Document: NUREG-0800
Document ID: 43123a17-321c-4751-b3ba-9ba5e9b0b364
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A726.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
lied to the modification of variables that have been previously licensed to the criteria of Revision 2 or 3. The applicant or licensee should document the proposed modifications in a table format that includes for each variable the following: variable name, current type, current function or purpose, current range, proposed type, proposed function or purpose, proposed range, and any criteria that would be changed. For variables for which there is a proposed change in type or purpose, the applicant or licensee should document the rationale for the change. Licensees may make modifications within the plant’s current licensing basis without referencing Revision 4 of RG 1.97. BTP 7-10-7 Draft Revision 6 – August 2015 4. Review Procedures SRP Section 7.5, Section III, describes the review procedure for accident monitoring instrumentation. BTP 7-10-8 Draft Revision 6 – August 2015 Table 1. For BWRs: Acceptable Deviations and Clarifications to Revisions 2 and 3 of Regulatory Guide 1.97 Variable Deviation Acceptance Guidelines/Clarification Neutron flux • Category • Equipment qualification • Redundancy • Power source • Quality assurance • Range Except for applications submitted after January 13, 1993 (which should satisfy the guidelines identified in RG 1.97), the design criteria identified in NEDO-31558-A, “Position on Nuclear Regulatory Commission (NRC) RG 1.97, Revision 3, Requirements for Post-Accident Neutron Monitoring System,” are an acceptable alternative to Category 1 criteria. Pursuant to these alternative criteria, the applicant/licensee should perform a plant-specific evaluation of the electrical power distribution to the neutron monitoring system (including the recorders) to verify that the instrument power is not lost during design basis events. Coolant level in reactor vessel • Range • Redundancy If redundant channels of Category 1 instrumentation cover the fuel zone and the wide range (i.e., all manual and automatic trip functions), a