Document: NUREG-0800
Document ID: 5c379bc2-cb0b-42ca-93af-dedf43c6cb30
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500542.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
Appendix 7-A Rev. 4 — June 1997 BTP HICB-10-1 NEW Branch Technical Position HICB-10 Guidance on Application of Regulatory Guide 1.97 A. Background This branch technical position (BTP) provides additional guidelines for reviewing an applicant/licensee's post-accident monitoring system. These guidelines are based on reviews of applicant/licensee design submittals that contained approved interpretations and alternatives for the guidance identified in Reg. Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." 1. Regulatory Basis 10 CFR 50.34(f)(2)(xvii), "Accident Monitoring Instrumentation," requires in part that instrumentation be provided to measure, record, and read out in the control room: containment pressure, containment water level, containment hydrogen concentration, containment radiation intensity (high-level), and noble gas effluents. 10 CFR 50 Appendix A, General Design Criterion (GDC) 13, "Instrumentation and Control," requires in part that instrumentation be provided to monitor variables and systems over their anticipated ranges for accident conditions, as appropriate, to ensure adequate safety. 10 CFR 50 Appendix A, GDC 19, "Control Room," requires in part that a control room be provided from which actions can be taken to maintain the nuclear power unit in a safe condition under accident conditions, including loss-of-coolant accidents. It also requires that equipment, including the necessary instrumentation, be provided at appropriate locations outside the control room; such equipment must have a design capability for prompt, hot shutdown of the reactor. 10 CFR 50, Appendix A, GDC 64, "Monitoring Radioactivity Releases," requires in part that means be provided to monitor (1) the reactor containment atmosphere, (2) spaces containing components for recirculation of loss-of-coolant accident fluid, (3) effluent discharge paths, and (4) the plant environs for