關於 別再相信資深反核人士的謠言 ，我們在網路上蒐集到這些相關的討論、資訊與評價

【美國核管會回信核電廠與斷層距離】
#別再相信資深反核人士的謠言 #寫信去問NRC囉
大概兩個月前寫信去給美國核管會NRC，今天打開信箱發現他們在我生日休假那天回信了XDD，人生成就解鎖(1/1 美國核管會回覆信件)。

我主要是想詢問到底核電廠選址與斷層的距離是否有清楚的規範？答案是 #沒有規定電廠選址與斷層的距離到底要多少或禁止核電廠建置於斷層周邊，而是要求特定距離的核電廠設施必須做地質危害評估以及禁得起地震考驗這樣。台灣也有做SSHAC，但還沒看到正式出爐的報告(就陳大教授搶先披露那個)。

然後她詳細列了一堆NRC評估核電廠附近能動斷層的步驟以及法條，我相信陳教授或DPP不分區第二名應該都沒看過任何一條啦。

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Dear Mr. Chen,

Thank you for your questions related to whether the NRC has regulations that state how far a nuclear power plant (NPP) should be located from a fault that might move and cause earthquakes. The following paragraphs respond to your questions. As you requested, this response also cites NRC regulations that explain how the NRC analyzes potential hazard at a NPP resulting from earthquakes caused by movement along a fault located near the NPP.

#這段很重要
The US NRC does not have a regulation that specifies the distance required between a fault and a nuclear power plant (NPP). However, in Title 10 of the Code of Federal Regulations (10 CFR), specifically 10 CFR Part 50 (Domestic Licensing of Production and Utilization Materials), Appendix A, Criterion 2, the NRC requires safety-related structures, systems, and components (SSCs) of a NPP to be designed to withstand the effects of natural phenomena such as earthquakes without losing the capability to perform their safety functions.

美國NRC沒有規定斷層和核電廠（NPP）之間所需距離的法規。但是，在聯邦法規（10 CFR）的標題10中，尤其是10 CFR第50部分（生產和使用材料的國內許可）附錄A，準則2中，NRC要求與安全相關的結構，系統和組件（ NPP的SSC）旨在承受地震等自然現象的影響而又不喪失執行其安全功能的能力。

As defined in 10 CFR Part 50, Appendix S (Earthquake Engineering Criteria for Nuclear Plants), a Safe Shutdown Earthquake (SSE) is the vibratory ground motion for which certain SSCs must be designed to remain functional if an earthquake occurs. 10 CFR Part 100.23(c) (Geological, Seismological, and Engineering Characteristics) requires that geological, seismological, and engineering characteristics of a site and its environs be investigated in sufficient scope and detail to permit an adequate evaluation of the proposed site, provide sufficient information to support evaluations performed to estimate the SSE vibratory ground motion, and permit adequate engineering solutions to actual or potential geologic and seismic effects at the proposed site. Part 100.23(d) (Geologic and Seismic Siting Factors) requires that geologic and seismic siting factors considered for design include a determination of the SSE vibratory ground motion for the site and the potential for surface deformation due to faulting (i.e., tectonic deformation of the ground surface). Part 100.23(d)(1) (Determination of the Safe Shutdown Earthquake Ground Motion) requires that uncertainties in SSE vibratory ground motion estimates be addressed through an appropriate analysis (e.g., a probabilistic seismic hazard analysis, or PSHA) with due consideration for the geologic characteristics specified in 10 CFR Part 100.23(c). For a fault that is considered to be a potential source of earthquakes (i.e., a seismic source), that geologic feature can be analyzed using the Senior Seismic Hazard Analysis Committee (SSHAC) process. That process is a formal approach for incorporating information about the fault into a model used to characterize the fault as a seismic source, which is analyzed as part of the SSHAC process.

In Regulatory Guide 1.208 (A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion). the NRC provides guidance for applicants and licensees regarding how to meet the regulatory requirements discussed above. In addition, criteria for NRC staff to review applications for constructing and operating a nuclear power plant related to geologic, seismic, and geotechnical site characteristics are found in Chapter 2.5 of NUREG-0800, the NRC’s Standard Review Plan. If assessment of the potential for surface deformation must be considered because a fault is located such that it could result in surface rupture at the NPP site and deformation of engineered plant structures as required in 10 CFR Part 100.23(d), guidance for evaluating surface deformation is provided in NUREG-0800, Chapter 2.5.3. NUREG-2213 presents updated implementation guidelines for SSHAC studies in case you might wish to learn more about that process.