Document: NUREG-0800
Document ID: 16650158-402d-4897-850a-bc9e2cce7648
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070726.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
uest from the RSBSRXB reviewer, other branches will provide input for the areas of 65 review stated in subsection I of this SRP section. The RSBSRXB reviewer obtains and uses 66 the input requested as required to assure ensure that the review procedure is complete. 67 For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.68 IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and that the review supports the following kinds of statements and conclusions, which should be included in the staff's safety evaluation report (SER): A number of plant transients can result in a decrease of reactor coolant inventory. Those that might be expected to occur with moderate frequency are pressure relief valve openings, minor primary pipe breaks, and (in BWRs) loss of feedwater. All of these * postulated transients have been reviewed. It was found that the most limiting in regard to core thermal margins and pressure within the reactor coolant and main steam systems was the transient. This transient was evaluated by the applicant using a mathematical model that had been previously reviewed and found acceptable by the staff. The parameters used as input to this model were reviewed and found to be suitably conservative. The results of the analysis of the transient showed that the specified acceptable fuel design limits were maintained by ensuring that the minimum departure from nucleate boiling