Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
ogram should address the disposition of failed fuel. In addition to the plant-specific surveillance program, a continuing fuel surveillance effort should exist for a given type, make, or class of fuel that can be suitably referenced by all plants using similar fuel. In the absence of such a generic program, the reviewer should expect more detail in the plant-specific program. 4.2-20 Revision 3 - March 2007 For a fuel design that introduces new features, a more detailed surveillance program commensurate with the nature of the changes should be described. This program should include appropriate qualitative and quantitative inspections to be carried out at interim and end-of-life refueling outages. This surveillance program should be coordinated with the prototype testing discussed in Subsection II.3.B. When prototype testing cannot be performed, a special detailed surveillance program should be planned for the first irradiation of a new design. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. 10 CFR 50.46 requires each PWR and BWR to be provided with an ECCS that must be designed so that its calculated cooling performance following a postulated LOCA conforms to acceptance criteria set forth in the regulation. Acceptance criteria in 10 CFR 50.46 establish both fuel system design limits and core cooling requirements. SRP Section 4.2 reviews the performance of the fuel system during postulated LOCAs related to flow blockage and the methods used to establish the initial fuel conditions before the LOCA. RG 1.157 or Appendix K to 10 CFR Part 50 presents acceptable methods to evaluate the performance of the ECCS. RG 1.126 provides an acceptable model for predicting the effects of fuel densification in commercial LWRs. Application of acceptance criteria established in 10 CFR 50.46 significantly reduces the possibility of a violent chemical