Document: NUREG-0800
Document ID: 1877a6e5-f5a2-4394-bd63-c323831e96d0
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2231/ML22319A149.pdf
Revision Date: 2023-07
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
er 1976 (ADAMS Accession No. ML13267A423). 10. 73 FR 60612, “Policy Statement on the Regulation of Advanced Reactors,” October 2008. 11. SECY-94-084, “Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs,” March 1994 (ADMAS Accession No. ML003708068). 12. SECY-95-132, “Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems (RTNSS) in Passive Plant Designs (SECY-94-084),” May 1995 (ADAMS Accession No. ML003708005). 13. SECY-96-128, “Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design,” June 1996 (ADAMS Accession No. ML003708224). 14. Regulatory Guide 1.226, “Flexible Mitigation Strategies for Beyond-Design-Basis Events,” June 2019 (ADAMS Accession No. ML19058A012). 15. Regulatory Guide 1.203, “Transient and Accident Analysis Methods,” December 2005 (ADAMS Accession No. ML053500170). 15.0-18 Draft Revision 4 – July 2023 Standard Review Plan Section 15.0, Draft Revision 4 “Introduction - Transient and Accident Analyses” Description of Changes This Standard Review Plan (SRP) section affirms the technical accuracy and adequacy of the guidance previously provided in SRP Section 15.0, Revision 3, dated March 2007. See Agencywide Documents Access and Management System Accession No. ML070710376. The main purpose of this revision is to update and reformat the analysis acceptance criteria consistent with the regulations. Specifically, outdated legacy information was removed and acceptance criteria were reformatted into tabular form. This update also provides additional staff guidance for new reactor-specific policies related to 72-hour and 7-day coping capabilities, safe and stable condition, and plant recovery following a design-basis event. Section I.6 was updated to clarify staff guidance related to non-safety-related SSCs and single failure assumptions. Additional references were added to