Published April 1994 | Version v1
Report Restricted

Handbook of methods for risk-based analysis of technical specification requirements

  • 1. Brookhaven National Lab., Upton, NY (United States)

Description

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: Quantitatively evaluate the risk and justify changes based on objective risk arguments; Provide a defensible basis for these requirements for regulatory applications. The US NRC Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

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Additional details

Publishing Information

Imprint Title
Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs
Imprint Pagination
586 p.
Journal Page Range
p. 363-373.
Report number
NUREG/CP--0133-Vol.1

Conference

Title
21. water reactor safety information meeting.
Dates
25-27 Oct 1993.
Place
Bethesda, MD (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26033779
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MANUALS; NUCLEAR POWER PLANTS; OPTIMIZATION; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SPECIFICATIONS
Descriptors DEC
DOCUMENT TYPES; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-931079--Vol.1.