Document: NUREG-0800
Document ID: ba51de63-39c0-4396-acd5-87521e5e5c74
Document Type: srp
Title: RELIABILITY ASSURANCE PROGRAM (RAP)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190018.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.4
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CFR Title: 

Content:
ness of Maintenance at Nuclear Power Plants,” is one acceptable method for establishing performance goals provided that SSCs are categorized as high safety significant. b. The feedback mechanism for periodically evaluating reliability assumptions on the basis of actual equipment, train, or system performance. This description should include any key assumptions and determinations of risk significance that are derived from probabilistic/PRA, deterministic, or other methods that consider operations, maintenance, and monitoring activities for identifying component reliability and failure data. The description should also include how industry operational experience will be used to verify that reliability assumptions remain valid. (The reliability performance monitoring does not need to statistically verify the numerical values. However, it provides a feedback mechanism for periodically evaluating equipment reliability on the basis of actual equipment, train, or system performance and other operational history.) 5. The process for providing corrective actions for design and operational errors that degrade nonsafety-related SSCs within the scope of the RAP. 6. Controls for the procedures and instructions used to implement reliability assurance activities. 7. The controls for records of activities involving SSCs within the scope of RAP. 8. The corrective action process applied to SSCs within the scope of RAP. 9. The audit plans for conducting QA audits of reliability assurance activities. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 17.4-8 March 2007 1. Per Commission policy contained in the SRM on SECY 95-132, RAP is codified by requiring, as part of design certification rulemaking. The design phase of the RAP is verified using the ITAAC process. 2. The RAP provides reasonable assurance that (1) a reactor is designed, constructed, and