美国三级PSA发展过程及研究进展

Abstract

Abstract: Public risk is an important index of Nuclear Power Plant (NPP) safety. WASH-740, which was issued in 1957, started introducing the concept of reactor risk analysis. In 1972, WASH-1400 accomplishedsystematically a Level 3 PSA for the first time, and gave rise to the development of CRAC series codes. Furthermore, NUREG-1550 was published in 1990, which indicated PSA application matured. NRC established the current framework for risk-informed regulation by issuing a PRA Policy Statement in 1995. In 2007, The SOARCA project was initiated to develop best estimates of the offsite radiologicalhealth consequences for potential severe reactor accidents for Peach Bottom Atomic Power Station and Surry Power Station. In 2011, NRC proposed to perform a new full-scope comprehensive Level 3 PSA which addressed additional considerations such as multi-unit site effects and other on-site radiological sources.

Key words: Nuclear power plant, Probabilistic safety analysis, Risk assessment

CLC Number:

TL364+5

Wang Jianhua, Chen Peng, Yang Jie, Su Yongjie. The Developing Process and Study Trends of Level 3 PSA in USA[J].RADIATION PROTECTION BULLETIN, 2015, 35(6): 7-12.

References

[1] NRC. Reactor Safety Study: An Assessment of Accident Risksin U.S. Commercial Nuclear Power Plants[R]. WASH-1400, NUREG-75/014, Washington: NRC, 1975.
[2] IAEA. Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 3)[R]. SSR-050-P-12, Vienna: IAEA, 1996.
[3] Kelly G N, Olast M, Sinnaeve J. The CEC Research Program onMethods for Assessing the Radiological Impact of Accidents (MARIA)[J]. Nuclear Technology, 1991,94(2):161.
[4] IAEA. The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety[R]. SSR No.106, Vienna:IAEA, 1992.
[5] AEC. Theoretical Possibilities and Consequences of Major Accident in Large Nuclear Power PlantsAtomic Energy Commission[R]. ORNL-3441, Washington: AEC, 1957.
[6] NRC. Code Manual for MACCS2 User's Guide[Z]. NUREG/CR-6613, Washington: NRC, 1998.
[7] NRC. CRAC2 Model Description[R]. NUREG/CR 2313, Washington, NRC, 1984.
[8] NRC. MELCOR Accident Consequence Code System (MACCS), Programmer's Reference Manual[R]. NUREG/CR-6613, Washington:　NRC, 1990.
[9] NRC. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants[R]. NUREG-1150, Washington: NRC, 1990.
[10] 濮继龙. 压水堆核电厂安全与事故对策[M]. 北京:原子能出版社, 1995.
[11] NRC. Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities[R]. 60 FR 42622, Washington: NRC, 1995.
[12] NRC. Safety Goals for the Operations Nuclear Power Plants; PolicyStatement[R]. 51 FR 30028, Washington: NRC, 1986.
[13] NRC. An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis[R]. RG 1.174, Washington: NRC, 2011.
[14] OECD/NEA. Probabilistic Accident Consequence Assessment Codes - Second International Comparison, Overview Report[R]. Paris: OECD, 1994.
[15] CEC. Probability Accident Consequence Assessment Codes - Second International Comparison[R]. Luxembourg: CEC, 1993.
[16] CEC. COSYMA: Users Intercomparison Exercise[R]. Luxembourg: CEC,1993.
[17] NRC. Comparison of MACCS Users Calculations for the InternationalComparison Exercise on Probabilistic Accident Consequence Assessment Codes[R].NUREG/CR-6053, Washington: NRC, 1993.
[18] NRC. State-of-the-Art Reactor Consequence Analyses (SOARCA) Report[R]. NUREG-1935, Washington: NRC, 2012.
[19] NRC. Options For Proceeding With Future Level 3 Probabilistic RiskAssessment Activities[R]. SECY-11-0089, Washington: NRC, 2011.
[20] NRC. Regulatory Analysis Guidelines of the U.S. Nuclear RegulatoryCommission[R]. NUREG/BR-0058, Washington: NRC, 2004.
[21] NRC. Regulatory Analysis Technical Evaluation Handbook[R]. NUREG/BR-0184, Washington: NRC, 1997.
[22] NRC. Feasibility Study for a Risk-Informed and Performance-BasedRegulatory Structure for Future Plant Licensing[R]. NUREG-1860, Washington:NRC, 2007.
[23] NRC. Potential Policy, Licensing, and Key Technical Issues for Small Modular Nuclear Reactor Designs[R]. SECY-10-0034, Washington: NRC, 2010.
[24] NRC. Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews[R]. SECY-11-0024, Washington: NRC, 2011.
[25] NRC. Modifying the Risk-Informed Regulatory Guidance for New Reactors[R]. SECY-10-0121, Washington: NRC, 2010.

