrieval system or device, unless permission in writing is obtained horn the copyright proprietors. 349R-1 1 .
26、 referred to as “the Code,” provides minimum requirements for reinforced concrete design or construction in applications where protection against potential radioactive releases is a concern. The scope of the Code has historically addressed new construction; however, this scope has recently been ex-
27、tended to providing recommendations for the analysis, de- sign, construction, testing, and evaluation of new and existing concrete nuclear structures. Wile the requirements of this Code pertain primarily to new concrete structures, corresponding recommendations for the evaluation of exist- ing concr
28、ete nuclear structures are provided in AC1 349.3R- 96.3 The Owner is to identify nuclear safety related structures and establish which of them are covered by “Code for Con- crete Reactor Vessels and Containments (AC1 359)” and its latest revisions in lieu of this Code. Some special structures involv
29、e unique problems which are not covered by the Code. However, many Code provi- sions, such as the concrete quality and design principles, are applicable for these special structures. R1 .2“Drawings, specifications, and calculations Guidelines for the preparation and retention of design doc- uments a
30、re covered by ANSUASME NQA-l. Any docu- mentation that uniquely reflects the as-built condition of the concrete nuclear structure should be considered for reten- tion, as a permanent record for the life of the structure. Drawings and specifications should be prepared under the direction of a license
31、d (or registered) engineer competent in the field of design of concrete structures, who is required to sign these documents signifying his approval. This Code re- quires that the Owner be responsible for drawings and calcu- lations, but does not preclude him from assigning the function of detailed i
32、mplementation to others. R1.3-Inspection and record keeping This Code requires that the Owner be responsible for in- spection but does not explicitly preclude him from assigning the function of detailed implementation to others. Inspection personnel should be qualified by the Owner. ANSYASME NQA-1 l
33、. or AC1 359 Appendix W may be used to qualify inspectors. Requirements for the retention of inspection records should follow ANSYASME NQA-l. R1 .4-Approval of special systems of design or construction New methods of design, new materials, and new uses of materials must undergo a period of developme
34、nt before be- ing specifically covered in a code. Hence, good systems or components might be exchided from use by implication if means were not available to obtain acceptance. This section permits proponents to submit data substantiating the adequa- cy of their system or component to the Regulatory
35、Authority, which presently is the United States Nuclear Regulatory Commission (USNRC) in the United States. R1.5-Quality assurance program Title 10 CFR 50, Appendix B, requires that the Owner have a quality assurance program approved by the Regulato- ry Authority and states that the Owner is respons
36、ible for the establishment and execution of programs developed by his engineers, construction contractors, and suppliers. More de- tailed requirements for development and implementation of a quality assurance program are contained in ANSYASME NQA-l. and ANSYASME NQA-2.lS2 References 1.1. American Na
37、tional Standards Institute (ANSI) and American Soci- ety of Mechanical Engineers (ASME), “Quality Assurance Requirements for Nuclear Facilities,” NQA-I, 1989. 1.2 ANWASME, “Quality Assurance Requirements for Nuclear Facil- ity Applications: NQA-2, 1989. 1.3 AC1 Committee 349, “Evaluation of Existing
38、 Nuclear safety related Concrete Structures” (ACI 349.38-96). Chapter 2-Definitions Definitions in this Code are the same as those in the Build- ing Code (AC1 318) except for a few which are added or modified to meet the structures and materials concerned in this Code. The deftions that differ from
39、or are not listed in ACI 3 18 a r e : Anchorage Cementitious material Creep Embedment Engineer Evaluation Effective prestress Load, dead Load, live Load, sustained Massive concrete Operating basis earthquake (OBE) Operating basis wind Owner Regulatory Authority Safe shutdown earthquake (SSE) Shrinka
40、ge Stress relaxation Tendon Unbonded tendons Wall In the definition of the term “Engineer,” the phrase “other documents” is used. Other documents” include quality as- surance plans, design guidelines, and other similar docu- ments for which the Engineer is responsible. Chapter 3”aterials The comment
41、ary on AC1 3 18 is applicable to this chapter except as described below: R3.1-Tests of materials R 3 . 1 3 The Owner shall designate the period of retention for all records of tests of materials and of concrete used in concrete nuclear structures. Typically, any documentation that uniquely describes
42、 tests of materials and of concrete used in concrete nuclear structures should be retained for the life of the plant. R3.2-Cements R 3 . 2 3 The requirement for receipt of certified 7-day mill test materials reports in advance of use is imposed to inform the materials engineer of changes in cement s
43、trength to pro- vide guidance in altering concrete mixes when significant changes in strength occur. Such alterations can both achieve increased assurance against low strengths and reduce the standard deviation of strengths, providing a means of opti- mizing the cement contents and reducing the heat
44、 of hydra- tion effects in these relatively massive structures. R3.3-Aggregates R 3 3 . 1 The reference to lightweight aggregates has been de- leted. The minimum thickness of most concrete members in nuclear plant construction is based on shielding requirements which are dependent on the density of
45、the concrete. Light- weight aggregates would require larger minimum thicknesses since the sizing of columns, spacing of walls, etc., is usually controlled by live load, seismic, or shielding requirements and not flmr dead loads. There appears to be no advantage in us- ing lightweight aggregates in n
46、uclear structures. R 3 3 . 3 Minimum testing requirements are specified to as- sure aggregate quality. R 3 3 3 . 3 Anytime there is a basic change in aggregate source, the aggregate should be tested to determine suitabil- ity for use. Retests for soundness (ASTM C 88), abrasion re- sistance (ASTM C
47、131), and potential reactivity (ASTM C 289) are required since they are not included in the routine testing of aggregates. R3.4-Water paragraph CC-2223 of AC1 359-92. Guidance for water quality may be obtained from Sub- R3.5-Metal reinforcement R 3 5 3 Zinc used i n t h e galvanizing process may neg
48、atively r e a c t with alkaline materials commonly found in conate. In addition, potential galvanic comion w i t h other embedded metals, as well as hydrogen generation and potential for hydro- gen embrittlement suggest t h a t such coatings may be detrimen- t a l . Research conducted by Sergi3*2 co
49、ncluded t h a t zinc coatings provide little value in providing long-term protection of reinfoming steel, and cautionary statements in AC1 Report u)1.2R-923*3 support this position. These industry concerns have p m p t e d the AU Committee 349 t o phibit use of zinc coatings on reinforcing steel in nuclear safety related structum until adequate data justifying its use can be reviewed. R 3 5 3 . 1 and R 3 5 . 4 . 1 Use of rail and axle steel rein- forcing bars is excluded because of inadequate traceability. ASTM A 615 covers defo