Document: NUREG-0800
Document ID: d5452e7b-1e61-498b-9e3d-71073b3328ef
Document Type: srp
Title: LEAK-BEFORE-BREAK EVALUATION PROCEDURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0302/ML030280295.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.3
CFR Part: 
CFR Title: 

Content:
DARD REVIEW PLAN Standord review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants These documents are made available to the public as part of the Commission's policy to inform the nuclear industry and the general public of regulatory procedures and policies Standard review plans are not substitutes for regulatory guides or the Commissionfs regulations and compliance with them is not required The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically. as appropriate, to accommodate comments and to reflect new informa tion and experience Comments and suggestions for improvement will be considered and should be sent to the U S Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Wesltngton. D.C 2OW Indirect failure mechanisms as defined in the plant FSAR which could lead to pipe rupture are investigated. These include seismic events and system over pressurizations due to accidents resulting from human error, fires, or flooding which cause electrical and mechanical control systems to malfunction. Missiles from equipment, damage from moving equipment and failures of structures, systems or components in close proximity to the piping are investigated as well. However, the results of prior analyses conducted to show compliance with Commission regulations can be applicable to potential sources of indirect pipe rupture. II. ACCEPTANCE CRITERIA Acceptance criteria are based on meeting the requirements of General Design Criterion 4 as it relates to the exclusion of dynamic effects of the pipe ruptures postulated in SRP Section 3.6.2. Analyses reviewed and approved by the staff must demonstrate that the probability of fluid system