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:
udden Loss of RCS Inventory During Low Coolant Level Operation.”, June 8, 1988. 19.0-38 Draft Revision 3 – September 2012 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50, 10 CFR Part 51, and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval numbers 3150-0011, 3150- 0021, and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. 19.0-39 Draft Revision 3 – September 2012 SRP SECTION 19.0 “Probabilistic Risk Assessment and Severe Accident Evaluation For New Reactors” Description of Changes This SRP section affirms the technical accuracy and adequacy of the guidance previously provided in Revision 2, dated June 2007 of this SRP. See ADAMS Accession No. ML071700652. The technical changes incorporated in Revision 3, dated September 2012 include: (1) incorporation of guidance previously contained in Interim Staff Guidance (ISG) DC/COL-ISG-003 ( ML081430087) concerning the review of PRA information and severe accident assessments submitted to support DC and COL applications, (2) incorporation of guidance previously contained in ISG DC/COL-ISG-020 (ML100491233) concerning review of information from PRA-based seismic margin analyses submitted in support of DC and COL applications, (3) incorporation of guidance previously contained in ISG DI&C/COL-ISG-003 (ML080570048) concerning review of DI&C system PRAs, including treatment of CCFs in PRAs and uncertainty analysis associated with new reactor digital systems, and (4) incorporation of additional procedures for review of PRA information and severe accident assessments developed during NRC reviews of DC and COL applications completed after Revision 2 of SRP 19.0 was issued. A