ASME RA-S-1.2 – 2024 Edition – Severe Accident Progression and Radiological Release (Level 2) PRA Standard for Nuclear Power Plant Applications for Light Water Reactors (LWRs)
The ASME RA-S-1.2-2024 is a standard that provides requirements for Probabilistic Risk Assessments (PRAs) used to support risk-informed decision-making for commercial Light Water Reactors (LWRs), including small modular reactors (SMRs). This standard is focused on the progression of severe accidents and the radiological release (Level 2 PRA) in nuclear power plant applications
Key Features of ASME RA-S-1.2-2024:
- Scope and Application:
- The standard is designed for LWRs and is applicable to both operating and under-design plants. It covers accident sequences initiated by internal events and hazards, focusing on single-reactor accidents
- It does not address multiunit accident sequences, as seen in incidents like Fukushima Daiichi, but it does provide limited requirements regarding the status of other units on-site .
- Significant Changes in 2024 Edition:
- Removal of the Level 3 Interface Technical Element, aligning with the ASME/ANS RA-S-1.3-2017 standards for offsite radiological accident consequences.
- Revision of Supporting Requirements (SRs) to improve clarity and consistency with the Level 1 PRA standards.
- Introduction of new sections on Configuration Control and Newly Developed Methods, along with a nonmandatory appendix defining action verbs used in the standard.
- Removal of Capability Category III, focusing instead on Capability Category II for a refined analysis.
- Radiological Assessment:
- The standard restricts radiological release assessment to radionuclides originating in reactor fuel and does not consider spent fuel pool releases or human-induced threats like sabotage.
- Technical and Peer-Review Enhancements:
- The 2024 revision emphasizes enhanced consistency among technical elements across various standards, especially in areas like screening, uncertainty, human reliability analysis, and documentation.
The standard aims to provide a comprehensive framework for assessing severe accident progression and radiological release to enhance safety and decision-making processes in nuclear power plant operations.
General Product Information:
| Edition | 2024 Edition |
| Document Type | |
| Document Language | English |
| Pages | 103 |
| Publisher | ASME International(ASME) |
| Status | Current |
