Document: NUREG-0800
Document ID: 81955d2c-b3de-4ce3-a132-7f798c711260
Document Type: srp
Title: INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070675.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
ed in the SRP sections for Chapter 15. Various anticipated process disturbances, equipment malfunctions, potential operator actions or errors, and component failures are examined to evaluate the plant capability to control or accommodate such failures and malfunctions. The RSBSRXB review includes an analysis of the pressure to which the reactor and steam systems are subjected and the need for engineered safety features to mitigate the consequences. The impact of various single failures on the course of anticipated operational occurrences and postulated accidents is also considered. For new applications, loss of offsite power should not be considered as a single-failure event; rather, it should be assumed in the analysis of each event without changing the event category. The applicant’s Safety Analysis Report should discuss each transient and accident analysis to justify that it conforms to General Design Criterion (GDC) 17 requirements. (This position is based upon interpretation of GDC 17, as documented in the Final Safety Evaluation Report for the ABB-CE System 80+ design certification.)17 15.0-3 DRAFT Rev. 3 - April 1996 The transient and accident sequences are reviewed to identify necessary operator actions and to confirm that actions prescribed by procedures developed under Action Plan Item I.C.1 emergency operating procedures have been appropriately accounted for. 18 The Procedures and Test Review Branch Human Factors Assessment Branch, upon request, 19 will assist the RSBSRXB reviewer in identifying all prescribed operator actions. As required by Item II.K.3.44 of NUREG-0737, boiling water reactor (BWR) applicants must 20 demonstrate that for anticipated transients combined with the worst single failure and assuming proper operator actions, the core remains covered or provide analysis to show that no significant fuel damage results from uncovering the core uncovery. Transients which result in a 21 stuck-open relief valve should be included in this category.