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
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Content:
ironment and is not part of a safety system, Category 3 instrumentation is acceptable in place of Category 2 instrumentation. BTP 7-10-10 Draft Revision 6 – August 2015 Table 2. For PWRs: Acceptable Deviations and Clarifications to Revisions 2 and 3 of Regulatory Guide 1.97 Variable Deviation Acceptance Guidelines/Clarification Neutron flux Environmental qualification A non-environmentally qualified instrument is acceptable if qualified core exit thermocouples and reactor coolant system (RCS) hot and cold leg temperature indications are provided in conjunction with directions in emergency procedures for operator action to ensure that boric acid injection is occurring. RCS pressure (Combustion Engineering [CE] reactors) Range A range of 0-3,000 psig is an adequate alternative to 0-4,000 psig if analysis is presented or referenced in the final safety analysis report (FSAR) that shows that pressure will remain on scale for all design basis transients and accidents. However, if an anticipated transient without scram (ATWS) analysis indicates that pressures exceeding FSAR values are possible, an expanded range of the Category 1 instrumentation should be provided. Containment sump level Range Separate narrow-range instrumentation is not required if the wide-range instrumentation satisfies the guidelines of RG 1.97 and is of sufficient range and accuracy to monitor the sump operation for all design basis conditions. Containment isolation valve position Redundancy A redundant position indication for each active containment isolation valve is not necessary because the valves are redundant. Likewise, position indication is not necessary for valves within the operator’s cognizance that are normally closed and remain closed after an accident, and that are administratively controlled. Radioactivity concentration or radiation level in circulating primary coolant N/A A continuous post-accident monitor is not necessary. Containment hydrogen concentration Category In accordance