1、Report on Evaluation and Repair of Existing Nuclear Safety-Related Concrete Structures Reported by ACI Committee 349 ACI 349.3R-18First Printing January 2018 ISBN: 978-1-64195-000-8 Report on Evaluation and Repair of Existing Nuclear Safety-Related Concrete Structures Copyright by the American Concr
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11、e reports are gathered together in the annually revised the ACI Collection of Concrete Codes, Specifications, and Practices. American Concrete Institute 38800 Country Club Drive Farmington Hills, MI 48331 Phone: +1.248.848.3700 Fax: +1.248.848.3701 www.concrete.orgThis report provides recommendation
12、s for the evaluation of existing nuclear safety-related concrete structures. The purpose of this report is to provide the owner, owner s engineering staff, consul- tants, and others with an appropriate procedure and background for examining concrete structural performance and taking appro- priate ac
13、tions based on observed conditions. Methods of examina- tion, including visual inspection and testing techniques and their recommended applications, are cited. Guidance related to accep- tance criteria for various forms of degradation and methods for repair are provided. Keywords: corrosion; crackin
14、g; degradation; inspection; load test; nonde- structive testing; nuclear plant; rehabilitation; reinforcement; repair; safety; serviceability; structural design; structural evaluation. CONTENTS CHAPTER 1INTRODUCTION AND SCOPE, p. 2 1.1Introduction, p. 2 1.2Scope, p. 2 CHAPTER 2DEFINITIONS, p. 3 CHAP
15、TER 3GENERAL METHODOLOGY AND EVALUATION PROCEDURE, p. 4 3.1General methodology, p. 4 3.2Scope, p. 4 3.3Selective evaluation, p. 4 3.4Periodic evaluation, p. 5 3.5Evaluation procedure document, p. 6 3.6Evaluation techniques, p. 6 CHAPTER 4DEGRADATION MECHANISMS, p. 10 4.1General, p. 10 Adeola K. Aded
16、iran * , Chair Lisa M. Anderson * , Secretary Branko Galunic, Vice Chair Partha S. Ghosal * , Vice Chair John F. Silva, Vice Chair ACI 349.3R-18 Report on Evaluation and Repair of Existing Nuclear Safety-Related Concrete Structures Reported by ACI Committee 349 Omesh B. Abhat Monzer M. Allam * Taha
17、D. Al-Shawaf Carlos Cantarero-Leal Mukti L. Das Rolf Eligehausen Farhad Farzam Werner A. F. Fuchs Stewart C. Gallocher Herman L. Graves III * Orhan Gurbuz James A. Hammell Joseph K. Harrold Charles J. Hookham * Thomas T. C. Hsu Ronald J. Janowiak Scott A. Jensen Ola Jovall Bernd R. Laskewitz Nam-Ho
18、Lee W. Calvin McCall Javeed Munshi * Dan J. Naus Nebojsa Orbovic Madhumita Sircar * Bozidar Stojadinovic Amit H. Varma Andrew S. Whittaker Charles A. Zalesiak * Consulting Members Hansraj G. Ashar Peter J. Carrato Ronald A. Cook Gunnar A. Harstead Richard S. Orr Barendra K. Talukdar Albert Y . C. Wo
19、ng The committee thanks M. DAmbrosia * , C. Larosche * , M. Sherman * , and D. Scott for their contributions to this report. * Members of the subcommittee authoring this report. ACI Committee Reports, Guides, and Commentaries are intended for guidance in planning, designing, executing, and inspectin
20、g construction. This document is intended for the use of individuals who are competent to evaluate the significance 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
21、 all responsibility for the stated principles. The Institute shall not be liable for any loss or damage arising therefrom. Reference to this document shall not be made in contract documents. If items found in this document are desired by the Architect/Engineer to be a part of the contract documents,
22、 they shall be restated in mandatory language for incorporation by the Architect/Engineer. ACI 349.3R-18 supersedes ACI 349.3R-02 and was adopted and published February 2018. Copyright 2018, American Concrete Institute. All rights reserved including rights of reproduction and use in any form or by a
23、ny 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 propri
24、etors. 14.2Concrete degradation, p. 10 4.3Steel reinforcement and structural steel degradation, p. 15 4.4Prestressing steel degradation, p. 16 CHAPTER 5EVALUATION CRITERIA, p. 17 5.1Acceptance without further evaluation, p. 17 5.2Acceptance after review, p. 19 5.3Acceptance after enhanced evaluation
25、, p. 20 CHAPTER 6EVALUATION FREQUENCY, p. 20 CHAPTER 7QUALIFICATIONS OF EVALUATION TEAM, p. 21 CHAPTER 8REPAIR, p. 22 8.1General, p. 22 8.2Design basis and compliance, p. 22 8.3Repair considerations, p. 23 8.4Design of structural repairs, p. 24 8.5Durability, p. 25 8.6Construction, p. 27 8.7Quality
26、assurance, p. 27 CHAPTER 9REFERENCES, p. 28 Authored documents, p. 29 CHAPTER 1INTRODUCTION AND SCOPE 1.1Introduction Recent structural challenges encountered from events such as the observed alkali-aggregate reactions (AARs)/cracking at Seabrook (U.S. Nuclear Regulatory Commission (U.S. NRC) 2011),
27、 cracking and chemical attack at Zion (Gregor and Hookham 1993), and the publicized reports of concrete degradation in domestic plants (Gregor and Hookham 1993; Electric Power Research Institute (EPRI) 1990; Ashar and Bagchi 1995) have highlighted the need for guidance on acceptable structural evalu
28、ation and repair methods from a code and regulatory viewpoint. These recommendations can be used to evaluate the condition of concrete structures at any point during their service life and following any imposed damage, aging, or loading event. For post-earth- quake evaluations, supplemental guidelin
29、es and evaluation criteria, such as those discussed in EPRI TR 3002005284 (EPRI 2015a) and International Atomic Energy Agency (IAEA) Safety Reports Series No. 66 (IAEA 2011), should also be considered. The evaluation process and techniques used in this report have been revised and updated to cover p
30、ossible scenarios that could be encountered in nuclear safety-related concrete structures, with insights from the state-of-the-practice in the construction industry included as well. This report provides the user with relevant and more up-to-date information on evaluation and repair of nuclear struc