The Developing Process and Study Trends of Level 3 PSA in USA

PDF (PC)

Like

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Metrics

Comments

Recommended 10

[1]	ZHOU Yuqing, NIU Xiaoqing. Control experience on collective dose during outage of CPR1000 unit [J]. RADIATION PROTECTION BULLETIN, 2024, 44(6): 28-33.
[2]	REN Xueming, MA Boyang, HE Weihua, ZHOU Jiequan, ZHU Shuiping. Some thoughts on neutron dose monitoring practice at Taishan Nuclear Power Plant [J]. RADIATION PROTECTION BULLETIN, 2024, 44(4): 32-37.
[3]	ZHANG Wei, WEI Peng, WANG Gang, PAN Hongliang, ZHANG Chongwen, LI Yongguo. Improvement and practice of safety management and control for Na¹³¹I solution in a nuclear power plant [J]. RADIATION PROTECTION BULLETIN, 2024, 44(3): 7-13.
[4]	LIU Wenyuan, SONG Yan, GUO Fei, ZHANG Zequn, PU Lixing. A brief introduction to source term control and management optimization measures for a domestic nuclear power plant [J]. RADIATION PROTECTION BULLETIN, 2024, 44(3): 21-25.
[5]	DAI Yupu, LI Xiaotian, XU Jiehao, QIAO Taifei, LIANG Xuefei, LIU Yongsong, LI Yingkai, ZHANG Cailiang. Application of metal air pre-filter in the AC building of a nuclear power plant [J]. RADIATION PROTECTION BULLETIN, 2024, 44(3): 32-35.
[6]	LI Hui, YANG Haoran, XIE Jiangshan. Application practice of domestic electronic personal dosimetry monitoring system in a nuclear power plant [J]. RADIATION PROTECTION BULLETIN, 2024, 44(2): 31-34.
[7]	LIU Wenyuan, YE Ming, GONG Xu. Hazardous waste volume and quantity reduction in a NPP [J]. RADIATION PROTECTION BULLETIN, 2024, 44(1): 21-24.
[8]	An Shifeng, Yang Jingping, Sun Bo, Xu Yaoyao. Research and Development of Online Radiation Monitoring System for Emergency Command Center of Nuclear Power Plants [J]. RADIATION PROTECTION BULLETIN, 2023, 43(5): 40-43.
[9]	Peng Hui, Zhou Qifu, Wang Xiaotao, Zhou Xiaojian. Analysis and Suggestions on Radiation Safety Risk Control for Nuclear Power Plants [J]. RADIATION PROTECTION BULLETIN, 2023, 43(3-4): 3-6.
[10]	Wu Huiyuan, Ma Xi. Management of Radiation Safety for Nuclear Technology Application in Nuclear Power Plant [J]. RADIATION PROTECTION BULLETIN, 2023, 43(3-4): 7-12.
[11]	Wang Wei, Guan Xiaoqiang, Kong Xiangchao. Research on Ag-110m Removal Method for Primary Circuit Coolant in Nuclear Power Plant [J]. RADIATION PROTECTION BULLETIN, 2023, 43(3-4): 26-29.
[12]	Sang Yanjie, Zhang Xueguang, Wang Wei, Guan Xiaoqiang, Chen Liang. Experience and Improvement in Safety Supervision of Radiographic Inspection in Nuclear Power Plants [J]. RADIATION PROTECTION BULLETIN, 2023, 43(3-4): 30-36.
[13]	Chen Bin. Application Practice of Source Term Investigation Technology in a Source Term Anomaly Analysis in a Nuclear Power Plant [J]. RADIATION PROTECTION BULLETIN, 2023, 43(3-4): 57-61.
[14]	Hong Lili, Liu Bin, Zhou Shudong, Zhao Yanpeng, Ding Zhibo, Wang Renke. Training Practice of Emergency Responder for Nuclear Power Plant [J]. RADIATION PROTECTION BULLETIN, 2023, 43(2): 25-31.
[15]	Jiang Dejuan, Zhao Han, Liu Chengjun, Yao Yebao, Wang Songlei, Wang Xiaoting. Analysis of the Micronucleus Test Results of Peripheral Blood Lymphocytesin Radiation Workers of a NPP [J]. RADIATION PROTECTION BULLETIN, 2022, 42(4-5): 30-33.