Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
192 Comprehensive Integrated Risk-Informed Safety Management for Commercial Nuclear Power Plants (PSAM-0377)
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Risk-informed safety management progress can be traced via the publication of several industry documents. The most recent of these is:
• Risk-Managed Technical Specifications (RMTS) Guidelines, Technical Update to EPRI Interim Report 1002965, EPRI, Palo Alto, CA, 2005. 1009674, Revision 1.
The purpose of this paper is to supplement and expand upon the concepts presented in EPRI 1009674, Revision 1, by presenting a suggested framework for developing a single comprehensive focused nuclear power plant integrated risk-informed safety management program (IRISMP) for existing and planned nuclear power plants. This paper provides utilities with an example of a broad-based nuclear power plant IRISMP. The example program encompasses not only risk-informed technical specifications, but also the full spectrum of other risk-informed applications. It has been developed to take advantage of successful applications previously approved for selected nuclear power plant diesel generator allowed outage time extension and the comments of NRC reviewers in response to these applications. With the information provided in this paper, utilities will be in a better position to predict and plan the scope of work required to produce their IRISMP request submittals. This approach complements and supplements, existing probabilistic safety assessment (PSA) and probabilistic risk assessment (PRA) methodologies.
The background for IRISMP development and implementation involves several historical developments and issues. Some of these are:
• Original deterministic plant technical specifications.
• Past, current, and follow-on efforts to implement risk-informed technical specifications applications and revisions (i.e., the Nuclear Energy Institute (NEI) Risk-Informed Technical Specifications Task Force (RITSTF) work and “standard technical specifications” development).
• Current efforts to “risk-inform” 10 CFR 50 (specifically Options 2 and 3, 10 CFR 50.69).
• Other risk-informed performance-based PRA applications such as:
̥ Risk-Informed In-Service Inspection (RI-ISI) and Testing (RI-IST) Programs
̥ Risk-Informed Graded Quality Assurance (RI-GQA) Programs
̥ PRA support of Risk-Informed Maintenance Rule Implementation
̥ … And others
• “State-of-the-Art” living PRA standards (e.g., current ASME and ANS PRA Standards), quality assurance, configuration control, and periodic update efforts.
• THE RISK INFORMED INTEGRATED SAFETY MANAGEMENT SPECIFICATION (RIISMS) CONCEPT PREVIOUSLY INFORMALLY REFERRED TO AS “ONE-PAGE TECH SPECS.”
• CURRENT EFFORTS TO VERIFY, VALIDATE, AND REFINE NUCLEAR REGULATORY COMMISSION (NRC) REGULATORY GUIDE (RG) 1.200 (FOR TRIAL USE).
• CURRENT EFFORTS TO IMPLEMENT MAINTENANCE RULE RISK ASSESSMENT, 10 CFR 50.65(A)(4).
This paper presents, among other guidelines, a framework of risk “speedometers” and “odometers” designed to improve overall plant safety management, while also supporting enhanced flexibility of nuclear power plant operations and maintenance policies and practices by encompassing the full range and scope of plant risk-informed applications in a comprehensive, integrated fashion.