Enforcement Rules of the Implementation of Nuclear Reactor Facilities Regulation Act Article 10
A situation arising during the operation period of a nuclear reactor facility that may pose risks to public health, safety, or the ecological environment, as stipulated in Paragraph 1 of Article 14 of this Act, refers to any of the following:1. The design thereof has been found to be gross imperfect or to be connected with the matters provided under Subparagraphs 2 to 6 of Article 8, but has not yet been appropriately evaluated and solved.2. There is a gross discrepancy between the operation on the scene of facility and the commitment under the safety analysis report, which affects the safety function.3. The performance of quality assurance program is seriously deficient, which has caused a gross impact on the quality of construction or the safety of operation on the scene of facility.4. A serious accident occurs, which adversely affects on-site operations at the facility.5. The hourly average concentration of radioactive nuclides in the air on the boundary of nuclear reactor facility caused by the gas containing radioactive materials released thereby exceeds ten times of that provided under the fourth ( 4th ) Column in table IV-II annexed to the Safety Standards for Protection against Ionizing Radiation, or the hourly average concentration of radioactive nuclides in the water on the boundary of nuclear reactor facility caused by the liquid containing radioactive materials released thereby exceeds ten times of that provided under the fifth (5th) Column in table IV-II annexed to the Safety Standards for Protection against Ionizing Radiation.6. According to the findings on environmental radiation monitoring, the external exposed radiation dose to the common people within the outside area of premises is estimated to be exceeding decimal naught two (0.02) milli-Sieverts (mSv) within one hour, or decimal five (0.5) milli-Sieverts (mSv) within one year.7. According to the findings on environmental radiation monitoring, the radiation dose on the common people is estimated to be exceeding the dose limit prescribed under the Safety Standards for Protection against Ionizing Radiation.8. The submitted document(s), materials or records are false, which has affected the accuracy of reviewing or issuing the license by the competent authority.9. The condition which the nuclear power reactor facilities is not properly assessed and is operated by reducing the power from full power to the non-original design power manually. However, in order to cope with the safety issues for the operation of power plants, to prevent the impact of natural disasters, to perform the inspection, maintenance and testing of the structures, systems and components, or to coast down at the end of the fuel cycle that is approved by the competent authority, the conditions are exempted.10. Other circumstances determined and published by the competent authority.The proper assessment referred to the Subparagraph 9 of previous paragraph shall include the following items:1. The comprehensive description of the time frame of power reduction and power rate.2. The assessment of power output control.3. The impact assessment of the components in the primary system.4. The considerations about power generation equipment.5. The considerations about operation.6. The evaluation of the operational procedures.
中文原文 核子反應器設施管制法施行細則第10條
本法第十四條第一項所稱核子反應器設施運轉期間，有危害公眾健康與安全或環境生態之虞者，指有下列情事之一：
一、發現設計有重大缺陷或涉及第八條第二款至第六款之事項，且未經適當評估解決。
二、設施現場作業與安全分析報告承諾有重大差異，且影響安全功能。
三、品質保證方案之執行有嚴重缺陷，對設施現場施工品質或運轉安全產生重大影響。
四、發生重大意外事件，對設施現場作業有不良影響。
五、所排放之含放射性物質氣體，造成核子反應器設施邊界空氣中之放射性核種一小時之平均濃度，超過游離輻射防護安全標準附表四之二第四欄所定之濃度十倍；或所排放之含放射性物質液體，造成核子反應器設施邊界水中之放射性核種一小時之平均濃度，超過游離輻射防護安全標準附表四之二第五欄所定之濃度十倍。
六、依環境輻射監測結果，估算廠外地區中一般人體外曝露之劑量，於一小時內超過○．○二毫西弗或一年內超過○．五毫西弗。
七、依環境輻射監測結果，估算一般人之劑量超過游離輻射防護安全標準規定之劑量限度。
八、提供不實之文件、資料或紀錄，致影響主管機關審核或核發執照之正確性。
九、動力用核子反應器設施未經適當安全評估之人為機組降載至非原設計全功率運轉之情事。
但為因應電廠運轉安全問題、避免天然災害之影響、執行結構、系統及組件檢查、維護及測試作業，或燃料週期末遞載運轉且經主管機關審查同意者，不在此限。
十、其他經主管機關認定並發布之情事。
前項第九款適當安全評估，應包括下列事項：
一、降載運轉時程、功率之綜合說明。
二、功率輸出控制評估。
三、一次側系統組件衝擊評估。
四、發電設備考量。
五、運轉考量。
六、運轉操作程序評估。
一、發現設計有重大缺陷或涉及第八條第二款至第六款之事項，且未經適當評估解決。
二、設施現場作業與安全分析報告承諾有重大差異，且影響安全功能。
三、品質保證方案之執行有嚴重缺陷，對設施現場施工品質或運轉安全產生重大影響。
四、發生重大意外事件，對設施現場作業有不良影響。
五、所排放之含放射性物質氣體，造成核子反應器設施邊界空氣中之放射性核種一小時之平均濃度，超過游離輻射防護安全標準附表四之二第四欄所定之濃度十倍；或所排放之含放射性物質液體，造成核子反應器設施邊界水中之放射性核種一小時之平均濃度，超過游離輻射防護安全標準附表四之二第五欄所定之濃度十倍。
六、依環境輻射監測結果，估算廠外地區中一般人體外曝露之劑量，於一小時內超過○．○二毫西弗或一年內超過○．五毫西弗。
七、依環境輻射監測結果，估算一般人之劑量超過游離輻射防護安全標準規定之劑量限度。
八、提供不實之文件、資料或紀錄，致影響主管機關審核或核發執照之正確性。
九、動力用核子反應器設施未經適當安全評估之人為機組降載至非原設計全功率運轉之情事。
但為因應電廠運轉安全問題、避免天然災害之影響、執行結構、系統及組件檢查、維護及測試作業，或燃料週期末遞載運轉且經主管機關審查同意者，不在此限。
十、其他經主管機關認定並發布之情事。
前項第九款適當安全評估，應包括下列事項：
一、降載運轉時程、功率之綜合說明。
二、功率輸出控制評估。
三、一次側系統組件衝擊評估。
四、發電設備考量。
五、運轉考量。
六、運轉操作程序評估。