31、tures with a focus on those that have been deemed nuclear safety-related. Note that this report provides recommendations for performing an eval- uation. The responsible engineer and evaluation team should use engineering judgment in applying these recommenda- tions. Visual inspection is the recommen
32、ded primary evalu- ation tool for identification of degradation. A more exhaus - tive evaluation, using nondestructive examination (NDE) and invasive tests, could be warranted by observations subject to the responsible engineers evaluation perspective. 1.2Scope Chapters 1 and 3 provide the introduct
33、ory material and general methodology used, respectively. Chapters 4 through 7 and Chapter 9 include new information, expanded coverage, and relevant references for continued research. Chapter 8 provides guidance on the need for repair; use of proven methods, including those recently implemented in s
34、pecific nuclear plants; and relevant industry references (ACI/ICRI 2013). To ensure that evaluations and any follow- up repairs are properly implemented, it is recommended that the responsible engineer remains in charge throughout the completion of all the tasks up to documentation, including evalua
35、tion reports and repair programs as defined herein. This report supplements the ACI 349 code by presenting a framework for conducting an evaluation and developing any associated repair procedures for nuclear safety-related concrete structures. Before initiating this report, the scope of ACI 349 was
36、self-limited to the design and inspection of newly constructed concrete nuclear structures. As the nuclear power plants in the United States grow older and become susceptible to the adverse effects of aging, their periodic inspection, proper evaluation, and repair have become more important issues.
37、Recent U.S. NRC regu- lations 10 CFR50.65 and 10 CFR54 (U.S. NRC 2015a,b) require licensees to inspect and evaluate the condition of concrete nuclear structures that may have experienced age- related degradation. Also, following the accident at the Fukushima Daiichi nuclear power plant resulting fro
38、m the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami in Japan, the NRC established the Near Term Task Force (NTTF) to conduct a review of the NRC processes and regulations, and provide recommendations to the NRC regu- latory process to enhance reactor safety. Subsequent to the NTTF f
39、indings, the NRC issued a letter under 10 CFR50.54 (U.S. NRC 2015a) on March 12, 2012, requiring owners of every U.S. nuclear power plant to perform seismic (Sezen et al. 2011) walkdowns to identify and address degraded, nonconforming, or unanalyzed conditions, and to verify the current plant config
40、uration with respect to the current design basis and state of knowledge gained since such was prepared on seismic and flood hazards. The evaluation scope herein was tailored to support structural evaluations required by periodic regulatory requests and in support of hazard anal- yses. Documents incl
41、uding EPRI TR 3002005284 (EPRI 2015a) and NUREG/CR-5042 Supplement 2 (U.S. NRC 1989) should also be considered. Effective maintenance, modification, and repair of any concrete structure begins with a comprehensive program of inspection and evaluation. This evaluation can include a visual review of p
42、reviously accomplished repairs or main- tenance, and performing condition surveys, testing, mainte- American Concrete Institute Copyrighted Material www.concrete.org 2 EVALUATION AND REPAIR OF EXISITING NUCLEAR SAFETY -RELATED CONCRETE STRUCTURES (ACI 349.3R-18)nance, and structural analysis. The te
43、rm “concrete nuclear structure” denotes concrete structures used in a nuclear application, while the term “nuclear safety-related concrete structure” refers to a specific quality classification and a subset of concrete nuclear structures. Although this report was written to provide guidelines for co
44、mpleting an evalua- tion of nuclear safety-related structures, such guidance can also be used for other similar concrete structures in U.S. Department of Energy (DOE) nuclear facilities/laborato- ries, Independent Spent Fuel Storage Installations (ISFSIs) licensed under 10 CFR72 (U.S. NRC 2000), or
45、any other applicable structures. The term “plant” is used interchange- ably for “nuclear power plants,” and “facilities” is used for DOE facilities and ISFSIs, which comply with the ACI 349 code (for example, Performance Category PC-3 or PC-4 and others defined per DOE Guide 420.1.2 U.S. DOE 2000) i
46、n the balance of this report. Nuclear safety-related concrete structures are designed to resist the loads associated with plant operating conditions, postulated accidents, and severe environmental conditions. These structures provide protection for nuclear safety-related components from hazards inte
47、rnal and external to the struc- ture, such as postulated missile impacts, impulsive loads, flooding, fire, earthquakes, and other severe environmental conditions. Additionally, the design for some of these struc- tures can be controlled by the required thickness of concrete intended for shielding ag
48、ainst radiation produced during the nuclear fission process. All nuclear safety-related struc- tures share a common function: they are integrally designed with the various systems, equipment, and components they support, and protect to restrict the spread of radiation and radioactive contamination t
49、o the general public. An effective evaluation procedure provides a rational meth- odology to maintain the serviceability of nuclear safety- related structures. Each evaluation should make reference to and preserve the design basis, as defined by the updated final safety analysis report (UFSAR), technical specifica- tions, codes and standards, calculations, drawings, and test records for the affected structure(s) in the disposition of findings and results. This includes qualification of any damage or degradation found, or necessity and suitabili
