Document: NUREG-0800
Document ID: c674c9e0-9f79-481c-9349-461015e181cb
Document Type: srp
Title: INADVERTENT LOADING AND OPERATION OF A FUEL ASSEMBLY IN AN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070719.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.7
CFR Part: 
CFR Title: 

Content:
hat will minimize the likelihood of loading fuel in a location other than its designated place. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.15 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. 15.4.7-5 DRAFT Rev. 2 - April 1996 This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 16 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.17 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants Criterion 13, "Instrumentation and Control."18 2. 10 CFR Part 100, "Reactor Site Criteria." DRAFT Rev. 2 - April 1996 15.4.7-6 [This Page Intentionally Left Blank] SRP Draft Section 15.4.7 Attachment A - Proposed Changes in Order of Occurrence 15.4.7-7 DRAFT Rev. 2 - April 1996 Item numbers in the following table correspond to superscript numbers in the redline/strikeout copy of the draft SRP section. Item Source Description 1. Current PRB name and abbreviation Changed PRB to Reactor Systems Branch (SRXB). 2. SRP-UDP format item Changed CPB to SRXB. The Core Performance Branch has been incorporated into the SRXB. 3. SRP-UDP format