Document: NUREG-0800
Document ID: 8dd882f4-a34f-4415-acd1-ebb441c72786
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1213/ML12132A481.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
design features that contribute to the mitigation of severe accidents. The Commission anticipates that these features will reduce the significant risk contributors when compared to existing operating plants. 8. The applicant’s containment performance evaluation meets the requirement of 10 CFR 50.44, the SECY-93-087 expectations for containment structural performance, and the staff’s expectation of the quality of the containment pressure fragility analysis. 9. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC and COL applications submitted pursuant to 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. 19.0-36 Draft Revision 3 – September 2012 The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI REFERENCES 1. ASME/ANS, “Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,” ASME/ANS RA-Sa-2009, New York, NY, 2009. 2. EPRI, “Methodology for Developing Seismic Fragilities,” EPRI Report TR-103959, Palo Alto, CA, June 1994. 3. EPRI, “Nuclear Plant Seismic Margin R-1,” EPRI Report NP-6041, Palo Alto, CA, August 1991. 4. NEI, “Guidelines for Industry Actions to Assess Shutdown Management,” NUMARC 91-06, December 1991. 5. NRC, RG 1.174, Revision 1, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” July 2002. 6. NRC,